Fuel Cycle Data Package Template Description

Fuel Cycle Data Package Template Description

Prepared for U.S. Department of Energy

Fuel Cycle Options Campaign

Edward A. Hoffman Taek K. Kim

Temitope A. Taiwo Argonne National Laboratory

November 30, 2012 FCRD-ODEV-2011-000054, Rev. 4

DISCLAIMER

This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trade mark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof.

Fuel Cycle Data Package Template Description November 30, 2012 i

Report Sign-off Page

Submitted by: 11/30/2012 Edward A. Hoffman Date FCDP Document Coordinator Argonne National Laboratory

Approved by: 11/30/2012 Taek K. Kim Date FCDP Development Team Leader Argonne National Laboratory

Fuel Cycle Data Package Template Description ii November 30, 2012

Fuel Cycle Data Package Template Description November 30, 2012 iii

REVISION HISTORY

Revision Number

Effective Date

Description of Revision

0 2/28/2011 Initial Release of Fuel Cycle Data Package Template Description

1 9/30/2011 Incorporated review comments from various sources: DOE, industry representatives, campaign representatives. Revised structure of the FCDP template to have System Datasheet and Technology Datafiles.

2 1/25/2012

Revision to reflect the feedbacks from the programmatic review of FCDP documents and data packages developed in FY 2011. Incorporated December 15, 2011 revisions to master template examples into Attachment A.

3 8/14/2012 Revision to reflect the feedbacks from the programmatic review of FCDP documents; revised Preparation, Review and Acceptance Procedure for Fuel Cycle Data Packages; and draft fuel cycle options list.

4 11/30/2012 Revision to reflect information in recent Fuel Cycle Option Campaign working documents supporting the planned 2013 Evaluation & Screening, and use of FCDPs in that process.

Fuel Cycle Data Package Template Description iv November 30, 2012

Fuel Cycle Data Package Template Description November 30, 2012 v

CONTENTS

ACKNOWLEDGMENTS .......................................................................................................................... vii

ACRONYMS ............................................................................................................................................. viii

1. INTRODUCTION AND BACKGROUND ........................................................................................ 1

1.1 Key Terminology ...................................................................................................................... 1 1.1.1 Nuclear Fuel Cycle Option .......................................................................................... 1 1.1.2 Fuel Cycle Strategy ...................................................................................................... 1 1.1.3 Fuel Cycle Stages ........................................................................................................ 2

2. TEMPLATE DESCRIPTION ............................................................................................................. 4

2.1 General Structure ...................................................................................................................... 4

2.2 System Datasheet ...................................................................................................................... 4

2.3 The Technology Datafile ........................................................................................................... 5

2.4 Technology Readiness Level Description ................................................................................. 6

ATTACHMENT A – FCDP MASTER TEMPLATE EXAMPLES ............................................................ 8

ATTACHMENT A.1 - Systems Datasheet Example ......................................................................... 8

ATTACHMENT A.2 – Nuclear Power Plant/Transmutation Technology Datafile......................... 18

ATTACHMENT A.3 - Fuel Technology Datafile ........................................................................... 23

ATTACHMENT A.4 – Reprocessing/Separations Technology Datafile ......................................... 28

ATTACHMENT B – GENERIC TEMPLATE COMPLETION INSTRUCTIONS .................................. 34

ATTACHMENT B.1 – System Datasheet Instructions .................................................................... 34

ATTACHMENT B.2 – Nuclear Power Plant/Transmutation Technology Datafile Instructions ............................................................................................................................. 43

ATTACHMENT B.3 – Fuel Technology Datafile Instructions ....................................................... 46

ATTACHMENT B.4 – Reprocessing/Separations and Technology Datafile Instructions .............. 49

REFERENCES ........................................................................................................................................... 52

Fuel Cycle Data Package Template Description vi November 30, 2012

TABLES

Table 1. Technology Readiness Level (TRL) Definitions and Descriptions ................................................ 7

Table B-1. Instructions for Summary Description Data of System Datasheet ............................................ 36

Table B-2. Material Flow Diagram Nomenclature and Symbols ............................................................... 38

Table B-3. Instructions for NPPT High Level Parameter Data in System Datasheet ................................. 39

Table B-4. Instructions for Nuclear Fuel High Level Parameter in System Datasheet .............................. 40

Table B-6. Instructions for Summary Description Data of NPPT Technology Datafile ............................ 44

Table B-7. Instructions for High Level Parameter Data in NPPT Technology Datafile ............................ 45

Table B-8. Instructions for Summary Description Data of Fuel Technology Datafile ............................... 47

Table B-9. Instructions for High Level Parameter Data in Fuel Technology Datafile ............................... 48

Table B-10. Instructions for Summary Description Data in Reprocessing/Separations Technology Datafile ....................................................................................................................................... 50

Table B-11. Instructions for High Level Parameter Data in Reprocessing/Separations Technology Datafile ....................................................................................................................................... 51

FIGURE

Figure 1. Illustration of Fuel Cycle Stages in Particular Fuel Cycle Options ............................................... 3

Fuel Cycle Data Package Template Description November 30, 2012 vii

ACKNOWLEDGMENTS

The authors of this report would like to thank the Fuel Cycle Options Campaign members and Jack Wheeler (Federal Manager for Integrated Fuel Cycle Analysis, U.S. Department of Energy) who have provided helpful input to this effort. Their assistance and advice were essential in the successful completion of this effort.

Fuel Cycle Data Package Template Description viii November 30, 2012

ACRONYMS

CR Conversion Ratio D&D Decontamination and Decommissioning DOE U.S. Department of Energy EDS Externally Driven System EST Evaluation and Screening Team FCDP Fuel Cycle Data Package FCT Fuel Cycle Technologies FOAK First-of-a-Kind FP Fission Products FY Fiscal Year GNEP Global Nuclear Energy Partnership GTCC Greater than Class C (waste) HLO High-level Objective HLW High-level Radioactive Waste LEU Low-enriched Uranium LLW Low-level Radioactive Waste LWR Light Water Reactor MA Minor Actinides MOX Mixed Oxide NPPT Nuclear Power Plant/Transmutation NTD National Technical Director Np Neptunium Pu Plutonium PWR Pressurized Water Reactor R&D Research and Development SFR Sodium-cooled Fast Reactor SWU Separative Work Unit Th Thorium TRU Transuranics TRL Technology Readiness Level U Uranium UOX Uranium Oxide

Fuel Cycle Data Package Template Description November 30, 2012 1

FUEL CYCLE OPTIONS CAMPAIGN

FUEL CYCLE DATA PACKAGE TEMPLATE DESCRIPTION

1. INTRODUCTION AND BACKGROUND The United States Department of Energy’s Office of Fuel Cycle Technologies (FCT) performs research and development (R&D) on nuclear fuel cycle technologies that have the potential of being deployed in the country in the future. Budgetary constraints dictate that available resources are applied selectively to R&D efforts having the greatest potential benefits and returns on investment. Consequently, the Office periodically reviews and prioritizes its R&D activities. An evaluation and screening process for fuel cycle options has been developed and is being refined to assist in such prioritization efforts. For future evaluations and screenings, the FCT Office is developing an electronic fuel cycle catalog that can be a repository of information on fuel cycle options and associated technologies [Catalog 2011]. At the current time, the so-called Fuel Cycle Data Package (FCDP) is being used as the mechanism to collect the available technical information that would be used to populate the fuel cycle catalog. An FCDP template is being defined to provide instructions on the required data and format of the data.

As currently designed, the FCDP template for characterizing fuel cycle options provides descriptions for two sets of files, namely the System Datasheet and Technology Datafiles. Both the System Datasheet and the Technology Datafile(s) will contain references to the systems analysis reports/calculation files and associated technology reports, respectively, on which they are based. The data contained in the System Datasheet will be used for the evaluation and screening of fuel cycle options, while those on the Technology Datafiles are for informational purposes only. This document describes the high-level structure of the FCDP template. The document is designed to support the FCDP preparers and reviewers by providing additional guidance on the overall content of the FCDP as well as the information to be included in specific fields of the template. This document will also control the latest version of the master FCDP template. The master FCDP template with examples of the data requested for these files are provided in Attachment A, including the general instructions in Appendix B.

1.1 Key Terminology To facilitate an understanding of the FCDP template, its structure, and the categories of fuel cycle options for which FCDPs will be developed, it is important to understand the key terms presented in this section.

1.1.1 Nuclear Fuel Cycle Option

A nuclear fuel cycle option is defined as a set of technologies and nuclear materials operating together in a unique and specific system arrangement to perform all the functions, from obtaining initial fuel resources through ultimate disposal of fuel and/or wastes, needed to produce useful energy. The “fuel cycle option” is also referred to as “nuclear energy system” in some reports.

1.1.2 Fuel Cycle Strategy

For the purposes of the catalog and the FCDP template, fuel cycle options which are being defined are placed into one of three categories with respect to the strategy for managing fuel discharged from the Nuclear Power Plant/Transmutation (NPPT) systems used in the fuel cycle. These categories are No Recycle, Limited Recycle, and Continuous Recycle based on the following definitions:

No Recycle or Once-Through – A fuel cycle strategy in which the discharged fuel from a NPPT system (reactor or other transmutation system) is not recycled for further use. A particular fuel cycle

Fuel Cycle Data Package Template Description 2 November 30, 2012

option in this strategy may exclude chemical separations, or may include some degree of separation or partitioning for waste management purposes, but without further transmutation. The fuel may stay in the original NPPT system for multiple irradiation cycles (e.g., as in shuffling) but after it is discharged, the nuclear material is not re-used again in the same or different NPPT system.

Limited Recycle – A fuel cycle strategy in which at least some of the material in discharged fuel is recycled back into a NPPT system at least once, but only for a limited number of times, to provide additional energy generation, non-proliferation, and/or waste management benefits. After limited recycle, the material is either disposed of directly as discharged fuel, or partitioned for waste management purposes prior to disposal.

Continuous Recycle– A fuel cycle strategy in which at least the primary fissile isotope(s) are recovered from discharged fuel, typically in combination with other elements or isotopes, and are continuously recycled to provide additional energy generation, non-proliferation, and/or waste management benefits. Discharged fuel is not directly disposed, with the possible exception of a small fraction of material potentially used in transmutation targets.

It should be noted that the template and catalog will also include a field which will allow categorization according to the fuel cycle strategies described in the Nuclear Energy R&D Roadmap [DOE-NE 2010], namely once-through, modified open, and full recycle fuel cycles. The above categories were established to promote clarity when categorizing options. The mapping of the strategies listed in the R&D Roadmap to those above is as follows:

Once-through fuel cycles would fall under the No Recycle category.

Modified open fuel cycles could fall under either the No Recycle or Limited Recycle categories, depending on the concept.

Full recycle fuel cycles would fall under the Continuous Recycle category.

1.1.3 Fuel Cycle Stages

A stage is defined as the collected set all the fuel cycle functions from fuel preparation to waste disposal needed to support operation of a single type of NPPT system using one or more particular fuel types. Any treatment or chemical separations of discharged fuel from an NPPT system and the associated wastes are included in the same stage as the NPPT which discharged the fuel. A fuel cycle option can be described by identifying the key technologies used in each stage and how the stages interrelated. At the current time, the FCDP focuses on fuel technologies, NPPT technologies, and reprocessing/separations technologies. Details on technologies used in the fuel cycle front-end, in transport and storage, and in back-end waste forms and repository/disposal functions are not currently specified in the FCDP, but could be added in the future.

A fuel cycle option may have one or more stages, in series and/or parallel with each other as shown in Figure 1. A change from one stage to the next occurs when there is a change in the NPPT system technology or a significant change in its equilibrium core fuel type(s) or in its operating conditions. Stages are numbered (1, 2, 3, etc.) to differentiate the NPPT system or equilibrium fuel used in one stage from another. NPPT systems may include critical reactors or externally driven system (EDS) used for power production and/or material irradiation purposes.

A single-stage fuel cycle option can involve recycling discharged fuel back into the same NPPT system with multiple fuel types (such as driver fuel and blanket fuel in a fast reactor, or seed and blanket fuel in a PWR). In this case and others where fuel is recycled back into either the same or a different NPPT system, the template requests all information on the equilibrium charge(s).


An additional stage can also be used to represent a change in the equilibrium-operating mode of the NPPT system at some point during the life of the system to a significantly different fuel type and/or core configuration. For example, an LWR could be operated using low-enriched uranium (LEU) oxide fuel for many years and then transition to an equilibrium core which consists of uranium oxide (UOX) fuel and uranium-plutonium mixed oxide (MOX) fuel. This 2-stage fuel cycle option could be modeled as a single-stage with portions of the core, representing the all UOX first stage and all MOX 2nd stage.

Another example could be a fast reactor system that operates in a “break-even” mode at a conversion ratio near unity (CR~1) for many years during an expansion phase of nuclear power, and later operates in a “burner” mode with CR <1. To support defining such possible strategies or options, additional fuel cycle stages can be designated as necessary. This is in effect using static snapshots to define fuel cycle options in a stair-step manner. Data for use in either steady-state or dynamic systems analysis can be included or referenced in FCDPs.

Figure 1. Illustration of Fuel Cycle Stages in Particular Fuel Cycle Options

For the 2013 fuel cycle evaluation and screening, transitions in time (dynamic scenarios) to deploy subsequent stages or to phase out earlier stages will not be part of the evaluation scope. Instead, fuel cycle options will be considered at steady-state equilibrium conditions where the mass flow rates are balanced between stages and invariant with time. However, future evaluations will examine dynamic scenarios involving time dependent variations of material flows from one stage to another.

Stage 1 Stage 2

Stage 1 Stage 2

Stage 3

Stage 4

Stage 1 Stage 2 Stage 3

(a) (b) (c)


2. TEMPLATE DESCRIPTION

2.1 General Structure The FCDP consists of files of two kinds: System Datasheet (a single file) to provide fuel cycle option data and the Technology Datafile(s) to provide wiki-style information on specific technologies (multiple files for the different technologies utilized in assembling the fuel cycle option). The contents of each file are identified below and their descriptions are provided in Sections 2.3 and 2.3, respectively.

The System Datasheet will contain information specific to the fuel cycle option, such as:

Summary description

Material flow diagram

High-level parameter data

Fuel cycle performance summary – evaluation criteria and metrics

Mass flow data

Transition and scenario analysis data (via reference to extent available)

References.

A Technology Datafile contains wiki-style information on a specific technology. A technology could be fuel type(s), NPPT system, reprocessing/separations, etc. More than one Technology Datafiles will be used to provide background information on the technologies supporting a fuel cycle option. A Technology Datafile can link to other Technology Datafile(s). For NPPT and reprocessing/separations, the Technology Datafiles contain generic high-level information (e.g., Pressurized-Water Reactor) and the technology variations are described in the technology summary description. Ideally, a Technology Datafile would be developed with input from technology campaigns or may be created by a technology campaign. The Technology Datafile should contain three sections and references. The sections are:

Summary description

Schematic diagram and pictures

High-level parameter data

References.

It is noted that the documents supporting the System Datasheet and Technology Datafiles, such as metrics/criteria calculation notes and the charge and discharge nuclide information, should be provided as reference documents.

2.2 System Datasheet The System Datasheet will contain information specific to a fuel cycle option. Attachment A contains as example a file having the System Datasheet that was developed for a three-stage system that includes a PWR-UOX system in the first stage, PWR-MOX system in the second stage, and SFR-Burner-metallic system in the third stage. The following is a general summary of the contents of the System Datasheet. The example of System Datasheet is provided in Appendix A.1 and more detailed descriptions of each field and any appropriate instructions for completion of that field are provided in Attachment B. The review procedures are provided in reference [Taiwo 2012].

Summary Description: This datasheet (first page of the file) provides a title and other identification and documentation information along with summary information and a high level qualitative description for each stage. As a minimum, this summary sheet should include clear information on the fuel cycle option,


discussing the objectives of the fuel cycle option. The types of NPPT systems, fuel types, and reprocessing/separation approaches used in the option should also be briefly discussed. If there are known deficiencies in the fuel cycle option or modeling approaches, they should be briefly summarized.

Material Flow Diagram: The sheet provides a space for the user to supply a sketch or picture showing the relationships of the stages and the material flow. One can create a picture from the notional picture shown in the template. The idea is to show the major stages and respective recycling of fuel products or transmutation of materials within and between the stages. Technologies on this sheet for each of the primary functions need to be clearly identified by name using a standard convention. This information would be used for linking to the Technology Datafiles in the fuel cycle catalog. If mass quantities are known, those would be presented in the later optional sheet entitled Mass Flow Data.

High Level Parameter Data: In this datasheet, high level information specific to the fuel cycle is provided. Information is given for the NPPT system, the fuel technology (information at the fuel type level), and reprocessing/separations technologies. The fact that a NPPT system in a given stage can use more than one fuel or utilize more than one reprocessing/separations technologies complicates the construction of the Table. Consequently, there are separate sub-sheets for each of the fuel cycle functions. The wiki-style, generic information of each technology in this datasheet is provided by Technology Datafiles but for evaluation purposes, the specific values used in the fuel cycle option are selected and organized here with entries pertinent to the fuel cycle option for three of the major fuel cycle functions. Consideration will be given in the future on the need for specifying relevant system data on other fuel cycle functions in this sheet, as it becomes necessary.

Fuel Cycle Performance Summary - Evaluation Criteria and Metrics: This sheet was originally intended to provide quantitative data on integral fuel cycle performance as opposed to the high level parameter data that provides data on the major components of the fuel cycle system. However, it was decided not to use this sheet because the qualitative information needed to support the fuel cycle evaluation and screening will be evaluated by the Evaluation and Screening Team (EST) and the quantitative metrics that can be calculated using the information in FCDPs will be provided through separate reports.

Mass Flow Data: This sheet provides the mass flow information of the nuclear materials from the whole nuclear fleet at the equilibrium state of the specific fuel cycle option. It contains the normalized masses of feed materials (with negative sign) and product materials (with positive sign) through each technology function used in each stage. In this table, the sum of each row indicates the normalized masses of the required resource (if negative) or the produced nuclear materials (if positive), and the loss from each technology is provided at the bottom of each column.

Transition and Scenario Analysis Data (Currently Optional): This sheet is currently an optional location where the user can provide any transition or scenario fuel cycle information. This information can be qualitative and/or quantitative.

References: This sheet contains a table of the references along with any distribution restriction on those references. Electronic copies of references are to be provided along with the completed System Datasheet.

2.3 The Technology Datafile A Technology Datafile contains wiki-style, generic information on a specific technology. The information is fuel cycle option and stage independent. A technology could be a NPPT system type, mining approach, enrichment technique, fuel type, reprocessing/separations approach, waste form, disposal approach, etc. The particular technologies used by a fuel cycle option are identified in the System Datasheet. Currently Technology Datafile templates have been created for fuel technology, NPPT technology, and


reprocessing/separations technology. Examples are provided in Attachments A.2 – A.4 and instructions for completing the datafiles are given on Attachment B.2 - B.4.

As many Technology Datafiles as needed to provide background information for a fuel cycle option must be provided. Once a Technology Datafile exists, however, it should not be reproduced. For example, the NPPT technology on the conventional Pressurized Water Reactor (PWR) will be included in many fuel cycle options, but only one Technology Datafile will exist for the relevant conventional PWR technology. Thus, the creator of a new FCDP should review the existing Technology Datafiles to determine applicability and avoid duplication. If the technology for the new fuel cycle option is a significant deviation from an existing one, then a new Technology Datafile, with a new unique identifier should be developed. This new file must also be reviewed by the review procedures provided in the Preparation, Review and Acceptance Procedure of Fuel Cycle Data Package [Taiwo 2012].

The following is a general summary of the contents of the Technology Datafiles, which all have the same general format with more detailed descriptions for each technology area and each field within that template. The specific instructions for completion of the fields in the Technology Datafiles are included in Attachment F-H.

Summary Description: This first page provides a title and other identification and documentation information along with summary information and a high level qualitative description for the technology. Since a Technology Datafile contains generic high-level information, in particular for the NPPT and reprocessing/separation technologies, description of the various possible uses of the technology is required in the summary description.

Schematic Diagrams and Pictures: This sheet provides a location to present diagrams and pictures of the technology. Thus, it may be diagrams of the fuel, a reactor site, reprocessing/separations flow diagrams, etc.

High Level Parameter Data: This is a summary table that provides high-level descriptive information of key parameters such as typical values, ranges, etc.

References: This sheet contains a table of the references along with any distribution restriction on those references. Electronic copies of all references are to be provided along with the completed Technology Datafile.

2.4 Technology Readiness Level Description An important entry in the template that is requested in many sheets is information concerning Technology Readiness Levels (TRLs) and specifics about what it takes to achieve industrial scale (often signified by a TRL of 9). TRLs provide an assessment of the maturity of a particular technology and a consistent comparison of maturity between different types of technologies, resulting in an evaluation of the uncertainty and programmatic risk in developing different technologies.

The methodology for determining TRLs and their application for fuel cycle options and associated fuel cycle technologies is under current development. Since multiple technologies are combined together in a specific fuel cycle option, the TRL of a specific fuel cycle option could be determined qualitatively rather than quantitatively. Thus, for consistency, the Evaluation and Screening Team (EST) will determine the TRL of each specific fuel cycle option. However, the FCDP creator can determine the TRL of a specific fuel cycle technology based on the general guidance contained in Table 1 which was used in the initial (pilot) screening of fuel cycle options [DOE-NE 2011].


Table 1. Technology Readiness Level (TRL) Definitions and Descriptions

Relative Level of Technology Development

TRL TRL Definition Abbreviated Description

System Operations

9 Actual system operated over the full range of expected conditions.

The technology is in its final form and operated under the full range of operating conditions.

System Commissioning

8 Actual system completed and qualified through test and demonstration.

The technology has been proven in its final form and under expected conditions.

7 Full-scale, similar (prototypical) system demonstrated in relevant environment.

This represents a major step up from TRL 6, requiring demonstration of an actual system prototype in a relevant environment.

Technology Demonstration

6 Engineering/pilot-scale, similar (prototypical) system validation in relevant environment.

Engineering-scale models or prototype are tested in a relevant environment.

5 Laboratory scale, similar system validation in relevant environment.

The basic technology components are integrated so that the system configuration is similar to (matches) the final application in almost all respects. Technology

Development 4

Component and/or system validation in laboratory environment.

The basic technological components are integrated to establish that the pieces will work together.

Research to Prove Feasibility

3 Analytical and experimental critical function and/or characteristic proof of concept.

Active research and development (R&D) is initiated.

2 Technology concept and/or application formulated.

Once basic principles are observed, practical applications can be invented. Applications are speculative, and there may be no proof or detailed analysis to support the assumptions. Examples are still limited to analytics studies. Basic

Technology Research

1 Basic principles observed and reported.

This is the lowest level of technology readiness. Scientific research begins to be translated into applied R&D.


ATTACHMENT A – FCDP MASTER TEMPLATE EXAMPLES This attachment contains the master template examples for the System Datasheet (Attachment A.1), Nuclear Power Plant/Transmutation Technology (NPPT) Datafile (Attachment A.2), Fuel Technology Datafile (Attachment A.3), and the Reprocessing/Separations Technology Datafile (Attachment A.4). Included in this master template are example data, which are provided for information purposes only and not necessarily the final data for the example utilized. The following example of a Fuel Cycle Data Package (FCDP) is for a three-stage full recycle fuel cycle option, “PWR-UOX to PWR-MOX and to SFR for full recycling,” which would consists of a single set of System Datasheet, two NPPT Technology datafiles, three Fuel Technology Datafiles, and two Reprocessing/Separation Technology Datafiles, with one of each type of datafile included as an example. It is noted that the FCDP template is a living document: i.e., the template and metrics/criteria could be revised as needed per the progress of the Fuel Cycle Option campaign activities.

ATTACHMENT A.1 - Systems Datasheet Example The following pages contain an example of the System Datasheet for the fuel cycle option MC04B, “PWR-UOX to PWR-MOX and to SFR for full recycling”.

Fuel Cycle Data Package (FCDP) System Datasheet PWR-UOX/PWR-MOX/SFR

FCDP Template Rev 0.4: November-30-2012 9

Summary Description

Fuel Cycle Option No. (Evaluation Group Nomenclature)

MC04B (C-T/F-U-TRU-Y)

Roadmap Strategy

Full Recycle Recycle Strategy

Continuous Recycle

Fuel Cycle Option Title PWR-UOX to PWR-MOX and to SFR for full recycling

Revision number Revision remarks

Rev. 0.0 Rev. 0.1 Rev. 0.2

Initial Revision Revised due to changes of references and FCDP template version (rev. 0.1) Template Revision

High-level Objective(s)

1) Produce electricity 2) Manage waste disposal by partitioning and/or transmuting actinide isotopes 3) Can utilize existing thermal reactor infrastructure 4) Provide input as needed (new proposed HLO)

No. of Stages 3 Stage Description

Stage 1 UOX fuel PWR

LEU oxide fuel is irradiated in PWR until burnup of 50 GWd/t. Discharge fuel (DF) is stored and then reprocessed. Recovered plutonium (Pu) and uranium (RU) are sent to Stage 2. Recovered minor actinides (MA) are sent to Stage 3. Fission products (FPs) and excess RU are stored and then sent to a disposal site.

Stage 2 MOX fuel PWR

Recovered Pu and RU from Stage 1 are used to make mixed (uranium/plutonium) oxide fuel. The Pu/RU mixed oxide fuel is irradiated to a burnup of 50 GWd/Mt in PWRs. Discharged fuel is stored and then reprocessed. Recovered TRU and RU are sent to Stage 3. FPs and excess RU are stored and then sent to a disposal site.

Stage 3 U/TRU metallic fuel SFR Burner

Recovered TRU and RU from Stage 3, recovered TRU from Stage 2, and recovered MA and RU from Stage 1 are used to make U/TRU metallic fuel. The metallic fuel is irradiated to a burnup of 100 GWd/MT in SFR burner with a medium TRU conversion ratio of 0.82. Discharged fuel is stored and reprocessed for recycle back into stage 3. FPs are stored and then sent to a disposal site.

Prepared by Name (Affiliation) Date TBD

Internally Reviewed by Name (Affiliation) Approval Date TBD

Externally Reviewed by Name (Affiliation) Approval Date TBD

Accepted by FCDP Team Leader Acceptance Date TBD

Fuel Cycle Data Package (FCDP) System Datasheet PWR-UOX/PWR-MOX/SFR PWR-UOX to PWR-MOX to SFR for Full Recycling


Note: Only primary material flows are shown. Material flows from imperfect separations (losses), low-level waste, and other secondary streams that will be produced in performing various fuel cycle functions are not shown.

Legend: NU = Natural Uranium DF = Discharged Fuel PWR = Pressurized Water Reactor = Nuclear Waste Disposal DU = Depleted Uranium FP = Fission Products SFR = Sodium Fast Reactor = Nuclear Material Storage LEU = Low-enriched Uranium TRU = Transuranics UOX = Uranium Oxide = Nuclear Material Transport RU = Recovered Uranium MA = Minor Actinides MOX = Mixed Oxide / = Co-separated products

NU FT-1.1 LEU Oxide driver fuel

LEUSep-A UOX Separations

DFPu/RU

MA

RU,FP

To ST-2To ST-3

Stage 1 (ST‐1)

DU

From ST-1 FT-2.1 Mixed Oxide driver fuel

Pu/RU Sep-B MOX Separations

DFRU,TRU

RU,FP

To ST-3Stage 2 (ST‐2)

Pu/RU

From ST-2 FT-3.1 Metallic driver fuel

TRU/RU Sep-C Metal Separations

DFRU, TRU

FP

To ST-3Stage 3 (ST‐3)

RU, TRU

From ST-3RU, TRU

SFR

PWR

PWR

Fuel Feed Material from Nature or other Stage

Nuclear Fuel by Fuel Type (FT)

Nuclear Power Plant/ Transmutation (NPPT)

Reprocessing/ Separations

Back‐end Storage and Disposal

MA From ST-1

(with MA)

Material Flow Diagram

Fuel Cycle Data Package (FCDP) System Datasheet PWR-UOX/PWR-MOX/SFR PWR-UOX to PWR-MOX to SFR Burner for Full Recycling


Technology category

Parameter Stage Number

1 2 3 4

Nu

clea

r P

ower

Pla

nt/

T

ran

smu

tati

on (

NP

PT

)

NPPT Technology Identifier PWR PWR SFR-Burner

Core Configuration PWR with UOX PWR with MOX SFR with

U-TRU-Zr

Core Thermal Power, MWth 3000 3000 1000

Net Thermal Efficiency, % 33 33 40

Capacity Factor, % 90 90 85

Specific Power Density, MW/IHHMT* 34 34 63.1

Technology Readiness Level (TRL) ** TBD TBD TBD

Brief Justification of TRL: TBD TBD TBD

Electrical Energy Generation Sharing, % 38.1 4.1 57.8

Reference(s) 1, 2 1, 2 1,2

* IHMMT: Initial Heavy Metal Metric Ton ** TRL will be evaluated by Evaluation Screening Team (EST), but input may be provided.

High Level Parameter Data



Technology category

Parameter Fuel Type Number (1st digit denotes Stage No.)

1.1 2.1 3.1 N

ucl

ear

Fu

el

Fuel Technology Identifier PWR-UOX PWR–MOX SFR-Metallic

Purpose Driver Driver Driver

Chemical Form Oxide Oxide Metal

Physical Form Pin Bundle –

Ductless Pin Bundle –

Ductless Pin Bundle –

Ducted

Average Discharge Burnup, GWd/t 50 50 92.4

Fuel Composition

Initial Nuclear Material(s) LEU Pu/RU TRU/RU

(U-235+ U-233)/Total U, % 4.21 0.79 0.11

Th/Total HM, % 0 0 0

TRU/Total HM, % 0 10.7 19.2

Non-fissionable Target materials n.a. n.a. n.a.

Non-fissionable Target Charge Rate, kg/GWe-yr n.a. n.a. n.a.

Non-fissionable Target Transmutation Fraction, % n.a. n.a. n.a.

Fabrication Losses, % 0.2 0.2 0.2

Separation Process(es) Used as Source n.a. A A,B,C

Enrichment Tailing, % 0.25 n.a. n.a.

Fuel Fabrication Time and Lag before Use in NPPT, years

a) 1.0 a) 1.0 a) 0.2

Fuel Residence Time in Reactor, EFPY 4.1 4.1 4.7

Post Irradiation and Separation (if applicable) Time before Fabrication/Disposal, years

5.0 5.0 a) 0.0

Technology Readiness Level (TRL) b) TBD TBD TBD


Reference(s) 1, 2 1, 2 1, 2

Note: Repeat table if additional columns are required for additional fuel types. a) Values are different from the values assumed in the FCT Fuel Cycle Analysis Assumption Document [Dixon 2012] because the physics calculations

were performed prior to define the assumptions and the difference is judged not to be significant enough to have an important bearing on evaluation and screening results.

b) TRL will be evaluated by Evaluation Screening Team (EST), but input may be provided.



Technology category

Parameter Reprocessing/Separation Processes

A B C

Rep

roce

ssin

g/S

epar

atio

ns

Potential Reprocessing/Separations Approach TBD TBD E-Chem

Separation U, Pu, MA, and FP U, TRU, and FP U/TRU, and FP

Fuel Type Used as Source 1.1 2.1 3.1

Recovery Efficiency (%) & Descriptive Information†

Recovery of 99% for all actinides. All

others (1% actinides and 100% FP) are treated as waste





Technology Readiness Level (TRL)** TBD TBD TBD


Reference(s) 2 2 2

Note: 1) Additional information included in the Material Flow Diagram. 2) Repeat table if additional columns are required for separation of additional fuel types.

† Net plant efficiency – fraction of material that ends up in recycled material or intended waste stream (e.g. excess recovered uranium) ** TRL will be evaluated by Evaluation Screening Team (EST), but input may be provided.



Fuel Cycle Performance Summary – Evaluation Criteria and Metrics

This sheet currently not used. The qualitative information needed to support the fuel cycle evaluation and screening will be evaluated by the Evaluation and Screening Team (EST), while the quantitative metrics that can be calculated using the information in FCDPs will be provided through separate reports.



Mass Flow Data

Stage 1 2 3 Sum b)

Technology Fuel NPPT Rep/Sep Fuel NPPT Rep/Sep Fuel NPPT Rep/Sec

Electricity, GWe-yr/yr 41.3 4.5 54.3 100

Feed or product of nuclear materials (metric ton) a)

Natural resource

NU - 7,766.2 - 7,766.2Th -

Products from fuel or NPPT technology

DU + 6,860.3 + 6,860.3U + 904.1 -904.1 + 87.0 -87.0 + 432.8 - 432.8 0.0Pu + 10.5 -10.5 + 92.9 - 92.9 0.0MA + 10.2 - 10.2 0.0DF + 904.1 -904.1 97.5 -97.5 + 535.9 -535.9 0.0

Products from Rep/Sep technology

RU + 836.7 - 87.2 + 83.1 - 433.6 + 383.6 + 782.5Pu + 10.5 - 10.5 +7.7 - 93.1 + 85.3 - 0.1MA + 1.2 + 0.8 - 10.2 + 8.3 + 0.1FP + 46.7 + 4.9 + 53.4 + 105.0

Loss + 1.8 + 9.0 + 0.2 + 1.0 + 1.1 0.0 + 5.4 + 18.5

References 2 2 2 a) Mass flow in metric ton was developed to produce 100.0 GWe-year from whole nuclear fleet and the signs (-) and (+) indicate the feed and production to or

from each technology category, respectively. b) Summation of each row indicates the required resource (-) or produced nuclear materials (+) per year to generate electricity of 100 GWe-yr.



Transition and Scenario Analysis Data (Provide references, if any, and brief description)

This sheet is currently optional, but the user can provide any available transition or scenario fuel cycle information.



References

Reference Distribution Restrictions

1. T. A. Taiwo, E. A. Hoffman, and T. K. Kim, Core Transmutation Data for Double-Tier Scenario Studies –Scenario 2, Intra-laboratory Memo, Argonne National Laboratory, Aug. 22, 2007.

None

2. T. K. Kim, Assessment of Fuel Cycle Parameters of PWR-UOX to PWR-MOX to SFR-Burner Continuous Recycling Fuel Cycle Option, Intra-Laboratory Memo, Argonne National Laboratory, Feb. 28, 2012.

None

Note: If possible, reference with distribution limitations should be avoided.


18 FCDP Template Rev 0.4: November-30-2012

ATTACHMENT A.2 – Nuclear Power Plant/Transmutation Technology Datafile An example of a Nuclear Power Plant/Transmutation (NPPT) technology datafile for the fuel cycle option MC04B, “PWR-UOX to PWR-MOX and to SFR for full recycling,” is provided on the next pages

Fuel Cycle Data Package (FCDP) Technology Datafile Nuclear Power Plant/Transmutation

Pressurized Water Reactor (PWR)

FCDP Template Rev 0.4 : November-30-2012

19

Summary Description

Technology Category Nuclear Power Plant/Transmutation (NPPT) Technology

Technology Option No. TBD NPPT Technology Identifier PWR

Technology Title Pressurized Water Reactor (PWR)

NPPT Group Thermal system

Coolant Type Light Water Neutron Balance Critical


Rev. 0.0 Rev. 0.1

Initial Revision Reflected FCDP development feedbacks

Description of Fuel Cycle Technology

This is the state of the art commercially deployed Pressurized Water Reactor (PWR). PWR technology is Light-Water Cooled Thermal Reactor (LWR) technology where the pressure/temperature in the primary coolant system is designed to prevent bulk boiling. The primary coolant flows through a steam generator where the nuclear heat is transferred to the secondary side to produce the steam to drive a conventional steam generator. The power level, power density, and other parameters vary substantial depending on the design. The power rating is typically around 1 GWe, but varies from somewhat less than 0.4 GWe to around 1.5 GWe depending on the specific design and desires of the customer. A wide range of fuel and targets have been designed for utilization in this type of reactor. Most currently operate on LEU oxide fuel with average discharge burnups of approximately 50 MWd/kg. However, there is experience with Pu-MOX fuel. Fuel and targets including Th-based, TRU, long-lived FPs, extended lifetime fuels, heterogeneous fuel assemblies in a driver and target/blanket type arrangement, and many other variations (for instance, CORAIL, CONFU, etc.) have been considered in varying levels of detail for irradiation in PWRs.

Prepared by Name (Affiliation) Date September 02, 2011

Internally Reviewed by Name (Affiliation) Approval Date September 10, 2011

Externally Reviewed by Name (Affiliation) Approval Date September 27, 2011





Schematic Diagrams and Pictures

Elevation View of Pressurized Water Plant (left) and Cutaway View of Reactor Vessel (right)

ROD TRAVELHOUSING

INSTRUMENTATIONPORTS

THERMAL SLEEVE

LIFTING LUG

CLOSURE HEADASSEMBLY

HOLD-DOWN SPRING

CONTROL RODGUIDE TUBE

CONTROL RODDRIVE SHAFT

INLET NOZZLE

CONTROL RODCLUSTER (WITHDRAWN)

ACCESS PORT

REACTOR VESSEL

LOWER CORE PLATE

CONTROL RODDRIVE MECHANISM

UPPER SUPPORTPLATE

INTERNALSSUPPORT

LEDGE

CORE BARREL

SUPPORT COLUMN

UPPER COREPLATE

OUTLET NOZZLE

BAFFLE RADIALSUPPORT

BAFFLE

CORE SUPPORTCOLUMNS

INSTRUMENTATIONTHIMBLE GUIDES

RADIAL SUPPORT

CORE SUPPORT



FCDP Template Rev 0.4 : November-30-2012

21


Parameter Value (or range) Ref.

Core Thermal Power, MWth 1200 – 4500 4 (page #)

Net Thermal Efficiency, % 33-35% 2 (page #)

Unit electric generating power, MWe 400 – 1500 4 (page #)

Average Annual Reactor Capacity Factor, % 80 - 90 1 (page #)

Reactor Operational Lifetime, years 30 - 60 1 (page #), 2 (page #)

Technology Readiness Level (TRL - scale of 9)* 9 1 (page #)

Brief Justification of TRL: Commercial Technology n.a.

Time to achieve TRL of 9, years 0 n.a. * Highest TRL achieved




References


1. 2010 – 2011 Information Digest, NUREG-1350, Volume 22, U.S. Nuclear Regulatory Commission (2010) - http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1350/.

None

2. Electric Power Annual 2009, DOE/EIA-0348, U.S. Energy Information Administration (2011). None

3. The Westinghouse AP100 Advanced Nuclear Plant, Westinghouse Electric Co., LLC None

4. Nuclear News, American Nuclear Society (March 2011) None

Note: If possible, references with distribution limitations should be avoided. No classified references.


ATTACHMENT A.3 - Fuel Technology Datafile The following is an example of a fuel technology datafile for the fuel cycle option MC04B, “PWR-UOX to PWR-MOX and to SFR for full recycling.”

Fuel Cycle Data Package (FCDP) Technology Datafile Nuclear Fuel

PWR UOX Driver Fuel


Summary Description

Technology Category Nuclear Fuel Technology

Technology Option No. TBD Fuel Technology Identifier PWR-UOX

Technology Title PWR UOX Driver Fuel

Chemical form Oxide Fuel Structure Container Cladding


Rev. 0.0 Rev. 0.1



Oxide fuel is composed of ceramic fuel pellets placed in fuel rods that are combined into fuel assemblies. A fuel pellet is a thimble-sized ceramic cylinder consisting of heavy metal in oxide form. The fuel rods are long, slender, zirconium metal alloy sealed pressure tube with the pellets stacked inside held in place by springs to allow for a large fission gas plenum to accommodate the release of some of the fission gases. The fuel assembly is a structured group of fuel rods, control rod guide tubes, and a central instrument thimble tube held in place by a series of Inconel grids along with hardware above and below the fuel pins to hold the assembly in place, for moving the assembly, coolant flow, etc. Current operation experience allows for average fuel assembly burnups of approximately 5%. Pellets are chamfered on the corners to reduce stress on the fuel rod, manufacture at approximately 95% of theoretical density to accommodate fission gases within the pellet, and smear density of approximately 90%.

Prepared by Name (Affiliation) Date September 02, 2011





PWR UOX Driver Fuel

FCDP Template Rev 0.4: November-30-2012

25


Schematics of Oxide Fuel Pellet (left), sample fuel stack (center) and assembly [ref 3] (right)


PWR UOX Driver Fuel



Parameter Value (or range) Ref.

Fuel Primary Purpose Driver n.a.

Initial Fuel Fissile Material Type* LEU n.a.

Initial Fuel Fertile Material Type** n.a. n.a.

Fuel Non-fissionable Target Material (e.g. LLFP) n.a. n.a.

Fuel Physical Form (Pellet, particle, etc.) Pellet 2 (page #)***

Bonding Material Helium 2 (page #)

Assembly Design Grid-spacer pin bundles 2 (page #)

Duct Ductless 2 (page #)

Cladding/Duct Material Zr Alloy 2 (page #)

Design Maximum Burnup, FIMA or target transmutation fraction, %

6 - 7 2 (page #)

Heavy metal composition

(U-235+ U-233)/Total U, % <5 2 (page #)

Th/Total HM, % 0 2 (page #)

TRU/Total HM, % 0 2 (page #)

Fabrication Technology Contact handled

Fabrication Losses % <1 Assumed

Fabrication Time, years 0.5 - 1 Assumed

Enrichment Tailing, % 0.2 – 0.4 Assumed

Fuel Lifetime Limitations Normal commercial reactor conditions allow operation up to approximately 60 MW-d/kg average discharge burnup

TBD

Time interval between fuel fabrication and fuel use, years 1 - 2 Assumed

Technology Readiness Level (TRL - scale of 9)**** 9 1 (page #)

Brief Justification of TRL: Commercial Technology n.a.

Time to achieve TRL of 9, years 0 n.a. * Material containing fissile material and not isotopes in fresh fuel (e.g., LEU, Pu, or none for breed and burn fuels) ** Materials added to the fuel material (e.g., none for LEU fuel, Th for LEU/Th fuel, DU or RU in MOX fuels) *** Provide page number if possible **** Highest TRL achieved


PWR UOX Driver Fuel


27

References


1. The Westinghouse AP1000 Advanced Nuclear Plant, Westinghouse Electric Co., LLC, www.AP1000.westinghousenuclear.com (2007).

None

2. Fuel Design Data, Nuclear Engineering International, September 2004, p26-35, Global Trade Media (2004)

None

3. http://www.nrc.gov/reading-rm/basic-ref.html None



ATTACHMENT A.4 – Reprocessing/Separations Technology Datafile The following is an example of a reprocessing/separations technology datafile for the fuel cycle option MC04B, “PWR-UOX to PWR-MOX and to SFR for full recycling.”

Fuel Cycle Data Package (FCDP) Technology Datafile Reprocessing/Separations

Aqueous Separations: UREX+


Technology Category Reprocessing/Separations Technology

Technology Option No. TBD Reprocessing/Separations Technology Identifier

UREX+

Technology Title Aqueous Separations: UREX+ and associated waste forms

Separation Process Aqueous


Rev. 0.0 Rev. 0.1



The generic name UREX+ reflects a design that initially extracts uranium (U) and technetium (Tc), which are subsequently separated by ion exchange, and followed by additional processing to recover transuranic (TRU) and fission product (FP) elements in different combinations. UREX is generally followed by sequestration of cesium and strontium (Cs/Sr). The major variants are then distinguished by the ensuing separation of the balance of the FPs from the TRU elements. UREX+ was intended primarily to provide options for the processing of spent nuclear fuel without separating a pure plutonium stream. UREX+1 maintains the TRU elements as a group, while the lanthanide (Ln) and non-lanthanide FPs are recovered separately. UREX+2 arranges these into three products: Pu/Np, Am/Cm/Ln, and the remaining non-Ln FPs. UREX+3 also recovers Pu/Np, but further separates Am and Cm from the Ln FPs. Finally UREX+4 adds the separation of Am from Cm to the UREX+3 process. There are minor variations of each UREX+ technology both in terms of processing and in terms of products generated, specifically variants that recover U with the Pu/Np-bearing streams. All of the UREX+ process variants were intended to provide the products needed for specific applications. For example, the UREX+3c process is intended for LWR recycle fuel, while the UREX+1a process is intended for FR recycle fuel; these two variants have been demonstrated at laboratory scale. Aqueous processes have exhibited very high recovery efficiencies and very high decontamination levels. Though the more complex extraction chemistries of UREX+ have been shown to be feasible, more work is required to develop, demonstrate, and scale these up, along with the associated peripheral processes. The waste forms are TBD.

Prepared by Name (Affiliation) Date August 30, 2011



Accepted by FCDP Team Leader Acceptance Date

Summary Description

Fuel Cycle Data Package (FCDP) Technology Datafile Reprocessing/Separation




Example Process Flow Diagram for UREX+1a showing intended product destinations




UREX+ Process Variant Table showing the products of the different UREX+ processes. The underlying extraction chemistries required

to achieve these separations are not specified as any of several options or combinations may be selected. (Ref. 2)

Fuel Cycle Data Package (FCDP) Technology Datafile Reprocessing/Separation




Parameter Element Recovery Efficiency, % Ref.

Primary Recovered Element and Recovery Efficiency

U 99.5 – 99.9 1 (p. #), 2 (p. #)

Np 99.0 – 99.9 1 (p. #), 2 (p. #)

Pu 99.0 – 99.9 1 (p. #), 2 (p. #)

Am 99.0 – 99.9 1 (p. #), 2 (p. #)

Cm,Bk,Cf 99.0 – 99.9 1 (p. #), 2 (p. #)

Tc >95.0 1 (p. #), 2 (p. #)

Cs/Sr 99.0 – 99.9 1 (p #)

Description of Separation Waste Streams

Tc, Cs/Sr, and non-volatile FP’s. The separated non-Ln FPs may be combined with the Ln FPs in a single waste form or kept as two separate waste forms.

# (p #)

Minimum Cooling Time before Separation, years 1-5 Assumed

Reprocessing/Separation Time, years <2 Assumed

Technology Readiness Level (TRL - scale of 9)* TBD Assumed

Brief Justification of TRL: TBD Assumed

Time to achieve TRL of 9, years >10 Assumed * Highest TRL achieved




33

References


1. D. Olander, Nuclear Fuels – Present and future, Journal of Nuclear Materials, 389, 1-22 (2009) None

2. www.nuclear.energy.gov/pdfFiles/DOENRCUREXSeminar.pdf None



ATTACHMENT B – GENERIC TEMPLATE COMPLETION INSTRUCTIONS

This attachment provides instructions for the fields that must be completed in the System Datasheet and the Technology Datafile(s). For the example provided, which is for a three-stage fuel cycle option, the complete FCDP would have the System Datasheet summarizing the fuel cycle option, three NPPT (reactor) Technology Datafiles, three fuel Technology Datafiles, two separation Technology Datafiles, and all necessary references for these nine sets of data. The information in those files must be completed in accordance with the Preparation, Review and Acceptance Procedure for Fuel Cycle Data Package [Taiwo 2012].

In the following subsections, tables that correspond to pages in the System Datasheet and the Technology Datafile are presented to describe the expected contents of the files. Each row of the table corresponds to a specific field on that sheet. When the field is self-explanatory, no additional information is provided beyond the field name. As needed, a brief description of the field is provided, along with any value restrictions that may apply, and any additional notes to guide the preparer in completing that specific field.

The header must be modified for the appropriate fuel cycle option or technology option by providing the option specific information in the header. The remainder of the header and the footer is template identifier information.

The final section of a System Datasheet or Technology Datafile contains the References. The specific bibliographic references need to be provided along with any specific restrictions on the distribution of this information. Also, all references should be provided in electronic format as part of the complete FCDP as described in more detail in the Preparation, Review and Acceptance Procedure for Fuel Cycle Data Package [Taiwo 2012]. The FCDP will not contain any classified data. As a goal, the FCDP should also not contain any unclassified sensitive information (e.g. Export Controlled or Proprietary data). The preparer may see a benefit or need to include unclassified sensitive data and/or references. In such cases, the FCDP preparer should discuss the matter with the FCDP Development Team Leader.

ATTACHMENT B.1 – System Datasheet Instructions Table B-1 provides a list of all the fields that must be completed for the Summary Description page of the System Datasheet.

The second page of the System Datasheet is the Material Flow Diagram. This figure will show the disposition path for the heavy metal and resulting fission products for the steady-state conditions that would eventually exist at equilibrium (or quasi-equilibrium) conditions. It typically starts with natural uranium (NU) and/or thorium (Th) fuel material and all material flow streams must either go to a specific stage or to disposal. Any streams that may be split, such as depleted uranium (DU), with some going to make recycled fuel and the excess going to waste, should be properly indicated. For example, the disposition of existing stores of DU is uncertain. However, if the LWR once-through cycle were to be the eventual steady-state fuel cycle, then material balances require the DU to be disposed of as waste. This is how it should be indicated on the material flow diagram for any steady state LWR once-through system. The preparer must use the correct symbols which are provided in the examples in this document and in the legend provided on the template. Table B- 2 provides a list of the nomenclature and symbols that are to be utilized in the Material Flow Diagram.

The names within the different technology options (yellow symbols) should clearly link them to the specific technology option and corresponding Technology Datafile. The fuel and separations processes


should include the fuel type number (e.g. FT-1.1) and reprocessing/separation processes letter (e.g. Sep-A), respectively as denoted in the High Level Parameter Data.

The next set of information is the High Level Parameter Data. This information is intended to capture a high-level summary of important information such as performance parameters that describe the specific fuel cycle option in much greater level of detail. This information is split according to the functionality into three separate tables (sub-sheets): 1) Nuclear Power Plant/Transmutation (NPPT); 2) Nuclear Fuel; and 3) Reprocessing/Separations. Each table has multiple columns that provide the parameter data for the threads.

Table B-3 provides a list of all the fields that must be completed for the NPPT High Level Parameter Data table of the System Datasheet. Similar information for the Nuclear Fuel and Reprocessing/Separations High Level Parameter Data tables are provided in Tables B-4 and B-5, respectively.

The next datasheet is the Fuel Cycle Performance Summary -- Evaluation Criteria and Metrics which is in essence the “output” of previous evaluations. This currently is a placeholder.

The next datasheet is the Mass Flow Data. This sheet is a table containing mass flow data within or 1between stages at equilibrium state. The table is structured to start with the natural resources (NU,Th), fuel products, reprocessing/separations products, loss, and the references for that data. The sign of the value has meaning as described in the footer. The data is normalized to 100.0 GWe-yr of energy generation from whole nuclear fleet at the equilibrium state. The signs (-) and (+) indicate the feed and products to or from each technology category, respectively. The columns are arranged by stage each with sub-columns for Fuel, NPPT, and Rep/Sep (reprocessing/separations). The rows are organized by different material streams related to the HM and FP content. The actual rows in fuel and Rep/Sep will likely need to be renamed and rows added or deleted as needed to describe the mass flow. This information is required to calculate some of the metrics and needs to be documented in this table.

The next datasheet is optional information of Transition and Scenario Analysis Data that have previously been analyzed for this fuel cycle option. This currently is a placeholder.


Table B-1. Instructions for Summary Description Data of System Datasheet Field Name Field Descriptions Value Restrictions Notes

Fuel Cycle Option No. (Evaluation Group Nomenclature)

Unique Fuel Cycle Option Number (Evaluation group Nomenclature)

FCDP Coordinator will provide the number based on the Evaluation Group ID number defined in the latest version of the Fuel Cycle Options List document [Todosow 2012]

Roadmap Strategy Nuclear Energy R&D roadmap strategy.

a. Once-through b. Modified Open c. Full Recycle

Recycle Strategy The used fuel recycle strategy.

a. No Recycle b. Limited Recycle c. Continuous Recycle

Fuel Cycle Option Title Option Description

Use value of Option Described in latest version of the Fuel Cycle Options List document [Todosow 2012] if available

Note if this information is not available, use same shorthand description

Revision Numbers Starts at 0.0 This is the revision number for the input data only.

Revision Remarks Brief description of revision

High-level Objective(s)

a. Produce electricity b. Provide or enhance ability

to use natural resources c. Manage waste disposal by

partitioning and/or transmuting actinide isotopes

d. Reduce quantity of plutonium (or strategic SNM) generated per unit energy

e. Can utilize existing thermal reactor infrastructure

f. No enrichment or separation required

g. Provide input as needed (new proposed HLO)

This list is likely to evolve over time, so if new entries are to be added, add them and bring them to the attention of the Document Coordinator for concurrence and inclusion.

No. of Stages

Stage Description

Stage ID Short identification for stage.

Stage #: Fuel type NPPT type

For example: Stage 1 TRU/U metallic fuel SFR

Description

Summary description of the stage material flow diagram for that stage and include fuel type and burnup.

Prepared by Date Internally Reviewed by


Approval Date Externally Reviewed by Approval Date Accepted by FCDP Team Leader Acceptance Date


Table B-2. Material Flow Diagram Nomenclature and Symbols Item Descriptions Notes NU Natural Uranium

LEU Low Enriched Uranium (<20% U-235)

Only refers toU-235 enrichment from natural or recycled uranium

DU Depleted Uranium Tails from Enrichment

Th Natural or recycled thorium

RU Recovered Uranium

Uranium recovered from irradiated uranium based fuels – Uranium-233 from Th-based fuels is identified by U3

U3 Uranium-233

Uranium-233 recovered from Th-based fuels. May include some minor uanium isotopes (e.g. U-232)

DF Discharged Fuel Irradiated fuels requiring recycle or disposal

FP Fission Product Waste Stream

LLFP Long-lived Fission Product

Fission product streams intended for recycle –specifically identify elements recycled

Np,Pu,Am,Cm+ Specific elements Cm+ indicates Cm and all higher actinides than Cm

TRU Lumped transuranics This includes all Pu and MA

MA All TRU except Pu

PWR,SFR, etc. Shorthand for NPPT technology

Be sure to include definition

UOX, MOX, etc. Shorthand for the Fuel technology

Be sure to include definition

Nuclear Waste Disposal

Nuclear Material Interim Storage

Nuclear Material Transport

On-site, off-site, or in-process movement of nuclear materials

/ Single material stream of multiple materials

For example Pu/RU indicates the Pu and RU are in a single product stream

, Separate material streams

For example Pu,RU would indicate that the Pu and RU are in two separate product streams

Note: Additional nomenclature may be required that is not included in this table. Use the same basic format and be sure to include a definition of terminology that may not be clear in the legend of the material flow diagram.


Table B-3. Instructions for NPPT High Level Parameter Data in System Datasheet Field Name Field Descriptions Value Restrictions Notes

NPPT Technology Identifier Short identifier.

Value from associated Technology Datafile.

Exact value from applicable Technology Datafile for file link under Catalog.

Core Configuration Configuration of core assumed in evaluation.

Core Thermal Power, MWth

Net Thermal Efficiency, % Capacity Factor, %

Specific power density, MW/IHMMT

MWt per initial heavy metal metric ton (IHMMT)

Technology Readiness Level TBD

TRL will be evaluated by Evaluation Screening Team (EST).

Brief Justification of TRL TBD Justification will be provided by the EST.

Electrical Energy Generation Sharing, %

Fraction of energy generated for steady state system.

Provide the information along with calculation file.

Reference(s) Specific references for above information.


Table B-4. Instructions for Nuclear Fuel High Level Parameter in System Datasheet Field Name Field Descriptions Value Restrictions Notes

Fuel Type Number x.y x – stage number y – sequential number

Each stage will utilize 1 or more fuel types. For example a breeder reactor will likely have driver fuel and blankets. In that case, single stage system we would need fuels 1.1 and 1.2 to specify the fuels.

Fuel Technology Identifier Short identifier Value from associated Technology Datafile.

Exact value from applicable Technology Datafile for file link under Catalog.

Purpose Primary Fuel Purpose

A. Driver B. Blanket C. Target D. Driver/Target

Driver is for maintaining nuclear reaction. Blanket is for breeding fissile material. Target is for waste management transmutation.

Chemical Form For example oxide, metallic, carbide, etc.

Physical Form For example Pin Bundle – Ductless for PWR fuel.

Average Discharge Burnup, GWd/t

Initial Nuclear Material(s) Specific types of material utilized.

For example, LEU, DU, Pu, TRU, etc. and any combinations of them.

(U-235+ U-233)/Total U, % Th/Total HM, % TRU/Total HM, % Non-fissionable Target materials

Target materials added for waste management purposes, not burnable poisons or other purposes.

Non-fissionable Target Charge Rate, kg/GWe-yr

Non-fissionable Target Transmutation Fraction, %

Fabrications Losses, %

Use the reference value assumed in the latest version of Assumption Document [Dixon 2012] unless not appropriate.

“FCT Fuel Cycle Analsysis Assumption Document,” [Dixon 2012] may not be the most recent one. The latest version could be available from the FCDP Coordinator.

Separation Process(es) Used as Source

Identifies source column letter in Separation Technology table.

Enrichment Tailing, %

Use the reference value assumed in the latest version of Assumption Document [Dixon 2012 unless not appropriate.]

Value could be different if the physics calculations were performed prior to the Assumption Document and if the difference is judged not to be significant enough to have an important bearing on evaluation and screening results.

Fuel Fabrication Time and lag before Use in NPPT, years

Use the reference value assumed in the latest

This is the total time between when product material is


version of Assumption Document [Dixon 2012] unless not appropriate.

considered to be available when it is loaded into a reactor. For recycle cases, product material is considered available immediately following completion of separations. Value could be different if the physics calculations were performed prior to the Assumption Document and if the difference is judged not to be significant enough to have an important bearing on evaluation and screening results.

Fuel Residence Time in Reactor, (EFPY)

Post Irradiation and Separation (if applicable) Time before Fabrication/Disposal, years

Use the reference value assumed in the latest version of Assumption Document [Dixon 2012] unless not appropriate.

This is the total time between when the fuel is discharged from reactor through completion of separations (for recycle cases) or through when it is disposed (for once-through cases). Value could be different if the physics calculations were performed prior to the Assumption Document and if the difference is judged not to be significant enough to have an important bearing on evaluation and screening results.

Technology Readiness Level TBD TRL will be evaluated by the EST.


Reference(s) * HM: heavy metal * EFPY: effective full power year


Table B-5. Instructions for Reprocessing/Separations High Level Parameter Data in System Datasheet

Field Name Field Descriptions Value Restrictions Notes

Column Identifier Sequential alphabetic letters.

Since separations may process fuel from multiple stages, simply using letters to identify the different process avoids confusion.

Potential Reprocessing/Separations Approach

Short identifier. Value from associated Technology Datafile.

Generally, potential Rep/Sep approach is TBD because various Rep/Sep technologies are available to separate materials. However, when a specific process is applied for the fuel cycle option, in that case provide the Rep/Sep approach.

Separation Process A short identifier/description of the specific process being used (e.g. UREX+3c).

Fuel Type Used as Source

Identifies source column number in Fuel Technology table.

For example, FT-1.1, FR-1.2, et al.

Recovery Efficiency (%) & Descriptive Information

Descriptive information of separation summarizing efficiency.

Since the recovery efficiencies may be complex elements specific data, this is intended to be a high level summary of the efficiency and not the detailed elemental information.

Technology Readiness Level

TBD TRL will be evaluated by the EST.


Reference(s) Specific References for above information.


ATTACHMENT B.2 – Nuclear Power Plant/Transmutation Technology Datafile Instructions

Table B-6 provides a list of all the fields that must be completed for the Summary Description page of the Nuclear Power Plant/Transmutation Technology Datafile. Since generic high-level information is described in the NPPT Technology Datafile, it is necessary to discuss the various uses of the technology in different fuel cycle options. The second page of the Technology Datasheet is the Schematic Diagrams and Pictures. These are figure(s) provided for information purposes to describe the technology.

The next set of information is the High Level Parameter Data. This information is intended to capture a high level summary of important information such as performance parameters that describe the specific technology in much greater level of detail. Table B-7 provides a list of all the fields that must be completed for the High Level Parameter table of the NPPT Technology Datafile. When the field is self-explanatory, no additional information is provided beyond the field name. A brief description of the field is provided as appropriate, and any value restrictions that may apply, and any additional notes to guide the preparer in completing that specific field are given.


Table B-6. Instructions for Summary Description Data of NPPT Technology Datafile Field Name Field Descriptions Value Restrictions Notes

Technology Category Nuclear Power Plant/Transmutation.

Technology Option No. Provided by the FCDP Coordinator.

TBD if not provided.

Technology Title

NPPT Group

A. Thermal system B. Intermediate system C. Fast system D. External driven system

NPPT Technology Identifier

Short Unique Technology Identifier.

Provided by Document Coordinator.

Coolant Type

Neutron Balance A. Critical B. Subcritical

Revision Numbers Starts at 0.0

Revision Remarks Brief description of revision


Summary description of the technology.

Include a description of all the different fuel types that are envisioned as potentially being utilized by this technology.

A brief description that will allow users not familiar with this technology to quickly understand it and how it differs from other/similar technologies.

Prepared by The preparer. Date Internally Reviewed by Approval Date Externally Reviewed by Approval Date Accepted by FCDP Team Leader. Acceptance Date


Table B-7. Instructions for High Level Parameter Data in NPPT Technology Datafile Field Name Field Descriptions Value Restrictions Notes Core Thermal Power, MWth

Appropriate range for this technology.

Net Thermal Efficiency, % Appropriate range for this technology.

Unit electric generating power, MWe

Average Annual Reactor Capacity Factor, %

Range for appropriate expected average at equilibrium.

This is not the range for individual reactors in individual years, but the average expected performance for this technology after the technology has fully matured.

Reactor Operational Lifetime, years

Range for appropriate expected average at equilibrium.

This is not the range for individual reactors, but the average expected performance for this technology after the technology has fully matured.

Technology Readiness Level (scale of 9)

Highest TRL achieved. Actual TRL for specific technology implemented will be included in system datasheet for the specific option.

See Table 1 for TRL definitions.

Brief Justification of TRL: Justify the basis for the TRL range specified.

Time to achieve TRL of 9, years



ATTACHMENT B.3 – Fuel Technology Datafile Instructions Table B-8 provides a list of all the fields that must be completed for the Summary Description page of the Fuel Technology Datafile. The second page of the Technology Datasheet is the Schematic Diagrams and Pictures. These are figure(s) provided for information purposes to describe the technology.

The next set of information is the High Level Parameter Data. This information is intended to capture a high level summary of important information such as performance parameters that describe the specific technology in much greater level of detail. Table B-9 provides a list of all the fields that must be completed for the High Level Parameter table of the fuel Technology Datafile. When the field is self-explanatory, no additional information is provided beyond the field name. A brief description of the field is provided as appropriate, and any value restrictions that may apply, and any additional notes to guide the preparer in completing that specific field are given.


Table B-8. Instructions for Summary Description Data of Fuel Technology Datafile Field Name Field Descriptions Value Restrictions Notes Technology Category Nuclear Fuel



Fuel Technology Identifier Short Unique Technology Identifier.

For example PWR-UOX driver is the identifier for standard PWR fuel.

Technology Title

Chemical Form For example, oxide, metallic, carbide, etc.

Fuel Structure Container

Specific description of the container (e.g. cylindrical cladding) for the fuel material.

Revision Numbers Starts at 0.0.

Revision Remarks Brief description of revision.



A brief description that will allow users not familiar with this technology to quickly understand it and how it differs from other/similar technologies.

Prepared by Date Internally Reviewed by Approval Date Externally Reviewed by Approval Date Accepted by FCDP Team Leader. Date


Table B-9. Instructions for High Level Parameter Data in Fuel Technology Datafile

Field Name Field Descriptions Value Restrictions

Notes

Fuel Primary Purpose Usage of fuel: e.g., driver, blanket, etc.

Initial Fuel Fissile Material Type

Material containing fissile material and not isotopes in fresh fuel (e.g., LEU, Pu, or none for breed and burn fuels).

Source of fissile component of driver fuel which may contain a significant fertile content (e.g. Pu).

Initial Fuel Fertile Material Type

Materials added to the fuel material (e.g., none for LEU fuel, Th for LEU/Th fuel, DU or RU in MOX fuels).

Non-inert matrix for driver fuel or breeding material for blankets.

Fuel Non-fissionable Target Material

E.g., long-lived fission products

Fuel Physical Form (Pellet, particle, etc.)

One word or short description of physical form (e.g. pellets, particles).

Bonding Material Material used to bond fuel to cladding: e.g., sodium, helium.

Assembly Design

Duct A. Duct B. Ductless C. n.a.

Cladding/Duct Material Design Maximum Burnup, % FIMA or target transmutation fraction, %

Approximate upper limit on average discharge burnup.

(U-235+ U-233)/Total U, %


This is not the fissile isotope mass fraction but U-235/U or Pu/HM as appropriate.

Th/Total HM, % Appropriate range for this technology. TRU/Total HM, % Appropriate range for this technology.

Fabrication Technology Brief description of the technology such as contact-handled.

Fabrication Losses % Appropriate range for this technology. Fabrication Time, years Appropriate range. Enrichment Tails % Appropriate range.

Fuel Lifetime Limitations

Description of the applicable fuel lifetime limit (e.g. fast fluence, DPA, burnup).

Time interval between fuel fabrication and fuel use, years




See Table 1 for TRL definitions.

Brief Justification of TRL: Justify the basis for the TRL specified. Time to achieve TRL of 9, years



ATTACHMENT B.4 – Reprocessing/Separations and Technology Datafile Instructions

Table B-10 provides a list of all the fields that must be completed for the Summary Description page of the Reprocessing/Separations Technology Datafile. Since the generic high-level information is described in the reprocessing/separations Technology Datafile, it is necessary to discuss potential uses of the technology in different fuel cycles. The second page of the Technology Datasheet is the Schematic Diagrams and Pictures. These are figure(s) provided for information purposes to describe the technology and should include information on the different product streams including waste product streams.

The next set of information is the High Level Parameter Data. This information is intended to capture a high level summary of important information such as performance parameters that describe the specific technology in much greater level of detail. Table B-11 provides a list of all the fields that must be completed for the High Level Parameter table of the reprocessing/separations Technology Datafile. When the field is self-explanatory, no additional information is provided beyond the field name. A brief description of the field is provided as appropriate, and any value restrictions that may apply, and any additional notes to guide the preparer in completing that specific field are given.


Table B-10. Instructions for Summary Description Data in Reprocessing/Separations Technology Datafile


Technology Category Separations and Waste Form Technologies



Reprocessing/Separations Technology Identifier

Short Unique Technology Identifier

For example UREX+ for the UREX+ series of technologies.

Technology Title

Separation Process Type of process This is aqueous, electrochemical, etc.

Revision Numbers Starts at 0.0 Revision Remarks



Description of the technology and should include a description of the different resulting waste form products.

A brief description that will allow users not familiar with this technology to quickly understand it and how it differs from similar/other technologies.

Prepared by Date Internally Reviewed by Approval Date Externally Reviewed by Approval Date Accepted by FCDP Team Leader Date


Table B-11. Instructions for High Level Parameter Data in Reprocessing/Separations Technology Datafile


Primary Recovered Element(s)

A list of the primary elements recovered/ separated.

This should include all the major components of the fuel material: Th, U, Pu & MA or TRU or other groupings, any FP streams not included in HLW, which is also a product stream or streams.

Recovery Efficiency Appropriate range of separation efficiency by element stream.

Required is how efficient the process is at getting the targeted material into the product stream. Does not include contamination with material from other product streams.

Description of Separation Waste Streams

Minimum Cooling Time before Separation, years


Reprocessing/Separation Time, years




See section Table 1 for TRL definitions.

Brief Justification of TRL: Justify the basis for the TRL range specified.

Time to achieve TRL of 9, years



REFERENCES

DOE-NE 2010 Nuclear Energy Research and Development Roadmap: Report to Congress, U.S. Department of Energy, Office of Nuclear Energy, April 2010.

DOE-NE 2011 A Screening Method for Guiding R&D Decisions: Pilot Application to Nuclear Fuel Cycle Options, U.S. Department of Energy, Office of Nuclear Energy, August,2011(http://www.nuclear.energy.gov/pdfFiles/DOE_NE_Screening%20Brochure_web.pdf)

Catalog 2011 L. L. Price and E. L. Hardin, Fuel Cycle Catalog Description and System Options for Initial Screening, FCRD-SYSE-2010-000203 Draft B, Sandia National Laboratories, September 29, 2011.

Dixon 2012 B. Dixon, Assumptions for Nuclear Energy Systems Analyses, Revision 1, FCRD-FCO-2012-000026, April 10, 2012.

Taiwo 2012 T. A. Taiwo, T. K. Kim, and E. A. Hoffman, Preparation, Review, and Acceptance Procedure for Fuel Cycle Data Packages, Argonne National Laboratory. FCRD-SYSE-2011-000301.Rev.3, Nov. 30, 2012.

Todosow 2012 M Todosow, et al, Draft of the Fuel Cycle Options List to be Used for the 2013 Screening, FCRD-FCO-2012-000164, July 2012.

Fuel Cycle Data Package Template Description

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