Fast Reactor Knowledge Preservation Efforts An Overview · PDF fileDecember 3-5, 2013 IAEA FR...

December 3-5, 2013 IAEA FR Knowledge Preservation Meeting 1

Fast Reactor Knowledge Preservation Efforts

An Overview

Christopher Grandy

Argonne National Laboratory

IAEA Fast Reactor Knowledge Preservation

Technical Exchange Meeting

December 3-5, 2013

Vienna, Austria


Outline

• DOE Advanced Reactor Concepts Fast Reactor (ARC-FR) Program

Overview

• Fast Reactor Information and Database

– EBR-II Test Database – T. Sofu (ANL)

– FFTF Reactor Test Data – Ron Omberg (PNNL)

– Transient Reactor Test Facility (TREAT) Database – Art Wright/T. Bauer (ANL)

– Fuels and Materials Irradiation Data – Latif Yacout (ANL)

• Use of Fast Reactor Database – IAEA EBR-II Benchmark

• Engineering Code Recovery

• Information on the DOE Office of Scientific and Technical Information

• Summary

ARC-AFR Objective

• ARC-AFR Objective - Develop advanced fast reactor

technology solutions to allow commercial deployment

by 2050 timeframe

• Supports Nuclear Energy R&D Roadmap Objectives 2

& 3

– (2) Develop improvements in the affordability of new reactors

to enable nuclear energy to help meet the Administration’s

energy security and climate change goals

– (3) Develop sustainable nuclear fuel cycles

• “The overall goal is to have demonstrated the technologies

necessary to allow commercial deployment of solution(s) for the

sustainable management of used nuclear fuel that is safe,

economic, and secure and widely acceptable to American society

by 2050.”


ARC-AFR Program Activities

• ARC-AFR Program is divided into various AFR-related subtasks

– Fast Spectrum Reactor

• Fast Reactor Concept Development

• Fast Reactor Safety and Licensing

• Fast Reactor Advanced Materials

• Fast Reactor Inspection Technology

• Fast Reactor Knowledge Preservation

– Cross Cutting Research Activities

• Energy Conversion Technologies

– Generation IV International Support (GIF)

– Modeling and Simulation (NEAMS) – high performance computing

– Nuclear Data


Fast Reactor Knowledge Preservation and

Database Goals

• Support the preservation of knowledge related to U.S. SFR

technology and data as well as professional expertise to facilitate

science-based R&D

– Transfer knowledge from personnel involved in fast reactor projects to

younger staff

• Provide data for validation of the advanced analysis methods and

codes for analysis of transients beyond routine operation

• Support continued participation in international passive safety

benchmark projects to fulfill specific DOE commitments

December 3-5, 2013 5IAEA FR Knowledge Preservation Meeting

Fast Reactor Knowledge Preservation

Focus Areas

• Identify areas where information is at risk of being lost or

destroyed

– Example – FFTF document preservation

• Collect and organize FR related information

– EBR-II database

– FFTF database

– TREAT Database

• Make information accessible to U.S. and other Fast Reactor

technology development countries

– Office of Scientific and Technical Information

– IAEA CRP on EBR-II Passive Testing Benchmark


Fast Reactor Database Development


8

EBR-II Test Database

• EBR-II Test Database covers all of the experiments conducted between

1984 and 1987 during a comprehensive testing program

– Data collected from the ~60 Shutdown Heat Removal Tests (SHRT),

Balance of Plant (BOP) Tests, and Plant Inherent Control Tests (PICT)

• Also includes landmark IFR inherent safety demonstration tests

– Organized based on the five testing windows (each with unique core,

plant, and data acquisition system configuration) and test categories

(such as the protected or unprotected loss of flow, loss of heat sink, or

reactivity perturbation tests)

– Access to up to 900 test-specific data acquisition system instruments

(grouped into 60 broad categories) to plot/tabulate and a document

archive

– This effort is being completed in 2013

December 3-5, 2013 IAEA FR Knowledge Preservation Meeting

9

FFTF Passive Safety Database

• Similar effort is underway at PNNL to

develop a database for FFTF passive

safety demonstration tests

– Objectives are to verify natural circulation as

a reliable means to safely remove decay

heat, extend passive safety experience to a

large-size LMR, develop and test passive

safety enhancements

– Will be useful to support future simulation and modeling efforts:

• Potential benchmarks of advanced simulation models against realistic

operational data

• Well-characterized environment for verifying coupled thermal

hydraulic/neutronic/mechanical codes


FFTF Passive Safety Database - Background

• All Passive Safety Testing (PST) related

data has been preserved

– ~ 100 documents related to PSTs were

identified and retrieved

– All 120 plant data tapes covering the PST

tests were located, retrieved, and the data

was extracted, secured, and decoded

• A web-based interface for accessing the

PST data similar to that for EBR-II data is

being developed

– Web-based structure was created and tested

and is working

– Data retrieval and display are handled using

modified versions of software developed and

used during FFTF operation

– Current Capability for generating data reports

for PST periods

IAEA FR Knowledge Preservation Meeting

Cycle Tests No. Tapes

7Reactivity

Feedbacks11

8AReactivity

Feedbacks49

8BNatural

Circulation8

8C LOFWOS 42

12B-1GEM Pump

Restart10

December 3-5, 2013 10

11

FFTF Passive Safety Database (cont.)

• Three 2013 activities:

– Time-averaging option: Database was modified to read the data records,

average over specified time ranges, and display the output. The averaging

methodology was complicated due to the data compression methods used

in the FFTF data.

• The CGULF and CDREVW programs used at FFTF were modified to read the

data files, average over specified time ranges and generate HTML output for

display in a web browser.

– Test Index File: Provides capability to select a test sub-period and sensors

of interest from a drop-down menu (rather than entering the date/time

range for data retrieval).

• All PST test reports were retrieved and are being reviewed and working

files/plant data are being reviewed

– Plotting capability: Being added and integrated with the data retrieval

features.

• Using Excel spreadsheet or GNUPLOT package.


TREAT experiments relational (TREXR)

database

• TREAT was designed for transient

testing of nuclear fuels and materials

under off-normal and accident

conditions

• Used in performing >800 experiments

from 1959 to 1994, most performed by

ANL

• Tests supported SFR and LWR

development

• TREAT is on non-operational standby

since 1994, but being considered for

re-use beginning in ~2019

TREAT - located at the

former ANL-W, which

operated it for ~35 yrs)IAEA FR Knowledge Preservation

Meeting12

December 3-5, 2013

TREAT air-cooled design allows for easy

core access to a variety of in-core

experiment hardware

IAEA FR Knowledge Preservation

Meeting13

December 3-5, 2013

Information from past TREAT experiments

is valuable for future reactor development

and licensing

TREAT experiments ranged from investigating individual phenomena to

demonstrating integral effects of multiple interactive phenomena

• Revealed phenomena, interactions, thresholds, rates, etc. about which

little was known or previously observed.

• Provided the basis of much of present knowledge and understanding

of transient fuel behavior and the basis for much model/code

development and validation.

• Investigated transient fuel behavior phenomena which are of

continuing importance

• Used techniques and approaches which can guide future experiments.

IAEA FR Knowledge Preservation

Meeting14

December 3-5, 2013

15

TREAT Experiments Database

• Information and data from TREAT Tests during 1959-1994

– An extensive archive of documents, meta-data and numerical data from one-of-

a-kind tests as the basis of much of present knowledge of transient fuel

behavior

– For investigation of key phenomena related to severe-accident energetics and

integral interactions among multiple phenomena related to accident progression

• Early experiments addressed fuel-coolant interactions for many different

fuel types for LWRs and SFRs.

• Later, focus shifted on oxide fuels for LMFBR development, both for severe

accident evaluations and for fuel qualification

• Latest tests focused on both LWR radiological source term investigations

and SFR metallic fuel over-power transient behavior.

• Four main experiment categories

– Principal objectives and/or outcomes (with twelve sub-categories)

– Test sample characteristics (with six sub-categories)

– Test conditions (with four sub-categories)

– Diagnostics and analyses (with three sub-categories)


16

TREAT Experiments Database:

Status of development

• Added a capability to search for documents containing information on

how specific, user-selected computer models and codes (more than 100

to select from) were validated by, or were used to analyze, TREAT

experiments.

• Completed the final report “TREXR: The TREAT Experiments Database”:

– The nature of TREAT experimentation, application of TREAT experiment results,

and need for the TREXR database

– Details of TREXR content, structure, and utilization.

• Of documents previously identified, scanned approximately 120, logged

in approximately 160, and added missing bibliographic metadata for

many more.

• Identified (from reference lists OSTI search) nearly 400 additional reports

and articles and entered their bibliographic metadata into the database.

• At present, about 2050 reports and articles have been at least partially

logged into the database; about 850 have been scanned.

• Database work will be completed this year


17

SFR Fuels Irradiation and Physics

Analysis Database

• Currently covers the irradiation

experiments at EBR-II

– Development of a framework for an

advanced metallic-alloy fuels database

and archiving of data from detailed pin-by-

pin fuel irradiation history

– Available documentation generated

through the EBR-II experimental program

and used in the calibration and validation

of physics and fuel performance codes

– Detailed core loading data, fuels

fabrication information, PIE results, and

operating parameters

– Established data models and resurrected

tools for data generation for EBR-II

irradiation experiments (PADB access

software, SUPERENERGY-II, LIFE-

METAL)


18

SFR Fuels Irradiation and Physics

Analysis Database

• Status of development:

– The calculations for detailed data packages for experiments X420, X421, X423,

and X429 were completed.

– SQL server for the database was established which is focused on EBR-II fuels.

– The full fabrication, operating, and irradiation data, as well as documentations for

experiments X419, X425, X430, X441, X447, X420, X421, X423, and X429 were

implemented into the database (tests associated with LIFE-METAL validation).

– Full web interface access to detailed data associated with each pin in those tests,

in each EBR-II run the pin was irradiated has been established.

– Plotting capabilities of the different data associated with each pin has been

implemented into the interface.

– Full access to documentations available for each experiment is currently available

through interface

– Clickable assembly map for each test (including all re-constitutions) is

implemented which shows location of each pin in the experiments, and provides

access to all pin information and data plotting


Examples of Use of FR Information Recovery Efforts


20

IAEA Coordinated Research Projects

• Initiation of IAEA benchmarks for EBR-II Shutdown Heat Removal Tests for inherent safety demonstration

– Approved by IAEA governing boards as the next major international project on fast reactors

– Kick-off research coordination meeting was held at Argonne in June 2012

– Next research coordination meeting was held at IAEA HQ in Vienna in November 2013


EBR-II Shutdown Heat Removal Tests

– Importance of passive decay heat removal capability of advanced reactor designs has been emphasized in the aftermath of Fukushima accident

– Potential of SFRs to survive even more severe accident initiators with no core damage has been demonstrated during the testing program with EBR-II

– Two EBR-II SHRT tests are selected as the benchmark problem:

• SHRT-17 (1984): A protected LOF from 100% power and flow

• SHRT-45R (1986): An unprotected LOF from 100% power and flow

– Two-volume benchmark specs provide comprehensive details of the plant and tests

21

IAEA Coordinated Research Projects:

EBR-II Benchmarks


22

IAEA Coordinated Research Projects:

EBR-II Benchmarks: Plan & Participants

EBR-II CRP: Participating Organizations

China: CIAE, Xian Jiaotong University Korea, Republic of: KAERI, KINS

France: IRSN The Netherlands: NRG

Germany: HZDR, KIT Russia: IPPE

Italy: ENEA, UNIPI (GRNSPG) Switzerland: PSI

India: IGCAR USA: ANL, TerraPower, MIT

Japan: JAEA, Fukui University, Kyushu University

Four year project

– 2013: Blind analyses

– 2014: Preliminary assessments and model revisions

– 2015: Uncertainty evaluations and parametric analyses

– 2016: Documentation of the contributions in a TECDOC.

Specific plans for FY14

– Argonne lead 2nd RCM in Nov. (blind simulation results were evaluated and test data recorded during the tests will be distributed)

– Model refinements and uncertainty evaluations will be performed


Code Recovery – NUBOW-3D

• ANL has been recovering the NUBOW code -

– core restraint design code

• NUBOW code was used to determine

– location of core restraint rings

– gaps between top load pads and core

restraint rings

– Sizing of the above core load pad

– Thicknesses of load pads

– Reactivity feedback during power to flow

mismatches

– Bowing (deflections) of the core

– Refueling load forces

• Recently, we used the NUBOW code to design

the core restraint system for the AFR-100


Code Recovery - SWAAM

• ANL has been recovering the SWAAM code

for a couple years

• Have upgrade the code to include sodium-

CO2 interactions and other fluids besides

sodium

• During this past year - calculations were

completed for a variety of leak sizes and

break locations within the sodium-CO2 heat

exchanger

• Leak sizes ranging from:

– 2 mm, 4mm, 6mm, and 16.1 mm were

considered.

• Break locations at the top, center, and

bottom of the sodium-CO2 heat exchanger

were also considered for 2.0 mm and 16.1

mm break sizes.


DOE Office of Scientific and Technical Information

(OSTI)


What Is OSTI?

• Free, unlimited public access to unclassified

• Restricted access to classified and sensitive

• Roles/responsibilities defined in DOE O 241.1B, Scientific and Technical Information Management

“The Secretary, through the Office of Scientific and Technical Information, shall

maintain within the Department publicly available collections of scientific and

technical information resulting from research, development, demonstration, and

commercial applications activities supported by the Department.”

OSTI’s role is anchored in law:

Energy Policy Act of 2005

OSTI is the DOE office responsible for ensuring

access to DOE (and predecessor) R&D results—

since 1947.


What Does OSTI Do?

We make DOE R&D results findable and accessible, not just

within DOE, but globally.

We make other people’s R&D results findable, bringing

worldwide R&D to DOE and beyond.

Accelerating the spread of knowledge inspires everything we do at OSTI.

“If I have seen further, it is

only by standing on the

shoulders of giants.”

—Isaac Newton, 1676Premise: Science advances only if knowledge is shared.

Corollary: Accelerating the sharing of scientific knowledge accelerates the advancement of science.

MISSIONTo advance science and sustain

technological creativity by making

R&D findings available and useful

to Department of Energy (DOE)

researchers and the public.


DOE Collection

• More than 300,000 electronic full-text technical reports

• Over 5 million scientific e-prints

• Over 2 million publicly available

citations

• More than 24,000 patents

• More than 500 websites & databases

• Conference papers & proceedings

• 1 million non-digitized documents


Integrates key DOE databases

Covers a range of R&D results (reports, patents, citations, project

summaries, eprints, etc.).

Integrates >70 nations

Provides over 400 million pages of science information from

databases and portals worldwide.

Integrates 13 U.S. science agencies

Databases and websites offer over 200 million pages of

science information.

What is special about OSTI?

• We integrate or aggregate multiple government R&D-related databases into single-search portals.

• Innovative technology drills down to selected databases and websites in parallel, then presents ranked search results.


� Free public access to over 308,000 full-text documents and

bibliographic citations of DOE research report literature.

� Documents are primarily from 1991 forward and produced by

DOE, the DOE contractor community, and/or DOE grantees.

� Legacy documents added as they become available in

electronic format.

Information Bridge


� Free public access to ~2,500,000 scientific research citations of

interest to DOE.

� Over 311,000 full-text documents, primarily from 1943 forward.

Energy Citation Database

Includes bibliographic citations

to report literature, conference

papers, journal articles, books,

dissertations, and patents.


o Consolidates Information Bridge and Energy Citations

Database.

o Will incorporate Semantic Search.

Launched in

March 2013


Some OSTI International Activities

• International Nuclear Information System – INIS

(www.IAEA.org/INIS)

– Multilateral agreement under International Atomic Energy Agency since

1969.

– World’s largest database on peaceful uses of nuclear energy and

technology.

– OSTI serves as U.S. representative and input center.

• Energy Technology Data Exchange – ETDE (www.ETDE.org)

– Multilateral agreement under International Energy Agency since 1987.

– Database of 4.5 million records in energy research, technology, and

development.

– OSTI serves as Operating Agent.


Grandy INIS Search – Dec 4, 2013

Searched for “Fast Reactor”

Total – 138,277

U.S – 9,700

IAEA – 3,300

Japan – 3,000

Germany – 2,400

France – 2,100

Netherlands – 1,600

Searched for “Fast Reactor”

with pdf available

Total – 44,984

U.S. – 8,000

IAEA – 5,400

France – 1,800

Canada – 1,400

Sweden – 1,200

Japan – 1,000


Office of Scientific & Technical Information

Large-Scale Digitization Project (LSDP)


LSDP OverviewOSTI Large Scale Digitization Project

• OSTI Large Scale Digitization Project (LSDP)

• Initial Proposal: Two year effort to digitize entire non-digitized DOE hardcopy collection.

• Only documents from OSTI legacy collection in hardcopy format located in OSTI’s unclassified vault

• Actual Project: 8 month effort that digitized 90,000 (5 Million pages) of non-digitized DOE hardcopy collection.

• Timeframe Sep 2012 to May 2013

• Total of 90k document digitized (5 million pages)

• On-site vendor handled digitization activities (prep, scan, QC)

• OSTI Federal staff and contractors support handled inventory, initial prep, sensitivity reviews and web product integration (Sci-Tech Connect, SRC, etc.)

• Approximately 18k have flowed through to various OSTI web products, remainder are in various stage of review process


Summary

• ARC-AFR Program is involved in a number of knowledge preservation

activities

• Recovery of Information from EBR-II, FFTF, and TREAT is very important

• Recovery of Information from Office of Scientific and Technical

Information (OSTI) and conversion to electronic format

• Organizing some data into electronic databases – EBR-II Plant Testing

Data, FFTF Plant Testing Data, TREAT Test Data, SFR Fuels and Materials

Irradiation Data, etc.

• Information is being used to support existing U.S. SFR programs along

with international programs such as the IAEA CRP EBR-II Safety

Benchmark


Fast Reactor Knowledge Preservation Efforts An Overview · PDF fileDecember 3-5, 2013 IAEA FR...

Documents

Transcript of Fast Reactor Knowledge Preservation Efforts An Overview · PDF fileDecember 3-5, 2013 IAEA FR...