The ART-GCR Methods Technical Program Plan · Shutdown Heat Removal System with water-cooled...
Transcript of The ART-GCR Methods Technical Program Plan · Shutdown Heat Removal System with water-cooled...
The ART-GCR Methods Technical Program Plan
William F. SkerjancResearch Scientist/Engineer
Gas-Cooled Reactor Program Review MeetingMay 8-9, 2018, at Idaho National Laboratory
Hans Gougar
ART-GCR National Technical Director
Plans Developed Under NGNP
• PLN-2804, Next Generation Nuclear Plant Steam Generator and
Intermediate Heat Exchanger Materials Research and Development Plan
• PLN-2497, Graphite Technology Development Plan
• PLN-2498, Revision 4, “Advanced Reactor Technologies High
Temperature Reactor Methods Technical Program Plan”
Last updated in 2016 (Gougar and Schultz)
Goals revised
• PLN-3636, Technical Program Plan for the ART-TDO/AGR Fuel
Development and Qualification Plan
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Objectives of the Plan
• To develop and demonstrate tools that can perform prototypical design and
licensing calculations with sufficient fidelity that residual and inherent
uncertainties in calculated safety and performance figures of merit (FOM) are
bounded and acceptable for the purpose of the simulation, and
• To conduct (or guide the design and execution of) experiments that yield a data
set that covers the anticipated operating envelope and are of sufficient quality
to validate computational models used for design and licensing of High
Temperature Reactors (HTRs) operating with reactor coolant outlet
temperatures between 650°C and 850°C. (Methods can be used with higher
temperatures but may require additional experiments to validate)
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Thermal Fluids Validation & Verification (Jim Wolf, Lead)
Experiment Matrix developed from the NGNP PIRT
• (Ball, S., et al., “Next Generation Nuclear Plant
Phenomena Identification and Ranking Tables
(PIRTs),” NUREG/CR-6944, 2008.) and INL/EXT-11-
21397, Assessment of NGNP Moisture Ingress
Event
• Assumed very high temperatures (up to 1000°C)
• Designed to address Phenomena considered to be
of highest importance but with limited knowledge
Lower Plenum mixing, Bypass flow, core heat
transfer, plenum-to-plenum heat transfer and
circulation, Air ingress, and (later) moisture ingress.
• Integral and associated separate effects and
fundamental experiments for validation of CFD and
System models4
Boundary Conditions
• NQA-1 standards for
experimental validation
A challenge to flow down to
NEUP projects
• RG 1.203 for model validation
CFD and system analyses
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Recent Updates
• Recent modifications to the plan
Focus on the minimal set of experiments needed to validate models of important scenarios: Normal ops, (likely to be
selected) Design Basis Events, and some Design Extension Conditions
Reactor vessel (cavity) cooling system performance (NSTF integral facility at ANL)
Shift the load to universities (NEUP)
• Integral Facility at Oregon State University
• Numerous separate/mixed effects experiment
• Priorities are being re-evaluated based upon
Knowledge gained from 10 years of testing, focus on the steam cycle
Vendor input
INL/EXT-17-43218, Schultz, et al, Identification and Characterization of Thermal Fluid Phenomena Associated with
Selected Operating/Accident Scenarios in Modular High Temperature Gas cooled Reactors”, under review 6
Scenarios Covered in the Experimental Matrix
• Normal Ops
Coolant flow and temp distributions (hot channels)
Mixing of jets in outlet plenum
• Loss of Forced Cooling – pressurized
Core heat transfer (conduction and radiation)
Coolant distribution under natural circulation
Vessel (cavity) cooling
• Loss of forced cooling – depressurized
All of the above plus air ingress
Reactor cavity gas distribution
• Steam generator tube break7
High Priority
• Complete modifications to the OSU High Temperature
Test Facility and resume matrix testing
• Demonstrate operation of the ANL Natural Circulation
Shutdown Heat Removal System with water-cooled
configuration, for studying reactor cavity cooling system
performance
• NEUP projects on moisture ingress, jet plume behavior
(in-core and from primary breaks) • Vendors participated in the design and test
matrix planning for the HTTR and NSTF
experiments.
• AREVA and X-Energy facilitated the
conversion of NSTF to a water-cooled
configuration.
• The NRC sponsored the design and
construction of HTTF8
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Schedule – 2010 plan versus status
Core Simulation (Gerhard Strydom, Lead)
• Development and demonstration of methods for simulating operational and transient scenarios that can be used for design and licensing
• Technical Scope
Coupled core neutronics and thermal fluids
Pebble bed and prismatic
Cross section generation
Uncertainty analyses
• Some synergy with NEAMS – especially in core thermal fluid analysis (PRONGHORN)
10The main objective is to identify the important physics to be captured and capabilities to be constructed (rather than to develop a code system that can be marketed or apply the latest computational techniques)
Activities
• Development (in part) driven by international benchmark activities and
collaborations (HTTR)
OECD-NEA: MHTGR-350 and HTTR LOFC projects
IAEA CRP on HTR-UAM
• Demonstrate basic and reproducible burnup and transient capabilities in
ways that can be adopted or emulated by vendors to use in their own code
systems (and better capture phenomena than the 1st generation HTGR
codes)
• Exploit developments in uncertainty analysis (e.g. SUSA, RAVEN,
TSUNAMI) to quantify sensitivities and to focus additional attention
11You will see more on these today.
Challenges to be Addressed
• Pebble bed reactors
Moving fuel
Undefined ‘assemblies’ (spectral zones) and the neutronic coupling between them
Radiative heat transfer between pebbles (and reflector), bypass flow in reflector
Cylindrical geometry
• Prismatic Reactors
Neutronic coupling between assemblies (blocks)
Burnable poisons, multiple fuel types (HTTR)
Streaming in control rod channels
Fidelity in thermal fluid analyses – a Goldilocks problem
Bypass flow 12RELAP5 model
CFD: This is accurate but
slow
This is fast but low resolution
Schedule: 2016 plan versus status
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?
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International Collaborations WP Lead
(208) 526-1314
art.inl.gov
Hans Gougar
International Collaboration WP in a nutshell