PROTEUS: High-Fidelity Neutronics Coderesearch.engr.oregonstate.edu/treat-irp/sites/...3D whole core...
Transcript of PROTEUS: High-Fidelity Neutronics Coderesearch.engr.oregonstate.edu/treat-irp/sites/...3D whole core...
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PROTEUS: High-Fidelity Neutronics Code
November 19, 2015
Changho LeeNeutronics Methods and Codes SectionNuclear Engineering DivisionArgonne National Laboratory
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SHARP
Coupled Multi‐Physics Toolkit for Reactor Analysis, being developed under the DOE NEAMS program (Nuclear Energy Advanced Modeling & Simulation)– SHARP leverages state‐of‐the‐art physics codes to
take advantage of man‐years of effort, experience, and software V&V
– High fidelity modeling and massive algorithm parallelization enable fundamental insights unattainable through experiments alone
SHARP targets high‐fidelity transient phenomena– Address multi‐physics issues that are not well‐
represented in standard homogenized or empirical models
– Address problem‐size issues and/or compare against lower‐fidelity codes
Multi‐disciplinary, multi‐laboratory effortFuel Deformation in SFR
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Challenges in Neutronics
Sodium‐cooled fast reactors– Rod bowing – Flowering due to thermal expansion
Very high temperature reactors– Double heterogeneity effects due to TRISO fuel particles and compacts– Large leakage fraction due to large migration area and annular core shape– Strong core/reflector coupling and thermal flux peaking– Asymmetric loading of burnable poison compacts, large gas channels in fuel blocks– Relatively large temperature feedback due to large temperature variation
Light water reactors– Crud‐induced power shift and localized corrosion– Grid‐to‐rod fretting failure– Pellet clad interaction– Fuel assembly distortion: inhibit control rod insertion
Small modular reactors– Enhanced transport effects (high leakage, local heterogeneity effect, etc.)– Significant power and spectral shifts with time– Deformation and aging of reactor materials
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PROTEUS Development of high‐fidelity neutron
transport code, PROTEUS– High‐fidelity multi‐physics simulations with
geometry deformation– Reduce costly experiments, improve design
margin & safety
Key capabilities– Fully unstructured finite element mesh (mixed
finite element types with tri/quad or prism/hex/tet), DOFs from 109 to >1012
– Parallelization in space, angle, and energy: > 90% strong scaling, 75% weak scaling on BG/P
– Transport solver: SN2ND, MOC 2D, MOC 3D,MOC 2D/3D (axially discontinuous galerkin FEM)
– Transient capability (adiabatic) – Simulation and V&V: ZPR‐6, ZPPR‐15, Monju, EBR‐
II, ABTR, C5, ATR, VHTR, etc.
Total Cores
Vertices/Process
Total Time
(seconds)
ParallelEfficiency
8,192 7,324 2,402 100%
16,384 3,662 1,312 92%
24,576 2,441 873 92%
32,768 1,831 637 94%
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Hexagonal Lattices (Fast Reactors)
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Geometry Deformation (Advanced Burner Fast Reactor)
Limited free bow restraint system allows deformation of assembly ducts as the system temperature rises
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ABTR Simulation with PROTEUS
Multigroup cross section generation using MC2‐3
Two models in terms of heterogeneity– Homogeneous assemblies
(conventional model)– Partially homogeneous assemblies
(heterogeneous duct + homogeneous fuel)
3D whole core calculations compared with MCNP solutions
Fast FluxThermal Flux
Configuration MCNP PROTEUS
Control Rod Out 1.23388 ±0.00010
‐152 pcm(116 groups)
Control Rod In 1.04374 ±0.00011
26 pcm(230 groups)
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Zero Power Reactor Experiments
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y
x
Fuel Drawer
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ATR: Eigenvalue Comparison
MCNP PROTEUS
Angle Mesh ∆k (pcm)
1.08770 ±0.00026
L3T7 Mesh E ‐474
L3T15 Mesh E ‐397
L3T15 Mesh E x 4 ‐299
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Fast FluxThermal Flux* Mesh E x 4 : Auto‐refinement tool applied to Mesh E
Good agreement in eigenvalue between PROTEUS and MCNP
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2
3
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0 5 10 15 20
Normalize
d Group
Flux
Inner to Outer Fuel Meat
MCNP Group 1PROTEUS Group 1 (1MeV)MCNP Group 22PROTEUS Group 22 (0.1eV)
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C5: Group Fluxes
Initial Verification of PROTEUS for Heterogeneous Geometries ‐ April 19‐23, 2015
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Fast (G4: 111‐500 keV)
Thermal (G21: 0.14‐0.1 eV)
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Transient Reactor Test Facility(TREAT)
Operated from 1959‐1994, plan to restart Fueled with 93.1% enriched UO2 particles
finely dispersed in graphite– Carbon‐to‐235U atom ratio of
approximately 10000:1 Graphite‐moderated, graphite‐reflected,
air‐cooled, 4’x4’ fuel assembly Core can accommodate maximum of 361
fuel assemblies in a 19 x 19 array
Experiments performed in first six months of TREAT operation
Results include– Neutron Flux Distribution– Temperature Distribution– Approach to Criticality Experiment– Temperature Coefficient of Reactivity
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3D Heterogeneous Geometry Simulationusing PROTEUS
Top View of Fuel Section
Minimum Critical Core
Fuel / Reflector Control Rod
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Cross Sections for PROTEUS
Focus primarily on SFR and extensively on other reactor types (LWR, HTR, etc.)
Need a multi‐group cross section capability (methodology) applicable to various reactor types
Develop on‐line cross section generation capability (cross section API)
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SFRATR
LWR HTR
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PROTEUS
MC2-3
Genesis
BuildBot PERSENT
Multigroup cross section
Cross section library
Steady-state & transport calc.
Nightly regression test
Perturbation and sensitivity
SNMOC
NODAL
Mesh conversion
tools
Nek5000
Diablo
PROTEUS System