10
Work conducted by ANL for the GNEP Fast Reactor Simulation Andrew Siegel, ANL

Work conducted by ANL for the GNEP Fast Reactor Simulation Andrew Siegel, ANL

Embed Size (px)

Citation preview

Page 1: Work conducted by ANL for the GNEP Fast Reactor Simulation Andrew Siegel, ANL

Work conducted byANL for the GNEP

Fast Reactor Simulation

Andrew Siegel, ANL

Page 2: Work conducted by ANL for the GNEP Fast Reactor Simulation Andrew Siegel, ANL

Work conducted byANL for the GNEP

Key point of fast vs. thermal reactors

Thermal reactors (e.g. LWRs)– Neutrons moderated to thermal energies (usually using water)– Higher probability of fission -> relatively low U-235 enrichment – Also high probability of capture by U-238 -> buildup of transuranics

• Major burden for storage

Fast reactors (e.g. LMFBRs)– Neutron moderation minimized– Lower-probability of fission -> higher enrichment needed– Low probability of capture and ability to fission transuranics/breed

plutonium– Key to closing fuel cycle + long-term resource managment

Page 3: Work conducted by ANL for the GNEP Fast Reactor Simulation Andrew Siegel, ANL

Work conducted byANL for the GNEP

Fast reactors to date

A number of fast reactors have been designed/operated over the last 50 years– Most have been research or prototype reactors– Yet to be successfully commercialized

Major bottlenecks– Capital cost– Demonstration of safety

LWR performance has benefited tremendously from decades of operational experience

Want to use simulation to greatly accelerate for LMFBRs

Page 4: Work conducted by ANL for the GNEP Fast Reactor Simulation Andrew Siegel, ANL

Work conducted byANL for the GNEP

LMFBR Loop Design

~400C

~550C

Page 5: Work conducted by ANL for the GNEP Fast Reactor Simulation Andrew Siegel, ANL

5Work conducted byANL for the GNEP

Details on core geometry

Bottlenecks:– Varying fidelity geometry, mesh– Scalable geometry & mesh generation– Parallel mesh IO, representation to support UNIC– Need for mixed quad/tri extrusion, unavailable in CUBIT– Customized mesh generation would make this easy (simple swept

model)

1/6 ABTR core• 7k volumes (core, ctrl, reflect, shield)• 43k-5m hex elements•~6 GB to generate using CUBIT

217-pin fuel ass'y• Conformal hex mesh• 1520 vols• Multiple homogenization options, e.g. pins resolved

Page 6: Work conducted by ANL for the GNEP Fast Reactor Simulation Andrew Siegel, ANL

Work conducted byANL for the GNEP

Wire-Wrapped Fuel Pin AssemblySodium Coolant Cross-Flow

- Wire wrap used to space pins- Has significant impact on pressure drop,

mixing, cross flow

H

Fuel Pinand Wire

CornerSubchannel

EdgeSubchannel

InteriorSubchannel

Duct Wall

Fuel Pin D

P

Wire Wrap

Page 7: Work conducted by ANL for the GNEP Fast Reactor Simulation Andrew Siegel, ANL

Work conducted byANL for the GNEP

Current state of LMFBR modeling

Two broad classes of problems -- safety and design

Huge range of problems to be addressed within these– Mixing, shielding, power generation, structural feedback, fuel depletion,

cladding failure, transient overpower, transient undercooling, fission product release, sodium boiling, etc etc

All involve one or several of a handful of phenomena– Complex geometries– Neutron transport– Conjugate heat transfer (low Pr for LMFBR, mostly single phase)– Structural deformation– Fuel properties/behavior (Unal talk)– Lots of data -- cross sections, diffusivities, etc.

> 1000 person-years of codes developed and deployed in 70s-80s to design early LMFBRs– Many codes/models exist since mostly one code/model per phenomenon

Page 8: Work conducted by ANL for the GNEP Fast Reactor Simulation Andrew Siegel, ANL

Work conducted byANL for the GNEP

Really boiling it down

Much of these phenomena address two overarching problems– Demonstrate increase of

linear power to melting– Demonstrate unprotected

(passive) safety features

Two approaches– Advanced simulation leads to

lower rule-of-thumb design margins for existing designs

– Advanced simulation leads to design innovations with much better economics/safety

Improved Simulation

Validation andOperating Experience

Improved Designand Simulation

Experimental Uncertainty

Operational Margin

Prediction Uncertainty

Temperature Limit

Nominal Peak Temperature

AverageTemperature

Operating limit

Page 9: Work conducted by ANL for the GNEP Fast Reactor Simulation Andrew Siegel, ANL

Work conducted byANL for the GNEP

Software system view

neutrontransport fuel

thermohydraulics

Structuralmechanics

balance of plant

Coupling

Visualization

Mesh generation

High-performance i/o

Ultra-scalable solvers

Components•formalized interfaces•encapsulate physics•follow strict design rules•unit tests

Framework•provide services to components•Defines module structure•domain of CS

•MC•MOL•Direct

Uncertainty

Geometry

Enabling technologies

Page 10: Work conducted by ANL for the GNEP Fast Reactor Simulation Andrew Siegel, ANL

Work conducted byANL for the GNEP

Some research topics

Improvements to current models/technologies– Bigger/faster computers that are easier to program!– Highly scalable transport methods -- improved preconditioners for PN, scalabale ray

tracing algorithms for decomposed geometries, hybrid methods, etc.– Multi-scale approach for heat transfer, transport, bridging ab initio to engineering scale

modeling for fuels, …– Spatially coupling DNS, LES, RANS, sub-channel– Accurate coupling techniques for fast transients– Improved meshing technologies for complex domains– UQ for multiphysics simulations– Component architectures for tight/loose coupling– Subgrid fluid models, sodium boiling– Better characterizations of low Pr heat transfer– Structural modeling for rod bowing, vessel expansion, etc.– Petascale data management, vis, etc.

Application of modern techniques to specific poorly understood problems in design/safety with validation

– Thermal striping in plenum, flow orificing optimization, fission product release, stratified pipe flow, inter-channel flow, time/margin to cladding rupture, etc.