skip to main content

Title: The coupling of the neutron transport application RATTLESNAKE to the nuclear fuels performance application BISON under the MOOSE framework

The MOOSE neutron transport application RATTLESNAKE was coupled to the fuels performance application BISON to provide a higher fidelity tool for fuel performance simulation. This project is motivated by the desire to couple a high fidelity core analysis program (based on the self-adjoint angular flux equations) to a high fidelity fuel performance program, both of which can simulate on unstructured meshes. RATTLESNAKE solves self-adjoint angular flux transport equation and provides a sub-pin level resolution of the multigroup neutron flux with resonance treatment during burnup or a fast transient. BISON solves the coupled thermomechanical equations for the fuel on a sub-millimeter scale. Both applications are able to solve their respective systems on aligned and unaligned unstructured finite element meshes. The power density and local burnup was transferred from RATTLESNAKE to BISON with the MOOSE Multiapp transfer system. Multiple depletion cases were run with one-way data transfer from RATTLESNAKE to BISON. The eigenvalues are shown to agree well with values obtained from the lattice physics code DRAGON. The one-way data transfer of power density is shown to agree with the power density obtained from an internal Lassman-style model in BISON.
Authors:
; ; ; ; ; ; ;
Publication Date:
OSTI Identifier:
1177214
Report Number(s):
INL/CON--14-31079
TRN: US1500149
DOE Contract Number:
AC07-05ID14517
Resource Type:
Conference
Resource Relation:
Conference: PHYSOR 2014, Kyoto (Japan), 28 Sep - 3 Oct 2014
Research Org:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; NUCLEAR FUELS; MULTIGROUP THEORY; PERFORMANCE; FINITE ELEMENT METHOD; POWER DENSITY; EIGENVALUES; NEUTRON FLUX; BURNUP; COUPLING; RESONANCE; COMPUTERIZED SIMULATION; TRANSIENTS; REACTOR KINETICS; WATER COOLED REACTORS; WATER MODERATED REACTORS; B CODES; R CODES BISON; Fuels performance; Multiphysics; Neutron Transport; RattleSnake; Self Adjoint Angular Flux