RELAP-7 and PRONGHORN Initial Integration Plan

J. Ortensi ; D. Andrs ; A.A. Bingham ; R.C. Martineau ; J.W. Peterson

关键词: BENCHMARKS;    DIFFUSION;    FEEDBACK;    FLUID FLOW;    HEAT TRANSFER;    MATHEMATICAL MODELS;    NEUTRONS;    REACTORS;    REMOVAL;    RESOLUTION;    SAFETY;    TESTING coupled;    multiphysics;    pronghorn;    relap-7;   

DOI  :  10.2172/1048408
RP-ID  :  INL/EXT-12-26016
PID  :  OSTI ID: 1048408
Others  :  TRN: US1204264

美国|英语

来源: SciTech Connect

【 摘 要 】

Modern nuclear reactor safety codes require the ability to solve detailed coupled neutronicthermal fluids problems. For larger cores, this implies fully coupled 3-D spatial dynamics with appropriate feedback models that can provide enough resolution to accurately compute core heat generation and removal during steady and unsteady conditions. The reactor analyis code PRONGHORN is being coupled to RELAP-7 as a first step to extend RELAP's current capabilities. This report details the mathematical models, the type of coupling, and the testing that will be used to produce an integrated system. RELAP-7 is a MOOSE-based application that solves the continuity, momentum, and energy equations in 1-D for a compressible fluid. The pipe and joint capabilities enable it to model parts of the PCU system. The PRONGHORN application, also developed on the MOOSE infrastructure, solves the coupled equations that define the neutron diffusion, fluid flow, and heat transfer in a 3-D core model. Initially, the two systems will be loosely coupled to simplify the transition towards a more complex infrastructure. The integration will be tested with the OECD/NEA MHTGR-350 Coupled Neutronics-Thermal Fluids benchmark model.