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Title: Verification of the CENTRM Module for Adaptation of the SCALE Code to NGNP Prismatic and PBR Core Designs

The generation of multigroup cross sections lies at the heart of the very high temperature reactor (VHTR) core design, whether the prismatic (block) or pebble-bed type. The design process, generally performed in three steps, is quite involved and its execution is crucial to proper reactor physics analyses. The primary purpose of this project is to develop the CENTRM cross-section processing module of the SCALE code package for application to prismatic or pebble-bed core designs. The team will include a detailed outline of the entire processing procedure for application of CENTRM in a final report complete with demonstration. In addition, they will conduct a thorough verification of the CENTRM code, which has yet to be performed. The tasks for this project are to: Thoroughly test the panel algorithm for neutron slowing down; Develop the panel algorithm for multi-materials; Establish a multigroup convergence 1D transport acceleration algorithm in the panel formalism; Verify CENTRM in 1D plane geometry; Create and test the corresponding transport/panel algorithm in spherical and cylindrical geometries; and, Apply the verified CENTRM code to current VHTR core design configurations for an infinite lattice, including assessing effectiveness of Dancoff corrections to simulate TRISO particle heterogeneity.
Authors:
;
Publication Date:
OSTI Identifier:
1117514
Report Number(s):
DOE/NEUP--09-807
TRN: US1500029
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Research Org:
Univ. of Arizona, Tuscon, AZ (United States); Univ. of Tennessee, Knoxville (United States)
Sponsoring Org:
USDOE Nuclear Energy University Programs
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; CROSS SECTIONS; C Codes; S Codes; VERIFICATION; Prismatic Configuration; PBR Reactor; VHTR Reactor; Planning; Neutron Slowing-Down Theory; REACTOR MATERIALS; NEUTRON TRANSPORT; One-Dimensional Calculations; CONVERGENCE; CYLINDRICAL CONFIGURATION; SPHERICAL CONFIGURATION; Rectangular Configuration; ALGORITHMS; Reactor Cores; COMPUTER-AIDED DESIGN; NEUTRONS; DANCOFF CORRECTION; Coated Fuel Particles