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.
- Research Organization:
- Univ. of Arizona, Tucson, AZ (United States); Univ. of Tennessee, Knoxville, TN (United States)
- Sponsoring Organization:
- USDOE Nuclear Energy University Programs
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1117514
- Report Number(s):
- DOE/NEUP-09-807; TRN: US1500029
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
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