Final Technical Report

Anistratov, Dmitriy Y. ; Adams, Marvin L. ; Palmer, Todd S. ; Smith, Kord S. ; Clarno, Kevin ; Hiruta, Hikaru ; Nes, Razvan

Texas A & M University

关键词: Group Constants;    Diffusion;    Power Distribution;    Reactor Kinetics;    Cross Sections;   

DOI  :  10.2172/812590
RP-ID  :  NONE
RP-ID  :  FG03-99SF21922
RP-ID  :  812590

美国|英语

来源: UNT Digital Library

【 摘 要 】

OAK B202 Final Technical Report. The present generation of reactor analysis methods uses few-group nodal diffusion approximations to calculate full-core eigenvalues and power distributions. The cross sections, diffusion coefficients, and discontinuity factors (collectively called ''group constants'') in the nodal diffusion equations are parameterized as functions of many variables, ranging from the obvious (temperature, boron concentration, etc.) to the more obscure (spectral index, moderator temperature history, etc.). These group constants, and their variations as functions of the many variables, are calculated by assembly-level transport codes. The current methodology has two main weaknesses that this project addressed. The first weakness is the diffusion approximation in the full-core calculation; this can be significantly inaccurate at interfaces between different assemblies. This project used the nodal diffusion framework to implement nodal quasidiffusion equations, which can capture transport effects to an arbitrary degree of accuracy. The second weakness is in the parameterization of the group constants; current models do not always perform well, especially at interfaces between unlike assemblies. The project developed a theoretical foundation for parameterization and homogenization models and used that theory to devise improved models. The new models were extended to tabulate information that the nodal quasidiffusion equations can use to capture transport effects in full-core calculations.