Published 2006 | Version v1
Book

Assembly Based Modular Ray Tracing and CMFD Acceleration for BWR Cores with Different Fuel Lattices

  • 1. Purdue University, West Lafayette, IN 47906 (United States)
  • 2. Seoul National University, San 56-1, Sillim-dong, Seoul, 151-742 (Korea, Republic of)

Description

The geometry module of the DeCART direct whole core calculation code has been extended in order to analyze BWR cores which might have a mixed loading of different fuel types. First, an assembly based modular ray tracing scheme was implemented for the Method of Characteristic (MOC) calculation, and a CMFD formulation applicable for unaligned mesh conditions was then developed for acceleration the MOC calculation. The new calculation feature has been validated by comparing DeCART BWR assembly calculations with the MCU Monte Carlo calculations. A good agreement identified by the maximum eigenvalue difference of 120 pcm and the maximum pin power error of about 1% has been achieved. The CMFD scheme is shown to reduce the number of MOC iterations by factors of 12-25 without loss of accuracy. (authors)

Part of:
Validation of the TRACE Code Against Post-Dryout Experiments in Tubes and Annuli

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park (United States)
ISBN
0-89448-698-5
Imprint Title
Proceedings of the 2006 international congress on advances in nuclear power plants - ICAPP'06
Imprint Pagination
2734 p.
Journal Page Range
p. 2449-2453

Conference

Title
2006 International congress on advances in nuclear power plants - ICAPP'06
Dates
4-8 Jun 2006
Place
Reno - Nevada (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
39042930
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCURACY; BWR TYPE REACTORS; ERRORS; LOSSES; MONTE CARLO METHOD; NUCLEAR FUELS
Descriptors DEC
CALCULATION METHODS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
8 refs.