Published 1997
| Version v1
Journal article
Three-dimensional Monte Carlo model for BWR fluence calculations
Creators
- 1. General Electric Co., San Jose, CA (United States)
- 2. General Electric Co., Pleasanton, CA (United States)
Description
A three-dimensional Monte Carlo model has been developed for accurate boiling water reactor (BWR) neutron and gamma fluence calculations using continuous-energy MCNP. Unlike earlier light water reactor models being run in the fixed-source mode with simplified geometries, this model is run in the criticality mode with actual geometry and material composition. The MCNP fast flux shapes in the downcomer region are qualified against measurements and are compared with results from two-dimensional deterministic DORT calculations
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 77
- Journal Page Range
- p. 335-336.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- 1997 American Nuclear Society (ANS) winter meeting.
- Dates
- 16-20 Nov 1997.
- Place
- Albuquerque, NM (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 29021082
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CRITICALITY; M CODES; MONTE CARLO METHOD; NEUTRON FLUENCE; NEUTRON FLUX
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; RADIATION FLUX; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-971125--.