Published September 1999
| Version v1
Book
The MCU Monte Carlo Code for 3D Depletion Calculation
Creators
- 1. Institute of Nuclear Reactors, Russian Research Center 'Kurchatov Institute', Moscow (Russian Federation)
Description
The application of the Monte Carlo method to the analysis of fuel depletion is becoming more widely used nowadays. What is more - in some cases the Monte Carlo is the only reliable method for depletion calculation. The description of the MCU-B continuous energy Monte Carlo code for depletion calculation of 3D systems is given in this paper. Some results of depletion calculations obtained by MCU are also presented. (author)
Additional details
Publishing Information
- Publisher
- Senda Editorial S.A.
- Imprint Place
- Madrid (Spain)
- ISBN
- 84-699-0942-8
- Imprint Title
- M and C'99 - Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications
- Imprint Pagination
- 2249 p.
- Journal Page Range
- p. 997-1006
Conference
- Title
- Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications
- Acronym
- M and C'99
- Dates
- 27-30 Sep 1999
- Place
- Madrid (Spain)
INIS
- Country of Publication
- Spain
- Country of Input or Organization
- France
- INIS RN
- 54117008
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; MONTE CARLO METHOD; NUCLEAR FUELS
- Descriptors DEC
- CALCULATION METHODS; ENERGY SOURCES; FUELS; MATERIALS; REACTOR MATERIALS; SIMULATION
Optional Information
- Notes
- 7 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses