Published 1997
| Version v1
Book
Methodology for the calculation of neutron fluence onto VVER-440 reactor pressure vessel
Description
In the present paper we suggest a methodology to calculate the neutron fluence onto WWER type reactor pressure vessel. To simulate the penetration of neutrons outgoing from the core, an IBM PC version of the Monte Carlo code system HEXANN-EVALU is used. A survey of the improvements needed to perform this conversion is also presented. We show the procedure to obtain the neutron source data emerging from reactor core based on the results of the code SPPS-1, used to simulate the WWER-440 cycle. Finally, using the results of the code system, a sequence of mathematical expressions are given in order to estimate the fluence onto the vessel and the corresponding Lead Factor
Additional details
Additional titles
- Original title (Spanish)
- Metodologia para el calculo de la fluencia de neutrones en la vasija del reactor VVER-440
Publishing Information
- Publisher
- Centro de Informacion de la Energia Nuclear.
- Imprint Place
- La Habana (Cuba)
- Imprint Title
- Main scientific technical results of the Nuclear Technology Center. 1996
- Imprint Pagination
- 103 p.
- Journal Page Range
- p. 74-86.
INIS
- Country of Publication
- Cuba
- Country of Input or Organization
- Cuba
- INIS RN
- 28059692
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CALCULATION METHODS; COMPUTER CALCULATIONS; JURAGUA-1 REACTOR; MONTE CARLO METHOD; NEUTRON FLUENCE; PRESSURE VESSELS; S CODES; TRANSPORT THEORY
- Descriptors DEC
- COMPUTER CODES; CONTAINERS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- Imprint:Principales resultados Cientificos Tecnicos del Centro de Tecnologia Nuclear. 1996.