Spent VVER fuel storage subcriticality investigation
Creators
- 1. Nuclear Research Inst., Rez (Czech Republic). Nuclear Reactor Physics Div.
Description
The experimental method used on the LR-0 critical assembly to estimate the subcriticality of the spent fuel compact storage configurations is described. The experimental results obtained both for the VVER-1000 and VVER-440 assemblies are presented. Several calculations supporting experiments on the LR-0 critical assembly with a driver zone and a subcritical part of the core related to a spent fuel storage design were carried out. Using the ANISN and DOT 4.2 codes one and two dimensional criticality calculations resulted in finding out both z-axis power density behavior and the range of its asymptotic part. These calculations justify the applicability of the experimental method. Subcriticality calculations for all the experimental configurations modeling compact storage pools were performed by the WIMS code. The comparison of numerical results and experimental data was done
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0691-X
- Imprint Title
- Proceedings of the 1993 international conference on nuclear waste management and environmental remediation. Volume 1: Low and intermediate level radioactive waste management
- Imprint Pagination
- 776 p.
- Journal Page Range
- p. 291-296.
Conference
- Title
- '93 international conference on nuclear waste management and environmental remediation.
- Dates
- 5-11 Sep 1993.
- Place
- Prague (Czech Republic).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27008362
- Subject category
- S42: ENGINEERING; S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CALCULATION METHODS; CRITICALITY; EXPERIMENTAL DATA; SPENT FUEL STORAGE; W CODES; WWER-3 REACTOR; WWER-5 REACTOR
- Descriptors DEC
- COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTORS; STORAGE; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Secondary number(s)
- CONF-930906--.