Published 1989
| Version v1
Book
Parametric study of thermal feedback and other transient effects, based on the INTERPIN code
Description
This paper discusses the INTERPIN code, used for parametric sensitivity studies of thermal feedback. The variational parameter was the thermal gap prior to an overpower. The author states that INTERPIN, which models the fission gas release in a truly transient way, showed that for large gap prior to the overpower, significant gas release may be expected during a fast power increase, with continuing release during the overpower. In contrast, for small gap the release during the power rise may be negligible, while significant release can be expected during the first hours of the overpower, subject to grain boundary saturation. The findings are supported by a simplified analytical theory
Additional details
Publishing Information
- Publisher
- American Association for Structural Mechanics in Reactor Technology.
- Imprint Place
- Los Angeles, CA (USA)
- ISBN
- 0-9623306-0-4
- Imprint Title
- Transactions of the 10th international conference on structural mechanics in reactor technology
- Imprint Pagination
- 99 p.
- Series
- Fuel elements and assemblies.
- Journal Page Range
- p. 33-44.
Conference
- Title
- 10. international conference on Structural Mechanics in Reactor Technology (SMIRT).
- Dates
- 14-18 Aug 1989.
- Place
- Anaheim, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21088000
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALGORITHMS; ANALYTICAL SOLUTION; FAST REACTORS; FISSION PRODUCT RELEASE; GRAIN BOUNDARIES; I CODES; MULTI-PARAMETER ANALYSIS; REACTOR PHYSICS; SENSITIVITY ANALYSIS; THERMAL CYCLING; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CRYSTAL STRUCTURE; EPITHERMAL REACTORS; MICROSTRUCTURE; REACTOR ACCIDENTS; REACTORS
Optional Information
- Secondary number(s)
- CONF-890855--.