Published 1994
| Version v1
Book
Seismic behavior of a fuel assembly in the reactor core
Creators
- 1. Korea Atomic Energy Research Inst., Taejon (Korea, Republic of). Power Reactor Mechanical Engineering
- 2. Chonnam National Univ., Kwangju (Korea, Republic of). Dept. of Machine Design
Description
A general approach to the dynamic time-history analysis of the reactor core is presented in this paper as a part of the fuel assembly qualification program. Several detailed core models are set up to reflect the placement of the fuel assemblies within the core shroud. Peak horizontal responses are obtained for each model for the motions induced from earthquake. The dynamic responses such as fuel assembly deflected shapes and spacer grid impact loads are carefully investigated. Also, the sensitivity responses are obtained for the earthquake motions and the fuel assembly non-linear response characteristics are discussed
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-1198-0
- Imprint Title
- Seismic engineering -- 1994: Volume 1. PVP-Volume 275-1
- Imprint Pagination
- 287 p.
- Journal Page Range
- p. 123-128.
Conference
- Title
- 1994 pressure vessels and piping conference.
- Dates
- 19-23 Jun 1994.
- Place
- Minneapolis, MN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26021912
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ACCELERATION; CERTIFICATION; COMPUTERIZED SIMULATION; DESIGN; EXPERIMENTAL DATA; FUEL ASSEMBLIES; IMPACT SHOCK; MATHEMATICAL MODELS; PWR TYPE REACTORS; REACTOR CORES; RESPONSE FUNCTIONS; S CODES; SEISMIC EFFECTS; STRESS ANALYSIS
- Descriptors DEC
- COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; FUNCTIONS; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-940613--.