Parametric study of pipe whip behavior. 4B, sch-80 pipe under BWR condition
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki(Japan). Tokai Research Establishment
Description
A pipe whip test is one of the main subjects of the pipe rupture tests performed in Japan Atomic Energy Research Institute. In 1979, the pipe whip test of 4B, sch-80 pipe will be done under the BWR condition. As the preliminary analysis of this test, the pipe whip analysis of 4B, sch-80 pipe was implemented in order to make clear of the influences of the physical parameters on the pipe whip behavior. The pipe whip analysis was treated as nonlinear dynamic analysis of pipe-restraint system by using the general purpose finite element program ADINA. Overhang length, clearance between pipe and restraint, restraint length and cross section area of restraint were taken as physical parameters. It was clarified through this analysis how restraint displacement, restraint strain and distribution of energy between pipe and restraint were influenced by these parameters. (author)
Availability note (English)
Available from DOI: https://doi.org/10.3327/jaesj.21.518Abstract (Japanese)
軽水型原子力発電プラントではその安全性を確保するために、設計に際して想定事故を考慮しなければならない。冷却材喪失事故(LOCA)はこの想定事故の1つであるが、これは1次冷却系配管の瞬時破断により生じるものとされている。配管の瞬時破断が生じると、高温高圧の内部流体が配管の破断口から放出され、配管には大きなスラスト力が働く。スラスト力により配管が首振り運動することをパイプホイップ(pipewhip)と呼んでいる。配管の瞬時破断が生じても、パイプホイップによる配管の運動を制限し、他の隣接機器への波及効果を最小限にとどめるためにレストレントが取り付けられている。 (著者)Additional details
Additional titles
- Original title (Japanese)
- パイプホイップ現象に及ぼす各種パラメータの影響 BWR条件下の4B, sch-80パイプ
Identifiers
- DOI
- 10.3327/jaesj.21.518;
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai-Shi
- Journal Volume
- 21
- Journal Issue
- 6
- Journal Page Range
- p. 518-529
- ISSN
- 0004-7120
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 53100939
- Subject category
- S54: ENVIRONMENTAL SCIENCES;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BLOWDOWN; BWR TYPE REACTORS; DIAGRAMS; FINITE ELEMENT METHOD; MECHANICAL VIBRATIONS; NONLINEAR PROBLEMS; NUMERICAL SOLUTION; PIPES; PRIMARY COOLANT CIRCUITS; STRAINS; STRESS ANALYSIS; THEORETICAL DATA
- Descriptors DEC
- CALCULATION METHODS; COOLING SYSTEMS; DATA; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; INFORMATION; MATHEMATICAL SOLUTIONS; NUMERICAL DATA; NUMERICAL SOLUTION; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3412000; This record replaces 11548817