Published 1983 | Version v1
Book

Analytical and experimental evaluations of the blowdown thrust forces

  • 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Div. of Nuclear Safety Research

Description

An instantaneous pipe rupture is considered to be one of the hypothetical accidents in the light water reactor. To evaluate the dynamic responses of the pipe-restraint system under the LOCA conditions, the time hystories of the blowdown thrust force must be clarified both experimentally and analytically. The studies of pipe rupture accidents concerning both the jet discharge and the pipe whipping have been performed at the Japan Atomic Energy Research Institute (JAERI). This paper presents the experimental and analytical studies of the blowdown thrust forces. It comprises the evaluations of the time-dependent and the maximum blowdown thrust forces, and those influences by the break area and the break mode. The tests were carried out under the PWR or the BWR LOCA conditions using a 4-inch or 6-inch diameter pipe. The blow-down thrust forces were analytically evaluated both by the momentum equation, and by the thermal-hydraulic quantities which were obtained from the analysis by the RELAP4/MOD5 code. (orig./RW)

Additional details

Publishing Information

Publisher
North-Holland.
Imprint Place
Amsterdam (Netherlands)
ISBN
0 444 86695 7
Imprint Title
Transactions of the 7. international conference on structural mechanics in reactor technology. Vol. F
Imprint Pagination
426 p.
Journal Page Range
p. 29-38.

Conference

Title
7. international seminar on computational aspects of the finite element method (CAFEM-7) in conjunction with the 7. international conference on structural mechanics in reactor technology (SMIRT-7).
Dates
22-26 Aug 1983.
Place
Chicago, IL (USA).

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
15049632
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BLOWDOWN; DYNAMIC LOADS; LOSS OF COOLANT; PIPES; R CODES; REACTOR COMPONENTS; REACTOR SAFETY; RESTRAINTS; RUPTURES
Descriptors DEC
ACCIDENTS; COMPUTER CODES; FAILURES; REACTOR ACCIDENTS; SAFETY

Optional Information

Secondary number(s)
EUR--8596 DE/EN/FR.