Published November 1981 | Version v1
Report Restricted

German standard problem 4A. Technical report (final) October 1980-September 1981

Creators

Description

This study deals with structural piping response to dynamic loads generated by hydraulic transients in nuclear power plants. Transients were induced by means of a rupture disc and closure of a feedwater check valve at the Heissdampfreaktor, West Germany. Blind predictions of piping response were made using the computer code EASE2. Comparison between computer simulations and experimental observations are contained in the report

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS. PC A08/MF A01.

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Additional details

Publishing Information

Imprint Pagination
154 p.
Report number
NUREG/CR--2390

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
13699436
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Descriptors DEI
COMPUTERIZED SIMULATION; DYNAMIC LOADS; FINITE ELEMENT METHOD; HDR REACTOR; PIPELINES; REACTOR COOLING SYSTEMS; TESTING; TRANSIENTS
Descriptors DEC
BWR TYPE REACTORS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; NUMERICAL SOLUTION; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS