Published 1991 | Version v1
Report Metadata-only

German Standard Problem No. 4A 'Structural dynamic behaviour of a pipe with nonreturn valve during blowdown' (HDR-SRV 350, experiment no. 60.4.1, structural dynamics)

Creators

Description

The HDR-SRV 350 blowdown experiments reported here were to determine by measurement and calculation the structural dynamic reaction of the feedwater line in response to the pressure waves induced by pipe rupture or closing of the nonreturn valve. The two subreports present the evaluation of the maximum and the minimum of all measured and calculated structural displacements and of tangential stresses. (orig.)

Availability note (English)

Available from FIZ Karlsruhe.

Abstract (German)

In den HDR-SRV 350-Blowdown-Versuchen wurden strukturdynamische Reaktionen der Speisewasserleitung infolge Rohrbruch oder Absperren des Rueckschlagventils entstehender Druckwellen gemessen und berechnet. Die beiden Teilberichte enthalten die Auswertung des Maximum und Minimum aller gemessenen und berechneten Verschiebungen sowie der Tangentialspannungen. (orig.)

Additional details

Additional titles

Subtitle (English)
Comparative analysis report. Annex 6 and 7
Original title (German)
Deutsches Standard-Problem Nr. 4A 'Dynamisches Strukturverhalten einer Rohrleitung mit Rueckschlagventil bei Blowdown' (HDR-SRV 350 Versuch Nr. 60.4.1, Strukturdynamik)
Original subtitle (German)
Vergleichsbericht - Anhang 6 und 7.

Publishing Information

Imprint Pagination
201 p.
Series
Schriftenreihe Reaktorsicherheit und Strahlenschutz.
ISSN
0724-3316
Report number
BMU--1991-315

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
25074014
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
BLOWDOWN; COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; DYNAMIC LOADS; FEEDWATER; FLUID-STRUCTURE INTERACTIONS; HDR REACTOR; IMPACT SHOCK; PRIMARY COOLANT CIRCUITS; REACTOR SAFETY EXPERIMENTS
Descriptors DEC
BWR TYPE REACTORS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Contract/Grant/Project number
Project Number BMU SR 279
Secondary number(s)
GRS-A--1035/II.