Published 1993 | Version v1
Book Metadata-only

RELAP5/MOD2 analysis of the station blackout experiment SP-ST-01, performed in SPES facility

Creators

  • 1. NUC RIN ENEA, Bologna (Italy)

Description

SPES integral test facility is a scale model of a commercial three-loop PWR plant, allowing the simulation of a wide range of accident scenarios. A loss of on/off site power test was carried out on this facility in November 1989, with the aim of investigating the effects induced in the primary system by the application of a ''bleed and feed'' procedure. This test, planned in the frame of the ENEA-NRC cooperation on Accident Management Program, was included in the test matrix of the International Code Assessment Program for validation of RELAP5/Mod.2 code. This paper presents a survey of the results of the post-test calculations performed with the above mentioned code

Part of:
2nd ASME-JSME international conference on nuclear engineering -- 1993

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-0636-7
Imprint Title
2nd ASME-JSME international conference on nuclear engineering -- 1993
Imprint Pagination
770 p.
Journal Page Range
p. 237-246.

Conference

Title
2. Japan Society of Mechanical Engineers (JSME)/American Society of Mechanical Engineers (ASME) joint international conference on nuclear engineering.
Dates
21-24 Mar 1993.
Place
San Francisco, CA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
25058805
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
COMPUTER CALCULATIONS; DEPRESSURIZATION; EXPERIMENTAL DATA; OUTAGES; PWR TYPE REACTORS; R CODES; REACTOR ACCIDENTS; REACTOR SAFETY EXPERIMENTS; TEST FACILITIES; THEORETICAL DATA
Descriptors DEC
ACCIDENTS; COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-930352--.