Published 1996 | Version v1
Book Metadata-only

SPES-2, experimental results from the S00908 blind test: Cold leg balance line DEG break

Creators

  • 1. SIET S.p.A., Piacenza (Italy)
  • 2. Westinghouse Electric Co., Pittsburgh, PA (United States)
  • 3. ENEA-ERG-FISS, Bologna (Italy)

Description

The SPES-2 is a full height, full pressure experimental test facility reproducing the Westinghouse AP600 reactor with a scaling factor of 1/395. The experimental plant, designed and operated by, SIET in Piacenza, consists of a full simulation of the AP600 primary core cooling system including all the passive safety and active non-safety systems. In 1992, Westinghouse, in cooperation with ENEL, ENEA, SIET and ANSALDO developed an experimental program to test the integrated behavior of the AP600 passive safety systems. The SPES-2 test matrix, concluded in November '94, has examined the AP600 passive safety system response for a range of small break LOCAs at different locations on the primary system and on the passive system lines; single steam generator tube ruptures with both passive and active nonsafety systems, and a main steam line break transient to demonstrate the capability of passive safety systems for rapid cooldown. Each of the tests has provided detailed experimental results for verification of the capability of the analysis methods to predict the integrated passive safety system behavior

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-1226-X
Imprint Title
ICONE-4: Proceedings. Volume 2: Advanced reactors
Imprint Pagination
637 p.
Journal Page Range
p. 289-296.

Conference

Title
ASME/JSME international conference on nuclear engineering.
Acronym
ICONE 4
Dates
10-13 Mar 1996.
Place
New Orleans, LA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
27060020
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
COMPARATIVE EVALUATIONS; ENGINEERED SAFETY SYSTEMS; EXPERIMENTAL DATA; LOSS OF COOLANT; PERFORMANCE TESTING; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR SAFETY EXPERIMENTS; SCALE MODELS; TEST FACILITIES
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; DATA; ENRICHED URANIUM REACTORS; EVALUATION; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; STRUCTURAL MODELS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-960306--.