Published April 1996 | Version v1
Report Metadata-only

Experimental study of isolation condenser performances by PIPE-ONE apparatus

Creators

  • 1. Universita degli Studi, Pisa (Italy). Dipartimento di Construzioni Meccaniche e Nucleari

Description

The paper discussed an experiment performed in PIPER-ONE facility which simulates a General Electric BWR-6 with volume and height scaling ratios of 1/2200 and 1/1, respectively. The apparatus was properly modified to test the thermalhydraulic characteristics of an isolation condenser-type system. THis system consists in an once-through heat exchanger, immersed in a pool with water at ambient temperature and installed at about 10 m above the core. The analysis of a first test on isolation condenser behaviour, named PO-SD-8, performed in 1992 showed that the RELAP5 code predicts well the overall thermohydraulic behaviour, but discrepancies were identified in predicting local phenomena occurring in the pool and in the isolation condenser. Therefore a second test, (named PO-IC-2), has been performed with improved instrumentation. The paper describes the results obtained in test PO-IC-2 and discusses the capabilities of the Relap5/Mod3.1 code. (author). 22 refs, 10 figs, 4 tabs

Part of:
Progress in design, research and development and testing of safety systems for advanced water cooled reactors. Proceedings of a technical committee meeting

Additional details

Publishing Information

Imprint Title
Progress in design, research and development and testing of safety systems for advanced water cooled reactors. Proceedings of a technical committee meeting
Imprint Pagination
387 p.
Journal Page Range
p. 279-293.
ISSN
1011-4289
Report number
IAEA-TECDOC--872

Conference

Title
Technical committee meeting on progress in design, research and development and testing of safety systems for advanced water cooled reactors.
Dates
16-19 May 1995.
Place
Piacenza (Italy).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
27072899
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
BWR TYPE REACTORS; EXPERIMENTAL DATA; ISOLATION CONDENSERS; R CODES; REACTOR SAFETY; RELIABILITY; TESTING
Descriptors DEC
COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTORS; SAFETY; STEAM CONDENSERS; THERMAL REACTORS; VAPOR CONDENSERS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information