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Proceedings of the CSNI Specialist Meeting on Transient Two-Phase Flow - Current Issues in System Thermal Hydraulics

Abstract

The 4. Specialists' Meeting on Transient Two Phase Flow was organized by the Safety Research Department of the French Nuclear Safety and Protection Institute at the request of the OECD Committee for the Safety of Nuclear Installations. After Toronto in 1976, Paris in 1978 and Pasadena in 1981, the Aix-en-Provence meeting was in keeping with the course of studies initiated by the Thermalhydraulic Systems Behavior Task Group of the Principal Working Group No.2 for discussing the achievements and defining the needs of safety research in accident thermal-hydraulics. 60 Specialists from 14 Countries (Belgium, Canada, Finland, France, Germany, Italy, Japan, the Netherlands, the United Kingdom, the USA, Spain, Sweden, Switzerland, Taiwan) attended the meeting, representing a large spectrum of experts from National Safety Authorities, Research Laboratories, Universities, Vendors and Utilities. These specialists had to review the 15-year research period which had elapsed since the last meetings. This period had been characterized by the issuance of the large thermalhydraulic computer codes for LWR accidents, the performance of several hundreds of separate effect tests for the development and the qualification of the physical models, the carrying-out of the large experimental programmes on system loops (up to scale 1) for verifying the computer codes.  More>>
Authors:
Reocreux, M; Rubinstein, M C [1] 
  1. CEA-IPSN/DRS/SEMAR, Centre d'Etudes Nucleaires de Cadarache, 13108 Saint Paul-lez-Durance (France)
Publication Date:
Jul 01, 1992
Product Type:
Technical Report
Report Number:
NEA-CSNI-R-1992-12
Resource Relation:
Conference: CSNI Specialist Meeting on Transient Two-Phase Flow - Current Issues in System Thermal Hydraulics, Aix-en-Provence (France), 6-8 Apr 1992; Other Information: Country of input: International Atomic Energy Agency (IAEA)
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; COMPUTER CODES; EVALUATION; MEETINGS; NUCLEAR FACILITIES; PERFORMANCE; PROCEEDINGS; REACTOR ACCIDENTS; SAFETY; THERMAL HYDRAULICS; TRANSIENTS; TWO-PHASE FLOW
OSTI ID:
21176638
Research Organizations:
Organisation for Economic Co-Operation and Development - Nuclear Energy Agency, Committee on the safety of nuclear installations - OECD/NEA/CSNI, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)
Country of Origin:
NEA
Language:
English
Other Identifying Numbers:
TRN: XN09C0110052106
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
633 pages
Announcement Date:
Jul 06, 2009

Citation Formats

Reocreux, M, and Rubinstein, M C. Proceedings of the CSNI Specialist Meeting on Transient Two-Phase Flow - Current Issues in System Thermal Hydraulics. NEA: N. p., 1992. Web.
Reocreux, M, & Rubinstein, M C. Proceedings of the CSNI Specialist Meeting on Transient Two-Phase Flow - Current Issues in System Thermal Hydraulics. NEA.
Reocreux, M, and Rubinstein, M C. 1992. "Proceedings of the CSNI Specialist Meeting on Transient Two-Phase Flow - Current Issues in System Thermal Hydraulics." NEA.
@misc{etde_21176638,
title = {Proceedings of the CSNI Specialist Meeting on Transient Two-Phase Flow - Current Issues in System Thermal Hydraulics}
author = {Reocreux, M, and Rubinstein, M C}
abstractNote = {The 4. Specialists' Meeting on Transient Two Phase Flow was organized by the Safety Research Department of the French Nuclear Safety and Protection Institute at the request of the OECD Committee for the Safety of Nuclear Installations. After Toronto in 1976, Paris in 1978 and Pasadena in 1981, the Aix-en-Provence meeting was in keeping with the course of studies initiated by the Thermalhydraulic Systems Behavior Task Group of the Principal Working Group No.2 for discussing the achievements and defining the needs of safety research in accident thermal-hydraulics. 60 Specialists from 14 Countries (Belgium, Canada, Finland, France, Germany, Italy, Japan, the Netherlands, the United Kingdom, the USA, Spain, Sweden, Switzerland, Taiwan) attended the meeting, representing a large spectrum of experts from National Safety Authorities, Research Laboratories, Universities, Vendors and Utilities. These specialists had to review the 15-year research period which had elapsed since the last meetings. This period had been characterized by the issuance of the large thermalhydraulic computer codes for LWR accidents, the performance of several hundreds of separate effect tests for the development and the qualification of the physical models, the carrying-out of the large experimental programmes on system loops (up to scale 1) for verifying the computer codes. Although this research was mainly characterized by remarkable success, limitations still exist. In a safety approach, there need to be well identified and handled, and the specialists were asked to exchange their views in order to determine which solutions they expected to be affordable in the future. Safety applications have already started which use these latest research achievements. They raise specific problems such as the use of validation matrices, the evaluation of uncertainties, the identification and the control of unavoidable users' effects. The specialists were required to exchange their experience of applications and to define how to improve them in the future. Finally, one cannot consider the future without a careful review of the new and important problems raised by the safety issues of existing plants in Eastern Countries, as well as the new concepts of future plants and the increasing requirements for more detailed evaluations of severe accidents. These prospective areas were on the programme of the specialists in order that they define future needs and that they determine the research needed to satisfy them. The papers upon which this Specialist meeting was based, all invited, together with the exchanges of views and experiences which took place, undoubtedly succeeded in reaching the planned objectives. The present proceedings are the indication of how well this was accomplished.}
place = {NEA}
year = {1992}
month = {Jul}
}