You need JavaScript to view this

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

Abstract

The meeting covered the following topics: Developments in design of safety-related heat removal components and systems for advanced water cooled reactors; status of test programmes on heat removal components and systems of new designs; range of validity and extrapolation of test results for the qualification of design/licensing computer models and codes for advanced water cooled reactors; future needs and trends in testing of safety systems for advanced water cooled reactors. Tests of heat removal safety systems have been conducted by various groups supporting the design, testing and certification of advanced water cooled reactors. The Technical Committee concluded that the reported test results generally confirm the predicted performance features of the advanced designs. Refs, figs, tabs.
Authors:
"NONE"
Publication Date:
Apr 01, 1996
Product Type:
Conference
Report Number:
IAEA-TECDOC-872; CONF-9505376-
Reference Number:
SCA: 220400; 210200; 210100; PA: AIX-27:072935; EDB-96:164613; NTS-97:003948; SN: 96001686098
Resource Relation:
Conference: Technical committee meeting on progress in design, research and development and testing of safety systems for advanced water cooled reactors, Piacenza (Italy), 16-19 May 1995; Other Information: PBD: Apr 1996
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; REACTOR PROTECTION SYSTEMS; MEETINGS; WATER COOLED REACTORS; REACTOR SAFETY; AFTER-HEAT REMOVAL; COMPUTER CODES; COORDINATED RESEARCH PROGRAMS; DESIGN; IAEA; INTERNATIONAL COOPERATION; LEADING ABSTRACT; MEMBER STATES; REACTOR COMPONENTS; TECHNOLOGY TRANSFER; VALIDATION; VERIFICATION
OSTI ID:
390516
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Journal ID: ISSN 1011-4289; Other: ON: DE97604364; TRN: XA9642442072935
Availability:
INIS; OSTI as DE97604364
Submitting Site:
INIS
Size:
387 p.
Announcement Date:

Citation Formats

Progress in design, research and development and testing of safety systems for advanced water cooled reactors. Proceedings of a technical committee meeting. IAEA: N. p., 1996. Web.
Progress in design, research and development and testing of safety systems for advanced water cooled reactors. Proceedings of a technical committee meeting. IAEA.
1996. "Progress in design, research and development and testing of safety systems for advanced water cooled reactors. Proceedings of a technical committee meeting." IAEA.
@misc{etde_390516,
title = {Progress in design, research and development and testing of safety systems for advanced water cooled reactors. Proceedings of a technical committee meeting}
abstractNote = {The meeting covered the following topics: Developments in design of safety-related heat removal components and systems for advanced water cooled reactors; status of test programmes on heat removal components and systems of new designs; range of validity and extrapolation of test results for the qualification of design/licensing computer models and codes for advanced water cooled reactors; future needs and trends in testing of safety systems for advanced water cooled reactors. Tests of heat removal safety systems have been conducted by various groups supporting the design, testing and certification of advanced water cooled reactors. The Technical Committee concluded that the reported test results generally confirm the predicted performance features of the advanced designs. Refs, figs, tabs.}
place = {IAEA}
year = {1996}
month = {Apr}
}