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Sensitivity of performance and safety characteristics of PRISM oxide core to design methodologies and possible design optimization

Conference:

Abstract

Presently ENEA programs in the field of nuclear energy are focused principally on new concepts of advanced reactors, characterized by inherent and passive safety features. Among the several plants proposed or designed by organizations or industries in the world, great interest was aroused by the PRISM reactor, designed by General Electric, as a relatively small sodium-cooled fast reactor able to withstand severe uncontrolled accidents without serious core damages. U-Pu-Zr metal is the reference fuel for the PRISM core. However, an oxide core has been designed as an alternative within the same core envelope, aimed at achieving comparable transient response characteristics to the reference metal fuel. In 1989, General Electric and ENEA agreed on a joint activity to verify, compare and, if possible, optimize the alternative oxide core steady-state and transient characteristics, taking into account safety and economic requirements. The parallel utilization of USA (by GE) and European (by ENEA) methodologies allow a complete comparison of the results. The initial methodology sensitivity studies are summarized in this paper.
Publication Date:
Dec 31, 1991
Product Type:
Conference
Report Number:
ETDE-IT-93-13; CONF-911001-28
Reference Number:
SCA: 050700; 210500; PA: ITAN-93:000026; SN: 93000925445
Resource Relation:
Conference: International conference on fast reactor systems and fuel cycles,Kyoto (Japan),27 Oct - 1 Nov 1991; Other Information: PBD: 1991
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LIQUID METAL COOLED REACTORS; ALLOY NUCLEAR FUELS; MIXED OXIDE FUELS; COORDINATED RESEARCH PROGRAMS; TERNARY ALLOY SYSTEMS; URANIUM OXIDES; PLUTONIUM OXIDES; ZIRCONIUM ALLOYS; ITALIAN ENEA; USA; COMPARATIVE EVALUATIONS; 050700; 210500; FUELS PRODUCTION AND PROPERTIES; POWER REACTORS, BREEDING
OSTI ID:
10118509
Research Organizations:
ENEA, Bologna (Italy)
Country of Origin:
Italy
Language:
English
Other Identifying Numbers:
Other: ON: DE93758931; TRN: 93:000026
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
ITAN
Size:
10 p.
Announcement Date:
Jun 30, 2005

Conference:

Citation Formats

Lipps, A J, Wu, T, Cecchini, F, and Dominici, G. Sensitivity of performance and safety characteristics of PRISM oxide core to design methodologies and possible design optimization. Italy: N. p., 1991. Web.
Lipps, A J, Wu, T, Cecchini, F, & Dominici, G. Sensitivity of performance and safety characteristics of PRISM oxide core to design methodologies and possible design optimization. Italy.
Lipps, A J, Wu, T, Cecchini, F, and Dominici, G. 1991. "Sensitivity of performance and safety characteristics of PRISM oxide core to design methodologies and possible design optimization." Italy.
@misc{etde_10118509,
title = {Sensitivity of performance and safety characteristics of PRISM oxide core to design methodologies and possible design optimization}
author = {Lipps, A J, Wu, T, Cecchini, F, and Dominici, G}
abstractNote = {Presently ENEA programs in the field of nuclear energy are focused principally on new concepts of advanced reactors, characterized by inherent and passive safety features. Among the several plants proposed or designed by organizations or industries in the world, great interest was aroused by the PRISM reactor, designed by General Electric, as a relatively small sodium-cooled fast reactor able to withstand severe uncontrolled accidents without serious core damages. U-Pu-Zr metal is the reference fuel for the PRISM core. However, an oxide core has been designed as an alternative within the same core envelope, aimed at achieving comparable transient response characteristics to the reference metal fuel. In 1989, General Electric and ENEA agreed on a joint activity to verify, compare and, if possible, optimize the alternative oxide core steady-state and transient characteristics, taking into account safety and economic requirements. The parallel utilization of USA (by GE) and European (by ENEA) methodologies allow a complete comparison of the results. The initial methodology sensitivity studies are summarized in this paper.}
place = {Italy}
year = {1991}
month = {Dec}
}