Published 1988 | Version v1
Book

Transient safety performance of the PRISM innovative liquid metal reactor

  • 1. General Electric Co., San Jose, CA (USA). Nuclear Energy Div.

Description

The PRISM sodium-cooled reactor concept utilizes passive safety characteristics and modularity to increase performance margins, improve licensability, reduce owner's risk and reduce costs. The relatively small size of each reactor module (471 MWt) facilitates the use of passive self-shutdown and shutdown heat removal features, which permit design simplification and reduction of safety-related systems. Key to the transient performance is the inherent negative reactivity feedback characteristics of the core design resulting from the use of metal (U-Pu-Zr) swing, and very low control rod runout worth. Selected beyond design basis events relying only on these core design features are analyzed and the design margins summarized to demonstrate the advancement in reactor safety achieved with the PRISM design concept

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (USA)
ISBN
89448-1460-0
Imprint Title
Proceedings of the international topical meeting on safety of next generation power reactors
Imprint Pagination
933 p.
Journal Page Range
p. 813-820.

Conference

Title
American Nuclear Society topical meeting on the safety of next generation power reactors.
Dates
1-5 May 1988.
Place
Seattle, WA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
22023564
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT REMOVAL; PLUTONIUM; REACTIVITY; REACTOR SAFETY; SODIUM COOLED REACTORS; SPECIFICATIONS; URANIUM; ZIRCONIUM
Descriptors DEC
ACTINIDES; ELEMENTS; LIQUID METAL COOLED REACTORS; METALS; REACTORS; SAFETY; TRANSITION ELEMENTS; TRANSURANIUM ELEMENTS

Optional Information

Secondary number(s)
CONF-880506--.