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Title: PRISM: An innovative liquid metal fast breeder reactor

Abstract

This paper describes an innovative sodium-cooled reactor concept employing small certified reactor modules coupled with a standardized steam generator system. The total plant employs nine PRISM reactors (power reactor inherently safe module) in three 415 MWe power blocks. The PRISM design concept utilizes inherent safety characteristics and modularity to improve licensability, reduce owner's risk, and reduce costs. The relatively small size of each reactor module facilitates the use of passive, inherent self-shutdown and shutdown heat removal features, which permit design simplification and reduction of safety-related systems. It is proposed that a single PRISM module be used in a full-scale integrated reactor safety test. Results from the test would be used to obtain NRC certification of the standard design.

Authors:
; ; ;
Publication Date:
Research Org.:
General Electric Co., Nuclear Systems Technology Operation, Sunnyvale, CA
OSTI Identifier:
6613392
Report Number(s):
CONF-861005-
TRN: 87-018337
Resource Type:
Conference
Resource Relation:
Conference: Joint power generation conference, Portland, OR, USA, 19 Oct 1986
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LMFBR TYPE REACTORS; DESIGN; CAPITALIZED COST; FABRICATION; INVESTMENT; MODULAR STRUCTURES; OCCUPATIONAL SAFETY; PERFORMANCE TESTING; POWER RANGE 100-1000 MW; REACTOR SAFETY; RISK ASSESSMENT; SHUTDOWNS; STEAM GENERATORS; BOILERS; BREEDER REACTORS; COST; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTORS; SAFETY; TESTING; VAPOR GENERATORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210500 - Power Reactors, Breeding; 210800 - Nuclear Power Plants- Economics

Citation Formats

Kruger, G B, Boardman, C E, Olich, E E, and Switick, D M. PRISM: An innovative liquid metal fast breeder reactor. United States: N. p., 1986. Web.
Kruger, G B, Boardman, C E, Olich, E E, & Switick, D M. PRISM: An innovative liquid metal fast breeder reactor. United States.
Kruger, G B, Boardman, C E, Olich, E E, and Switick, D M. Wed . "PRISM: An innovative liquid metal fast breeder reactor". United States.
@article{osti_6613392,
title = {PRISM: An innovative liquid metal fast breeder reactor},
author = {Kruger, G B and Boardman, C E and Olich, E E and Switick, D M},
abstractNote = {This paper describes an innovative sodium-cooled reactor concept employing small certified reactor modules coupled with a standardized steam generator system. The total plant employs nine PRISM reactors (power reactor inherently safe module) in three 415 MWe power blocks. The PRISM design concept utilizes inherent safety characteristics and modularity to improve licensability, reduce owner's risk, and reduce costs. The relatively small size of each reactor module facilitates the use of passive, inherent self-shutdown and shutdown heat removal features, which permit design simplification and reduction of safety-related systems. It is proposed that a single PRISM module be used in a full-scale integrated reactor safety test. Results from the test would be used to obtain NRC certification of the standard design.},
doi = {},
url = {https://www.osti.gov/biblio/6613392}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1986},
month = {1}
}

Conference:
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