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Title: Prism sodium-cooled reactor design and performance

Abstract

The Power Reactor Inherently Safe Module (PRISM) program is being conducted at General Electric (GE) under U.S. Department of Energy sponsorship to develop a conceptual design for an advanced sodium-cooled liquid-metal reactor plant. The PRISM design emphasizes inherent safety, modular construction, and factory fabrication. A PRISM power plant includes a number of reactor modules, which will be fabricated in a factory and shipped by whatever combination of barge, rail, and road transport that is most economical for a particular site. The target commercial PRISM plant utilizes nine reactor modules arranged in three identical 465-MW(electric) power blocks for an overall plant net electrical rating of 1395 MW(electric). Each power block has three identical reactor modules, each with its own steam generator, that jointly supply saturated steam to a single turbine generator. The PRISM's features of fewer and simpler safety systems, seismic isolation, passive decay heat removal, inherent reactivity control, and generous margins from structural and fuel damage limits during potential accident situations will result in significant gains in public safety and protection of the owner's investment. The use of standardized modular construction and extensive factory fabrication is resulting in a plant design that is economically competitive against projected coal plants andmore » other nuclear design approaches.« less

Authors:
; ;  [1]
  1. GE, San Jose, CA (USA)
Publication Date:
OSTI Identifier:
6835209
Report Number(s):
CONF-890604-
Journal ID: ISSN 0003-018X; CODEN: TANSA; TRN: 90-023489
Resource Type:
Conference
Journal Name:
Transactions of the American Nuclear Society; (USA)
Additional Journal Information:
Journal Volume: 59; Conference: Annual meeting of the American Nuclear Society, Atlanta, GA (USA), 4-8 Jun 1989; Journal ID: ISSN 0003-018X
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; SODIUM COOLED REACTORS; REACTOR SAFETY; AFTER-HEAT REMOVAL; CONTAINMENT SYSTEMS; CONTROL ELEMENTS; DESIGN; FABRICATION; HEAT EXCHANGERS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MODULAR STRUCTURES; NATURAL CONVECTION; PERFORMANCE; POWER GENERATION; REACTOR CORES; REACTOR KINETICS; REACTOR VESSELS; SCRAM; STAINLESS STEEL-304; STAINLESS STEEL-316; STEAM GENERATORS; TRANSPORT; US DOE; WELDED JOINTS; ACCIDENTS; ALLOYS; AUSTENITIC STEELS; BOILERS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CONTAINERS; CONTAINMENT; CONVECTION; CORROSION RESISTANT ALLOYS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; FLUID MECHANICS; HEAT RESIS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; KINETICS; LIQUID METAL COOLED REACTORS; MASS TRANSFER; MATERIALS; MECHANICS; MOLYBDENUM ALLOYS; NATIONAL ORGANIZATIONS; NICKEL ALLOYS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR SHUTDOWN; REACTORS; REMOVAL; SAFETY; SHUTDOWNS; STAINLESS STEELS; STEEL-CR17NI12MO3; STEEL-CR19NI10; STEELS; US ORGANIZATIONS; VAPOR GENERATORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210500 - Power Reactors, Breeding

Citation Formats

Kwant, W, Magee, P M, and Patel, M R. Prism sodium-cooled reactor design and performance. United States: N. p., 1989. Web.
Kwant, W, Magee, P M, & Patel, M R. Prism sodium-cooled reactor design and performance. United States.
Kwant, W, Magee, P M, and Patel, M R. Sun . "Prism sodium-cooled reactor design and performance". United States.
@article{osti_6835209,
title = {Prism sodium-cooled reactor design and performance},
author = {Kwant, W and Magee, P M and Patel, M R},
abstractNote = {The Power Reactor Inherently Safe Module (PRISM) program is being conducted at General Electric (GE) under U.S. Department of Energy sponsorship to develop a conceptual design for an advanced sodium-cooled liquid-metal reactor plant. The PRISM design emphasizes inherent safety, modular construction, and factory fabrication. A PRISM power plant includes a number of reactor modules, which will be fabricated in a factory and shipped by whatever combination of barge, rail, and road transport that is most economical for a particular site. The target commercial PRISM plant utilizes nine reactor modules arranged in three identical 465-MW(electric) power blocks for an overall plant net electrical rating of 1395 MW(electric). Each power block has three identical reactor modules, each with its own steam generator, that jointly supply saturated steam to a single turbine generator. The PRISM's features of fewer and simpler safety systems, seismic isolation, passive decay heat removal, inherent reactivity control, and generous margins from structural and fuel damage limits during potential accident situations will result in significant gains in public safety and protection of the owner's investment. The use of standardized modular construction and extensive factory fabrication is resulting in a plant design that is economically competitive against projected coal plants and other nuclear design approaches.},
doi = {},
url = {https://www.osti.gov/biblio/6835209}, journal = {Transactions of the American Nuclear Society; (USA)},
issn = {0003-018X},
number = ,
volume = 59,
place = {United States},
year = {1989},
month = {1}
}

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