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Title: The U. S. advanced liquid-metal reactor program update

Abstract

The program for the development of the advanced liquid-metal-cooled reactor (ALMR) is proceeding under the sponsorship of the US Department of Energy. It is being carried out by a team involving wide participation by US industry, national laboratories, and international organizations in the advanced conceptual design phase, with key development and testing tasks proceeding in parallel. A major licensing goal of the program is to produce an ALMR standard design to be certified by the US Nuclear Regulatory Commission (NRC) by about the year 2005, ready for commercial use. The reactor design is based on the PRISM (power reactor innovative small module) concept originated by General Electric. The fuel is based on the integral metal fuel concept developed by Argonne National Laboratory. The ALMR design emphasizes natural safety features, modular construction, and factory fabrication. An ALMR power plant includes reactor modules sized to be fabricated in a factory and shipped by the most economic combination of barge, rail, and road transport. The reactors, the fuel service facility, the reactor auxiliary systems, the remote shutdown facility, and the central fuel cycle facility are nuclear safety grade. The balance of the plant will be of high quality, industrial grade construction.

Authors:
; ;
Publication Date:
OSTI Identifier:
6180404
Report Number(s):
CONF-900608-
Journal ID: ISSN 0003-018X; CODEN: TANSA; TRN: 91-008325
Resource Type:
Conference
Journal Name:
Transactions of the American Nuclear Society; (USA)
Additional Journal Information:
Journal Volume: 61; Conference: American Nuclear Society (ANS) annual meeting, Nashville, TN (USA), 10-14 Jun 1990; Journal ID: ISSN 0003-018X
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; LIQUID METAL COOLED REACTORS; DEMONSTRATION PROGRAMS; AFTER-HEAT REMOVAL; ANL; DESIGN; ECONOMICS; EFFICIENCY; ENGINEERED SAFETY SYSTEMS; EPRI; FABRICATION; FUEL CYCLE; HIGH-LEVEL RADIOACTIVE WASTES; MODULAR STRUCTURES; ORNL; PROBABILITY; REACTOR ACCIDENTS; REACTOR KINETICS; REACTOR PHYSICS; RELIABILITY; RESEARCH PROGRAMS; RISK ASSESSMENT; SEISMIC EFFECTS; SPENT FUELS; STANDARDIZATION; TRANSPORT; US DOE; US NRC; USA; ACCIDENTS; ENERGY SOURCES; FUELS; KINETICS; MATERIALS; NATIONAL ORGANIZATIONS; NORTH AMERICA; NUCLEAR FUELS; PHYSICS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTOR MATERIALS; REACTORS; REMOVAL; US AEC; US ERDA; US ORGANIZATIONS; WASTES; 210500* - Power Reactors, Breeding

Citation Formats

Berglund, R C, Salerno, L N, and Tippets, F E. The U. S. advanced liquid-metal reactor program update. United States: N. p., 1990. Web.
Berglund, R C, Salerno, L N, & Tippets, F E. The U. S. advanced liquid-metal reactor program update. United States.
Berglund, R C, Salerno, L N, and Tippets, F E. Fri . "The U. S. advanced liquid-metal reactor program update". United States.
@article{osti_6180404,
title = {The U. S. advanced liquid-metal reactor program update},
author = {Berglund, R C and Salerno, L N and Tippets, F E},
abstractNote = {The program for the development of the advanced liquid-metal-cooled reactor (ALMR) is proceeding under the sponsorship of the US Department of Energy. It is being carried out by a team involving wide participation by US industry, national laboratories, and international organizations in the advanced conceptual design phase, with key development and testing tasks proceeding in parallel. A major licensing goal of the program is to produce an ALMR standard design to be certified by the US Nuclear Regulatory Commission (NRC) by about the year 2005, ready for commercial use. The reactor design is based on the PRISM (power reactor innovative small module) concept originated by General Electric. The fuel is based on the integral metal fuel concept developed by Argonne National Laboratory. The ALMR design emphasizes natural safety features, modular construction, and factory fabrication. An ALMR power plant includes reactor modules sized to be fabricated in a factory and shipped by the most economic combination of barge, rail, and road transport. The reactors, the fuel service facility, the reactor auxiliary systems, the remote shutdown facility, and the central fuel cycle facility are nuclear safety grade. The balance of the plant will be of high quality, industrial grade construction.},
doi = {},
url = {https://www.osti.gov/biblio/6180404}, journal = {Transactions of the American Nuclear Society; (USA)},
issn = {0003-018X},
number = ,
volume = 61,
place = {United States},
year = {1990},
month = {6}
}

Conference:
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