Published 1992 | Version v1
Book

U.S. ALMR safety approach and licensing status

  • 1. USDOE, Washington, DC (United States)

Description

The Advanced Liquid Metal Cooled Reactor (ALMR) in the United States is based on the Power Reactor Innovative Small Module (PRISM) concept originated by the General Electric Company (GE). This concept features a compact modular system suitable for factory fabrication, and a high degree of passive and natural safety characteristics. The safety approach emphasizes accident prevention, backed up by accident mitigation. First-round safety evaluations by U.S. regulators have found that the design provides passive, natural, and other desirable features enhancing the safety of the power plant. A Preapplication Safety Evaluation Report (PSER) from the U.S. Nuclear Regulatory Commission (NRC) is anticipated in early 1993. (author)

Part of:
ANP'92 international conference on design and safety of advanced nuclear power plants

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan.
Imprint Place
Tokyo (Japan)
Imprint Title
ANP'92 international conference on design and safety of advanced nuclear power plants
Imprint Pagination
[2182 p.].
Journal Page Range
v. 3 p. 29.2/1-29.2/6.

Conference

Title
international conference on design and safety of advanced nuclear power plants.
Acronym
ANP'92
Dates
25-29 Oct 1992.
Place
Tokyo (Japan).

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
25022803
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACTINIDES; AFTER-HEAT REMOVAL; DESIGN; LICENSING REGULATIONS; LIQUID METAL COOLED REACTORS; MODIFICATIONS; REACTOR SHUTDOWN; RECYCLING; SAFETY ANALYSIS; SEISMIC ISOLATION; SODIUM
Descriptors DEC
ALKALI METALS; ELEMENTS; LAWS; METALS; REACTORS; REGULATIONS; REMOVAL; SHUTDOWN

Optional Information

Notes
Imprint:Composed of four volumes.