Published October 2014 | Version v1
Journal article Metadata-only

Comparison on LOCA characteristics and analysis method of M310 and AP1000 nuclear power plant

Creators

  • 1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu (China)

Description

Large Break Loss-of-Coolant Accident (LOCA) is the most limiting design base accident. With the development of the third generation nuclear power plant, it is necessary to study the LOCA characteristics and new LOCA analysis method. In this paper, M310 and AP1OOO nuclear power plants are taken for example, comparisons are made from the following aspects: safety injection system; progression of the accident; important phenomena; analysis method and code. To master the LOCA analysis method is very meaningful to the absorption of the third generation nuclear power plant technologies, also can help the development of self-design nuclear power plant. (authors)

Additional details

Publishing Information

Journal Title
China Nuclear Power
Journal Volume
7
Journal Issue
suppl.1
Journal Page Range
p. 295-301
ISSN
1674-1617

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
49058086
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ABSORPTION; COMPARATIVE EVALUATIONS; DESIGN; DESIGN-BASIS ACCIDENTS; LBLOCA; LOSSES; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; SAFETY INJECTION
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; EVALUATION; LOSS OF COOLANT; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SORPTION; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
2 tabs., 5 refs.