Published 1990 | Version v1
Book Metadata-only

Analysis of the load rejection test performed at the CHIN-SHAN power station unit 1 with plant analyzer

Creators

  • 1. Institute of Nuclear Energy Research, Lung-Tan (Taiwan, Province of China)
  • 2. Taiwan Power Co., Taipei, Taiwan (China)

Description

This paper reports on a load rejection test, conducted as a part of the CHIN-SHAN Power Station unit 1 startup test, which was analyzed using plant analyzer computer program. The plant analyzer computer program was converted from the Brookhaven National Laboratory plant analyzer using the ADSIM simulation language on an AD-100 peripheral processor. The converted program was modified for the CHIN-SHAN Boiling Water Reactor power plant. A load rejection transient was analyzed with the plant analyzer and compared with test data

Additional details

Publishing Information

Publisher
American Society of Mechanical Engineers.
Imprint Place
New York, NY (United States)
ISBN
0-7918-0585-9
Imprint Title
Proceedings of power plant transients---1990
Imprint Pagination
128 p.
Journal Page Range
p. 101-108.

Conference

Title
American Society of Mechanical Engineers (ASME) winter annual meeting.
Dates
25-30 Nov 1990.
Place
Dallas, TX (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
24022613
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BNL; BWR TYPE REACTORS; CALCULATION METHODS; COMPUTER CODES; COMPUTERIZED SIMULATION; DESIGN; FAILURE MODE ANALYSIS; PERFORMANCE TESTING; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR SAFETY; REACTOR SIMULATORS; SAFETY STANDARDS
Descriptors DEC
ACCIDENTS; ANALOG SYSTEMS; ENRICHED URANIUM REACTORS; FUNCTIONAL MODELS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTORS; SAFETY; SIMULATION; SIMULATORS; STANDARDS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TESTING; THERMAL REACTORS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-901194--.