Published 1984 | Version v1
Book Metadata-only

Applications of TPCSBL code on emergency planning drills of Taipower nuclear power plants

Creators

  • 1. Taiwan Power Co., Taipei

Description

A simple, faster than real time thermal-hydraulic code -TPCSBL- for predicting system response during accident has been developed. TPCSBL consists of three models: TPCSBLC for CHINSHAN BWR 4; TPCSBLK for KUOSHENG BWR 6; and TPCSBLM for MAANSHAN PWR. The three models differ in plant specific system but have the same thermal-hydraulic basis. TPCSBL is installed on TPC IBM 3031/3033 system and the computing time for case running is only about 1% of transient time. A scoping and spectrum analyses using TPCSBLM, TPCSBLK, and TPCSBLC show that TPCSBL is effective in calculation of RCS pressure, temperature and inventory. Moreover, TPCSBL can be started at any time with only a minor initial condition change. Due to these special features, it is then suitable to apply TPCSBL on Emergency Plan Drill. At present TPCSBL is an important analysis tool used by Assessment Group of TPC's Emergency Plan Executing Commission for technical support during emergency

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (USA)
Imprint Title
Proceedings of international nuclear power plant thermal hydraulics and operations topical meeting
Journal Page Range
p. A9-1-A9-7.

Conference

Title
International thermal hydraulics and plant operations topical meeting.
Dates
22-24 Oct 1984.
Place
Taipei, TW (China).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17078707
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CHINA; CHINSAN-1 REACTOR; CHINSAN-2 REACTOR; COMPUTERIZED SIMULATION; EDUCATION; ELECTRIC UTILITIES; EMERGENCY PLANS; HEAT TRANSFER; HYDRAULICS; KUOSHENG-1 REACTOR; KUOSHENG-2 REACTOR; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; SYSTEMS ANALYSIS; T CODES
Descriptors DEC
ACCIDENTS; ASIA; BWR TYPE REACTORS; COMPUTER CODES; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; PUBLIC UTILITIES; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS