Published 1989 | Version v1
Book Metadata-only

Real-time accident tracking of steam generator tube rupture in pressurized water reactors

Creators

  • 1. Kyoto Univ., Uji (Japan). Inst. of Atomic Energy

Description

An accident tracking calculation of a steam generator tube rupture (SGTR) accident is investigated by using a real-time accident tracking calculation code TOKRAC for the small break loss-of-coolant accidents (SBLOCAs) of pressurized water reactor plant. In order to accomplish the accurate calculation for the mild SBLOCA such as an SGTR accident, a non-equilibrium pressurizer model is developed and the models for both physical properties of coolant and primary coolant pump are improved. In this paper the accident tracking scheme by TOKRAC is described for typical three types of SBLOCA. The accident tracking capability of the revised TOKRAC for an SGTR accident is evaluated through a calculation of the Prairie Island SGTR Unit 1 accident. The calculation results for 3000 seconds from the occurrence of tube rupture showed rather good coincidence with both the plant records and the simulation results by the safety analysis code RELAP5/MOD1

Additional details

Publishing Information

Publisher
University of Tennessee at Knoxville.
Imprint Place
Knoxville, TN (United States)
Imprint Title
Proceedings of the 7th power plant dynamics, control and testing symposium
Imprint Pagination
vp.
Journal Page Range
p. 41.01-41.19.

Conference

Title
7. power plant dynamics, control and testing symposium.
Dates
15-17 May 1989.
Place
Knoxville, TN (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
23036808
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CALCULATION METHODS; COOLANT LOOPS; LOSS OF COOLANT; PRESSURIZERS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR SAFETY EXPERIMENTS; REACTOR SIMULATORS; REAL TIME SYSTEMS; RUPTURES; SAFETY ANALYSIS; SIMULATION; STEAM GENERATORS; T CODES; TESTING; TUBES
Descriptors DEC
ACCIDENTS; ANALOG SYSTEMS; BOILERS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FAILURES; FUNCTIONAL MODELS; POWER REACTORS; REACTORS; SIMULATORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-890555--.