Published May 1989 | Version v1
Report Open

Numerical simulation of natural circulation phenomena in a PWR during TMLB' transients prior to core damage

Creators

Description

Multidimensional thermal-hydraulic simulation of natural circulation phenomena during a TMLB' transient prior to core damage has been performed by using the COMMIX computer code. Both a three-loop and a four-loop PWR plant are analyzed. Effects of various parameters on natural circulation are investigated. The most important result is that natural circulation exists during a TMLB' transient for all the cases investigated so far. 190 figs., 34 tabs

Availability note (English)

MF available from INIS under the Report Number; NTIS, PC A13/MF A01 - US Govt. Printing Office. - OSTI as TI89012221.

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Additional details

Publishing Information

Imprint Pagination
289 p.
Report number
NUREG/CR--5274

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
20066178
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
Descriptors DEI
C CODES; CLOSED-CYCLE SYSTEMS; DIAGRAMS; HEAT TRANSFER; HYDRAULICS; NUCLEAR MODELS; NUMERICAL SOLUTION; PIPES; PRESSURE CONTROL; PUMPS; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR SAFETY; STEAM GENERATORS; SUPPORTS; TRANSIENTS; VALVES; VELOCITY; ZION-1 REACTOR; ZION-2 REACTOR
Descriptors DEC
BOILERS; COMPUTER CODES; CONTROL; CONTROL EQUIPMENT; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; INFORMATION; MATHEMATICAL MODELS; MECHANICAL STRUCTURES; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
ANL--88-47.