Published 1992 | Version v1
Book Metadata-only

Experimental simulation of LOCA in a PWHR : analytical study of similarity of thermal response between fuel rod simulators and nuclear fuel rods under reflood conditions

Creators

  • 1. Reactor Safety Division, Bhabha Atomic Research Centre, Bombay (India)

Description

For the safety analysis of a nuclear reactor, the similarity of the thermal response of an electrically heated Fuel Rod Simulator (FRS), mostly used in Loss-of-Coolant-Accident (LOCA) experiments, to that of a nuclear fuel rod is of great significance. The present analysis describes the characteristics and the similarity of thermal response fuel rods under reflood conditions of LOCA. The analysis has shown that the thermal response of a nuclear fuel rod can be well simulated by the use of an electrically heated FRS. (author). 7 refs., 12 figs

Additional details

Publishing Information

Publisher
Tata McGraw-Hill Publishing Co. Ltd.
Imprint Place
New Delhi (India)
Imprint Title
Heat and mass transfer : proceedings of the 11"t"h national heat and mass transfer conference [held at Madras during Dec 21-23, 1991]
Imprint Pagination
439 p.
Journal Page Range
p. 217-222.

Conference

Title
11. National heat and mass transfer conference.
Dates
21-23 Dec 1991.
Place
Madras (India).

INIS

Country of Publication
India
Country of Input or Organization
India
INIS RN
24019622
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
BOUNDARY CONDITIONS; ECCS; EXPERIMENTAL DATA; FUEL CANS; FUEL RODS; H CODES; HEAT TRANSFER; LOSS OF COOLANT; PHWR TYPE REACTORS; SIMULATION
Descriptors DEC
ACCIDENTS; COMPUTER CODES; DATA; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; FUEL ELEMENTS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INFORMATION; NUMERICAL DATA; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS