Published November 1976 | Version v1
Journal article

Analysis of in-core processes during a loss-of-coolant accident in the absence of ECCS

Creators

Description

A loss-of-coolant accident in the absence of the emergency core cooling system is analyzed using computer programmes. Programme BOIL is capable of analyzing 3 types of accidents. Results are reported obtained using the programme for a large PWR reactor for the temperature course of fuel sections in the central part of the core and for the effect of the model of core melting on the amount of molten fuel. Programme CHEMLOC-II debugged and modified by the Power Research Institute in Prague is compared to programmes NURLOC 1.0 and BOIL. Using programme CHEMLOC-II, model problems were calculated for various selectable parameters of the WWER type reactors (fuel temperature and cladding temperature) submitted in a graphical representation. The programme was found to be an adequate tool for the analysis of bare core heating; it contains the mathematical models of all significant processes and is not demanding on machine time. (Oy)

Additional details

Additional titles

Original title (Czech)
Analyza procesu v aktivni zone pri havarii se ztratou chladiva bez cinnosti havarijniho chlazeni

Publishing Information

Journal Title
Jad. Energ.
Journal Volume
22
Journal Issue
10
Series
Jad. Energ.
Journal Page Range
394-397

Conference

Title
Nonsteady operating and emergency states of pressurized water reactor power plants.
Dates
11 May 1976.
Place
Plzen, Czechoslovakia.

INIS

Country of Publication
Serbia and Montenegro
Country of Input or Organization
Serbia and Montenegro
INIS RN
8324893
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
B CODES; C CODES; HEATING; LOSS OF COOLANT; N CODES; REACTOR CORES; THERMAL ANALYSIS; WWER TYPE REACTORS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS