Published 1978 | Version v1
Miscellaneous Restricted

Methods of analysis for core meltdown accidients in light water reactors

Creators

  • 1. Battelle Columbus Labs., OH (USA)

Description

This paper describes the status of two research programs at the Battelle, Columbus Laboratories, in which improved methods of analyzing the behavior of hypothetical fuel melting accidents in LWR being developed. In one program the MARCH/CORRAL code package has been written to perform an integrated analysis of thermal-hydraulic response and radionuclide transport within containment in meltdown accidents. In the other program, the TRAP code is under development for the analysis of radionuclide transport and deposition in the reactor primary system. (orig./HP)

Availability note (English)

MF available from INIS under the Report Number.

Abstract (German)

Dieser Beitrag beschreibt den Status zweier Forschungsprogramme, die in den Batelle Laboratories in Columbus durchgefuehrt und in deren Rahmen verbesserte Verfahren zur Untersuchung des Ablaufs hypothetischer Stoerfaelle mit Brennstoffschmelzen in LWR entwickelt werden. Im Rahmen des einen Programms wurde das Rechenprogrammsystem MARCH/CORRAL geschrieben, um eine zusammenfassende Analyse des thermohydraulischen Verhaltens und des Spaltprodukttransports im Containment bei Kernschmelzunfaellen durchzufuehren. Im Rahmen des anderen Forschungsprogramms wird das Rechenprogramm TRAP entwickelt, mit dem eine Analyse des Transports und der Ablagerung von Radionukliden im Primaersystem des Reaktors moeglich wird. (orig./HP)

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Additional details

Publishing Information

Imprint Pagination
26 p.
Report number
INKA-Conf--78-078-005

Conference

Title
6. annual colloquium of the Projekt Nukleare Sicherheit of the Kernforschungszentrum Karlsruhe G.m.b.H.
Dates
28 - 29 Nov 1978.
Place
Karlsruhe, Germany, F.R.

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
10452729
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; C CODES; FISSION PRODUCT RELEASE; HYDRAULICS; M CODES; MELTDOWN; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; RESEARCH PROGRAMS; T CODES; THERMODYNAMICS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS