Published 1989 | Version v1
Book

JERICHO, a code for computation of containment thermal-hydraulic behaviour during a severe accident in a NPP

  • 1. CEA Centre d'Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire

Description

The JERICHO code has been developed in the context of the ESCADRE system in order to analyse the evolution of thermal-hydraulic conditions in the containment over a period of several days in the event of a severe accident. These conditions are assessed by dividing the available energy between the containment atmosphere, the sump water volume and the walls. The containment can be divided into several compartments describing the gas atmosphere, the sump water and the structures. The subcompartments are assumed to be homogeneous, pressure and temperature balanced. The containment atmosphere can consist of oxygen, nitrogen, steam, hydrogen, carbon monoxide and carbon dioxide. The application of the code allows computation of the thermal-hydraulic behaviour of the containment of a nuclear power plant for a large range of severe accidents scenarios including the use of the main accident mitigation procedures. (orig./DG)

Additional details

Publishing Information

Publisher
Braun.
Imprint Place
Karlsruhe (Germany, F.R.)
ISBN
3-7650-1116-9
Imprint Title
Fourth international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4). Proceedings. Vol. 2
Imprint Pagination
696 p.
Journal Page Range
p. 909-914.

Conference

Title
4. international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4).
Dates
10-13 Oct 1989.
Place
Karlsruhe (Germany, F.R.).

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
22038371
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CALCULATIONS; CONTAINMENT; FAILURES; HYDRAULICS; J CODES; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS