Published 1985 | Version v1
Report Open

PKL

Creators

  • 1. CEA CEN Fontenay-aux-Roses, 92 (France). IPSN, Dept. Etudes et Recherches en Securite
  • 2. CEA CEN Cadarache, 13 Saint-Paul-lez- Durance (France). IRDI, DRE, STRE

Description

This study concerns the simulation of the behavior of a PWR during a LOCA. One studies more particularly the refilling and reflooding phase (PKLI) and the end of the depressurization phase (PKLII). The aim of this test program is to provide the information needed for the validation/verification of computer codes (RELAP4 MOD6, TRAC PF1) and to test an instrumentation realized for the 2D/3D program. A comparison calculation/experiment is presented. 5 refs

Availability note (English)

MF available from INIS under the Report Number.

Abstract (French)

Le programme PKL a pour objectif la simulation du comportement d'un REP lors d'un accident de perte de refrigerant. On etudie plus particulierement les phases de remplissage et de renoyage (installation PKLI) et de fin de depressurisation (PKL II). Le but du programme est de fournir les informations necessaires a la validation/verification des codes de calcul (RELAP4 MOD6, TRAC PF1) et de tester une instrumentation realisee pour le programme 2D/3D. On presente une comparaison calcul/experience

Files

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Additional details

Additional titles

Original title (French)
PKL

Publishing Information

Imprint Pagination
66 p.
Report number
CEA-CONF--8348

Conference

Title
RELAP TRAC Seminar.
Dates
15 Nov 1983.
Place
Fontenay-aux-Roses (France).

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
18002612
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; R CODES; REACTOR SAFETY EXPERIMENTS; T CODES; VERIFICATION
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EVALUATION; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS