Published September 2008 | Version v1
Journal article Metadata-only

Assessment of FEMAXI and TESPA-ROD codes for modelling of BDBA in RBMK-1500

Creators

  • 1. Lithuanian Energy Institute, Kaunas (Lithuania). Lab. of Nuclear Installation Safety
  • 2. Institute of Physics, Vilnius (Lithuania)
  • 3. Gesellschaft fuer Anlagen und Reaktorsicherheit GRS (mbH), Garching (Germany)

Description

Processes occurring during the reactor operation and accidents change the thermal, chemical and other properties in nuclear fuel rods. This paper describes the processes in the nuclear fuel rods and tools for simulation at these processes. Fuel rods used at Ignalina NPP were simulated with FEMAXI-V (Japan) and TESPA-ROD (Germany) codes. Developed models were employed for the analysis of processes in fuel rods in case of large LOCA beyond design basis accident (BDBA). The developed models and results of the analysis are presented in this paper. (orig.)

Additional details

Publishing Information

Journal Title
Kerntechnik (1987)
Journal Volume
73
Journal Issue
4
Journal Page Range
p. 197-206
ISSN
0932-3902
CODEN
KERNEU

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
39111402
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
COMPUTERIZED SIMULATION; CONTAINMENT BUILDINGS; DIAGRAMS; ECCS; F CODES; FLOW RATE; FLOWSHEETS; IGNALINA-1 REACTOR; IGNALINA-2 REACTOR; LOSS OF COOLANT; MASS TRANSFER; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; REACTOR CORES; REACTOR SAFETY; THERMAL HYDRAULICS
Descriptors DEC
ACCIDENTS; BUILDINGS; COMPUTER CODES; CONTAINMENT; DIAGRAMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; GRAPHITE MODERATED REACTORS; HYDRAULICS; INFORMATION; LWGR TYPE REACTORS; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS