Published April 1990 | Version v1
Report Metadata-only

A suite of codes for the nuclear power plant design safety analysis

Creators

  • 1. Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Obninsk (USSR). Fiziko-Ehnergeticheskij Inst.

Description

The system of computer codes used for safety analyses at the Institute of Physics and Power Engineering is described. The system, constructed around the codes RAPIRA, ROPAS and VIBROS can calculate the plant dynamics, radioactive transient and offsite consequences during a severe accident scenario. At present the codes are being used for plants under design, including combined heat and power generating plants. Studies for BN-800 liquid metal fast reactors were also carried out. (author). 1 fig

Part of:
Computer aided safety analysis 1989

Additional details

Publishing Information

Imprint Title
Computer aided safety analysis 1989
Imprint Pagination
212 p.
Journal Page Range
p. 205-208.
Report number
IAEA-TC--560.03

Conference

Title
Technical committee/workshop on computer aided safety analysis.
Dates
17-21 Apr 1989.
Place
Berlin (German Democratic Republic).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
21080223
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; FISSION PRODUCT RELEASE; LMFBR TYPE REACTORS; MELTDOWN; R CODES; SAFETY ANALYSIS; SOURCE TERMS; SPECIFICATIONS; TRANSIENTS; V CODES
Descriptors DEC
ACCIDENTS; BREEDER REACTORS; COMPUTER CODES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION

Optional Information