Published 2022 | Version v1
Report Metadata-only

Practical application of uncertainty and sensitivity analysis methodologies for the analysis of severe accidents in VVER reactors

Creators

  • 1. NRC "Kurchatov Institute" (Russian Federation)

Description

Nowadays numerical simulation is an aspect of great importance for safety demonstration of nuclear power plants. An integral best estimate computer code SOCRAT-B1/B2 is applied for safety justification of VVER in Russia.

Part of:
International Conference on Topical Issues in Nuclear Installation Safety: Strengthening Safety of Evolutionary and Innovative Reactor Designs. Book of Abstracts

Additional details

Identifiers

URL
https://conferences.iaea.org/event/277/;

Publishing Information

Imprint Title
International Conference on Topical Issues in Nuclear Installation Safety: Strengthening Safety of Evolutionary and Innovative Reactor Designs. Book of Abstracts
Imprint Pagination
146 p.
Journal Page Range
p. 86-87
Report number
IAEA-CN--308

Conference

Title
Strengthening Safety of Evolutionary and Innovative Reactor Designs
Acronym
International Conference on Topical Issues in Nuclear Installation Safety
Dates
18-21 Oct 2022
Place
Vienna (Austria)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
54004934
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; COMPUTERIZED SIMULATION; NUCLEAR POWER PLANTS; REACTOR SAFETY; SENSITIVITY ANALYSIS; SEVERE ACCIDENTS; WWER TYPE REACTORS
Descriptors DEC
ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; ENRICHED URANIUM REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; SIMULATION; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
IAEA-CN--308-137