Published August 2015 | Version v1
Miscellaneous Open

Codes for NPP severe accident simulation: development, validation and applications

  • 1. Nuclear Safety Institute of the Russian Academy of Sciences, B. Tulskaya 52, 115191 Moscow (Russian Federation)

Description

The software tools that describe various safety aspects of NPP with VVER reactor have been developed at the Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE RAN). Functionally, the codes can be divided into two groups: the calculation codes that describe separate elements of NPP equipment and/or a group of processes and integrated software systems that allow solving the tasks of the NPP safety assessment in coupled formulation. In particular, IBRAE RAN in cooperation with the nuclear industry organizations has developed the integrated software package SOCRAT designed to analyze the behavior of NPP with VVER at various stages of beyond-design-basis accidents, including the stages of reactor core degradation and long-term melt retention in a core catcher. The general information about development, validation and applications of SOCRAT code is presented and discussed in the paper. (author)

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Part of:
The 11th National Conference on Nuclear Science and Technology. Agenda and Abstracts

Additional details

Publishing Information

Imprint Title
The 11th National Conference on Nuclear Science and Technology. Agenda and Abstracts
Imprint Pagination
215 p.
Journal Page Range
8 p.
Report number
INIS-VN--002

Conference

Title
11. National Conference on Nuclear Science and Technology
Original Conference Title
Hoi nghi Khoa hoc va Cong nghe Hat nhan Toan quoc lan thu 11
Dates
5-7 Aug 2015
Place
Da Nang City (Viet Nam)

INIS

Country of Publication
Viet Nam
Country of Input or Organization
Viet Nam
INIS RN
47065296
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; DESIGN BASIS ACCIDENTS; INFORMATION; NUCLEAR POWER PLANTS; REACTOR ACCIDENT SIMULATION; REACTOR SAFETY; RETENTION; RISK ASSESSMENT; SIMULATION; VALIDATION
Descriptors DEC
ACCIDENTS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; SAFETY; SIMULATION; TESTING; THERMAL POWER PLANTS

Optional Information

Notes
3 refs, 7 figs, 2 tabs