Codes for NPP severe accident simulation: development, validation and applications
Creators
- 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)
Files
47065296.pdf
Files
(8.2 MB)
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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