Gen-IV Reactor Systems Criteria Implementation in BN-1200
Creators
- 1. State Science Center of the Russian Federation – Leipunskii Institute for Physics and Power Engineering (IPPE) (Russian Federation)
- 2. Afrikantov Experimental Design Bureau of Mechanical Engineering (OKBM Afrikantov) (Russian Federation)
Description
The design of the BN-1200 sodium-cooled fast reactor is analyzed from the standpoint of its compliance with the criteria fitting the promising Gen-IV reactor facilities. The basic technical solutions adopted in the BN-1200 design making it possible to meet the requirements of consistent development of non-proliferation and safety, cost-effectiveness, and physical protection are described. The BN-1200 concept is evaluated on the basis of 26 criteria developed as part of the Generation IV international forum for the Gen-IV sodium-cooled fast reactor. The compliance of the safety requirements used in the development of the BN-1200 design with the design criteria for the Gen-IV sodium-cooled fast reactor developed as part of the Generation IV international forum is analyzed.
Additional details
Identifiers
Publishing Information
- Journal Title
- Atomic Energy (New York, N.Y.)
- Journal Volume
- 125
- Journal Issue
- 6
- Journal Page Range
- p. 351-358
- ISSN
- 1063-4258
- CODEN
- AENYEZ
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54081611
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BN-1200 REACTOR; PHYSICAL PROTECTION; REACTOR DESIGN; REACTOR SAFETY
- Descriptors DEC
- BREEDER REACTORS; DESIGN; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; POWER REACTORS; REACTOR LIFE CYCLE; REACTORS; SAFETY; SODIUM COOLED REACTORS
Optional Information
- Copyright
- Copyright (c) 2019 Springer Science+Business Media, LLC, part of Springer Nature