Published 1983
| Version v1
Book
Some safety aspects of the fast gas-cooled reactor BGR-300
Creators
- 1. Scientific Inst. of Power Engineering, Moscow (USSR)
Description
This paper considers inherent safety features of the BGR-300 reactor design with helium coolant ensuring its safe operation. The nuclear safety of the reactor, main components of the primary circuit and residual heat removal system is analysed for compliance with safety criteria. The system of gas injection to maintain circulation in the primary circuit during loss of coolant accidents is shown to be justified. The main characteristics of the BGR-300 reactor safety systems are given. (author)
Additional details
Publishing Information
- Publisher
- BNES.
- Imprint Place
- London (UK)
- ISBN
- 0 7277 0168 1
- Imprint Title
- Gas-cooled reactors today. (Volume 4). Papers, discussion, closing address, corrigenda. Proceedings of the conference held in Bristol on 20-24 September 1982
- Imprint Pagination
- 328 p.
- Journal Page Range
- p. 191-195.
Conference
- Title
- Gas-cooled reactors today.
- Dates
- 20-24 Sep 1982.
- Place
- Bristol (UK).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 15047326
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FAST REACTORS; GAS INJECTION; HEAT EXCHANGERS; HELIUM COOLED REACTORS; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; REACTOR SAFETY; SAFETY ANALYSIS; SAFETY ENGINEERING; SAFETY STANDARDS; USSR
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; DEVELOPED COUNTRIES; EPITHERMAL REACTORS; EUROPE; FLUID INJECTION; GAS COOLED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY