Design, fabrication and installation of primary heat transport system for prototype FBR development
- 1. Power Reactor and Nuclear Fuel Development Corp., Tsuruga (Japan). Monju Construction Office
Description
The design study of the heat transport system for 300 MWe class FBR based; on the experience of MONJU is described here. The heat transport system is composed of three loops, based on the single failure criterion, that is, the decay heat after reactor trip can be removed by at least one heat transport system with the consideration of subsequent loss of any safety equipment. The sodium is used as a coolant for FBR, and is in liquid-phase without pressuring it. So, it needs not to consider the depressurizing, boiling even at the unexpected pipe rupture accident. The piping system in the primary heat transport system is designed with the consideration of the unexpected pipe rupture, therefore nearly all the primary piping is arranged in layout to be placed in a high position and some of the piping together with components are equipped with the guard vessel, to keep the sodium above a certain level for securing the core coolability
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0636-7
- Imprint Title
- 2nd ASME-JSME international conference on nuclear engineering -- 1993
- Imprint Pagination
- 770 p.
- Journal Page Range
- p. 645-647.
Conference
- Title
- 2. Japan Society of Mechanical Engineers (JSME)/American Society of Mechanical Engineers (ASME) joint international conference on nuclear engineering.
- Dates
- 21-24 Mar 1993.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25058925
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; DESIGN; FLOW RATE; HEAT EXCHANGERS; MONJU REACTOR; NATURAL CONVECTION; PRIMARY COOLANT CIRCUITS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; SECONDARY COOLANT CIRCUITS
- Descriptors DEC
- BREEDER REACTORS; CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAT TRANSFER; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; REMOVAL; SAFETY; SODIUM COOLED REACTORS
Optional Information
- Secondary number(s)
- CONF-930352--.