Published May 1998
| Version v1
Journal article
Natural circulation induced by the decay heat in primary loops of a molten salt reactor
- 1. Dept. of Mech. Eng., Toyohashi Univ. of Technology, Toyohashi, Aichi (Japan)
Description
A computer simulation is performed for the flow rates and temperature distributions in primary loops of a molten salt reactor. Equivalent pipes with proper diameter and length are used in this study to simulate fuel salt flow passages in the reactor, the main piping and the heat exchanger. Momentum and heat balances are considered in these pipes. By using this equivalent pipe model', the flow rates and temperature distributions in the primary loops are calculated in the case when the pump was stopped in an accident and the decay heat was released. The maximum temperature of about 925degC appeared in the fuel salt in the upper fuel path between reflector and reactor vessel at about 30 minutes after the reactor shutdown. (author)
Additional details
Publishing Information
- Journal Title
- Nippon Dennetsu Shinpojiumu Koen Ronbunshu
- Journal Volume
- 35
- Journal Issue
- 1
- Journal Page Range
- p. 33-34
- CODEN
- NDSRD4
Conference
- Title
- 35. national heat transfer symposium of Japan
- Dates
- 27-29 May 1998
- Place
- Nagoya (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 30042481
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT; COMPUTERIZED SIMULATION; EVALUATION; MOLTEN SALT REACTORS; NATURAL CONVECTION; NUMERICAL ANALYSIS; PRIMARY COOLANT CIRCUITS; REACTOR SAFETY
- Descriptors DEC
- CONVECTION; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; HEAT TRANSFER; MASS TRANSFER; MATHEMATICS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; SIMULATION