Thermal hydraulic analysis of a passive residual heat removal system
Description
A theoretical investigation on the thermal hydraulic characteristics of a new type of passive residual heat removal system (PRHRS) for an integrated pressurized water reactor is presented in this paper. The residual decay heat of the reactor core should be removed safely through multi-interknit natural circulation loops on the occasion of normal or accidental reactor shutdown. A one-dimensional model and a simulation code are developed to theoretically predict the transient behavior of the PRHRS. It is found that the calculated parameter (such as heat transfer capacity, pressure and mass flow rate) variation trends are reasonable. The decay heat can be safely removed by the PRHRS. However, the peak value of the secondary loop pressure is higher than the expected one. A protection measure of the secondary loop pressure should be considered in the model. (authors)
Additional details
Publishing Information
- Publisher
- Atomic Energy Press
- Imprint Place
- Beijing (China)
- ISBN
- 7-5022-3400-4
- Imprint Title
- The 13th international conference on nuclear engineering abstracts
- Imprint Pagination
- 604 p.
- Journal Page Range
- p. 488
Conference
- Title
- 13. international conference on nuclear engineering
- Dates
- 16-20 May 2005
- Place
- Beijing (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 38013966
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; COMPUTER CODES; COMPUTERIZED SIMULATION; FLOW RATE; HEAT TRANSFER; NATURAL CONVECTION; ONE-DIMENSIONAL CALCULATIONS; PRESSURE DEPENDENCE; PWR TYPE REACTORS; REACTOR SAFETY; RHR SYSTEMS; SECONDARY COOLANT CIRCUITS; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- CONVECTION; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS