Simulation Research on Loss of Normal Feedwater for Passive Nuclear Power Plant
Creators
- 1. National Defense Key Subject Laboratory for Nuclear safety and Simulation Technology, Harbin Enginveering University, Harbin (China)
Description
The passive safety system of AP1000 is a new type of safety system,which is different to the second generation nuclear power plant in principle and system layout. There is no actual operation experience of AP1000, therefore, the design principle of AP1000 still need be further verified and analyzed. This paper uses JTopmeret and THEATRe modeling software to carry out simulation on passive residual heat removal system (PRHRS) and core made tank (CMT) system of AP1000. The simulation object is to verify the feasibility and validity of PRHRS and CMT system during accidental conditions. The simulation results show that PRHRS and CMT system can discharge decay heat timely and effectively and guarantee safety of reactor core. The conclusions have reference value in helping operation of AP1000. (authors)
Additional details
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 44
- Journal Issue
- 4
- Journal Page Range
- p. 436-440
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 43085022
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT REMOVAL; COMPUTER CODES; DESIGN; FEEDWATER; LOSS OF FLOW; NUCLEAR POWER PLANTS; OPERATION; PWR TYPE REACTORS; REACTOR CORES; RHR SYSTEMS; SAFETY; SIMULATION; TANKS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; NUCLEAR FACILITIES; OXYGEN COMPOUNDS; POWER PLANTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; THERMAL POWER PLANTS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 figs., 1 tabs., 4 refs.