Integrated functional modeling method for NPP plant DiD risk monitor and its application for conventional PWR
Creators
- 1. College of Nuclear Science and Technology, Harbin Engineering University, Harbin (China)
Description
The development of a new risk monitor system is introduced in this paper, which can be applied not only to severe accident prevention in daily operation but also to serve as to mitigate the radiological hazard just after severe accident happens and long term management of post-severe accident consequences. The summary of the fundamental method is given on how to configure the Plant Defense in-Depth (DiD) Risk Monitor by object-oriented software system based on functional modeling approach. Following the authors' preceding preliminary study for AP1000, the way of realizing the proposed method of configuring the plant DiD risk monitor was investigated for a safety-enhanced Japanese PWR design to meet with the tight anti-severe accident requirements set by national regulation in Japan after Fukushima Daiichi accident. The result of this example practice of the presented preliminary study for Japanese PWR was for the level 4 of the DiD in case of beyond design basis accident, that is, loss of all AC power + RCP seal LOCA, against the former case of AP1000 for level 3 DiD in case of large LOCA. (author)
Availability note (English)
Available from http://www.ijnsweb.comAdditional details
Identifiers
Publishing Information
- Journal Title
- International Electronic Journal of Nuclear Safety and Simulation
- Journal Volume
- 5
- Journal Issue
- 3
- Journal Page Range
- p. 205-212
- ISSN
- 2185-0577
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 48085763
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCIDENT MANAGEMENT; COMPUTER CODES; ECCS; FUKUSHIMA DAIICHI NUCLEAR POWER STATION; LOSS OF COOLANT; MELTDOWN; NUCLEAR POWER PLANTS; POWER LOSSES; PWR TYPE REACTORS; REACTOR CORE DISRUPTION; REACTOR MONITORING SYSTEMS; REACTOR OPERATION; SCRAM
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; ENERGY LOSSES; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; LOSSES; MANAGEMENT; NUCLEAR FACILITIES; OPERATION; POWER PLANTS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR LIFE CYCLE; REACTOR PROTECTION SYSTEMS; REACTOR SHUTDOWN; REACTOR SITES; REACTORS; SEVERE ACCIDENTS; SHUTDOWN; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 refs., 6 figs., 2 tabs.