Development of incident progress prediction technologies for nuclear emergency preparedness. Current status and future subjects
Creators
- 1. Inst. of Nuclear Safety System, Inc., Inst. of Nuclear Technology, Mihama, Fukui (Japan)
- 2. Kansai Electric Power Co., Inc., Osaka (Japan)
Description
Nuclear licensees are required to maintain a prediction system during normal condition for using a nuclear emergency by the Basic Plan for Disaster Prevention of government. With prediction of the incident progress, if the present condition of nuclear power plant is understood appropriately and it grows more serious with keeping the present situation, it is in predicting what kind of situation will be occurred in the near future, choosing the effective countermeasures against the coming threat, and understanding the time available of intervention time. Following the accident on September 30 1999 in the nuclear fuel fabrication facility in Tokai Village of Ibaraki Prefecture, the Institute of Nuclear Safety System started development of incident progress prediction technologies for nuclear emergency preparedness. We have performed technical applications and made improvements in nuclear emergency exercises and verified the developed systems using the observed values of the Fukushima Daiichi Nuclear Power Plant accident. As a result, our developed Incident Progress Prediction System was applied to nuclear emergency exercises and we accumulated knowledge and experience by which we improved the system to make predictions more rapidly and more precisely, including for example, the development of a prediction method for leak size of reactor coolant. On the other hand, if a rapidly progressing incident occurs, since end users need simple and quick predictions about the public's protection and evacuation areas, we developed the Radioactive Materials Release, Radiation Dose and Radiological Protection Area Prediction System which changed solving an inverse problem into a forward problem solution. In view of the water-level-decline incident of the spent fuel storage facility at the Fukushima Daiichi Nuclear Power Plant, the spent fuel storage facility water level and the water temperature evaluation tool were improved. Such incident progress prediction technologies were applied to predictive analysis using the limited information available at Fukushima accident of those days, and checked the validity of the prediction method. In the future, we would like to aim at technical developments for preventing decision-making errors and at accumulating know-how on regional pollution by radioactive materials. (author)
Additional details
Publishing Information
- Journal Title
- INSS Journal
- Journal Volume
- 21
- Journal Page Range
- p. 223-237
- ISSN
- 1340-4482
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 48062331
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCIDENT MANAGEMENT; DECISION MAKING; EMERGENCY PLANS; FISSION PRODUCT RELEASE; FUKUSHIMA DAIICHI NUCLEAR POWER STATION; LOSS OF COOLANT; LOSS OF FLOW; MELTDOWN; NUCLEAR POWER PLANTS; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; MANAGEMENT; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; REACTOR SITES; THERMAL POWER PLANTS
Optional Information
- Notes
- 22 refs., 30 figs.; This record replaces 46078382