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NUREG-1150 ("Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants", published December 1990 by the Nuclear Regulatory Commission "This study was a significant turning point in the use of risk-based concepts in the regulatory process and enabled the NRC to greatly improve its methods for assessing containment performance after core damage and accident progression." () However significant, and sometimes unrealistic, conservatisms were applied in this study () and it is () being replaced with a new state-of-the-art study entitled State-of-the-Art Reactor Consequence Analyses(see below). == Results == Results of NUREG-1150 (page 12-3): *Average probability of an individual early fatality per reactor per year: : *NRC Safety Goal: 5 x 10−7 : *Typical Pressurized Water Reactor(PWR): 2 x 10−8 : *Typical Boiling Water Reactor(BWR): 5 x 10−11 *Average probability of an individual latent cancer death per reactor per year: : *NRC Safety Goal: 2 x 10−6 : *Typical PWR: 2 x 10−9 : *Typical BWR: 4 x 10−10 Using the data on pages 3-5, 3-7, 4-5 and 4-7 the probability of some U.S. plant having core damage is about 30% over 20 years - this number doesn't include containment failure, which is conservatively estimated at 8% for PWRs (page 3-13, weighting by the probabilities at the bottom) and 84% for BWRs (page 4-14, same technique). Assuming that the 104 current-design (2005) U.S. plants are similar to the two "typical" plants, the chance of a major release of radiation is under 8% every 20 years. The typical BWR was the Peach Bottom plant and the typical PWR was the Surry plant. Parts of NUREG-1150 were compiled by Sandia National Laboratories, which continues to do such research. () NUREG-1420 contains the Kouts’ Committee peer review of NUREG-1150. 抄文引用元・出典: フリー百科事典『 ウィキペディア（Wikipedia）』 ■ウィキペディアで「NUREG-1150」の詳細全文を読む スポンサード リンク
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