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付表1, 2の参考文献<br />

(1) 「発電用軽水型原子炉施設に関する安全設計審査指針」(平成2年8月30日)原子力安全委員会決定(一部改訂 H13.3.29).<br />

(2) 「再処理施設安全審査指針」(昭和61年2月20日)原子力安全委員会決定(一部改訂 H1.3.27、H13.3.29、H18.9.19、H22.12.20).<br />

(3) IAEA NS-G-1.5, “External Events excluding Earthquakes in the Design of Nuclear Power Plants,” IAEA, 2003.<br />

(4) IAEA NS-G-1.6, “Seismic Design and Qualification for Nuclear Power Plants,” IAEA, 2003.<br />

(5) “WENRA Reactor Safety Reference Levels”, WENRA(Western European Nuclear Regulators’ Association) Reactor Harmonization Working Group, January 2008.<br />

(6) 英国SAP, “Safety Assessment Principles for Nuclear Facilities,” 2006 Edition, Revision 1, Health and Safety Executive, January 2008.<br />

(7) フィンランドYVL 1.0, “Safety criteria for design of nuclear power plants,” Finnish Centre for Radiation and Nuclear Safety(STUK), January 1996.<br />

(8) 米国NRC, Title <strong>10</strong>, Code of Federal Regulations, <strong>10</strong> CFR 50 Appendix A to Part 50, “General Design Criteria for Nuclear Power Plants,” USNRC.<br />

(9) American Society of Mechanical Engineers and American Nuclear Society, “Addenda to ASME/ANS RA-S-2008 Standard for Level 1/Large Early Release<br />

Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications,” ASME/ANS RA-Sa-2009, February 2009.<br />

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