References
- Boyack B, Lellouche G, Griffith P, Duffey R, Levy S. Quantifying reactor safety margins: application of code scaling, applicability, and uncertainty evaluation methodology to a large-break, loss-of-coolant accident ( U.S. Nuclear Regulatory Commission Report, NUREG/CR-5249). Washington: US Nuclear Regulatory Commission; Dec 1989.
- Atomic Energy Society of Japan. Code on implementation and review of statistical safety evaluation: 2008 (AESJ-SC-001: 2008). Tokyo: Atomic Energy Society of Japan; May 2009, 25–26. Japanese.
- Wilson GE, Boyack BE. The role of the PIRT process in experiments, code development and code applications associated with reactor safety analysis. Nucl Eng Des. 1998;186:23–37.
- Horie H, Matsumiya H, Miyagi K, Nishi Y, Grenci T, Fontana MH, Moody FJ, Ninokata H, Wilson GE, Yamaguchi A. Phenomena Identification and Ranking Tables (PIRTs) for 4S -loss of offsite power, failure of a cavity can, and sodium leakage from intermediate piping scenarios. The 13th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13) N13P1093; 2009 Sep. 27–Oct. 2; Kanazawa City, Ishikawa Prefecture, Japan.
- European Commission Joint Research Centre, European Network for Inspection and Qualification. ENIQ recommended practice 1: influential/essential parameters issue 2 ( ENIQ Report No. 24). Petten (The Netherlands): European Commission Joint Research Centre; June 2005, 13–18.
- Terachi T, Fujii K, Arioka K. Microstructural characterization of SCC crack tip and oxide film for SUS 316 stainless steel in simulated PWR primary water at 320°C. J Nucl Sci Technol. 2005;42(2):225–232.
- Horinouchi S, Ikeuchi M, Shintaku Y, Ohara Y, Yamanaka K. Evaluation of closed stress corrosion cracks in Ni-based alloy weld metal using subharmonic phased array. Jpn J Appl Phys. 2012;51:07GB15-1-5.