The regulatory authorities need in the licensing process to examine the licensee's safety analysis by analyzing by themselves some events independently. For this purpose, Japan Institute of Nuclear Safety (JINS) was established in Nuclear Power Engineering Center (NUPEC) in 1980. Since then, JINS has been preparing, improving and developing safety analysis codes, and applied them to audit calculations for nuclear power plants (NPP) and fuel cycle facilities (FCF). Further, JINS is conducting the probabilistic safety assessment (PSA) with the aim to complement the deterministic safety assessment.
This review describes the development at JINS of safety anlysis techniques for NPP (Chap. II) and FCF (Chap. III), of the PSA (Chap. IV) and of environmental dose assessment (Chap. V). Most of the codes have been completed to be applicable for safety examination by the regulatory authorities.