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The purpose of this report is to update findings of the International Nuclear Safety Advisory Group's Summary Report on the Post-Accident Review Meeting on the Chernobyl Accident (INSAG-1), published in September 1986, in the light of further information that has been revealed since that meeting. INSAG stands by the general ...
The Chernobyl Accident: Updating of INSAG-1: A Report by the International Nuclear Safety Advisory Group
The purpose of this report is to update findings of the International Nuclear Safety Advisory Group's Summary Report on the Post-Accident Review Meeting on the Chernobyl Accident (INSAG-1), published in September 1986, in the light of further information that has been revealed since that meeting. INSAG stands by the general conclusions of INSAG-1 about the accident's causes and their implications for the safety of the Chernobyl type light water cooled graphite moderated RBMK reactors. However, the new information, which derives from studies made in the then USSR on the physical origins of the accident, has led INSAG to shift the emphasis of its conclusions from the actions of the operating staff to faulty design of the reactor's control rods and safety systems. Deficiencies in the regulation and management of safety matters throughout the Soviet nuclear power industry have also been revealed and are discussed. Two detailed Soviet reports on the causes and circumstances of the Chernobyl accident, translated into English by the IAEA, and a statement of measures that have been taken to enhance the safety of RBMK reactors are included.
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These Standards, co-sponsored by FAO, ILO, OECD/NEA. PAHO and WHO, are based on assessments of the biological effects of irradiation made by the United Nations Scientific Committee on the Effects of Atomic Radiation, and on the recommendations of the International Commission on Radiological Protection and the International Nuclear Safety Advisory ...
International Basic Safety Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources
These Standards, co-sponsored by FAO, ILO, OECD/NEA. PAHO and WHO, are based on assessments of the biological effects of irradiation made by the United Nations Scientific Committee on the Effects of Atomic Radiation, and on the recommendations of the International Commission on Radiological Protection and the International Nuclear Safety Advisory Group. The Standards represent an international consensus on qualitative and quantitative requirements for protection and safety for: planned practices such as nuclear power generation and the use of radiation and radioactive materials in medicine and industry; intervention in existing situations such as chronic exposure to natural sources of radiation or exposure following an accident; control of radiation sources, including notification and authorization, and criteria for exemption. Consensus guidance is also given on: occupational radiation protection; protection of patients in radiography, fluoroscopy, computer tomography, mammography and nuclear medicine; protection of members of the public from exposure to radioactive materials released to the environment; prevention of incidents giving rise to potential exposures; and intervention in a radiological emergency.
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This Safety Practice provides guidance on how to conduct a Level 2 probabilistic safety assessment (PSA) of a nuclear power plant for the use of those performing or managing Level 2 PSAs. Emphasis is placed on the procedural steps of a PSA rather than on detailed methods. The aim is ...
Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants (Level 2): Accident Progression, Containment Analysis and Estimation of Accident Source Terms: A Safety Practice
This Safety Practice provides guidance on how to conduct a Level 2 probabilistic safety assessment (PSA) of a nuclear power plant for the use of those performing or managing Level 2 PSAs. Emphasis is placed on the procedural steps of a PSA rather than on detailed methods. The aim is to standardize the framework, terminology and forms of documentation for Level 2 PSAs to facilitate their external review. This report complements Safety Series No. 50-P-4, Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants (Level 1).
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