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Bucuresti Effects of Ni on Irrad. Also referenced as: SKI report Task reliability data collection and analysis to support probabilistic safety analysis PSA : an evaluation of questionnaire results, Risk-based management of safety systems' availability: risk based configuration control, In-Vessel core debris cooling through external flooding of the reactor pressure vessel: situation report, Task3: New man-machine interfaces in nuclear power plants. PartII: Appendices, Also referenced as: GRS KfK Separate effects test matrix for thermal-hydraulic code validation, Vol.

International standard problem distribution of hydrogen within the HDR containment under severe accident conditions: final comparison report, Also referenced as: KfK Instrumentation for accident management in containment: a preliminary technical document, Source term uncertainties: recent developments in understanding fission product behaviour, Workshop on aerosol behaviour and thermal-hydraulics in the containment, Fontenay-aux-Roses, technical summary.

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The Complementary roles of fracture mechanics and non-destructive examination in the safety assessment of components: proceedings of a Workshop : Wuerenlingen, Switzerland , Regulatory practices on pressurized thermal shock: results of an international survey, International practices for analyzing, regulating and improving human performance of maintenance activities at nuclear power plants, Specialist meeting on pump performance and reliability: meeting proceedings : Cologne, Germany , Current national source term positions and practices in OECD member countries, International workshop on boiling water reactor stability: proceedings : Holtsville, New York , Workshop on aerosol behaviour and thermal-hydraulics in the containment: proceedings : Fontenay-aux-Roses, France , Santa-Fe, New Mexico, September , Report on the use of probabilistic safety assessment for nuclear power plant safety management: utilities' reply to a questionnaire, Human reliability in probabilistic risk assessments: use of operating experience, Generic study of events involving loss of residual heat removal function: potential loss of RHR function on PWRs, Benchmark exercise on the chemical modelling of the release of radionuclides due to core-concrete interactions, International standard problem: ISP "rupture of a large diameter pipe within the HDR-containment": final comparison report, Also referenced as: EUR N.

Proceedings specialist meeting on intentional coolant system depressurization : Garching, Germany , Report of task group on ex-vessel thermal-hydraulics: status of direct containment heating in CSNI member countries, Filtered containment venting systems : note on the outcome of the specialists' meeting on filtered containment venting systems : Paris, France , International standard problem : steam generator tube rupture : nuclear power plant Doel 2 : Belgium : final report, Specialist meeting on filtered containment venting systems : proceedings : Paris, France , The relevance of the Chernobyl accident to source terms for severe accidents in water-cooled and moderated reactors of western design, The role of human intervention in the prevention and mitigation of severe accidents : tabular comparison of the approaches taken by various member countries, Compendium and comparison of international practice for plugging, repair and inspection of steam generator tubing, Environment sensitive cracking in pressure boundary materials of light water reactors, Source term assessement, containment atmosphere control systems, and accident consequences, International standard problem no.

Comparison of regulations and licensing procedures for fuel cycle facilities particularly with regard to external hazards : proceedings of a specialists' meeting : Salamanca, Spain , Loss of safety system functions: pilot examination of generic safety questions, Proceedings of the CSNI workshop on probabilistic safety assessment as an aid to nuclear power plant management : Brighton, U.

A survey of the applications made of the results of probabilistic safety analyses of nuclear power plants, Also referenced as: S. Detailed illustration of the defects present in Plate No. Proceedings CSNI specialist meeting on operating experience relating to on-site electric power sources : London, England , Proceedings of the specialists' workshop on iodine chemistry in reactor safety, September , , Harwell, England.

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Stable crack growth during overstressing or proof testing of pressure vessels, International standard problem ISP 16 : rupture of a steam line within the HDR-containment leading to an early two-phase-flow : results of post-test analyses Appendix IV : final comparison report, International standard problem ISP 16 : rupture of a steam line within the HDR-containment leading to an early two-phase-flow : results of post-test analyses : final comparison report, The March revision of the specification for the digital recording of ultrasonic signals, International Standard problem ISP 14 : behaviour of a fuel bundle simulator during a specified heatup and flooding period Rebeka experiment : results of post-test analyses : final comparison report, Also referenced as: ND-R R.

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  • Progress in nuclear energy;v. Preliminary comparison report for ISP N. Standard problem exercise on criticality codes for large arrays of packages of fissile materials, Vol 1. Proceedings of the CSNI specialist meeting on interaction of fire and explosion with ventilation systems in nuclear facilities, Also referenced as: CONF Proceedings of a specialist meeting on defect detection and sizing, Ispra, May Also referenced as: EUR 1.

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    Status of LMFBR safety technology: improving the performance and reliability of protection and shutdown systems, Proceedings CSNI specialist meeting on instrumented precracked charpy testing, ResearchProject Analysis of the PISC trials results for alternative procedures: report no 6. Proceedings of the specialist meeting on reliability of the ultrasonic inspection of austenitic materials : Brussels, Belgium , Proceedings specialist meeting on probabilistic methods in seismic assessment for nuclear power plants, Vol 3. Vol 2. Proceedings specialist meeting on regulatory review in the licensing process November , Madrid, Spain , Volume 3.

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    Safety and siting of nuclear installations near international borders in NEA member, Code assessment and applications program : United States standard problem 7 and international standard problem 5: final report, Meeting of a task force on problems of rare events in the reliability analysis of nuclear power plants 3rd : : Garching, Germany , Proceedings of the specialists' meeting on the safety problems associated with the handling and storage of UF6 : Boekelo, The Netherlands ,