Channels Advances in reliability analysis and probabilistic safety assessment for nuclear power reactors: Report of a Technical Committee meeting held in Budapest, 7-11 September 1992.
Human reliability data collection and modelling: Report of a Technical Committee Meeting held in Vienna, 26 February-2 March 1990.
Collection and classification of human reliability data for use in probabilistic safety assessments.
Proceedings of the IAEA technical committee meeting on RF launchers for plasma heating and current drive.
Fusion reactor safety: Report of a technical committee meeting on fusion reactor safety.
Fuel performance at high burnup for water reactors: proceedings of a technical committee meeting.
Use of probabilistic safety assessment to evaluate nuclear power plant technical specifications.
Report on atomic power symposium held at Chalk River, Ontario 9th, 10th, and 11th of september, 1953.
PROBABILISTIC SAFETY ASSESSMENT FOR SEISMIC EVENTS.
Living probabilistic safety assessment [LPSA].
A probabilistic safety assessment peer review: case study on the use of probabilistic safety assessment for safety decisions.
Use of probabilistic safety assessment for operational safety.
Generic component reliability data for research reactor PSA [Probabilistic Safety Analysis].
Defining initiating events for purposes of probabilistic safety assessment.
Computer codes for level 1 probabilistic safety assessment.
cento symposium on mining geology and the base metals, held in Ankara, Turkey, 14-29 September 1964 /
Applications of probabilistic safety assessment [PSA] for nuclear power plants.
Regulatory review of probabilistic safety assessment [PSA] level 2.
Regulatory review of probabilistic safety assessment [PSA]: level 1.
KfK-seminar series on supercomputing and visualization from may till september 1992: Seminar report.
Nuclear Fusion Project Annual Report of the Association KfK/EURATOM October 1991 - September 1992.
Nuclear fusion project annual report of the association KfK/EURATOM: October 1992 - September 1993.
Boletín Energético, Año 7, N° 11 (Número Completo)
Procedures for conducting common cause failure analysis in probabilistic safety assessment.
Application and development of probabilistic safety assessment for nuclear power plant operations.