-
1
-
-
0003383302
-
-
BFS, 1997a. Bundesamt für Strahlenschutz (BfS), facharbeitskreis probabilistische Sicherheitsanalyse für Kernkraftwerke, Daten zur Quantifizierung von Ereignisablaufdiagrammen und Fehlerbäumen, BfS-KT-18/97, Salzgitter.
-
-
-
-
2
-
-
0003401472
-
-
BFS, 1997b. Bundesamt für Strahlenschutz (BfS), facharbeitskreis probabilistische Sicherheitsanalyse für Kernkraftwerke, Methoden zur probabilistischen Sicherheitsanalyse für Kernkraftwerke, BfS-KT-16/97, Salzgitter.
-
-
-
-
3
-
-
0003341208
-
-
GRS, 1979. Gesellschaft fuer Reaktorsicherheit, Deutsche Risikostudie Kernkraftwerke, Verlag TUEV Rheinland, Bonn.
-
-
-
-
4
-
-
0003399350
-
-
IAEA, 1988. Basic Safety Principles for Nuclear Power Plants (75-INSAG-3). Vienna.
-
-
-
-
5
-
-
0003451630
-
-
IAEA, 1992a. Probabilistic Safety Assessment (75-INSAG-6). Vienna.
-
-
-
-
6
-
-
0003463165
-
-
IAEA, 1992b. Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants (Level 1) (50-P-4). Vienna.
-
-
-
-
7
-
-
0003435602
-
-
IAEA, 1992c. The Role Probabilistic Safety Assessments and Probabilistic Safety Criteria in Nuclear Power Plant Safety (Safety Series 106). Vienna.
-
-
-
-
8
-
-
0003337263
-
-
IAEA 1992d. The Safety of Nuclear Power Plants (75-INSAG-5). Vienna.
-
-
-
-
9
-
-
0003340509
-
-
IAEA, 1995a. Human Reliability Analysis in Probabilistic Safety Assessments of Nuclear Power Plants (50-P-10). Vienna.
-
-
-
-
10
-
-
0003451632
-
-
IAEA, 1995b. Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants (Level 2) (50-P-8). Vienna.
-
-
-
-
11
-
-
0003340150
-
-
IAEA, 1995c. Treatment of External Hazards in Probabilistic Safety Assessments for Nuclear Power Plants (50-P-7). Vienna.
-
-
-
-
12
-
-
0003462428
-
-
IAEA, 1996a. Harmonisation of WWER PSA Model Assumptions and Data (WWER-SC-195). Vienna.
-
-
-
-
13
-
-
0003456573
-
-
IAEA, 1996b. Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants (Level 3) (50-P-12). Vienna.
-
-
-
-
14
-
-
0003398742
-
-
IAEA, 1999a. A Framework for a Quality Assurance Programme for PSA (IAEA-TECDOC-1101).
-
-
-
-
15
-
-
0003328418
-
-
IAEA, 1999b. Basic Safety Principles for Nuclear Power Plants (75-INSAG-3 Rev. 1, INSAG-12). Vienna.
-
-
-
-
16
-
-
0003382141
-
-
IAEA, 1999c. DRAFT Working Material (Report of a Technical Meeting on Comparison of PSA Level 1 for WWER-1000 Reactors). Erlangen, Germany, (7-11 June).
-
-
-
-
17
-
-
0003338926
-
-
IAEA, 1999d. IAEA Safety Glossary Terminology used in Radiation Protection and in Nuclear, Radiation, Waste and Transport Safety. Working Material Draft.
-
-
-
-
18
-
-
0003404872
-
-
IAEA, 1999e. Living Probabilistic Safety Assessment (LPSA) (IAEA-TECDOC-1106).
-
-
-
-
19
-
-
0003404874
-
-
IAEA, 1999f. Safety Assessment and Verification, Draft Safety Guide.
-
-
-
-
20
-
-
0003341538
-
-
IAEA, 1999g. Working Material (Summary Report, Workshop on Probabilistic Safety Assessments for Pressurized Heavy Water Reactors). Toronto, Canada, (3-6 May).
-
-
-
-
21
-
-
0003459549
-
-
IAEA, 2000a. Applications of Probabilistic Safety Assessments (PSA) for Nuclear Power Plants (Draft IAEA-TECDOC-XXXX). Vienna.
-
-
-
-
22
-
-
0003340152
-
-
IAEA, 2000b. Probabilistic Safety Assessments of Nuclear Power Plants for Low Power and Shutdown Modes (IAEA-TECDOC-1144). Vienna.
-
-
-
-
23
-
-
0003479783
-
-
IAEA, 2000c. Regulatory Review of Probabilistic Safety Assessments (PSA) Level 1 (IAEA-TECDOC-1135) Vienna. (in co-operation with NEA/OECD).
-
-
-
-
24
-
-
0003340154
-
-
IAEA, 2000d. Safety of Nuclear Plants: Design (Safety Standard Series NS-R-1). Vienna.
-
-
-
-
25
-
-
0003396488
-
-
NEA/OECD, 1996. Committee on Nuclear Regulatory Activities (CNRA) of the OECD Nuclear Energy Agency (NEA), Regulatory Approaches to PSA (Report on the Survey of National Practices. NEA/CNRA/R(95)2; OCDE/GD(96)7). Paris.
-
-
-
-
26
-
-
0003336642
-
-
Swain, A.D., Guttmann, H.E., (USNRC), 1983. Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications (NUREG/CR-1278). Washington, DC.
-
-
-
-
27
-
-
0003340511
-
-
UKHSE, 1999. Reducing Risks, Protecting People, Discussion Document, HSE, Risk Assessment Policy Unit, London.
-
-
-
-
28
-
-
0003336644
-
-
USNRC, 1975. Reactor Safety Study: An Assessment of Accident Risks in US Commercial Nuclear Power Plants (WASH-1400-MR; NUREG-75/014). Washington, DC.
-
-
-
-
29
-
-
0003484687
-
-
USNRC, 1981. Fault Tree Handbook (NUREG-0492). Washington, DC.
-
-
-
-
30
-
-
0003337265
-
-
USNRC, 1983. Probabilistic Risk Analysis: Procedures Guide (NUREG/CR-2300). Washington, DC.
-
-
-
-
31
-
-
0003456575
-
-
USNRC, 1985. Probabilistic Risk Analysis: Procedures Guide, rev. 1 (NUREG/CR-2815 BNL-NUREG-51559). Washington, DC.
-
-
-
-
32
-
-
0003340513
-
-
USNRC, 1990. Severe Accident Risks: An Assessment for Five US Nuclear Power Plants (Final Summary Report, NUREG/CR-1150). Washington, DC.
-
-
-
-
33
-
-
0003462432
-
-
USNRC, 1997. Individual Plant Examination Program: Perspectives on Reactor Safety and Plant Performance (NUREG-1560). Washington, DC.
-
-
-
-
34
-
-
0003401474
-
-
USNRC, 1998a. An Approach for Plant specific, Risk-Informed Decision-making: Graded Quality Assurance (Regulatory Guide 1.176). Washington, DC.
-
-
-
-
35
-
-
0003337267
-
-
USNRC, 1998b. An Approach For Plant-Specific Risk-informed Decision-making: Inservice Inspection of Piping (Regulatory Guide 1.178). Washington, DC.
-
-
-
-
36
-
-
0003395954
-
-
USNRC, 1998c. An Approach for Plant specific, Risk-Informed Decision-making: Inservice Testing (Regulatory Guide 1.175). Washington, DC.
-
-
-
-
37
-
-
0003466988
-
-
USNRC, 1998d. An Approach for Plant specific, Risk-informed Decision-making: Technical Specifications (Regulatory Guide 1.177). Washington, DC.
-
-
-
-
38
-
-
0003484689
-
-
USNRC, 1998e. An Approach for Using Probabilistic Risk Assessment in Risk-informed decisions on Plant specific Changes to the Licensing Basis (Regulatory Guide 1.174). Washington, DC.
-
-
-
-
39
-
-
0003463167
-
-
USNRC/EC, 1998. Probabilistic Accident Consequence Uncertainty Analysis (NUREG/CR-6571,6555,6526, EUR 16773).
-
-
-
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