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| LEADER |
00000cam a2200000Mu 4500 |
| 001 |
EBSCO_on1319221176 |
| 003 |
OCoLC |
| 005 |
20231017213018.0 |
| 006 |
m o d |
| 007 |
cr cnu---unuuu |
| 008 |
221015s2020 xx o ||| 0 eng d |
| 040 |
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|a EBLCP
|b eng
|c EBLCP
|d N$T
|d EBLCP
|d OCLCQ
|d N$T
|d OCLCQ
|d OCLCF
|d OCLCQ
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| 020 |
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|a 9201067224
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| 020 |
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|a 9789201067227
|q (electronic bk.)
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| 035 |
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|a (OCoLC)1319221176
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4 |
|a TK9152
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| 082 |
0 |
4 |
|a 621.4835
|2 23/eng/20230112
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| 049 |
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|a UAMI
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| 100 |
1 |
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|a IAEA.
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| 245 |
1 |
0 |
|a Safety Analysis and Licensing Documentation for Nuclear Fuel Cycle Facilities
|h [electronic resource].
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| 260 |
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|a Havertown :
|b International Atomic Energy Agency,
|c 2020.
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| 300 |
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|a 1 online resource (126 p.).
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| 490 |
1 |
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|a Safety Reports Ser. ;
|v v.102
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| 500 |
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|a Description based upon print version of record.
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| 505 |
0 |
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|a Intro -- 1. INTRODUCTION -- 1.1. Background -- 1.2. Objective -- 1.3. Scope -- 1.4. Structure -- 2. GENERAL CONSIDERATIONS IN SAFETY ANALYSISOF NUCLEAR FUEL CYCLE FACILITIES -- 2.1. Purpose of safety analysis -- 2.1.1. Safety analysis for design -- 2.1.2. Safety analysis for licensing and periodic safety reviews -- 2.1.3. Safety analysis supporting emergency planning and accident management -- 2.1.4. Analysis of operating experience -- 2.2. Types of safety analysis and computational tools -- 2.2.1. Types of safety analysis -- 2.2.2. Calculation tools and data
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| 505 |
8 |
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|a 2.3. Acceptance criteria for safety analysis -- 2.4. Features of nuclear fuel cycle facilities affecting safety analysis -- 2.5. Use of a graded approach in safety analysis -- 3. PERFORMING SAFETY ANALYSIS FOR NUCLEAR FUEL CYCLE FACILITIES -- 3.1. Identification of hazards -- 3.1.1. Internal hazards -- 3.1.2. External hazards -- 3.2. Identification and selection of postulated initiating events -- 3.2.1. Postulated initiating events -- 3.2.2. Combination of events -- 3.2.3. Grouping of events -- 3.3. Evaluation of event sequences -- 3.3.1. Modelling the scenario
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| 505 |
8 |
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|a 3.3.2. Identifying physical phenomena and evaluation of associated parameters -- 3.3.3. Defining boundary and initial conditions -- 3.4. Analysis of facility states -- 3.4.1. Anticipated operational occurrences -- 3.4.2. Design basis accidents -- 3.4.3. Design extension conditions -- 3.5. Evaluation of consequences -- 3.6. Comparison against acceptance criteria -- 3.7. Presentation of safety analysis and conclusions -- 3.7.1. Introduction -- 3.7.2. Facility characteristics -- 3.7.3. Identification of hazards and selection of PIEs -- 3.7.4. Evaluation of event sequences
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| 505 |
8 |
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|a 3.7.5. Transient and accident analysis -- 3.7.6. Summary and conclusions -- 4. APPLICATION OF SAFETY ANALYSIS -- 4.1. Hazard categorization of the facility -- 4.2. Safety classification of structures, systems and components -- 4.3. Derivation of operational limits and conditions -- 4.4. Modifications -- 4.5. Ageing management and lifetime extension -- 4.6. Emergency preparedness and response -- 5. LICENSING DOCUMENTATION -- 5.1. General considerations -- 5.1.1. Scope and amount of information in licensing documentation -- 5.1.2. Types of licensing documentation
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| 505 |
8 |
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|a 5.1.3. Sites with multiple facilities -- 5.2. Information needed at various steps of the licensing process -- 5.2.1. Site evaluation -- 5.2.2. Design and construction -- 5.2.3. Commissioning -- 5.2.4. Operation -- 5.3. Content of the safety analysis report -- 6. MANAGEMENT SYSTEM FOR SAFETY ANALYSIS AND LICENSING DOCUMENTATION -- 6.1. Management responsibility -- 6.2. Resource management -- 6.3. Process implementation -- 6.4. Measurement, assessment and improvement -- Appendix INDICATIVE CONTENT OF SAFETY ANALYSIS REPORT FOR A NUCLEAR FUEL CYCLE FACILITY -- REFERENCES
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| 500 |
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|a Annex I FACTORS AFFECTING THE APPLICATION OF A GRADED APPROACH AND AREAS SUBJECTED TO GRADING IN SAFETY ANALYSIS OF NUCLEAR FUEL CYCLE FACILITIES
|
| 590 |
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|a eBooks on EBSCOhost
|b EBSCO eBook Subscription Academic Collection - Worldwide
|
| 650 |
|
0 |
|a Nuclear facilities
|x Safety measures.
|
| 650 |
|
0 |
|a Nuclear facilities
|x Licenses
|x Documentation.
|
| 650 |
|
0 |
|a Nuclear fuels
|x Management.
|
| 650 |
|
7 |
|a Nuclear facilities
|x Safety measures.
|2 fast
|0 (OCoLC)fst01040151
|
| 650 |
|
7 |
|a Nuclear fuels
|x Management.
|2 fast
|0 (OCoLC)fst01040228
|
| 655 |
|
0 |
|a Electronic books.
|
| 776 |
0 |
8 |
|i Print version:
|a IAEA
|t Safety Analysis and Licensing Documentation for Nuclear Fuel Cycle Facilities
|d Havertown : International Atomic Energy Agency,c2020
|
| 830 |
|
0 |
|a Safety Reports Ser.
|
| 856 |
4 |
0 |
|u https://ebsco.uam.elogim.com/login.aspx?direct=true&scope=site&db=nlebk&AN=3282300
|z Texto completo
|
| 938 |
|
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|a ProQuest Ebook Central
|b EBLB
|n EBL6985957
|
| 938 |
|
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|a ProQuest Ebook Central
|b EBLB
|n EBL6985957
|
| 938 |
|
|
|a EBSCOhost
|b EBSC
|n 3282300
|
| 994 |
|
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|a 92
|b IZTAP
|
