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00000cam a2200000Mu 4500 |
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EBSCO_on1319220270 |
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OCoLC |
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20231017213018.0 |
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221015s2020 xx o ||| 0 eng d |
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|a EBLCP
|b eng
|c EBLCP
|d N$T
|d EBLCP
|d OCLCQ
|d N$T
|d OCLCF
|d OCLCO
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| 020 |
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|a 920105422X
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|a 9789201054227
|q (electronic bk.)
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|a (OCoLC)1319220270
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|a TK1078
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|a 621.483
|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 Periodic Safety Review for Research Reactors
|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 (117 p.).
|
| 490 |
1 |
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|a Safety Reports Ser. ;
|v v.99
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| 500 |
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|a Description based upon print version of record.
|
| 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 -- 2.1. Objectives of periodic safety review -- 2.2. Roles and responsibilities -- 2.2.1. Operating organization -- 2.2.2. Regulatory body -- 2.2.3. Communication -- 2.3. Phases of a periodic safety review project -- 2.4. Periodic safety review methodology -- 2.5. Periodic safety review process -- 2.5.1. Preparation of the PSR project -- 2.5.2. Review of safety factors -- 2.5.3. Global assessment -- 2.6. Use of a graded approach
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| 505 |
8 |
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|a 3. REVIEW PROCESS OF THE OPERATING ORGANIZATION -- 3.1. Safety factors relating to the facility -- 3.1.1. Safety factor 1: Facility design -- 3.1.2. Safety factor 2: Actual condition of SSCs important to safety -- 3.1.3. Safety factor 3: Equipment qualification -- 3.1.4. Safety factor 4: Ageing -- 3.1.5. Safety factor 5: Utilization -- 3.2. Safety factors relating to safety analysis -- 3.2.1. Safety factor 6: Deterministic safety analysis including hazard analysis -- 3.3. Safety factors relating to operating experience -- 3.3.1. Safety factor 7: Operating experience
|
| 505 |
8 |
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|a 3.3.2. Safety factor 8: Use of experience from other facilities and research findings -- 3.4. Safety factors relating to organizational effectiveness -- 3.4.1. Safety factor 9: Organization, the management system and safety culture -- 3.4.2. Safety factor 10: Procedure management -- 3.4.3. Safety factor 11: Human factors -- 3.4.4. Safety factor 12: Emergency planning -- 3.5. Safety factors relating to radiological safety -- 3.5.1. Safety factor 13: Operational radiation protection -- 3.5.2. Safety factor 14: Radiological impact on the environment -- 3.6. Global assessment
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| 505 |
8 |
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|a 3.7. Integrated implementation plan -- 3.8. Documentation -- 4. REVIEW PROCESS OF THE REGULATORY BODY -- 5. POST-REVIEW ACTIVITIES -- Appendix DOCUMENTATION OF THE PERIODIC SAFETY REVIEW -- REFERENCES -- Annex I TYPICAL INPUTS, OUTPUTS AND RELEVANT PUBLICATIONS FOR THE REVIEW OF SAFETY FACTORS -- Annex II PERIODIC SAFETY REVIEW FOR THE OPAL REACTOR: OVERVIEW AND LESSONS LEARNED -- Annex III REGULATORY ASSESSMENT OF THE BUDAPEST RESEARCH REACTOR PERIODIC SAFETY REVIEW -- ABBREVIATIONS -- CONTRIBUTORS TO DRAFTING AND REVIEW
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| 590 |
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|a eBooks on EBSCOhost
|b EBSCO eBook Subscription Academic Collection - Worldwide
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| 650 |
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0 |
|a Nuclear power plants
|x Safety measures.
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| 650 |
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|a Industrial safety.
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| 650 |
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|a System safety.
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| 650 |
|
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|a Centrales nucléaires
|x Sécurité
|x Mesures.
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| 650 |
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|a Sécurité du travail.
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| 650 |
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6 |
|a Sécurité des systèmes.
|
| 650 |
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7 |
|a occupational safety.
|2 aat
|
| 650 |
|
7 |
|a Industrial safety
|2 fast
|
| 650 |
|
7 |
|a Nuclear power plants
|x Safety measures
|2 fast
|
| 650 |
|
7 |
|a System safety
|2 fast
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| 776 |
0 |
8 |
|i Print version:
|a IAEA
|t Periodic Safety Review for Research Reactors
|d Havertown : International Atomic Energy Agency,c2021
|
| 830 |
|
0 |
|a Safety Reports Ser.
|
| 856 |
4 |
0 |
|u https://ebsco.uam.elogim.com/login.aspx?direct=true&scope=site&db=nlebk&AN=3282297
|z Texto completo
|
| 938 |
|
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|a ProQuest Ebook Central
|b EBLB
|n EBL6986020
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| 938 |
|
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|a EBSCOhost
|b EBSC
|n 3282297
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| 994 |
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|a 92
|b IZTAP
|
