MARC details
| 000 -LEADER |
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| fixed length control field |
04626cam a2200457Mi 4500 |
| 001 - CONTROL NUMBER |
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| control field |
on1319221176 |
| 003 - CONTROL NUMBER IDENTIFIER |
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| control field |
OCoLC |
| 005 - DATE AND TIME OF LATEST TRANSACTION |
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| control field |
20240726104852.0 |
| 008 - FIXED-LENGTH DATA ELEMENTS--GENERAL INFORMATION |
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| fixed length control field |
221015s2020 xx o ||| 0 eng d |
| 040 ## - CATALOGING SOURCE |
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| Original cataloging agency |
EBLCP |
| Language of cataloging |
eng |
| Description conventions |
rda |
| Transcribing agency |
EBLCP |
| Modifying agency |
NT |
| -- |
EBLCP |
| -- |
OCLCQ |
| -- |
NT |
| 020 ## - INTERNATIONAL STANDARD BOOK NUMBER |
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| International Standard Book Number |
9201067224 |
| 020 ## - INTERNATIONAL STANDARD BOOK NUMBER |
|---|
| International Standard Book Number |
9789201067227 |
| Qualifying information |
|
| 050 04 - LIBRARY OF CONGRESS CALL NUMBER |
|---|
| Classification number |
TK9152 |
| Item number |
.S244 2020 |
| 049 ## - LOCAL HOLDINGS (OCLC) |
|---|
| Holding library |
MAIN |
| 100 1# - MAIN ENTRY--PERSONAL NAME |
|---|
| Personal name |
IAEA. |
| Relator term |
Author |
| 245 10 - TITLE STATEMENT |
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| Title |
Safety Analysis and Licensing Documentation for Nuclear Fuel Cycle Facilities |
| 260 ## - PUBLICATION, DISTRIBUTION, ETC. |
|---|
| Place of publication, distribution, etc. |
Havertown : |
| Name of publisher, distributor, etc. |
International Atomic Energy Agency, |
| Date of publication, distribution, etc. |
(c)2020. |
| 300 ## - PHYSICAL DESCRIPTION |
|---|
| Extent |
1 online resource (126 pages). |
| 336 ## - CONTENT TYPE |
|---|
| Content type term |
text |
| Content type code |
txt |
| Source |
rdacontent |
| 337 ## - MEDIA TYPE |
|---|
| Media type term |
computer |
| Media type code |
c |
| Source |
rdamedia |
| 338 ## - CARRIER TYPE |
|---|
| Carrier type term |
online resource |
| Carrier type code |
cr |
| Source |
rdacarrier |
| 347 ## - DIGITAL FILE CHARACTERISTICS |
|---|
| File type |
data file |
| Source |
rda |
| 490 1# - SERIES STATEMENT |
|---|
| Series statement |
Safety Reports Ser. ; |
| Volume # |
v.102 |
| 500 ## - GENERAL NOTE |
|---|
| General note |
Description based upon print version of record. |
| 504 ## - BIBLIOGRAPHY, ETC. NOTE |
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| Bibliography, etc. note |
Includes bibliographies and index. |
| 505 00 - FORMATTED CONTENTS NOTE |
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| Formatted contents note |
Intro -- |
| Title |
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 |
| 505 00 - FORMATTED CONTENTS NOTE |
|---|
| Formatted contents note |
2.3. Acceptance criteria for safety analysis -- |
| Title |
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 |
| 505 00 - FORMATTED CONTENTS NOTE |
|---|
| Formatted contents note |
3.3.2. Identifying physical phenomena and evaluation of associated parameters -- |
| Title |
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 |
| 505 00 - FORMATTED CONTENTS NOTE |
|---|
| Formatted contents note |
3.7.5. Transient and accident analysis -- |
| Title |
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 |
| 505 00 - FORMATTED CONTENTS NOTE |
|---|
| Formatted contents note |
5.1.3. Sites with multiple facilities -- |
| Title |
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 |
| 500 ## - GENERAL NOTE |
|---|
| General note |
Annex I FACTORS AFFECTING THE APPLICATION OF A GRADED APPROACH AND AREAS SUBJECTED TO GRADING IN SAFETY ANALYSIS OF NUCLEAR FUEL CYCLE FACILITIES |
| 530 ## - COPYRIGHT INFORMATION: |
|---|
| COPYRIGHT INFORMATION |
COPYRIGHT NOT covered - Click this link to request copyright permission: |
| Uniform Resource Identifier |
<a href="b">b</a> |
| 650 #0 - SUBJECT ADDED ENTRY--TOPICAL TERM |
|---|
| Topical term or geographic name entry element |
Nuclear facilities |
| General subdivision |
Safety measures. |
| 650 #0 - SUBJECT ADDED ENTRY--TOPICAL TERM |
|---|
| Topical term or geographic name entry element |
Nuclear facilities |
| General subdivision |
Licenses |
| -- |
Documentation. |
| 650 #0 - SUBJECT ADDED ENTRY--TOPICAL TERM |
|---|
| Topical term or geographic name entry element |
Nuclear fuels |
| General subdivision |
Management. |
| 655 #1 - INDEX TERM--GENRE/FORM |
|---|
| Genre/form data or focus term |
Electronic Books. |
| 856 40 - ELECTRONIC LOCATION AND ACCESS |
|---|
| -- |
Click to access digital title | log in using your CIU ID number and my.ciu.edu password. |
| Uniform Resource Identifier |
<a href="httpss://search.ebscohost.com/login.aspx?direct=true&scope=site&db=nlebk&db=nlabk&AN=3282300&site=eds-live&custid=s3260518">httpss://search.ebscohost.com/login.aspx?direct=true&scope=site&db=nlebk&db=nlabk&AN=3282300&site=eds-live&custid=s3260518</a> |
| 942 ## - ADDED ENTRY ELEMENTS (KOHA) |
|---|
| Koha item type |
Online Book (LOGIN USING YOUR MY CIU LOGIN AND PASSWORD) |
| DONATED BY: |
|
| VENDOR |
EBSCO |
| Classification part |
TK |
| PUBLICATION YEAR |
2020 |
| LOCATION |
ONLINE |
| REQUESTED BY: |
|
| -- |
|
| -- |
NFIC |
| Source of classification or shelving scheme |
|
| 994 ## - |
|---|
| -- |
92 |
| -- |
NT |
| 902 ## - LOCAL DATA ELEMENT B, LDB (RLIN) |
|---|
| a |
1 |
| b |
Cynthia Snell |
| c |
1 |
| d |
Cynthia Snell |