000			04626cam a2200457Mi 4500
001			on1319221176
003			OCoLC
005			20240726104852.0
008			221015s2020 xx o ||| 0 eng d
040			_aEBLCP _beng _erda _cEBLCP _dNT _dEBLCP _dOCLCQ _dNT
020			_a9201067224
020			_a9789201067227 _q((electronic)l(electronic)ctronic)
050	0	4	_aTK9152 _b.S244 2020
049			_aMAIN
100	1		_aIAEA. _e1
245	1	0	_aSafety Analysis and Licensing Documentation for Nuclear Fuel Cycle Facilities
260			_aHavertown : _bInternational Atomic Energy Agency, _c(c)2020.
300			_a1 online resource (126 pages).
336			_atext _btxt _2rdacontent
337			_acomputer _bc _2rdamedia
338			_aonline resource _bcr _2rdacarrier
347			_adata file _2rda
490	1		_aSafety Reports Ser. ; _vv.102
500			_aDescription based upon print version of record.
504			_a2
505	0	0	_aIntro -- _t1. INTRODUCTION -- _t1.1. Background -- _t1.2. Objective -- _t1.3. Scope -- _t1.4. Structure -- _t2. GENERAL CONSIDERATIONS IN SAFETY ANALYSISOF NUCLEAR FUEL CYCLE FACILITIES -- _t2.1. Purpose of safety analysis -- _t2.1.1. Safety analysis for design -- _t2.1.2. Safety analysis for licensing and periodic safety reviews -- _t2.1.3. Safety analysis supporting emergency planning and accident management -- _t2.1.4. Analysis of operating experience -- _t2.2. Types of safety analysis and computational tools -- _t2.2.1. Types of safety analysis -- _t2.2.2. Calculation tools and data
505	0	0	_a2.3. Acceptance criteria for safety analysis -- _t2.4. Features of nuclear fuel cycle facilities affecting safety analysis -- _t2.5. Use of a graded approach in safety analysis -- _t3. PERFORMING SAFETY ANALYSIS FOR NUCLEAR FUEL CYCLE FACILITIES -- _t3.1. Identification of hazards -- _t3.1.1. Internal hazards -- _t3.1.2. External hazards -- _t3.2. Identification and selection of postulated initiating events -- _t3.2.1. Postulated initiating events -- _t3.2.2. Combination of events -- _t3.2.3. Grouping of events -- _t3.3. Evaluation of event sequences -- _t3.3.1. Modelling the scenario
505	0	0	_a3.3.2. Identifying physical phenomena and evaluation of associated parameters -- _t3.3.3. Defining boundary and initial conditions -- _t3.4. Analysis of facility states -- _t3.4.1. Anticipated operational occurrences -- _t3.4.2. Design basis accidents -- _t3.4.3. Design extension conditions -- _t3.5. Evaluation of consequences -- _t3.6. Comparison against acceptance criteria -- _t3.7. Presentation of safety analysis and conclusions -- _t3.7.1. Introduction -- _t3.7.2. Facility characteristics -- _t3.7.3. Identification of hazards and selection of PIEs -- _t3.7.4. Evaluation of event sequences
505	0	0	_a3.7.5. Transient and accident analysis -- _t3.7.6. Summary and conclusions -- _t4. APPLICATION OF SAFETY ANALYSIS -- _t4.1. Hazard categorization of the facility -- _t4.2. Safety classification of structures, systems and components -- _t4.3. Derivation of operational limits and conditions -- _t4.4. Modifications -- _t4.5. Ageing management and lifetime extension -- _t4.6. Emergency preparedness and response -- _t5. LICENSING DOCUMENTATION -- _t5.1. General considerations -- _t5.1.1. Scope and amount of information in licensing documentation -- _t5.1.2. Types of licensing documentation
505	0	0	_a5.1.3. Sites with multiple facilities -- _t5.2. Information needed at various steps of the licensing process -- _t5.2.1. Site evaluation -- _t5.2.2. Design and construction -- _t5.2.3. Commissioning -- _t5.2.4. Operation -- _t5.3. Content of the safety analysis report -- _t6. MANAGEMENT SYSTEM FOR SAFETY ANALYSIS AND LICENSING DOCUMENTATION -- _t6.1. Management responsibility -- _t6.2. Resource management -- _t6.3. Process implementation -- _t6.4. Measurement, assessment and improvement -- _tAppendix INDICATIVE CONTENT OF SAFETY ANALYSIS REPORT FOR A NUCLEAR FUEL CYCLE FACILITY -- _tREFERENCES
500			_aAnnex I FACTORS AFFECTING THE APPLICATION OF A GRADED APPROACH AND AREAS SUBJECTED TO GRADING IN SAFETY ANALYSIS OF NUCLEAR FUEL CYCLE FACILITIES
530			_a2 _ub
650		0	_aNuclear facilities _xSafety measures.
650		0	_aNuclear facilities _xLicenses _xDocumentation.
650		0	_aNuclear fuels _xManagement.
655		1	_aElectronic Books.
856	4	0	_zClick to access digital title | log in using your CIU ID number and my.ciu.edu password. _uhttpss://search.ebscohost.com/login.aspx?direct=true&scope=site&db=nlebk&db=nlabk&AN=3282300&site=eds-live&custid=s3260518
942			_cOB _D _eEB _hTK _m2020 _QOL _R _x _8NFIC _2LOC
994			_a92 _bNT
999			_c81144 _d81144
902			_a1 _bCynthia Snell _c1 _dCynthia Snell