000 | 04627cam a2200457Mi 4500 | ||
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001 | on1319213923 | ||
003 | OCoLC | ||
005 | 20240726104852.0 | ||
008 | 221015s2020 xx o ||| 0 eng d | ||
040 |
_aEBLCP _beng _erda _cEBLCP _dNT _dEBLCP _dOCLCQ _dNT |
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020 | _a9201064225 | ||
020 |
_a9789201064226 _q((electronic)l(electronic)ctronic) |
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050 | 0 | 4 |
_aTK9212 _b.D475 2020 |
049 | _aMAIN | ||
100 | 1 |
_aIAEA. _e1 |
|
245 | 1 | 0 |
_aDesign of the Reactor Coolant System and Associated Systems for Nuclear Power Plants _bSpecific Safety Guide. _c |
260 |
_aHavertown : _bInternational Atomic Energy Agency, _c(c)2020. |
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300 | _a1 online resource (102 pages). | ||
336 |
_atext _btxt _2rdacontent |
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337 |
_acomputer _bc _2rdamedia |
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338 |
_aonline resource _bcr _2rdacarrier |
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347 |
_adata file _2rda |
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490 | 1 |
_aIAEA Safety Standards Ser. ; _vv.SSG-56 |
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500 | _aDescription based upon print version of record. | ||
504 | _a2 | ||
505 | 0 | 0 |
_aIntro -- _t1. INTRODUCTION -- _tBackground -- _tObjective -- _tScope -- _tStructure -- _t2. Extent of the reactor coolant system and associated systems -- _tReactor coolant system -- _tSystems for heat removal in shutdown conditions -- _tSystems for coolant inventory control in operational states -- _tSystems for control of core reactivity in operational states -- _tSystems for core cooling and residual heat removal in accident conditions -- _tSystems for control of core reactivity in accident conditions -- _tUltimate heat sink and residual heat transfer systems in all plant states |
505 | 0 | 0 |
_a3. DESIGN BASIS OF THE REACTOR COOLANT SYSTEM AND ASSOCIATED SYSTEMS -- _tGeneral -- _tSafety functions -- _tPostulated initiating events -- _tInternal hazards -- _tExternal hazards -- _tAccident conditions -- _tDesign basis accidents -- _tDesign extension conditions without significant fuel degradation -- _tDesign limits and acceptance criteria -- _tReliability -- _tSystems designed to cope with design basis accidents -- _tSafety features for design extension conditions without significant fuel degradation -- _tDefence in depth -- _tSafety classification -- _tEnvironmental qualification of items important to safety |
505 | 0 | 0 |
_aLoads and load combinations -- _tMaterials -- _tMaterials in contact with radioactive fluids -- _tMaterials exposed to high neutron flux -- _tManufacturing and installation -- _tCalibration, testing, maintenance, repair, replacement, inspection and monitoring -- _tPre-service and in-service inspection of the reactor coolant system -- _tInspection of steam generators -- _tOverpressure protection -- _tLayout -- _tRadiation protection -- _tCombustible gas accumulation in normal operation -- _tVenting and draining -- _tInterfaces between the reactor coolant system and associated systems -- _tContainment isolation |
505 | 0 | 0 |
_aInstrumentation -- _tMultiple units at a site -- _tCodes and standards -- _tUse of probabilistic analyses in design -- _t4. ULTIMATE HEAT SINK AND RESIDUAL HEAT TRANSFER SYSTEMS -- _tUltimate heat sink -- _tResidual heat transfer systems -- _tResidual heat transfer in operational states -- _tResidual heat transfer for design basis accidents -- _tResidual heat transfer for design extension conditions -- _t5. SPECIFIC CONSIDERATIONS IN DESIGN OF THE REACTOR COOLANT SYSTEM -- _tStructural design -- _tDesign basis loads and load combinations -- _tControl of cooling conditions in operational states |
505 | 0 | 0 |
_aPressure control and overpressure protection -- _tIsolation of the reactor coolant pressure boundary -- _tPostulated initiating events -- _tInternal hazards -- _tExternal hazards -- _tLayout -- _tDesign limits -- _tSafety classification -- _tEnvironmental qualification -- _tPressure tests -- _tVenting -- _tFor pressurized water reactors -- _tFor boiling water reactors -- _tFor pressurized heavy water reactors -- _tSpecific design aspects -- _tReactor pressure vessel -- _tReactor pressure vessel internals (for PWRs and BWRs) -- _tFuel channel assemblies (for PHWRs) |
500 | _aReactor coolant pumps (for PWRs and PHWRs) and reactor recirculation pumps (for BWRs) | ||
530 |
_a2 _ub |
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650 | 0 |
_aNuclear power plants _xDesign and construction. |
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650 | 0 |
_aNuclear reactors _xCooling. |
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650 | 0 |
_aNuclear power plants _xSafety measures. |
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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=3282288&site=eds-live&custid=s3260518 |
942 |
_cOB _D _eEB _hTK _m2020 _QOL _R _x _8NFIC _2LOC |
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994 |
_a92 _bNT |
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999 |
_c81139 _d81139 |
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902 |
_a1 _bCynthia Snell _c1 _dCynthia Snell |