| 000 | 01922cam a22005537a 4500 | ||
|---|---|---|---|
| 001 | 000981 | ||
| 003 | armpuni | ||
| 005 | 20160923145024.0 | ||
| 008 | 160923s1981####xx#a##########000#0#und#d | ||
| 040 |
_aarmpuni _carmpuni |
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| 041 | _aen | ||
| 080 | _a536.2 | ||
| 080 | _a621.039 | ||
| 080 | _a66.045 | ||
| 100 | 1 |
_aJones, Owen _4edit. |
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| 245 | 1 | 0 |
_aNuclear reactor safety heat transfer / _cOwen Jones |
| 260 |
_aWashington : _bHemisphere Publishing Corporation, _cc 1981 |
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| 300 |
_axix, 959 p. : _bil.;, 23 cm. |
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| 440 | 0 |
_aProceedings of the International Centre for Heat and Mass Transfer ; _v12 |
|
| 500 | _aApéndices | ||
| 500 | _aIncluye índices | ||
| 500 | _aReferencias al final de los capítulos | ||
| 550 | _aAccident initiation and clad relocation | ||
| 550 | _aBlockages in LMFBR subassemblies | ||
| 550 | _aBlowdown phase | ||
| 550 | _aCore disruptive accidents | ||
| 550 | _aEmergency cooling water ingection | ||
| 550 | _aExperimental methods in two-Phase flows | ||
| 550 | _aEx-Vessel post accident heat removal | ||
| 550 | _afuel motion | ||
| 550 | _aIn-Vessel post accident heat removal | ||
| 550 | _aLMFBR System safety analysis | ||
| 550 | _aLoss of coolant accident | ||
| 550 | _aLWR system safety analysis | ||
| 550 | _aNatural convection cooling | ||
| 550 | _aNuclear system safety modeling | ||
| 550 | _aPower reactor concepts and systems overview | ||
| 550 | _aReflood and rewet heat transfer | ||
| 550 | _aSafety Issues-Thermal hydraulic considerations | ||
| 550 | _aSingle- and two-Phase flow | ||
| 550 | _aSingle- and two-Phase heat transfer | ||
| 550 | _aSodium boiling | ||
| 550 | _aThe accident at Three Mile Island | ||
| 550 | _aTransient response of light water reactors | ||
| 550 | _aTransient response of liquid metal fast breeder reactors | ||
| 550 | _aVapor explosions | ||
| 942 |
_cLB _2cdu |
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| 945 |
_aR G _d1995-09-14 |
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| 999 |
_c980 _d2155 |
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