Nuclear Reactors Cooling

452 books
An evaluation of steam-cooled fast breeder reactorsOak Ridge National Laboratory.
⏱ 6h 0m

An evaluation of steam-cooled fast breeder reactors

Oak Ridge National Laboratory.

1969360 pp.
An evaluation of alternate coolant fast breeder reactorsUnited States. Alternate Coolant Task Force.
⏱ 2h 34m

An evaluation of alternate coolant fast breeder reactors

United States. Alternate Coolant Task Force.

1969154 pp.
Evaluation of long-term post-accident core cooling of Three Mile Island unit 2U.S. Nuclear Regulatory Commission. Division of Systems Safety.
⏱ 5h 8m

Evaluation of long-term post-accident core cooling of Three Mile Island unit 2

U.S. Nuclear Regulatory Commission. Division of Systems Safety.

1979308 pp.
Boil-off experiments with the EIR-NEPTUN facilityS. N. Aksan
⏱ 44m

Boil-off experiments with the EIR-NEPTUN facility

S. N. Aksan

199244 pp.
Modular High-temperature Gas-cooled Reactor Power PlantKurt Kugeler
⏱ 14h 59m

Modular High-temperature Gas-cooled Reactor Power Plant

Kurt Kugeler

2018899 pp.
Effect of particle blending on HTGR fuel rod temperature profilesP. Angelini
⏱ 1h 11m

Effect of particle blending on HTGR fuel rod temperature profiles

P. Angelini

197971 pp.
Evaluation of simulated-LOCA tests that produced large fuel cladding ballooningD. A. Powers
⏱ 33m

Evaluation of simulated-LOCA tests that produced large fuel cladding ballooning

D. A. Powers

197933 pp.
Modeling and performance of the MHTGR reactor cavity cooling systemJ. C. Conklin
⏱ 27m

Modeling and performance of the MHTGR reactor cavity cooling system

J. C. Conklin

199027 pp.
Heisei 19-nendo PWR sanpusukurīn heisoku jishō ni kansuru shiken hōkokushoGenshiryoku Anzen Kiban Kikō

Heisei 19-nendo PWR sanpusukurīn heisoku jishō ni kansuru shiken hōkokusho

Genshiryoku Anzen Kiban Kikō

2008No page data
Nuclear Reactor Thermal-HydraulicsPradip Saha

Nuclear Reactor Thermal-Hydraulics

Pradip Saha

2017No page data
Transactions of the Twenty-fifth Water Reactor Safety Information MeetingWater Reactor Safety Information Meeting (25th 1997 Bethesda, Md.)
⏱ 2h 12m

Transactions of the Twenty-fifth Water Reactor Safety Information Meeting

Water Reactor Safety Information Meeting (25th 1997 Bethesda, Md.)

1997132 pp.
Integrated fuel-coolant interaction (IFCI 6.0) codeF. J. Davis
⏱ 56m

Integrated fuel-coolant interaction (IFCI 6.0) code

F. J. Davis

199456 pp.
Standard technical specifications for Westinghouse pressurized water reactorsUnknown Author

Standard technical specifications for Westinghouse pressurized water reactors

Unknown Author

1981No page data
Estimate of radionuclide release characteristics into containment under severe accident conditionsH. P. Nourbakhsh
⏱ 2h 4m

Estimate of radionuclide release characteristics into containment under severe accident conditions

H. P. Nourbakhsh

1992124 pp.
Decay heat removal using feed-and-bleed for U.S. pressurized water reactorsGuy G. Loomis
⏱ 40m

Decay heat removal using feed-and-bleed for U.S. pressurized water reactors

Guy G. Loomis

198840 pp.
Draft regulatory guide DG-1107U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.
⏱ 30m

Draft regulatory guide DG-1107

U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.

200330 pp.
Brief description of a one megawatt convection cooled homogeneous reactor - Lapre IIU.S. Atomic Energy Commission
⏱ 18m

Brief description of a one megawatt convection cooled homogeneous reactor - Lapre II

U.S. Atomic Energy Commission

195518 pp.
How the optimum cost of a dry/wet cooling system is affected by the variance of system operating parametersDennis Kurt Davis
⏱ 2h 34m

How the optimum cost of a dry/wet cooling system is affected by the variance of system operating parameters

Dennis Kurt Davis

1979154 pp.
Direct containment heating experiments at low reactor coolant system pressure in the Surtsey test facilityT. K. Blanchat
⏱ 1h 34m

Direct containment heating experiments at low reactor coolant system pressure in the Surtsey test facility

T. K. Blanchat

199994 pp.
Istechenie teplonositeli︠a︡ pri potere germetichnosti reaktornogo konturaVladimir Vladimirovich Fisenko
⏱ 2h 8m

Istechenie teplonositeli︠a︡ pri potere germetichnosti reaktornogo kontura

Vladimir Vladimirovich Fisenko

1977128 pp.
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