AN INTEGRAL EFFECT TEST ON THE REFLOOD PERIOD OF A LARGE-BREAK LOCA FOR THE APR1400 USING ATLAS.
- Published in:
- Nuclear Technology, 2010, v. 170, n. 1, p. 100, doi. 10.13182/NT10-A9449
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- Publication type:
- Article
Works matching DE "COOLANT loss in pressurized water reactors"
Results: 8
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2
LARGE BREAK LOSS-OF-COOLANT ACCIDENT ANALYSIS OF VVER-1000 REACTOR USING CATHARE CODE.
- Published in:
- Nuclear Technology, 2010, v. 170, n. 1, p. 123, doi. 10.13182/NT10-A9451
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- Publication type:
- Article
3
DEVELOPMENT OF PARAMETER-IDENTIFICATION CAPABILITY FOR MAAP4 CODE.
- Published in:
- Nuclear Technology, 2008, v. 161, n. 3, p. 203, doi. 10.13182/NT08-A3923
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- Publication type:
- Article
4
Thermodynamic consequences of hydrogen combustion within a containment of pressurized water reactor.
- Published in:
- Archives of Thermodynamics, 2011, v. 32, n. 4, p. 67, doi. 10.2478/v10173-011-0032-2
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- Publication type:
- Article
5
Validation of Analytical Capabilities of RELAP5/MOD3.3 on Boron Dilution during SBLOCA and Loss of Residual Heat Removal System.
- Published in:
- Heat Transfer Engineering, 2008, v. 29, n. 8, p. 721, doi. 10.1080/01457630801981713
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- Publication type:
- Article
6
Investigation of heat transfer and hydraulic resistance during the flow of water with supercritical parameters in application to reactor facilities.
- Published in:
- Atomic Energy, 2010, v. 108, n. 6, p. 415, doi. 10.1007/s10512-010-9310-3
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- Publication type:
- Article
7
30th anniversary of VVER-1000 startup.
- Published in:
- Atomic Energy, 2010, v. 108, n. 5, p. 325, doi. 10.1007/s10512-010-9297-9
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- Publication type:
- Article
8
Experimental study of a passive system for lowering damaging pressure levels in the protective shell of the KLT-40S reactor facility.
- Published in:
- Atomic Energy, 2010, v. 108, n. 5, p. 343, doi. 10.1007/s10512-010-9299-7
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- Publication type:
- Article