Works matching DE "PRESSURIZED water reactor safety measures"
Results: 6
Application of ASTEC, MELCOR, and MAAP Computer Codes for Thermal Hydraulic Analysis of a PWR Containment Equipped with the PCFV and PAR Systems.
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- Science & Technology of Nuclear Installations, 2017, p. 1, doi. 10.1155/2017/8431934
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- Article
Preliminary accident analysis of Flexblue<sup>®</sup> underwater reactor.
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- EPJ Nuclear Sciences & Technologies, 2015, v. 1, p. 1, doi. 10.1051/epjn/e2015-50030-x
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- Article
Possible in-vessel corium progression way in the Unit 1 of Fukushima Dai-ichi nuclear power plant using a phenomenological analysis.
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- EPJ Nuclear Sciences & Technologies, 2015, v. 1, p. 1, doi. 10.1051/epjn/e2015-50001-5
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- Article
Experimental Research on Passive Residual Heat Removal System of Chinese Advanced PWR.
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- Science & Technology of Nuclear Installations, 2014, p. 1, doi. 10.1155/2014/325356
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- Article
PANDA: A Multipurpose Integral Test Facility for LWR Safety Investigations.
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- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/239319
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- Article
The LOBI Integral System Test Facility Experimental Programme.
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- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/238019
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- Article