Determining Reactor Graphite Lifespan from Thermal Properties Degradation
| Parent link: | Advanced Materials Research : Radiation and nuclear techniques in material science: Scientific Journal Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014).— 2015.— [P. 294-297] |
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| Drugi avtorji: | , , , , |
| Izvleček: | Title screen This work assesses real graphite lifespan distribution of pressurized-tube reactors (RBMK) with graphite moderator. The changes in heat exchange and heat transfer conditions were taken into consideration, which changes are induced by the thermal properties’ degradation and the changes in the form of structural elements. Besides, some features associated with the differences in the neutron flux spectrum and differences in characteristics of gamma radiation field in the fuel and in the channels of control and protection system (CPS) were all taken into account. Режим доступа: по договору с организацией-держателем ресурса |
| Izdano: |
2015
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| Serija: | Nuclear Engineering and Fuel Cycles |
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| Online dostop: | http://dx.doi.org/10.4028/www.scientific.net/AMR.1084.294 |
| Format: | Elektronski Book Chapter |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=640325 |
| Izvleček: | Title screen This work assesses real graphite lifespan distribution of pressurized-tube reactors (RBMK) with graphite moderator. The changes in heat exchange and heat transfer conditions were taken into consideration, which changes are induced by the thermal properties’ degradation and the changes in the form of structural elements. Besides, some features associated with the differences in the neutron flux spectrum and differences in characteristics of gamma radiation field in the fuel and in the channels of control and protection system (CPS) were all taken into account. Режим доступа: по договору с организацией-держателем ресурса |
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| DOI: | 10.4028/www.scientific.net/AMR.1084.294 |