A. (1981) Testing of RBMK-1500 cassettes in the reactor at the Leningrad power station. At. Énerg. 51: pp. 150V. G. Aden, I. A. Varovin, B. A. Vorontsov, et al., “Testing of RBMK-1500 cassettes in the reactor at the Leningrad power station,” At. Énerg., 51 , No. ...
6) carbon uranium reactor 铀石墨反应堆补充资料:铀石 分子式:U(SiO4)1-X(OH)XCAS号:性质:又称铀石。含二氧化铀46.37%～68.29%,二氧化硅5.20%～31.17%,水1.51%～7.86%,此外还含有铝、铁、铅、钙及镁等杂质元素。四方晶系,锆石型结构。单晶体呈短柱状、针状,集合体呈球粒状或皮壳状。黑色或褐黑色不...
The authors calculate fuel burnup fractions for the four RBMK reactors of the Leningrad plant for both unloaded and loaded fuel and graph the predicted dependence of average burnup for both scenarios on reactor operation time, the distribution function for a steady-state mode of continuous fuel re...
heat removal from graphite stack using direct water supply into reactor cavity; heat removal from fuel channels through the core graphite structures by control rods cooling system; heat removal in loss of long term cooling case using de-pressurisation of the reactor coolant system and water supply...
But you don't need to be a nuclear scientist to understand what happened at Chernobyl. You only need to know this: There are essentially two things that happen inside a nuclear reactor. The reactivity, which generates power, either goes up or it goes down. That's it. All the operators ...
Physical startup of the RBMK-reactor of the second unit of the V. I. Lenin nuclear power station, LeningradPhysical startup of the RBMK-reactor of the second unit of the V. I. Lenin nuclear power station, LeningradClocksElectronic componentsInductors...
If mentioned conditions will be fulfilled, the reactor core will be cooled by natural circulation of air and peak fuel temperature will be below 400 掳C.Algirdas KaliatkaEugenijus UspurasGeorgij KrivosheinBegel House Inc
6) carbon uranium reactor 铀石墨反应堆补充资料:铀石 分子式:U(SiO4)1-X(OH)XCAS号:性质:又称铀石。含二氧化铀46.37%～68.29%,二氧化硅5.20%～31.17%,水1.51%～7.86%,此外还含有铝、铁、铅、钙及镁等杂质元素。四方晶系,锆石型结构。单晶体呈短柱状、针状,集合体呈球粒状或皮壳状。黑色或褐黑色不...
During the whole life of reactor equipment it has to be shown that safety relevant limitations of general reactivity characteristics are not exceeded. Usually, safety margins of these characteristics are listed in a technical certificate (reactor passport). This paper presents the calculation results ...
The response of reactor cooling system and the processes in the reactor cavity and its venting system in case of a few fuel-channel ruptures due to overheating were demonstrated. The possible measures for prevention of the development of this beyond design basis accident (BDBA) to a severe ...