期刊文献+
共找到3篇文章
< 1 >
每页显示 20 50 100
Effect of Potential Energy Stored in Reactor Facility Coolant on NPP Safety and Economic Parameters 被引量:1
1
作者 g. I. Toshinsky o. g. komlev +1 位作者 I. V. Tormyshev V. V. Petrochenko 《World Journal of Nuclear Science and Technology》 2013年第2期59-64,共6页
Potential (non-nuclear) energy stored in reactor facility coolant is a crucial factor determining the NPP safety/hazard characteristics as it is inherent property of the material and cannot be changed. Enhancing safet... Potential (non-nuclear) energy stored in reactor facility coolant is a crucial factor determining the NPP safety/hazard characteristics as it is inherent property of the material and cannot be changed. Enhancing safety of the NPP with traditional type reactor facilities, in which potential energy is stored in large quantities, requires buildup of the number of safety systems and in-depth defense barriers, which reduce the probability of severe accidents (but do not exclude the opportunity of their realization) and seriousness of their consequences. Keeping the risk of radioactivity release for different type reactor facilities at a same level of social acceptability, the number of safety systems and in-depth defense barriers, which determine essentially the NPP economical parameters, can be reduced with diminishing the potential energy stored in the reactor facility. To analyze the effect of potential energy on reactor facility safety/hazard, a diagram of reactor facility hazard has been proposed. It presents a probability of radioactivity release as a function of radioactivity release values for reactor facilities with identical radiation potential, which differ by values of potential energy stored in coolant. It is proposed to account NPP safety/hazard effect on economics by adding a certain interest on the electricity cost for making payments in a special insurance fund assigned to compensate the expenses for elimination of consequences of a possible accident. 展开更多
关键词 Potential Energy NPP SAFETY COOLANT
下载PDF
Americium Transmutation in the SVBR-100 Reactor
2
作者 A. V. gulevich V. A. Eliseev +2 位作者 o. g. komlev I. V. Tormyshev g. I. Toshinsky 《World Journal of Nuclear Science and Technology》 2020年第3期116-128,共13页
One of the postponed problems of nuclear power (NP) is the problem of the management of long-lived radioactive waste (RAW), and, first of all, with minor actinides (MA), of which americium-241 is the most difficult. T... One of the postponed problems of nuclear power (NP) is the problem of the management of long-lived radioactive waste (RAW), and, first of all, with minor actinides (MA), of which americium-241 is the most difficult. The aim of this work is to study the efficiency of americium transmutation in a fast reactor with a heavy liquid metal coolant lead-bismuth eutectic alloy. The article presents the results of calculations of the transmutation of americium in the SVBR-100 reactor using standard uranium oxide fuel with the addition of americium-241. The obtained values of the rate of transmutation of americium are compared with similar values for the SVBR-100 reactors on MOX-fuel and in the BN-800 reactor. 展开更多
关键词 SVBR-100 Fast Reactor Nuclear Power Lead-Bismuth Eutectic Minor Actinides AMERICIUM Nuclear Fuel Cycle Neutron Spectrum CORE
下载PDF
Lead-Bismuth and Lead as Coolants for Fast Reactors
3
作者 g. I. Toshinsky A. V. Dedul +2 位作者 o. g. komlev A. V. Kondaurov V. V. Petrochenko 《World Journal of Nuclear Science and Technology》 2020年第2期65-75,共11页
Fast reactors used lead-bismuth eutectic (LBE) and lead as coolants possess very high level of inherent self-protection and passive safety against severe accident. So, population radiophobia can be overcome. That type... Fast reactors used lead-bismuth eutectic (LBE) and lead as coolants possess very high level of inherent self-protection and passive safety against severe accident. So, population radiophobia can be overcome. That type of reactors can be simultaneously more safely and more cheaply. As all other coolants, LBE and lead coolant (LC) possess the certain virtues and shortcomings. The presented report includes the comparative analysis of characteristic properties of those coolants, their impact on reactor safety, reliability and operating characteristics. The conclusion is made about promising usage of FRs with these coolants in future NP after the experience in operating of the prototypes of such reactors has been obtained. 展开更多
关键词 SVBR-100 Fast Reactor LEAD-BISMUTH COOLANT LEAD COOLANT Nuclear Power Plant Inherent SELF-PROTECTION Melting Point 210Po BISMUTH Recourses
下载PDF
上一页 1 下一页 到第
使用帮助 返回顶部