In WWR-M reactors, the parameter used as the operational indicator of fuel elements non-integrity is the criterion (b), defined as the ratio of the number of fission fragments leaking out in the coolant to the number of fission fragments generated in the fuel [1, 2]. For stable equilibrium conditions: V b =--- , where q V- is the leakage out rate of nuclide from the fuel element into the coolant, and q- is the rate of nuclide generation in the fuel. The notion of non-integrity may be applied to an individual assembly, the entire core, or an individual fuel element. Admissible b values for a reactor core is limited on the radiation created by fission products within the reactor premises and environment. The average non-integrity of each fue...
Fuel failures during operation of Nuclear Power Plants (NPPs) may lead to substantial economic losse...
International audienceExperiments on nuclear fuels and materials in MTRs are a mandatory step for su...
The study of fission yields has a major impact on the characterization and understanding of the fiss...
Fuel performance analysis can be used to show compliance with regulatory criteria, such as criteria ...
Fuel failures may occur during operation of nuclear power plants. One of the possible and most sever...
There is a need for a special type of nuclear reactor that can test fuel elements nondestructively t...
Analysis of release data obtained during High Burnup Fuel Test 10 (HBU-10) has been completed. In th...
Instant release fraction is used in spent fuel final disposal studies to estimate the quickly releas...
The new results on the regularities of the fission yield from matrix nuclear fuel have been obtained...
The results of in-pile irradiation tests of PWR fuel materials with particular regard to the chemica...
An assessment is made of recent test data from France, Japan, and Russia, and of earlier test data f...
In order to derive the burnup of spent nuclear fuel from the concentration of selected fission produ...
The present work continues the series of papers on the revision of the conventional technique for ev...
International audienceDuring the irradiation of nuclear fuel in a light water reactor (LWR), fission...
International audienceQualitative and quantitative analyses on the VERDON-1 sample made it possible ...
Fuel failures during operation of Nuclear Power Plants (NPPs) may lead to substantial economic losse...
International audienceExperiments on nuclear fuels and materials in MTRs are a mandatory step for su...
The study of fission yields has a major impact on the characterization and understanding of the fiss...
Fuel performance analysis can be used to show compliance with regulatory criteria, such as criteria ...
Fuel failures may occur during operation of nuclear power plants. One of the possible and most sever...
There is a need for a special type of nuclear reactor that can test fuel elements nondestructively t...
Analysis of release data obtained during High Burnup Fuel Test 10 (HBU-10) has been completed. In th...
Instant release fraction is used in spent fuel final disposal studies to estimate the quickly releas...
The new results on the regularities of the fission yield from matrix nuclear fuel have been obtained...
The results of in-pile irradiation tests of PWR fuel materials with particular regard to the chemica...
An assessment is made of recent test data from France, Japan, and Russia, and of earlier test data f...
In order to derive the burnup of spent nuclear fuel from the concentration of selected fission produ...
The present work continues the series of papers on the revision of the conventional technique for ev...
International audienceDuring the irradiation of nuclear fuel in a light water reactor (LWR), fission...
International audienceQualitative and quantitative analyses on the VERDON-1 sample made it possible ...
Fuel failures during operation of Nuclear Power Plants (NPPs) may lead to substantial economic losse...
International audienceExperiments on nuclear fuels and materials in MTRs are a mandatory step for su...
The study of fission yields has a major impact on the characterization and understanding of the fiss...