Nuclear technology hazard factors in the nuclear power station fuel cycle: Relation to the federal target program for nuclear and radiation safety in Russia

Atomic Energy ◽  
1997 ◽  
Vol 83 (2) ◽  
pp. 570-572
Author(s):  
V. M. Lebedev
Keyword(s):  
Nuclear Power ◽  
Radiation Safety ◽  
Fuel Cycle ◽  
Nuclear Technology ◽  
Power Station ◽  
Federal Target Program ◽  
Target Program ◽  
Station Fuel ◽  
Nuclear And Radiation Safety ◽  
Power Station Fuel

A new method of diagnosing hydrogen contents in specimens of nuclear power station fuel

1990 ◽  
Vol 68 (3) ◽  
pp. 214-216 ◽  
Author(s):  
A. P. Babichev ◽  
N. E. Baulevich ◽  
S. D. Lazarev ◽  
S. S. Yakimov
Keyword(s):  
Nuclear Power Station ◽  
Nuclear Power ◽  
New Method ◽  
Power Station ◽  
Station Fuel ◽  
Power Station Fuel

Automatic defect identification on PWR nuclear power station fuel pellets

2012 ◽  
Vol 245 ◽  
pp. 62-77 ◽  
Author(s):  
Adriano Fortunato de Oliveira ◽  
Antônio Carlos de Abreu Mól ◽  
Celso Marcelo Franklin Lapa ◽  
Victor Gonçalves Gloria Freitas ◽  
Cláudio Marcio do N. de A. Pereira ◽  
...  
Keyword(s):  
Nuclear Power Station ◽  
Nuclear Power ◽  
Power Station ◽  
Defect Identification ◽  
Fuel Pellets ◽  
Station Fuel ◽  
Power Station Fuel

Deformation and damage of nuclear power station fuel elements under cyclic loading

2019 ◽  
Vol 54 (5-6) ◽  
pp. 348-359
Author(s):  
Dmitry Breslavsky ◽  
Aleksandr Chuprynin ◽  
Oleg Morachkovsky ◽  
Oksana Tatarinova ◽  
Will Pro
Keyword(s):  
Cyclic Loading ◽  
Fuel Element ◽  
Nuclear Power Station ◽  
Constitutive Equations ◽  
Nuclear Power ◽  
Creep Damage ◽  
Creep Model ◽  
Power Station ◽  
Station Fuel ◽  
Power Station Fuel

Deformation and damage of nuclear power station fuel element shells under irradiation and cyclic loading due vibrations are studied. Constitutive equations include dependencies for a creep-damage equation with a scalar damage parameter, as well as terms for thermal and irradiation creep strains, elastic, thermal, and swelling strains. The acceleration of the creep-damage process due to cyclic variation of internal pressure is considered with a dynamic creep model, for which constitutive equations are derived using the method of asymptotic expansions and averaging over a period of cyclic loading. Stress and strain states in the fuel element shell are determined by use of an in-house finite element method creep-damage code for shells of revolution. Results show the essential variation in the initially symmetric fuel element shell form, as well as the acceleration of creep-damage processes due to the cyclic pressure.

Gas-thermal treatment of nuclear power-station fuel elements to separate the core from the can

1977 ◽  
Vol 42 (2) ◽  
pp. 100-103
Author(s):  
G. P. Martynovskikh ◽  
A. T. Ageenkov ◽  
M. M. Arduanov ◽  
A. F. Bogatov ◽  
E. M. Valuev ◽  
...  
Keyword(s):  
Thermal Treatment ◽  
Nuclear Power Station ◽  
Nuclear Power ◽  
Power Station ◽  
The Core ◽  
Station Fuel ◽  
Fuel Elements ◽  
Power Station Fuel

Optimizing extractant molecular structure for reprocessing spent nuclear power station fuel

1985 ◽  
Vol 58 (1) ◽  
pp. 45-51 ◽  
Author(s):  
A. M. Rozen ◽  
A. S. Nikiforov ◽  
V. S. Shmidt ◽  
Z. I. Nikolotova ◽  
N. A. Kartasheva ◽  
...  
Keyword(s):  
Molecular Structure ◽  
Nuclear Power Station ◽  
Nuclear Power ◽  
Power Station ◽  
Station Fuel ◽  
Power Station Fuel

Development Trends in Nuclear Technology and Related Safety Aspects

2002 ◽  
Author(s):  
B. Kuczera ◽  
P. E. Juhn ◽  
K. Fukuda
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Fuel Cycle ◽  
Nuclear Reactors ◽  
Nuclear Technology ◽  
User Requirements ◽  
Safety Standards ◽  
Safety Requirements ◽  
Fuel Cycles ◽  
High Level

The IAEA Safety Standards Series include, in a hierarchical manner, the categories of Safety Fundamentals, Safety Requirements and Safety Guides, which define the elements necessary to ensure the safety of nuclear installations. In the same way as nuclear technology and scientific knowledge advance continuously, also safety requirements may change with these advances. Therefore, in the framework of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) one important aspect among others refers to user requirements on the safety of innovative nuclear installations, which may come into operation within the next fifty years. In this respect, the major objectives of the INPRO subtask “User Requirements and Nuclear Energy Development Criteria in the Area of Safety” have been: a. to overview existing national and international requirements in the safety area, b. to define high level user requirements in the area of safety of innovative nuclear technologies, c. to compile and to analyze existing innovative reactor and fuel cycle technology enhancement concepts and approaches intended to achieve a high degree of safety, and d. to identify the general areas of safety R&D needs for the establishment of these technologies. During the discussions it became evident that the application of the defence in depth strategy will continue to be the overriding approach for achieving the general safety objective in nuclear power plants and fuel cycle facilities, where the emphasis will be shifted from mitigation of accident consequences more towards prevention of accidents. In this context, four high level user requirements have been formulated for the safety of innovative nuclear reactors and fuel cycles. On this basis safety strategies for innovative reactor designs are highlighted in each of the five levels of defence in depth and specific requirements are discussed for the individual components of the fuel cycle.

scholarly journals Regulatory Nuclear and Radiation Safety Requirements for NPP Power Supply Systems

2017 ◽  
pp. 46-49
Author(s):  
V. Levakin ◽  
K. Yefimova ◽  
S. Polyvoda ◽  
V. Iokst
Keyword(s):  
Power Supply ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Radiation Safety ◽  
Safety Requirements ◽  
Electrical Systems ◽  
Emergency Power ◽  
Nuclear And Radiation Safety ◽  
Supply Systems

The paper presents review of the requirements from the new regulation NP 306.2.205-2016 “Requirements for Power Supply Systems Important to Safety of Nuclear Power Plants” and recommendations of IAEA and WENRA for the construction of electrical systems important to safety of nuclear power plants. The research is focused on main differences of NP 306.2.205-2016 from standards that applied to NPP emergency power supply systems (PNAE G-9-026-90, PNAE G-9-027- 91) and which were cancelled in 2016.

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