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

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.

Post-pile studies of fuel elements in service for 626 effective days in the core of the VV�R-1 reactor of the Novo-Voronezh nuclear power station

1971 ◽  
Vol 30 (2) ◽  
pp. 267-271
Author(s):  
V. S. Belokopytov ◽  
S. N. Votinov ◽  
Z. I. Pakhomov ◽  
M. D. Deribizov ◽  
V. Ya. Gabeskiriya ◽  
...  
Keyword(s):  
Nuclear Power Station ◽  
Nuclear Power ◽  
Power Station ◽  
The Core ◽  
Fuel Elements

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

Mechanical Engineering Aspects of Concrete Reactor Pressure Vessels for Oldbury Nuclear Power Station

1965 ◽  
Vol 180 (1) ◽  
pp. 927-948
Author(s):  
R. W. Lakin
Keyword(s):  
Nuclear Power Station ◽  
Nuclear Power ◽  
Mechanical Engineering ◽  
Nuclear Reactor ◽  
Pressure Vessels ◽  
Integral Type ◽  
Power Station ◽  
The Core ◽  
Reactor Pressure

The use of prestrcssed concrete vessels to contain a nuclear reactor is not in itself novel, as the French in their G2 and G5 vessels at Marcoule had pioneered this form of construction, but the Oldbury vessels contained the first reactors of the integral type in which the core, boilers and gas circuit are contained within the same vessel. This type of reactor had been under consideration for some time by the author's company, and during the early part of 1960 a study had been completed which showed that this design was both feasible and economically attractive. The design formed the basis for the Oldbury Power Station, construction of which started in 1962.

scholarly journals THE HGCR-1, A DESIGN STUDY OF A NUCLEAR POWER STATION EMPLOYING A HIGH- TEMPERATURE GAS-COOLED REACTOR WITH GRAPHITE-UO$sub 2$ FUEL ELEMENTS

1959 ◽  
Author(s):  
W.B. Cottrell ◽  
C.M. Copenhaver ◽  
H.N. Culver ◽  
M.H. Fontana ◽  
V.J. Kelleghan ◽  
...  
Keyword(s):  
High Temperature ◽  
Nuclear Power Station ◽  
Nuclear Power ◽  
Power Station ◽  
Design Study ◽  
Fuel Elements ◽  
High Temperature Gas

Steam-superheating fuel elements of the reactors in the I. V. Kurchatov Beloyarsk nuclear power station

1976 ◽  
Vol 40 (5) ◽  
pp. 451-457 ◽  
Author(s):  
A. G. Samoilov ◽  
A. V. Pozdnyakova ◽  
V. S. Volkov
Keyword(s):  
Nuclear Power Station ◽  
Nuclear Power ◽  
Power Station ◽  
Beloyarsk Nuclear Power Station ◽  
Fuel Elements ◽  
Steam Superheating
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