scholarly journals Fission product control and fuel element release at the Peach Bottom HTGR Nuclear Power Station. Results of postconstruction research and development procedures DM-1, GM-1, GM-2, JM-1, and JM-8

1972 ◽  
Author(s):  
D.R. Lofing ◽  
E.E. Anderson ◽  
W.E. Bell
Keyword(s):  
Research And Development ◽  
Fuel Element ◽  
Fission Product ◽  
Nuclear Power Station ◽  
Nuclear Power ◽  
Power Station ◽  
Product Control

Experimental double-fuel-element channel for the reactor of the world's first nuclear power station

1975 ◽  
Vol 39 (4) ◽  
pp. 867-869
Author(s):  
M. G. Bul'kanov ◽  
V. A. Kurov ◽  
V. D. Lazarevskaya ◽  
V. G. Potolovskii ◽  
V. S. Sever'yanov
Keyword(s):  
Fuel Element ◽  
Nuclear Power Station ◽  
Nuclear Power ◽  
Power Station

Operating experience with the VV�R-1000 reactor fuel-element assemblies of the fifth unit of the Novovoronezh nuclear power station

1983 ◽  
Vol 54 (3) ◽  
pp. 165-169
Author(s):  
Yu. V. Vikhorev ◽  
V. A. Voznesenskii ◽  
V. V. Goncharov ◽  
K. P. Dubrovin ◽  
V. N. Proselkov ◽  
...  
Keyword(s):  
Fuel Element ◽  
Nuclear Power Station ◽  
Nuclear Power ◽  
Operating Experience ◽  
Reactor Fuel ◽  
Power Station ◽  
Reactor Fuel Element

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.

Research and development activities for cleanup of the Fukushima Daiichi Nuclear Power Station

2013 ◽  
Vol 1518 ◽  
pp. 257-268
Author(s):  
Toshiki Sasaki ◽  
Shuji Kaminishi ◽  
Yasuaki Miyamoto ◽  
Hideyuki Funasaka
Keyword(s):  
Radioactive Waste ◽  
Research And Development ◽  
Nuclear Power Station ◽  
Nuclear Power ◽  
Hydrogen Generation ◽  
Power Station ◽  
Power Stations ◽  
Fukushima Daiichi ◽  
Different Characteristics ◽  
And Diffusion

ABSTRACTThe Fukushima Daiichi nuclear power station accident and restoration works have produced significant volume of radioactive waste. The waste has very different characteristics from usual radioactive waste produced in nuclear power stations and it requires extensive research and development for management of the waste. R&D works such as analysis of the waste properties, hydrogen generation by radiolysis and diffusion in a storage vessel and corrosion of storage vessels, etc. have been performed for characterization and safe storage of the waste. The detailed R&D plan for processing and disposal waste will be established by the end of FY2012.

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