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

Development and investigations of compact heat-transfer equipment for a nuclear power station equipped with a high-temperature gas-cooled reactor

2013 ◽  
Vol 60 (7) ◽  
pp. 514-520 ◽  
Author(s):  
V. F. Golovko ◽  
I. V. Dmitrieva ◽  
N. G. Kodochigov ◽  
O. A. Bykh
Keyword(s):  
Heat Transfer ◽  
High Temperature ◽  
Nuclear Power Station ◽  
Nuclear Power ◽  
Power Station ◽  
High Temperature Gas

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

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

Filtration Technology Research of Graphite Dust Produced in Spent Fuel Transportation Process in HTR-PM

2018 ◽  
Author(s):  
Jinhua Wang ◽  
Bing Wang ◽  
Bin Wu ◽  
Yue Li ◽  
Haitao Wang
Keyword(s):  
High Temperature ◽  
Fuel Element ◽  
Nuclear Power ◽  
Storage System ◽  
Spent Fuel ◽  
Graphite Matrix ◽  
Fuel Storage ◽  
Fuel Elements ◽  
And Storage ◽  
High Temperature Gas

With the continuous development of the nuclear power technology in the world, all countries in the world are becoming more and more interested in the inherent safety of nuclear power technology, while the research and development of the spherical bed type high temperature gas cooled reactor nuclear power technology in China has formally catered to this demand. As a major national science and technology project, since the construction of the high temperature gas cooled reactor demonstration project (HTR-PM) since 2012, the civil construction of the nuclear island has been basically completed, the installation of equipment has been carried out orderly, and many process systems have entered debugging and operation stage gradually. As an important auxiliary process system, fuel handling and storage system for online refueling of the pebble bed high temperature gas cooled reactor, plays an important role in relation to the stable operation of the reactor. The main functions of the fuel handling and storage system are loading the fresh fuel elements and unloading the spent fuel elements which has reached its target burnup continuously for reactor operation, the spent fuel elements would be discharged into the spent fuel canister firstly, when the spent fuel storage canister is full of spent fuel, the canister would be sealed through welding method, and then the spent fuel canister would be transferred and stored in the spent fuel storage silo with the ground crane system. The fuel element of the pebble bed high temperature gas cooled reactor is spherical fuel element with graphite matrix, the fuel elements will have friction and collision with the inner wall of the pipeline in transporting process, which will produce graphite dust, the graphite dust should be removed continuously though filtration method, so as not to affect the fuel elements transportation in pipeline. This article focus on the production mechanism and filtering method of the graphite dust in graphite matrix fuel element transporting process in pipeline, to study the graphite dust removal technology, and then we could provide theoretical guidance for the design and operation of the key system and equipment for HTR-PM.

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

Formation of the Microflora of the Tashlyk Cooling Pond of the Southern Ukrainian Nuclear Power Station

2002 ◽  
Vol 38 (6) ◽  
pp. 8
Author(s):  
N. G. Tkachuk ◽  
A. I. Merezhko ◽  
B. A. Shimanskiy
Keyword(s):  
Nuclear Power Station ◽  
Nuclear Power ◽  
Cooling Pond ◽  
Power Station
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