Start-up and operation of channel-type uranium-graphite reactor with tubular fuel elements and nuclear steam superheating

Aleshchenkov, P. I.; Zvereva, G. A.; Kireev, G. A.; Knyazeva, G. D.; Kononov, V. I.; Lunina, L.I.; Mityaev, Yu. I.; Nevskii, V. P.; Polyakov, V.K.

doi:10.1007/bf01139493

Cited by 4 publications

(3 citation statements)

References 4 publications

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“…The start-up testing of the Unit 1 and Unit 2 reactors of the BNPP are described in this section. During the Unit 1 start-up, both loops were filled with deaerated water, water circulation was established, air was removed, and the pressure was raised up to 10 MPa and 3 MPa in the primary and secondary loops, respectively (Aleshchenkov et al 1971). Equipment was heated up at 10 -14% of reactor power.…”

Section: Start-up Of Beloyarsk Npp Reactorsmentioning

confidence: 99%

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World experience in nuclear steam reheat

Saltanov

Pioro

2016

Handbook of Generation IV Nuclear Reactors

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Section: Start-up Of Beloyarsk Npp Reactorsmentioning

confidence: 99%

“…The automatic level control system was put into operation as soon as the water in the separators reached the rated level. The subsequent reactor power increase, turbine preparation, and connection of the turbine to the power line were the same as for Unit 1 (Aleshchenkov et al 1971).…”

Section: Start-up Of Beloyarsk Npp Reactorsmentioning

confidence: 99%

World experience in nuclear steam reheat

Saltanov

Pioro

2016

Handbook of Generation IV Nuclear Reactors

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“…A design for such channels (so-called, re-entrant flow channel design (see Fig. 5)) was proven in Russia at the Beloyarsk NPP (Dollezhal' et al 1980(Dollezhal' et al , 1974(Dollezhal' et al , 1971(Dollezhal' et al , 1958Grigor'yants et al 1979;Aleshchenkov et al 1971).…”

Section: Canadian Scwr Conceptmentioning

confidence: 99%

Icone15-10276 Advanced Concepts for Pressure-Channel Reactors : Modularity, Performance and Safety

Duffey

Pioro²,

Kuran³

2007

ICONE

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Based on an analysis of the development of advanced concepts for pressure-tube reactor technology, we adapt and adopt the pressure-tube reactor advantage of modularity, so that the subdivided core has the potential for optimization of the core, safety, fuel cycle and thermal performance independently, while retaining passive safety features. In addition, by adopting supercritical water-cooling, the logical developments from existing supercritical turbine technology and "steam" systems can be utilized.Supercritical and ultra-supercritical boilers and turbines have been operating for some time in coal-fired power plants. Using coolant outlet temperatures of about 625ºC achieves operating plant thermal efficiencies in the order of 45 -48%, using a direct turbine cycle. In addition, by using reheat channels, the plant has the potential to produce low cost process heat, in amounts that are customer and market dependent. The use of reheat systems further increases the overall thermal efficiency to 55% and beyond. With the flexibility of a range of plant sizes suitable for both small (400 MW e ) and large (1400 MW e ) electric grids, and the ability for co-generation of electric power, process heat, and hydrogen, the concept is competitive. The choice of core power, reheat channel number and exit temperature are all set by customer and materials requirements.The pressure channel is a key technology that is needed to make use of supercritical water (SCW) in CANDU ®1 reactors feasible. By optimizing the fuel bundle and fuel channel, convection and conduction assure heat removal using passive-moderator cooling. Potential for severe core damage can be almost eliminated, even without the necessity

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SCW Pressure-Channel Nuclear Reactors: Some Design Features and Concepts

Duffey

Pioro

Gabaraev

et al. 2006

Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nu

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Concepts of nuclear reactors cooled with water at supercritical pressures were studied as early as the 1950s and 1960s in the USA and Russia. After a 30-year break, the idea of developing nuclear reactors cooled with supercritical water (SCW) became attractive again as the ultimate development path for water-cooling. The main objectives of using SCW in nuclear reactors are 1) to increase the thermal efficiency of modern nuclear power plants (NPPs) from 33–35% to about 40–45%, and 2) to decrease capital and operational costs and hence decrease electrical energy costs (∼$1000 US/kW). SCW NPPs will have much higher operating parameters compared to modern NPPs (pressure about 25 MPa and outlet temperature up to 625 °C), and a simplified flow circuit, in which steam generators, steam dryers, steam separators, etc., can be eliminated. Also, higher SCW temperatures allow direct thermo-chemical production of hydrogen at low cost, due to increased reaction rates. Pressure-channel SCW nuclear reactor concepts are being developed in Canada and Russia. Design features related to both channels and fuel bundles are discussed in this paper. Also, Russian experience with operating supercritical steam heaters at NPP is presented. The main conclusion is that development of SCW pressure-channel nuclear reactors is feasible and significant benefits can be expected over other thermal energy systems.

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Start-up and operation of channel-type uranium-graphite reactor with tubular fuel elements and nuclear steam superheating

Cited by 4 publications

References 4 publications

World experience in nuclear steam reheat

World experience in nuclear steam reheat

Icone15-10276 Advanced Concepts for Pressure-Channel Reactors : Modularity, Performance and Safety

SCW Pressure-Channel Nuclear Reactors: Some Design Features and Concepts

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