Supercritical-Pressure Water Nuclear Reactors

Baranaev, Yu.D.; Kirillov, P. L.; Poplavskii, V. M.; Шарапов, В. Н.

doi:10.1023/b:aten.0000038101.90666.da

Cited by 16 publications

(2 citation statements)

References 2 publications

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“…WWER reactors use water pressurized up to 16 MPa with a temperature of up to 324 °C as the coolant. Increasing the coolant pressure to 25 MPa and the reactor outlet coolant temperature to 550 °C increases the thermal efficiency of the units (up to 45%) and reduces the environmental impact by reducing heat losses in the thermodynamic cycle from 67% (WWER-1000) to 55% (WWER SWC) [ 1 , 2 , 3 , 4 , 5 ]. Another advantage of SWCR is the possibility of different active core designs: with a thermal neutron spectrum for operation in an open fuel cycle with UO 2 fuel and with a fast neutron spectrum for operation in a closed fuel cycle with MOX fuel [ 6 ].…”

Section: Introductionmentioning

confidence: 99%

Investigation of Stress Corrosion Cracking Resistance of Irradiated 12Cr Ferritic-Martensitic Stainless Steel in Supercritical Water Environment

et al. 2023

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The supercritical water-cooled reactors (SWCR) belong to Generation IV of reactors. These reactors have a number of advantages over currently operating WWERs and PWRs. These advantages include higher thermal efficiency, a more simplified unit design, and the possibility of incorporating it into a closed fuel cycle. It is therefore necessary to identify candidate materials for the SWCR and validate the safety and effectiveness of their use. 12Cr ferritic–martensitic (F/M) stainless steel is considered a candidate material for SWCR internals. Radiation embrittlement and corrosion cracking in the primary circuit coolant environment are the main mechanisms of F/M steels degradation during SWCR operation. Here, the stress corrosion cracking (SCC) in supercritical water at 390 and 550 °C of 12Cr F/M steel irradiated by neutrons to 12 dpa is investigated. Autoclave tests of specially designed disk specimens in supercritical water were performed. The tests were carried out under different constant load (CL), temperature 450 °C, and pressure in autoclave 25 MPa. The threshold stress, below which the SCC initiation of irradiated 12Cr F/M steel does not occur, was determined.

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Section: Introductionmentioning

confidence: 99%

Investigation of Stress Corrosion Cracking Resistance of Irradiated 12Cr Ferritic-Martensitic Stainless Steel in Supercritical Water Environment

et al. 2023

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“…Therefore, a study on the heat transfer of supercritical fluid flows is of great significance for the design and improvement of the design of those systems operating at the supercritical pressures. The recent developments in supercritical fluid technologies, e.g., the supercritical watercooled reactor (SCWR) [1], the supercritical water oxidation (SCWO) for organic waste disposal [2], and the supercritical water gasification (SCWG) of biomass for hydrogen production [3], also necessitate the study.…”

Section: Introductionmentioning

confidence: 99%

A Novel Model of Turbulent Convective Heat Transfer in Round Tubes at Supercritical Pressures

Mao¹,

Bai²,

Guo³

2011

Heat Transfer Engineering

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In the present study, a novel model was established to investigate the enhanced heat transfer to turbulent pipe flow of supercritical pressure fluids. The governing equations for the steady turbulent compressible pipe flow were simplified into the one-dimensional nondimensionalized forms based on the boundary layer theory. A conventional mixing length turbulence model for constant-property pipe flows was modified by introducing the effect of density fluctuations into the equations of turbulent transport, and the modified turbulence model was applicable to both constant-property and variable-property pipe flows. With the suggested model, which was a combination of the nondimensional governing equations and the modified turbulence model, the numerical calculations were carried out for the turbulent convective heat transfer of water in round tubes at supercritical pressures. The results showed that the present model can provide a relatively precise prediction about the effect of pressure, mass flux, and wall heat flux on heat transfer for supercritical fluid flows and greatly reduce the calculation workload. The modified turbulence model showed a much better agreement with the experimental results than the original turbulence model.

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Determination of the region of vibroacoustic resonances of coolant and fuel assemblies in advanced enhanced-power reactors

Proskuryakov

Novikov

2010

At Energy

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Computational methods and algorithms for determining the region of vibroacoustic resonances of fuel elements and fuel assemblies for existing and planned VVER, VVER-SKD have been developed. The results obtained are used to analyze the region of vibroacoustic resonances of the coolant and fuel assemblies in the new-generation reactors VVER-1200VVER- , -1700 In order to increase the fraction of electricity production by nuclear power plants in the next few decades, the plants will have to be operated in a partial power regime and in diverse transient regimes. Operation at constant (nominal) power will create additional low-cycle thermal loads on the equipment, which will increase the high-cycle loads which are due to more intense vibration of the equipment in nonstationary regimes. High-cycle dynamic loads can grow in some regimes with partial power [1,2]. Together with operating nuclear power plants in a partial power mode there arises the problem of increasing the service life from 30 to 50 and even 60 years. This requires upgrading of equipment and regimes at the design stage. Some of the main problems in the solution of this problem are determining and preventing conditions which result in resonance interaction of the acoustic oscillations of the coolant and vibrations of the equipment [1]. These problems arise in the development of new modifications of fuel elements and fuel assemblies. The experience gained in VVER operation shows that vibrations could be responsible for damage to fuel assemblies.The present article examines the problem of determining the conditions resulting in resonance interaction of acoustic vibrations of the coolant and equipment vibrations. The calculations permit determining the region of the resonance interaction of the natural frequency of the pressure oscillations of the coolant with the oscillations of the fuel elements, fuel assemblies, and shaft of the reactor. The methods and algorithms developed are used for quantitative evaluation of the natural frequency of the coolant pressure oscillations, figure of merit (Q) and transmission band of the existing and planned VVER and VVER-SKD.The dependence of the transmission band of the acoustic oscillations on the reactor regime is investigated to solve this problem. To this end, an acoustic model of the coolant in the core taking account of and neglecting the gas phase, formed during radiolysis, is used (Fig. 1) [3].Evaluations of Q and the transmission band of the acoustic oscillations in the coolant flows in a nuclear reactor have not been made before. The present article presents the results of calculations of Q and the transmission band for different VVER-1000 modifications.On the basis of the fact that the equations describing vibrational processes in hydraulic, acoustic, and electric systems are of the same form [4-7], a system of analogies holds (acoustic parameters of hydraulic elements -electric parameters): pressure drop ΔP, Pa -voltage, V; volume flow rate W v , m 3 /sec -current, A; acoustic compliance c, m 4 ·sec 2 /kg -cap...

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Supercritical-Pressure Water Nuclear Reactors

Cited by 16 publications

References 2 publications

Investigation of Stress Corrosion Cracking Resistance of Irradiated 12Cr Ferritic-Martensitic Stainless Steel in Supercritical Water Environment

Investigation of Stress Corrosion Cracking Resistance of Irradiated 12Cr Ferritic-Martensitic Stainless Steel in Supercritical Water Environment

A Novel Model of Turbulent Convective Heat Transfer in Round Tubes at Supercritical Pressures

Determination of the region of vibroacoustic resonances of coolant and fuel assemblies in advanced enhanced-power reactors

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