CANDU technology for Generation III+ and IV reactors

Torgerson, D.F.; Shalaby, B.A.; Pang, Simon H.

doi:10.1016/j.nucengdes.2006.04.020

Cited by 71 publications

(33 citation statements)

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“…The successful deployment and long term operation of these SCWR depends on the durability of the materials in the presence of water under conditions of extreme temperature, pressure, and radiation [15,[18][19][20]. Mo-bearing alloys are among the candidate materials considered in the construction of SCWR.…”

Section: Relevance Of Moo 2 Solubility To Supercritical-watercooled Rmentioning

confidence: 99%

“…For example, the Generation-IV SCWR, which is designed to function at temperatures up to 625 ∘ C and pressures ranging from 25 to 30 MPa [15], is one of the six reactor design concepts developed to meet the need for an energy efficient advanced reactor [17]. An important challenge in the design and successful deployment of a SCWR is controlling water chemistry under conditions of high temperature and pressure [15,[18][19][20][21]. Hence, knowledge of the solubility of metal oxides produced at the steel-supercritical water interface is important for predicting corrosion and corrosion product transport within the reactor.…”

Section: Introductionmentioning

confidence: 99%

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The Solubility of Tugarinovite (MoO₂) in H₂O at Elevated Temperatures and Pressures

et al. 2017

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The solubility of tugarinovite (MoO 2 ) in pure water was investigated at temperatures between 400 and 800 ∘ C and at pressures ranging between 95 and 480 MPa by using in situ synchrotron X-ray fluorescence (SXRF) to separately analyze high temperature aqueous solutions in a hydrothermal diamond anvil cell (HDAC). The concentration of molybdenum in the fluid at 400 and 500 ∘ C was below detection; however, at temperatures between 600 and 800 ∘ C, the solubility of tugarinovite increased with increasing temperature by two orders of magnitude. The molybdenum concentration at 600 ∘ C and 800 ∘ C is 44 ppm and 658 ppm, respectively. The results complement the data of Kudrin (1985) and provide the first measurement of MoO 2 solubility at pressure and temperature conditions comparable to intrusion-related Mo deposit formation. The data are also relevant to the study of water chemistry and corrosion product transport in supercritical-water-cooled reactors, where Mo-bearing steel alloys interact with aqueous solutions at temperatures greater than 600 ∘ C. The application of in situ SXRF to solubility measurements of sparingly soluble minerals is recommended because it circumvents analytical uncertainties inherent in determinations obtained by quenching and weight loss measurements.

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Section: Relevance Of Moo 2 Solubility To Supercritical-watercooled Rmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

The Solubility of Tugarinovite (MoO₂) in H₂O at Elevated Temperatures and Pressures

et al. 2017

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“…The insulated pressure tube is a key technology that is needed to make use of supercritical water in channel-type reactors. 21) In this design, the pressure tube is internally insulated from the high-temperature coolant by using an internal layer of low-neutron absorbing material and externally indirect contact with the cool moderator. The usual calandria tube is eliminated and this allows the pressure tube to operate at much lower temperatures, which are close to the moderator temperature.…”

Section: Configuration Of Scwrmentioning

confidence: 99%

“…Moreover, most simulations have been conducted for the triangular and square subchannels, which may not be representative of the entire fuel rod channel, for example, the horizontally arranged CANDU 37-element fuel bundle, which has three different kinds of subchannels, triangular, square, and wall subchannels. 5,10) Several researchers [11][12][13][14] have studied the whole fuel bundles for SCWR using the subchannel approach, for example, the subchannel thermal-hydraulic analysis codes such as STAFAS, SUBCHAN, and ATHAS. The maximum cladding surface temperature (MaxCST) is an important value to ensure that nuclear reactors operate safely; yet, the current subchannel approach for SCWR simulations is unable to provide the three-dimensional cladding surface temperature (CST) distributions.…”

Section: Introductionmentioning

confidence: 99%

Numerical Simulation of Fluid Flow and Heat Transfer of Supercritical Fluids in Fuel Bundles

Zhang

Jiang

2011

Journal of Nuclear Science and Technology

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A supercritical water-cooled reactor (SCWR) was proposed as a kind of generation IV reactor in order to improve the efficiency of nuclear reactors. Although investigations on the thermal-hydraulic behavior in SCWR have attracted much attention, there is still a lack of CFD study on the heat transfer of supercritical water in fuel channels. In order to understand the thermal-hydraulic behavior of supercritical fluids in nuclear reactors, the local fluid flow and heat transfer of supercritical water in a 37-element fuel bundle has been studied numerically in this work. Results show that secondary flow appears and the cladding surface temperature (CST) is very nonuniform in the fuel bundle. The maximum cladding surface temperature (MaxCST), which is an important design parameter for SCWR, can be predicted and analyzed using the CFD method. Due to a very large circumferential temperature gradient in cladding surfaces of the fuel bundle, the precise cladding temperature distributions using the CFD method is highly recommended.

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“…In nuclear industry, Atomic Energy of Canada Limited (AECL) has the long-term plan to develop the supercritical water reactor (SCWR) CANDU that is for generation IV nuclear reactor. This kind of nuclear reactor will have the higher thermal efficiency compared with the light water reactor of generation III and generation III+ in [3]. Recently, the more advanced concept of the supercritical water fast reactor has already been put forward in [4][5].…”

Section: Introductionmentioning

confidence: 99%

Numerical investigation of diameter effect on heat transfer of supercritical water flows in horizontal round tubes

Shang

Chen

2011

Applied Thermal Engineering

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The diameter effect on the heat transfer of supercritical water (SCW) flows in horizontal round tubes has been studied using computational fluid dynamics (CFD) technique. The numerical simulations are carried out by the STAR-CD solver combined with the user developed subroutines that control the numerical calculation procedures.Through the tests it is found that the discretization scheme using CD, LUD or MARS will not affect the accuracy of the numerical simulations. Through the diameter effect studies, it is found that the heat transfer of supercritical water flows in the horizontal round tube is strongly affected by the buoyancy especially for the large diameter tube.The large diameter (D=10mm) tube will have the high risk to have the strong heat transfer deterioration that can introduce 180 o C wall temperature difference between the top and bottom surfaces due to the buoyancy effects.The magnitudes of the effects can be quantificationally expressed by a ratio of Grashof number over Reynolds number square. Under the high mass flux regime, the heat transfer deterioration will disappear for all the diameters from 5mm to 10mm. The different secondary flow patterns at different tube diameters are also studied.

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CANDU technology for Generation III+ and IV reactors

Cited by 71 publications

References 1 publication

The Solubility of Tugarinovite (MoO₂) in H₂O at Elevated Temperatures and Pressures

The Solubility of Tugarinovite (MoO₂) in H₂O at Elevated Temperatures and Pressures

Numerical Simulation of Fluid Flow and Heat Transfer of Supercritical Fluids in Fuel Bundles

Numerical investigation of diameter effect on heat transfer of supercritical water flows in horizontal round tubes

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CANDU technology for Generation III+ and IV reactors

Cited by 71 publications

References 1 publication

The Solubility of Tugarinovite (MoO2) in H2O at Elevated Temperatures and Pressures

The Solubility of Tugarinovite (MoO2) in H2O at Elevated Temperatures and Pressures

Numerical Simulation of Fluid Flow and Heat Transfer of Supercritical Fluids in Fuel Bundles

Numerical investigation of diameter effect on heat transfer of supercritical water flows in horizontal round tubes

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Product

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The Solubility of Tugarinovite (MoO₂) in H₂O at Elevated Temperatures and Pressures

The Solubility of Tugarinovite (MoO₂) in H₂O at Elevated Temperatures and Pressures