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Research Papers

Various Design Aspects of the Canadian Supercritical Water-Cooled Reactor Core

[+] Author and Article Information
Metin Yetisir

Fluid Sealing Technology,
Canadian Nuclear Laboratories Limited,
Chalk River Laboratories,
286 Plant Road, Chalk River, ON K0J 1J0, Canada
e-mail:metin.yetisir@cnl.ca

Rui Xu

Fluid Sealing Technology,
Canadian Nuclear Laboratories Limited,
Chalk River Laboratories,
286 Plant Road, Chalk River, ON K0J 1J0, Canada
e-mail: rui.xu@cnl.ca

Michel Gaudet

Fluid Sealing Technology,
Canadian Nuclear Laboratories Limited,
Chalk River Laboratories,
286 Plant Road, Chalk River, ON K0J 1J0, Canada
e-mail: michel.gaudet@cnl.ca

Mohammad Movassat

Fluid Sealing Technology,
Canadian Nuclear Laboratories Limited,
Chalk River Laboratories,
286 Plant Road, Chalk River, ON K0J 1J0, Canada
e-mail: mo.movassat@cnl.ca

Holly Hamilton

Fuel Development Branch,
Canadian Nuclear Laboratories Limited,
Chalk River Laboratories,
286 Plant Road, Chalk River, ON K0J 1J0, Canada

Mohammedhossein Nimrouzi

Mechanical and Aerospace Engineering,
Carleton University,
1125 Colonel By Dr., Ottawa, ON K1S 5B6, Canada
e-mail: mh.nimrouzi@gmail.com

John A. Goldak

Mechanical and Aerospace Engineering,
Carleton University,
1125 Colonel By Dr., Ottawa, ON K1S 5B6, Canada
e-mail: jgoldak@mrco2.carleton.ca

Manuscript received May 25, 2015; final manuscript received July 14, 2015; published online December 9, 2015. Assoc. Editor: Thomas Schulenberg.

ASME J of Nuclear Rad Sci 2(1), 011007 (Dec 09, 2015) (8 pages) Paper No: NERS-15-1093; doi: 10.1115/1.4031247 History: Received May 25, 2015; Accepted August 05, 2015

The Canadian Supercritical Water-Cooled Reactor (SCWR) is a 1200 MW(e) channel-type nuclear reactor. The reactor core includes 336 vertical pressurized fuel channels immersed in a low-pressure heavy water moderator and calandria vessel containment. The supercritical water (SCW) coolant flows into the fuel channels through a common inlet plenum and exits through a common outlet header. One of the main features of the Canadian SCWR concept is the high-pressure (25 MPa) and high-temperature (350°C at the inlet, 625°C at the outlet) operating conditions that result in an estimated thermal efficiency of 48%. This is significantly higher than the thermal efficiency of the present light water reactors, which is about 33%. This paper presents a description of the Canadian SCWR core design concept; various numerical analyses performed to understand the temperature, flow, and stress distributions of various core components; and how the analyses results provided input for improved concept development.

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References

Figures

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Fig. 1

Canadian SCWR core concept: (a) rector core schematic and (b) 3D view

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Fig. 2

Maximum-effective (von-Mises) stress in the inlet plenum

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Fig. 3

Maximum effective plastic strain

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Fig. 4

Temperature and velocity distributions predicted by the CFD analysis: (a) temperature and (b) velocity distribution

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Fig. 5

Canadian SCWR fuel concept. The fuel channel consists of a pressure tube and a pressure tube extension. All fuel channel internals are part of the fuel assembly and removed after three refueling cycles. (a) Fuel channel schematic and (b) fuel channel with fuel assembly

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Fig. 6

Cross section of fuel channel and fuel assembly

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Fig. 7

3D model of fuel channel bottom

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Fig. 8

Modeled geometry of the crossover piece and maximum-effective (von-Mises) thermal stress

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Fig. 9

Comparison of a typical longitudinal ridge and the simulated deformed shape of fuel element cladding. (a) A photo of a typical longitudinal ridge and (b) deformed shape of fuel element in ANSYS model

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Fig. 10

Radial deflection at the maximum gap location as a function of external pressure for Canadian SCWR fuel cladding (high sheath temperature case, sheath thickness=0.2  mm, radial gap=0.1  mm)

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Fig. 11

Maximum strain variation as a function of cladding thickness for a Canadian SCWR fuel element at 25 MPa pressure

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