Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Effect of PT/CT contact on the circumferential temperature distribution over a fully voided nuclear channel of IPHWR

  • Sharma, Mukesh (Department of Mechanical and Industrial Engineering, Indian Institute of Technology) ;
  • Kumar, Ravi (Department of Mechanical and Industrial Engineering, Indian Institute of Technology) ;
  • Majumdar, Prasanna (Bhabha Atomic Research Centre) ;
  • Mukhopadhyay, Deb (Bhabha Atomic Research Centre)
  • Received : 2018.01.03
  • Accepted : 2019.03.24
  • Published : 2019.06.25
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Abstract

In case of multiple failure scenario, such as LOCA with ECCS failure, the decay heat continues to raise the reactor core temperature, eventually leading to the core voiding. In such scenario the convective heat transfer becomes poor and the majority of the heat transfer from fuel bundle takes place by radiation mode. During this abnormal working condition, if the channel pressure is less than 1 MPa, the PT sags and come in contact with the CT. This results in high rate of heat transfer from contact location to moderator. The present paper aims to capture the temperature profile over a simulated nuclear channel during such scenario at a steady state temperature of $600^{\circ}C$ (Centre pin) at two different configurations of PT i.e. PT concentric with CT and PT contact with CT. The results showed that the bottom nodes of all the components (Fuel bundle, PT and CT) of the simulated channel was greatly influenced by the PT/CT contact. Moreover, higher temperature were observed at top nodes of the PT and outer pins of the fuel bundle. However, no significant variation in temperatures were obtained in fuel bundle and CT in concentric condition.

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References

  1. Anjan Sarkar, S.K. Mahapatra, A. Sarkar, Opposing mixed convection and its interaction with radiation inside eccentric horizontal cylindrical annulus, Int. J. Numer. Methods Fluids 61 (3) (2009) 291-310. https://doi.org/10.1002/fld.1958
  2. Ashwini K. Yadav, P. Majumdar, Ravi Kumar, B. Chatterjee, Akhilesh Gupta, Experimental simulation of asymmetric heat up of coolant channel under small break LOCA condition for PHWR, Nucl. Eng. Des. 255 (2013) 138-145. https://doi.org/10.1016/j.nucengdes.2012.11.002
  3. Ashwini K. Yadav, Ravi Kumar, Akhilesh Gupta, Barun Chatterjee, H.G. Lele, Experimental investigation on circumferential and axial temperature gradient over fuel channel under LOCA, Heat Mass Transf. 50 (6) (2014) 737-746. https://doi.org/10.1007/s00231-013-1279-8
  4. C.B. So, G.E. Gillespie, R.G. Moyer, D.G. Litke, The experimental determination of circumferential temperature distributions developed in pressure tube during slow coolant boil down, in: Proceedings of the CNS 8th Annual Conference, Saint John, 1987, pp. 241-248.
  5. D. Mukhopadhyay, P. Majumdar, G. Behera, S.K. Gupta, V.V. Raj, Thermal analysis of severe channel damage caused by a stagnation channel break in PHWR, J. Press. Vessel Technol. 124 (2002) 161-167. https://doi.org/10.1115/1.1463036
  6. Gopal Nandan, P.K. Sahoo, Ravi Kumar, B. Chatterjee, D. Mukhopadhyay, H.G. Lele, Experimental investigation of sagging of a completely voided pressure tube of Indian PHWR under heatup condition, Nucl. Eng. Des. 240 (2010) 3504-3512. https://doi.org/10.1016/j.nucengdes.2010.05.042
  7. Gopal Nandan, P. Majumdar, P.K. Sahoo, Ravi Kumar, B. Chatterjee, D. Mukhopadhyay, H.G. Lele, Study of ballooning of a completely voided pressure tube of Indian PHWR under heat up condition, Nucl. Eng. Des. 243 (2012) 301-310. https://doi.org/10.1016/j.nucengdes.2011.11.007
  8. S.K. Gupta, B.K. Dutta, V. Venkat Raj, A. Kokodkar, A Study of the Indian PHWR Reactor Channel under Prolonged Deteriorated Flow Conditions, vol. 475, International Atomic Energy Agency, Vienna (Austria), 1997, pp. 331-359.
  9. J.W. Spore, M.M. Giles, R.W. Shumway, Best estimate radiation heat transfer model developed for TRAC-BD1, in: 20th National Heat Transfer Conference, Milwaukee, WI, USA, 2 Aug, 1981.
  10. M. Shoukri, A.M.C. Chan, On the thermal analysis of pressure tube/calandria tube contact in CANDU reactors, Nucl. Eng. Des. 104 (1987) 197-206. https://doi.org/10.1016/0029-5493(87)90299-8
  11. P.S. Yuen, K.A. Haugen, D.G. Litke, R.G. Moyer, H.E. Rosinger, The experimental measurements of circumferential temperature distributions developed on pressure tubes under stratified two-phase flow conditions: tests 1 to 5, in:Proceedings of the CNS 10th Annual Conference, AECL, Pinawa, 1989, pp. 9-18.
  12. R.S.W. Shewfelt, L.W. Layall, D.P. Godin, High temperature creep model for Zr-2.5 wt % Nb pressure tubes, J. Nucl. Mater. 125 (1984) 228-235. https://doi.org/10.1016/0022-3115(84)90548-8
  13. S.W. Churchill, H.H.S. Chu, Correlating equations for laminar and turbulent free convection from a vertical plate, Int. J. Heat Mass Transf. 18 (1975) 1323-1329. https://doi.org/10.1016/0017-9310(75)90243-4