Experimental investigation on circumferential and axial temperature gradient over fuel channel under LOCA

Author:

Yadav Ashwini Kumar,kumar Ravi,Gupta Akhilesh,Chatterjee Barun,Mukhopadhyay Deb,Lele H. G.

Publisher

Springer Science and Business Media LLC

Subject

Fluid Flow and Transfer Processes,Condensed Matter Physics

Reference15 articles.

1. Brown RA, Blahni C, Mujumdar AP (1984) Degraded cooling in a CANDU reactor. Nucl Sci Eng 88(3):425–435

2. Gillespie GE, Moyer RG, Litke D C (1987) The experimental determination of circumferential temperature distributions developed in pressure tube during slow coolant boil down. In: Proc. CNS 8th Annual Conference, Saint John, pp 241–248

3. Gulshani P (1987) Prediction of pressure tube integrity for a small LOCA and total loss of emergency coolant injection in CANDU. Trans Am Nucl Soc 55:461

4. Gupta SK, Dutta BK, Venkatraj V, Kakodkar A (1996) A study of Indian PHWR reactor channel under prolonged deteriorated flow conditions. In: IAEA TCM on advances in heavy water reactor. India, Bhabha Atomic Research Centre

5. Hanna BN (1998) CATHENA: a thermalhydraulic code for CANDU analysis. Nucl Eng Des 180:113–131

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