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Results: 1-10 |
Results: 10
Studies on the behaviour of a passive containment cooling system for the Indian Advanced Heavy Water Reactor
Authors: Maheshwari, NK Saha, D Chandraker, DK Raj, VV Kakodkar, A
Citation: Nk. Maheshwari et al., Studies on the behaviour of a passive containment cooling system for the Indian Advanced Heavy Water Reactor, KERNTECHNIK, 66(1-2), 2001, pp. 15-20
Importance of delayed neutrons on the coupled neutronic-thermohydraulic stability of a natural circulation heavy water-moderated boiling light water-cooled reactor
Authors: Nayak, AK Aritomi, M Raj, VV
Citation: Ak. Nayak et al., Importance of delayed neutrons on the coupled neutronic-thermohydraulic stability of a natural circulation heavy water-moderated boiling light water-cooled reactor, NUCL SCI EN, 138(3), 2001, pp. 315-321
Experimental studies on rewetting of hot vertical annular channel
Authors: Saxena, AK Raj, VV Rao, VG
Citation: Ak. Saxena et al., Experimental studies on rewetting of hot vertical annular channel, NUCL ENG DE, 208(3), 2001, pp. 283-303
An assessment of pressure drop and void fraction correlations with data from two-phase natural circulation loops
Authors: Vijayan, PK Patil, AP Pilkhwal, DS Saha, D Raj, VV
Citation: Pk. Vijayan et al., An assessment of pressure drop and void fraction correlations with data from two-phase natural circulation loops, HEAT MASS T, 36(6), 2000, pp. 541-548
Analytical study of nuclear-coupled density-wave instability in a natural circulation pressure tube type boiling water reactor
Authors: Nayak, AK Vijayan, PK Saha, D Raj, VV Aritomi, M
Citation: Ak. Nayak et al., Analytical study of nuclear-coupled density-wave instability in a natural circulation pressure tube type boiling water reactor, NUCL ENG DE, 195(1), 2000, pp. 27-44
Experimental studies on the pressure drop across the various components ofa PHWR fuel channel
Authors: Vijayan, PK Pilkhwal, DS Saha, D Raj, VV
Citation: Pk. Vijayan et al., Experimental studies on the pressure drop across the various components ofa PHWR fuel channel, EXP THERM F, 20(1), 1999, pp. 34-44
Probabilistic assessment of reactor pressure vessel integrity under pressurised thermal shock
Authors: Dutta, BK Kushwaha, HS Raj, VV
Citation: Bk. Dutta et al., Probabilistic assessment of reactor pressure vessel integrity under pressurised thermal shock, INT J PRES, 76(7), 1999, pp. 445-453
Deterministic assessment of reactor pressure vessel integrity under pressurised thermal shock
Authors: Mukhopadhyay, NK Kumar, TVP Chattopadhyay, J Dutta, BK Kushwaha, HS Raj, VV
Citation: Nk. Mukhopadhyay et al., Deterministic assessment of reactor pressure vessel integrity under pressurised thermal shock, INT J PRES, 75(15), 1998, pp. 1055-1064
Linear analysis of thermo-hydraulic instabilities of the advanced heavy water reactor (AHWR)
Authors: Nayak, AK Vijayan, PK Saha, D Raj, VV Aritomi, M
Citation: Ak. Nayak et al., Linear analysis of thermo-hydraulic instabilities of the advanced heavy water reactor (AHWR), J NUC SCI T, 35(11), 1998, pp. 768-778
Adequacy of power-to-volume scaling philosophy to simulate natural circulation in integral test facilities
Authors: Nayak, AK Vijayan, PK Saha, D Raj, VV Aritomi, H
Citation: Ak. Nayak et al., Adequacy of power-to-volume scaling philosophy to simulate natural circulation in integral test facilities, J NUC SCI T, 35(10), 1998, pp. 712-722
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