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Anantharaman K., Kamath H.S., Majumdar S., Ramanujam A., and Venkatramani M. Thorium Based Fuel Reprocessing & Refabrication Technologies and Strategies, INSAC-2000. Mumbai, 1-2 June (2000)
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Anantharaman, K.1
Kamath, H.S.2
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Ramanujam, A.4
Venkatramani, M.5
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4
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33646491958
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Design of passive systems of Indian AHWR and CHTR
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IAEA, Vienna, June 13-17
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Bhat N.R., Dulera I.V., Andhansare M.G., Saha D., and Sinha R.K. Design of passive systems of Indian AHWR and CHTR. Paper Presented in IAEA Technical Meeting I3-TM-26926 on 'Review of Passive Safety Design Options for Small and Medium Sized Reactors'. IAEA, Vienna, June 13-17 (2005)
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Paper Presented in IAEA Technical Meeting I3-TM-26926 on 'Review of Passive Safety Design Options for Small and Medium Sized Reactors'
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Bhat, N.R.1
Dulera, I.V.2
Andhansare, M.G.3
Saha, D.4
Sinha, R.K.5
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5
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33646472834
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A computer code for the thermal hydraulic analysis of a natural circulation reactor
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Department of Mechanical Engineering, Jadhavpur University, Calcutta, India
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Chandraker D.K., Maheshwari N.K., Saha D., and Sinha R.K. A computer code for the thermal hydraulic analysis of a natural circulation reactor. 16th National Heat and Mass Transfer Conference and 5th ISHMT-ASME Heat and Mass Transfer Conference. Department of Mechanical Engineering, Jadhavpur University, Calcutta, India (January 2002)
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(2002)
16th National Heat and Mass Transfer Conference and 5th ISHMT-ASME Heat and Mass Transfer Conference
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Chandraker, D.K.1
Maheshwari, N.K.2
Saha, D.3
Sinha, R.K.4
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6
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33646488583
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Gupta, S.K., Lele, H.G., 2002. Safety analyses of AHWR: approaches, methodology and applications. In: Paper Presented in the First National Conference on Nuclear Reactor Technology, Mumbai, India, 25-27 November.
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7
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33646476216
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International Atomic Energy Agency, 2002. IAEA CRP on Final Stage of the WIMS-D Library Update Project (WLUP), http://www.iaea-nds.org.
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8
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33646472672
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Kumar, A., Srivenkatesan, R., 1984. Nodal Expansion Method for Reactor Core Calculation. BARC Report. BARC-1249.
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9
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74549163599
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Physics design of advanced heavy water reactor utilising thorium
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IAEA, Vienna
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Kumar A., Kannan U., Padala Y., Behera G.M., and Srivenkatesan R. Physics design of advanced heavy water reactor utilising thorium. Paper Presented in the Technical Committee Meeting on Utilization of Thorium Fuel Options. IAEA, Vienna (November 1999)
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Paper Presented in the Technical Committee Meeting on Utilization of Thorium Fuel Options
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Kumar, A.1
Kannan, U.2
Padala, Y.3
Behera, G.M.4
Srivenkatesan, R.5
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10
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33646466712
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Effect of various geometric parameters on the design safety considerations of a natural circulation boiling water reactor: thermal margin vs stability margin
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BARC, Mumbai, India, 25-27 November
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Kumar N., Chandraker D.K., Nayak A.K., Vijayan P.K., Saha D., and Sinha R.K. Effect of various geometric parameters on the design safety considerations of a natural circulation boiling water reactor: thermal margin vs stability margin. First National Conference on Nuclear Reactor Technology. BARC, Mumbai, India, 25-27 November (2002)
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(2002)
First National Conference on Nuclear Reactor Technology
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Kumar, N.1
Chandraker, D.K.2
Nayak, A.K.3
Vijayan, P.K.4
Saha, D.5
Sinha, R.K.6
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12
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0035249076
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Studies on the behaviour of a passive containment cooling system for the Indian heavy water reactors
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Maheshwari N.K., Saha D., Chandraker D.K., Venkat Raj V., and Kakodkar A. Studies on the behaviour of a passive containment cooling system for the Indian heavy water reactors. Kerntechnik 66 (2001) 15-22
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Kerntechnik
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Maheshwari, N.K.1
Saha, D.2
Chandraker, D.K.3
Venkat Raj, V.4
Kakodkar, A.5
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13
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33646477351
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IAEA TEC-DOC 1451, Vienna, 7-11 June
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Maheshwari N.K., Vijayan P.K., Saha D., and Sinha R.K. Passive Safety Features of Indian Innovative Nuclear Reactors, Innovative Small and Medium Sized Reactors: Design Features, Safety Approach and R&D Trends. IAEA TEC-DOC 1451, Vienna, 7-11 June (2004)
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Passive Safety Features of Indian Innovative Nuclear Reactors, Innovative Small and Medium Sized Reactors: Design Features, Safety Approach and R&D Trends
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Maheshwari, N.K.1
Vijayan, P.K.2
Saha, D.3
Sinha, R.K.4
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14
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0036567562
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Analytical study of flow instability behaviour in a boiling two phase natural circulation loop under low quality conditions
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Nayak A.K., Kumar N., Vijayan P.K., Saha D., and Sinha R.K. Analytical study of flow instability behaviour in a boiling two phase natural circulation loop under low quality conditions. Kerntechnik 67 (2002) 95-101
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(2002)
Kerntechnik
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Nayak, A.K.1
Kumar, N.2
Vijayan, P.K.3
Saha, D.4
Sinha, R.K.5
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15
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33646479261
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Rao, G.S.S.P., Vijayan, P.K., Jain, V., Borgohain, A., Sharma, M., Nayak, A.K., Belokar, D.G., Pal, A.K., Saha, D., Sinha, R.K., 2002. AHWR integral test loop scaling philosophy and system description, BARC Report, BARC/2002/E/017.
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16
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0038115389
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Design and development of AHWR-the Indian thorium fuelled innovative nuclear reactor, INSAC-2000
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Mumbai, 1-2 June
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Sinha R.K., Kushwaha H.S., Agarwal R.G., Saha D., Dhawan M.L., Vyas H.P., and Rupani B.B. Design and development of AHWR-the Indian thorium fuelled innovative nuclear reactor, INSAC-2000. Annual Conference of Indian Nuclear Society. Mumbai, 1-2 June (2000)
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(2000)
Annual Conference of Indian Nuclear Society
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Sinha, R.K.1
Kushwaha, H.S.2
Agarwal, R.G.3
Saha, D.4
Dhawan, M.L.5
Vyas, H.P.6
Rupani, B.B.7
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18
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0006120012
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Physics considerations for utilization of thorium in power reactors and subcritical cores, INSAC-2000
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Mumbai, 1-2 June
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Srivenkatesan R., Kumar A., Kannan U., Raina V.K., Arora M.K., Ganesan S., and Degwekar S.B. Physics considerations for utilization of thorium in power reactors and subcritical cores, INSAC-2000. Annual Conference of Indian Nuclear Society. Mumbai, 1-2 June (2000)
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(2000)
Annual Conference of Indian Nuclear Society
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Srivenkatesan, R.1
Kumar, A.2
Kannan, U.3
Raina, V.K.4
Arora, M.K.5
Ganesan, S.6
Degwekar, S.B.7
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