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Volumn 49, Issue 8, 2008, Pages 2032-2046

Reactor physics ideas to design novel reactors with faster fissile growth

Author keywords

Fast reactor; Fissile growth; Minimum control maneuvers; Thorium breeders; Two year cycle length

Indexed keywords

FISSION REACTIONS; NUCLEAR ENERGY; NUCLEAR FUELS; PLUTONIUM;

EID: 44249084637     PISSN: 01968904     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.enconman.2008.02.019     Document Type: Article
Times cited : (11)

References (15)
  • 1
    • 0032169181 scopus 로고    scopus 로고
    • Core performance of equilibrium fast reactors for different coolant materials and fuel types
    • Mizutani A., and Sekimoto H. Core performance of equilibrium fast reactors for different coolant materials and fuel types. Ann Nucl Energy 25 13 (1998) 1011-1020
    • (1998) Ann Nucl Energy , vol.25 , Issue.13 , pp. 1011-1020
    • Mizutani, A.1    Sekimoto, H.2
  • 2
    • 0030241081 scopus 로고    scopus 로고
    • Negative coolant void reactivity in large fast breeder reactors with hydrogenous moderator layer
    • Oka Y., and Jevremovic T. Negative coolant void reactivity in large fast breeder reactors with hydrogenous moderator layer. Ann Nucl Energy 23 14 (1996) 1105-1115
    • (1996) Ann Nucl Energy , vol.23 , Issue.14 , pp. 1105-1115
    • Oka, Y.1    Jevremovic, T.2
  • 3
    • 33747882212 scopus 로고    scopus 로고
    • Conceptual design of compact supercritical water-cooled fast reactor with thermal hydraulic coupling
    • Yoo J., Ishiwatari Y., Oka Y., and Liu J. Conceptual design of compact supercritical water-cooled fast reactor with thermal hydraulic coupling. Ann Nucl Energy 33 (2006) 945-956
    • (2006) Ann Nucl Energy , vol.33 , pp. 945-956
    • Yoo, J.1    Ishiwatari, Y.2    Oka, Y.3    Liu, J.4
  • 4
    • 44249118413 scopus 로고    scopus 로고
    • Lee SM, Govindarajan S, Indira R, John TM, Mohanakrishnan P, Shankar Singh R, Bhoje SB. Conceptual design of PFBR core. IAEA-TECDOC-907; 1995. p. 83-99.
    • Lee SM, Govindarajan S, Indira R, John TM, Mohanakrishnan P, Shankar Singh R, Bhoje SB. Conceptual design of PFBR core. IAEA-TECDOC-907; 1995. p. 83-99.
  • 5
    • 0035128273 scopus 로고    scopus 로고
    • ATBR - a thorium breeder reactor concept for an early induction of thorium in an enriched uranium reactor
    • Jagannathan V., Pal U., Karthikeyan R., Ganesan S., Jain R.P., and Kamat S.U. ATBR - a thorium breeder reactor concept for an early induction of thorium in an enriched uranium reactor. J Nucl Technol 133 (2001) 1-32
    • (2001) J Nucl Technol , vol.133 , pp. 1-32
    • Jagannathan, V.1    Pal, U.2    Karthikeyan, R.3    Ganesan, S.4    Jain, R.P.5    Kamat, S.U.6
  • 6
    • 33745187117 scopus 로고    scopus 로고
    • Towards an intrinsically safe and economic thorium breeder reactor
    • Jaganathan V., and Pal U. Towards an intrinsically safe and economic thorium breeder reactor. EC&M J 47 (2006) 2781-2793
    • (2006) EC&M J , vol.47 , pp. 2781-2793
    • Jaganathan, V.1    Pal, U.2
  • 7
    • 44249107415 scopus 로고    scopus 로고
    • Jagannathan V. Reactor physics ideas for large scale utilization of thorium in India. Invited talk delivered at the NSRP-14 symposium at Amritsar, India, November 1-3; 2001.
    • Jagannathan V. Reactor physics ideas for large scale utilization of thorium in India. Invited talk delivered at the NSRP-14 symposium at Amritsar, India, November 1-3; 2001.
  • 8
    • 44249113422 scopus 로고    scopus 로고
    • Transient and Accident Analysis of a BN-800 Type LMFR with Near Zero Void Effect. IAEA TECDOC-1139; 1994-1998.
    • Transient and Accident Analysis of a BN-800 Type LMFR with Near Zero Void Effect. IAEA TECDOC-1139; 1994-1998.
  • 9
    • 44249095955 scopus 로고    scopus 로고
    • Doncals RA, Paik NC, Dickson PW. Transposition of fuel and blanket assemblies in LMFBRs. Trans Am Nucl Soc, June 12, 1977, NY, USA.
    • Doncals RA, Paik NC, Dickson PW. Transposition of fuel and blanket assemblies in LMFBRs. Trans Am Nucl Soc, June 12, 1977, NY, USA.
  • 10
    • 44249086744 scopus 로고    scopus 로고
    • WLUP website - http://www-nds.iaea.org/wimsd/.
    • WLUP website - http://www-nds.iaea.org/wimsd/.
  • 11
    • 0025399204 scopus 로고
    • A diffusion iterative model for simulation of reactivity devices in pressurized heavy water reactors
    • Jagannathan V., Jain R.P., Kumar V., Gupta H.C., and Krishnani P.D. A diffusion iterative model for simulation of reactivity devices in pressurized heavy water reactors. Nucl Sci Eng 104 (1990) 222-238
    • (1990) Nucl Sci Eng , vol.104 , pp. 222-238
    • Jagannathan, V.1    Jain, R.P.2    Kumar, V.3    Gupta, H.C.4    Krishnani, P.D.5
  • 12
    • 44249110813 scopus 로고    scopus 로고
    • Jagannathan V. TRISUL - a code for thorium reactor investigations with segregated uranium loading. Report B.A.R.C./2000/E/028; 2000.
    • Jagannathan V. TRISUL - a code for thorium reactor investigations with segregated uranium loading. Report B.A.R.C./2000/E/028; 2000.
  • 14
    • 44249118414 scopus 로고    scopus 로고
    • Karthikeyan R, Jagannathan V. Monte Carlo validation of FTBR lattice and core design. Paper presented at Advances in Reactor Physics, ARP-2007, May 24-25; 2007, Bhabha Atomic Research Centre, Mumbai, India.
    • Karthikeyan R, Jagannathan V. Monte Carlo validation of FTBR lattice and core design. Paper presented at Advances in Reactor Physics, ARP-2007, May 24-25; 2007, Bhabha Atomic Research Centre, Mumbai, India.
  • 15
    • 84964504654 scopus 로고    scopus 로고
    • Jaganathan V, Usha Pal, Karthikeyan R. A search into the optimal U-Pu-Th fuel cycle options for the next millennium. In: Proceedings of PHYSOR'2000 international conference - ANS International topical meeting on advances in reactor physics and mathematics and computation into the next millennium, Session XV.C on Advanced reactor concepts and design, Pittsburgh, PA, USA, May 7-11; 2000.
    • Jaganathan V, Usha Pal, Karthikeyan R. A search into the optimal U-Pu-Th fuel cycle options for the next millennium. In: Proceedings of PHYSOR'2000 international conference - ANS International topical meeting on advances in reactor physics and mathematics and computation into the next millennium, Session XV.C on Advanced reactor concepts and design, Pittsburgh, PA, USA, May 7-11; 2000.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.