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Volumn 43, Issue 8, 2006, Pages 829-843

A feasibility study on a small sodium cooled reactor as a diversified power source

Author keywords

Diversified power source; Electromagnetic pump; Fast breeder reactor; Long life core; Metal fuel; Modular reactor; Passive safety; Remote power source; Sodium cooled reactor

Indexed keywords

DIVERSIFIED POWER SOURCE; FAST BREEDER REACTOR; LONG LIFE CORE; METAL FUEL; MODULAR REACTOR; PASSIVE SAFETY; REMOTE POWER SOURCE; SODIUM COOLED REACTOR;

EID: 33748375356     PISSN: 00223131     EISSN: 00223131     Source Type: Journal    
DOI: 10.3327/jnst.43.829     Document Type: Article
Times cited : (5)

References (43)
  • 1
    • 34249108565 scopus 로고    scopus 로고
    • IRIS reactor design overview and status update
    • Seoul, Korea, May 2005
    • M. D. Carelli, "IRIS reactor design overview and status update," ICAPP'05, Seoul, Korea, May 2005, No. 5059, (2005).
    • (2005) ICAPP'05 , Issue.5059
    • Carelli, M.D.1
  • 2
    • 34249092296 scopus 로고    scopus 로고
    • Development status of integrated modular water reactor (IMR)
    • Seoul, Korea, May 2005
    • T. Kanagawa, K. Hibi, A. Serizawa, T. Kunugi, T. Matsumura, T. Hida, "Development status of integrated modular water reactor (IMR)," ICAPP'05, Seoul, Korea, May 2005, No. 5204, (2005).
    • (2005) ICAPP'05 , Issue.5204
    • Kanagawa, T.1    Hibi, K.2    Serizawa, A.3    Kunugi, T.4    Matsumura, T.5    Hida, T.6
  • 3
    • 34249012441 scopus 로고    scopus 로고
    • Development status of compact containment BWR plant
    • Seoul, Korea, May 2005
    • H. Heki, M. Nakamuram, M. Tsutagawa, M. Kuroki, K. Arai, T. Hida, "Development status of compact containment BWR plant," ICAPP'05, Seoul, Korea, May 2005, No. 5174, (2005).
    • (2005) ICAPP'05 , Issue.5174
    • Heki, H.1    Nakamuram, M.2    Tsutagawa, M.3    Kuroki, M.4    Arai, K.5    Hida, T.6
  • 4
    • 0024755944 scopus 로고
    • The integrated fast reactor
    • Y. I. Chang, "The Integrated Fast Reactor," Nucl. Technol., 88, 129-138 (1989).
    • (1989) Nucl. Technol. , vol.88 , pp. 129-138
    • Chang, Y.I.1
  • 5
    • 0036393422 scopus 로고    scopus 로고
    • Current status of sodium cooled super-safe small and simple reactor
    • Arlington, USA, April 2002, No. 22353
    • N. Ueda, et al., "Current status of sodium cooled super-safe small and simple reactor," ICONE-10, Arlington, USA, April 2002, No. 22353, (2002).
    • (2002) ICONE-10
    • Ueda, N.1
  • 6
    • 34249024823 scopus 로고    scopus 로고
    • Development of an advanced controlling system for non-refueling reactors
    • May 2005
    • I. Kinoshita, T. Koga, T. Takeda, T. Higuchi, S. Okajijma, "Development of an advanced controlling system for non-refueling reactors," ICAPP'2005, May 2005, No. 5115, (2005).
    • (2005) ICAPP'2005 , Issue.5115
    • Kinoshita, I.1    Koga, T.2    Takeda, T.3    Higuchi, T.4    Okajijma, S.5
  • 8
    • 33748366092 scopus 로고    scopus 로고
    • Feasibility study of a compact loop type fast reactor without refueling for a remote place power source
    • Tsukuba, Japan
    • Y. Chikazawa, et al., "Feasibility study of a compact loop type fast reactor without refueling for a remote place power source," Proc. GLOBAL2005, Tsukuba, Japan, No. 044, (2005).
    • (2005) Proc. GLOBAL2005 , Issue.44
    • Chikazawa, Y.1
  • 10
    • 33748337990 scopus 로고    scopus 로고
    • A new concept of hydrogen production system for sodium cooled FBR
    • Yokohama Japan, 30J-07
    • T. Nakagiri, K. Aoto, T. Hoshiva, "A new concept of hydrogen production system for sodium cooled FBR," 15th World Hydrogen Energy Conf., Yokohama Japan, 30J-07, (2004).
    • (2004) 15th World Hydrogen Energy Conf.
    • Nakagiri, T.1    Aoto, K.2    Hoshiva, T.3
  • 11
    • 28144431659 scopus 로고    scopus 로고
    • A feasibility study of a steam methane reforming hydrogen production plant with a sodium cooled fast reactor
    • Y. Chikazawa, T. Hori, M. Konomura, S. Uchida, Y. Tsuchiyama, "A feasibility study of a steam methane reforming hydrogen production plant with a sodium cooled fast reactor," Nucl. Technol., 152, 266-272 (2005).
    • (2005) Nucl. Technol. , vol.152 , pp. 266-272
    • Chikazawa, Y.1    Hori, T.2    Konomura, M.3    Uchida, S.4    Tsuchiyama, Y.5
  • 12
    • 33748349920 scopus 로고    scopus 로고
    • Conceptual design of hydrogen production plant with thermochemical and electrolytic hybrid cycle using a sodium cooled reactor
    • Seoul, Korea
    • Y. Chikazawa, T. Hori, M. Konomura, S. Uchida, T. Tsuchiyama, "Conceptual design of hydrogen production plant with thermochemical and electrolytic hybrid cycle using a sodium cooled reactor," Proc. ICAPP'05, Seoul, Korea, No. 5084, (2005).
    • (2005) Proc. ICAPP'05 , Issue.5084
    • Chikazawa, Y.1    Hori, T.2    Konomura, M.3    Uchida, S.4    Tsuchiyama, T.5
  • 13
    • 34248996861 scopus 로고    scopus 로고
    • Advanced core design studies with oxide and metal fuels for next generation sodium cooled fast reactor
    • Seoul, Korea, May 2005
    • T. Mizuno, T. Ogawa, K. Sugino, M. Naganuma, "Advanced core design studies with oxide and metal fuels for next generation sodium cooled fast reactor," ICAPP'05, Seoul, Korea, May 2005, No. 5195, (2005).
    • (2005) ICAPP'05 , Issue.5195
    • Mizuno, T.1    Ogawa, T.2    Sugino, K.3    Naganuma, M.4
  • 14
    • 33748359949 scopus 로고    scopus 로고
    • Advanced metal fuel core design study for SFR in the feasibility study in Japan
    • Oct. 2005
    • S. Sugino, T. Ogawa, Y. Okano, T. Mizuno, "Advanced metal fuel core design study for SFR in the Feasibility Study in Japan," GLOBAL 2005, Oct. 2005, No. 399, (2005).
    • (2005) GLOBAL 2005 , Issue.399
    • Sugino, S.1    Ogawa, T.2    Okano, Y.3    Mizuno, T.4
  • 20
    • 0034546196 scopus 로고    scopus 로고
    • Tube manufacturing and characterization of oxide dispersion strengthened ferritic steels
    • S. Ukai, et al., "Tube manufacturing and characterization of oxide dispersion strengthened ferritic steels," J. Nucl. Mater., 283-287, 702-706 (2000).
    • (2000) J. Nucl. Mater. , vol.283-287 , pp. 702-706
    • Ukai, S.1
  • 21
    • 0034264859 scopus 로고    scopus 로고
    • Tensile properties of 11Cr-0.5Mo-2W,V,Nb stainless steel in LMFBR environment
    • A. Uehira, et al., "Tensile properties of 11Cr-0.5Mo-2W,V,Nb stainless steel in LMFBR environment," J. Nucl. Sci. Technol., 37[9], 780-786 (2000).
    • (2000) J. Nucl. Sci. Technol. , vol.37 , Issue.9 , pp. 780-786
    • Uehira, A.1
  • 31
    • 33748339259 scopus 로고
    • Feasibility study on double-wall-tube type primary steam generator
    • Kyoto, Japan, Oct. 1991
    • N. Kisohara, et al., "Feasibility study on double-wall-tube type primary steam generator," Proc. Int. Conf. on Fast Reactors and Related Fuel Cycles, Kyoto, Japan, Oct. 1991, (1991).
    • (1991) Proc. Int. Conf. on Fast Reactors and Related Fuel Cycles
    • Kisohara, N.1
  • 32
    • 85088003953 scopus 로고    scopus 로고
    • Realistic safety margin analysis of Monju based on plant performance measurements
    • F. Yamada, K. Kitamura, "Realistic safety margin analysis of Monju based on plant performance measurements," ICONE-12, (2003).
    • (2003) ICONE-12
    • Yamada, F.1    Kitamura, K.2
  • 33
    • 33646696189 scopus 로고
    • Role of feedback reactiveities in the passive safety of nuclear reactors: The case of the fast flux test facility
    • D. H. Nguyen, "Role of feedback reactiveities in the passive safety of nuclear reactors: the case of the fast flux test facility," Nucl. Technol., 91, 61-74 (1990).
    • (1990) Nucl. Technol. , vol.91 , pp. 61-74
    • Nguyen, D.H.1
  • 38
    • 33748376104 scopus 로고    scopus 로고
    • Seismic response analysis of FBR core by FI-NAS code
    • Lyon, France, Aug. 1997
    • M. Morisita, "Seismic response analysis of FBR core by FI-NAS code," SMiRT-14, Lyon, France, Aug. 1997, (1997).
    • (1997) SMiRT-14
    • Morisita, M.1
  • 40
    • 33748375215 scopus 로고    scopus 로고
    • A statistical analysis on failure-to-open/close probability of pneumatic valves in sodium cooling systems
    • Osaka, Japan Nov. 2000
    • K. Kurisaka, "A statistical analysis on failure-to-open/close probability of pneumatic valves in sodium cooling systems," Proc. Int. Conf. on Probabilistic Safety Assessment and Management, Osaka, Japan Nov. 2000, (2000).
    • (2000) Proc. Int. Conf. on Probabilistic Safety Assessment and Management
    • Kurisaka, K.1
  • 42
    • 0036773308 scopus 로고    scopus 로고
    • An innovative concept of sodium-cooled reactor pursuing high economic competitiveness
    • Y. Shimakawa, et al., "An innovative concept of sodium-cooled reactor pursuing high economic competitiveness," Nucl. Technol., 140[1], 1-17 (2002).
    • (2002) Nucl. Technol. , vol.140 , Issue.1 , pp. 1-17
    • Shimakawa, Y.1
  • 43
    • 33748356758 scopus 로고    scopus 로고
    • The promising fast reactor systems and their development plans in Japan
    • Seoul, Korea, paper 5466
    • S. Kotake, Y. Sakamoto, Y. Enuma, M. Ando, A. Nishikawa, Y. Sagayama, "The promising fast reactor systems and their development plans in Japan," Proc. ICAPP'05, Seoul, Korea, paper 5466, (2005).
    • (2005) Proc. ICAPP'05
    • Kotake, S.1    Sakamoto, Y.2    Enuma, Y.3    Ando, M.4    Nishikawa, A.5    Sagayama, Y.6


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.