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Volumn 81, Issue 8-14 PART B, 2006, Pages 1239-1244

Neutronics analysis for a compact reversed shear tokamak CREST

Author keywords

3D calculations; CREST; Neutronics

Indexed keywords

COSTS; STEEL; THERMAL EFFECTS; TOKAMAK DEVICES;

EID: 32444432530     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.fusengdes.2005.09.057     Document Type: Article
Times cited : (17)

References (12)
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    • Compact reversed shear tokamak reactor with a superheated steam cycle
    • K. Okano, Y. Asaoka, T. Yoshida, M. Furuya, K. Tomabechi, and Y. Ogawa Compact reversed shear tokamak reactor with a superheated steam cycle Nucl. Fusion 40 3Y 2000 635 646
    • (2000) Nucl. Fusion , vol.40 , Issue.3 , pp. 635-646
    • Okano, K.1    Asaoka, Y.2    Yoshida, T.3    Furuya, M.4    Tomabechi, K.5    Ogawa, Y.6
  • 3
    • 0036863081 scopus 로고    scopus 로고
    • Materials design data for reduced activation martensitic steel type F82H
    • A.-A.F. Tavassoli, J.-W. Rensman, M. Schirra, and K. Shiba Materials design data for reduced activation martensitic steel type F82H Fusion Eng. Des. 61-62 2002 617 628
    • (2002) Fusion Eng. Des. , vol.61-62 , pp. 617-628
    • Tavassoli, A.-A.F.1    Rensman, J.-W.2    Schirra, M.3    Shiba, K.4
  • 5
    • 0342662271 scopus 로고
    • ANISN-JR, a one-dimensional discrete ordinates code for neutron and gamma-ray transport calculations
    • K. Koyama, Y. Taji, K. Minami, ANISN-JR, a one-dimensional discrete ordinates code for neutron and gamma-ray transport calculations, JAERI-M 6954, 1977.
    • (1977) JAERI-M , vol.6954
    • Koyama, K.1    Taji, Y.2    Minami, K.3
  • 6
    • 84890266196 scopus 로고    scopus 로고
    • MCNP4C General Monte Carlo N-particle transport Code
    • J.F. Briesmeister (Ed.)
    • J.F. Briesmeister (Ed.), MCNP4C General Monte Carlo N-Particle Transport Code, Los Alamos National Laboratory, Report LA-13709-M, 2000.
    • (2000) Los Alamos National Laboratory, Report , vol.LA-13709-M
  • 8
    • 32444436074 scopus 로고    scopus 로고
    • Development of the automatically modeling system for MCNP particle transport simulation
    • Y. Wu, Y. Li, L. Lu, A. Ding, H. Hu, and Q. Zeng Development of the automatically modeling system for MCNP particle transport simulation Chin. J. Nucl. Sci. Eng. 25 2005 4
    • (2005) Chin. J. Nucl. Sci. Eng. , vol.25 , pp. 4
    • Wu, Y.1    Li, Y.2    Lu, L.3    Ding, A.4    Hu, H.5    Zeng, Q.6
  • 11
    • 0031372549 scopus 로고    scopus 로고
    • Overview of ARIES-RS neutronics and radiation shielding: Key issues and main conclusions
    • The ARIES Team L.A.
    • L.A. El-Guebaly The ARIES Team Overview of ARIES-RS neutronics and radiation shielding: key issues and main conclusions Fusion Eng. Des. 38 1997 139 158
    • (1997) Fusion Eng. Des. , vol.38 , pp. 139-158
    • El-Guebaly, L.A.1
  • 12
    • 0034316034 scopus 로고    scopus 로고
    • Neutronic shielding analysis of the water-cooled lithium lead test blanket module in the ITER machine
    • M. Rapisarda Neutronic shielding analysis of the water-cooled lithium lead test blanket module in the ITER machine Fusion Eng. Des. 49-50 2000 637 641
    • (2000) Fusion Eng. Des. , vol.49-50 , pp. 637-641
    • Rapisarda, M.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.