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TECHNICAL REPORT

Evaluation of Shutdown Gamma-ray Dose Rates around the Duct Penetration by Three-Dimensional Monte Carlo Decay Gamma-ray Transport Calculation with Variance Reduction Method

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Pages 1237-1246 | Received 27 Jun 2002, Accepted 18 Sep 2002, Published online: 07 Feb 2012

References

  • Maki , K. , Takatsu , H. , Sato , S. and Seki , Y. 1994 . “Biological shield around the neutral beam injector ducts in the ITER conceptual design,” . Fusion Eng. Des. , 24 : 315
  • Sato , S. and Iida , H. 2000 . “Monte Carlo analyses for ITER NBI duct by 1/4 tokamak model,” . J. Ncul. Sci. Technol. , Supplement 1 : 258
  • Sato , S. , Iida , H. , Plenteda , R. , Valenza , D. and Santoro , R. T. 2000 . “Evaluation of biological dose rates around the ITER NBI ports by 2D SN/Activation and 3-D Monte Carlo analyses,” . Fusion Eng. Des. , 47 : 425
  • Mori , S. , Ito , A. Sato , S. 2000 . “Dose rate analyses around the equatorial and divertor ports during ITER in-vessel components maintenance,” . J. Nucl. Sci. Technol. , Supplement 1 : 248 – 252 .
  • Iida , H. , Valenza , D. , Plenteda , R. and Santoro , R. T. 2000 . “Radiation shielding for ITER to allow for hands-on maintenance inside the cryostat (Methodology for estimating shutdown dose rate in a complex geometry),” . J. Ncul. Sci. Technol. , Supplement 1 : 235
  • Seki , Y. , Iida , H. Kawasaki , H. 1986 . THIDA-2: An Advanced Code System for Transmutation, Activation, Decay Heat and Dose Rate , Japan Atomic Energy Research Institute . JAERI 1301
  • Fukumoto , H. 1986 . “New approach to neutron-induced transmutation, radioactivity and afterheat calculations and its application to fusion reactors,” . J. Ncul. Sci. Technol. , 23 : 97
  • Cierjacks , S. W. 1993 . “Development of a novel algorithm and production of new nuclear data libraries for the treatment of sequential(x n) reactions in fusion material activation calculations,” . Fusion Technol. , 24 : 277 – 287 .
  • Valenza , D. , Iida , H. , Plenteda , R. and Santoro , R. T. 2001 . “Proposal of shutdown dose estimation method by Monte Carlo code,” . Fusion Eng. Des. , 55 : 411
  • Briesmeister , J. F. 1995 . MCNP 4A Monte Carlo N-Particle Transport Code System , Oak Ridge National Laboratory, RSICC Computer Code Collection .
  • IAEA Specialist Meeting on the Fusion Evaluated Nuclear Data Library (FENDL) . 1989 . Vienna, Austria, May 1989; Summary Report edited by V.Goulo and published as IAEA Nuclear Data Section Report INDC (NDC)-223/GF
  • Ueki , K. and Kawai , M. 2000 . “Analyses and development of effective compensation shields in a multilegged duct streaming system,” . Nucl. Technol. , 132 : 281

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