Radiation Streaming Calculations for Intor-J-Reference-Cited by-同舟云学术

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Radiation Streaming Calculations for Intor-J

Published:1982-04 Issue:2 Volume:2 Page:272-285
ISSN:0272-3921
Container-title:Nuclear Technology - Fusion
language:en
Short-container-title:Nuclear Technology - Fusion

Author:

Seki Yasushi¹,Iida Hiromasa¹,Santoro Robert T.²,Kawasaki Hiromitsu³,Yamauchi Michinori⁴

Affiliation:

1. Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken, Japan

2. Oak Ridge National Laboratory P.O. Box X, Oak Ridge, Tennessee 37830

3. Century Research Center Corporation, Ltd. Tokyo, Japan

4. NAIG Nuclear Research Laboratory Kawasaki, Japa

Publisher

Informa UK Limited

Subject

General Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/FST82-A20760

Reference15 articles.

1. R. T. SANTORO, R. A. LILLIE, R. G. ALSMILLER, Jr., and J. M. BARNES, “Two- and Three-Dimensional Neutronics Calculations for the TFTR Neutral Beam Injectors,” ORNL/TM-6354, Oak Ridge National Laboratory (1978).

2. K. SAKO et al. “Engineering Aspects of the JAERI Proposal for INTOR(II),” JAERI-M 8518, Japan Atomic Energy Research Institute (1979).

3. E. A. STRAKER, P. N. STEVENS, D. C. IRVING, and V. R. CAIN, “The MORSE Code—A Multigroup Neutron and Gamma Ray Monte Carlo Transport Code,” ORNL-4585, Oak Ridge National Laboratory (1970).

4. A Point Detector Scoring Method Compatible with Monte Carlo Transport Calculations of Specularly Reflected Particles

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1. Monte Carlo analysis of helium production in the ITER shielding blanket module;Fusion Engineering and Design;1999-10

2. Design Analysis to Reduce the Equivalent Dose Rate of the Neutral Beam Injection System in a Fusion Experimental Reactor;Fusion Technology;1996-09

3. Biological shield around the neutral beam injector ducts in the ITER conceptual design;Fusion Engineering and Design;1994-06

4. Radiation shielding for superconductive toroidal field coils around the neutral beam injector duct in the ITER design;Fusion Engineering and Design;1993-07

5. Empirical-analytical formulae for shield effectiveness examination of an experimental thermonuclear reactor;Fusion Engineering and Design;1993-04

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