Analysis of a 14-MeV Neutron Streaming Through a Narrow Hole Duct Using the Monte Carlo Coupling Technique-Reference-Cited by-同舟云学术

Analysis of a 14-MeV Neutron Streaming Through a Narrow Hole Duct Using the Monte Carlo Coupling Technique

Published:1985-01 Issue:1 Volume:7 Page:90-98
ISSN:0748-1896
Container-title:Fusion Technology
language:en
Short-container-title:Fusion Technology

Author:

Ueki Kohtaro¹,Ogawa Yuichi²,Naito Hiroshi²,Hyodo Tomonori³

Affiliation:

1. Ship Research Institute, Nuclear Ship Division 6-38-1 Shinkawa, Mitaka, Tokyo 181, Japan

2. Institute of Plasma Physics Nagoya University, Furo-Cho, Chikusa-Ku, Nagoya 464, Japan

3. Kyoto University, Department of Nuclear Engineering Yoshida-Honmachi, Sakyo-Ku, Kyoto 606, Japan

Publisher

Informa UK Limited

Subject

General Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/FST85-A24521

Reference16 articles.

1. F. R. MYNATT et al. “Development of Two-Dimensional Discrete Ordinates Transport Theory for Radiation Shielding,” CTC-INF-952, Union Carbide Corporation (1969);

2. see also “DOT 3.5, Two-Dimensional Discrete Ordinates Radiation Transport Code,” RSIC Computer Code Collection CCC-276, Oak Ridge National Laboratory (1975).

3. Fundamental Theory of the Direct Integration Method for Solving the Steady-State Integral Transport Equation for Radiation Shielding Calculation

4. Neutronic Calculations for the Tokamak Fusion Test Reactor Diagnostic Penetrations

Cited by 14 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Analyses and Development of Effective Compensation Shields in a Multilegged Duct Streaming System;Nuclear Technology;2000-11

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

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