Qualification of Neutronic Blanket and Shielding Calculations in a One-Dimensional Approach to a Tokamak Reactor-Reference-Cited by-同舟云学术

Qualification of Neutronic Blanket and Shielding Calculations in a One-Dimensional Approach to a Tokamak Reactor

Published:1992-09 Issue:2 Volume:22 Page:251-270
ISSN:0748-1896
Container-title:Fusion Technology
language:en
Short-container-title:Fusion Technology

Author:

Fischer Ulrich¹

Affiliation:

1. Association KfK-Euratom Kernforschungszentrum Karlsruhe Institut für Neutronenphysik und Reaktortechnik Postfach 3640, W-7500 Karlsruhe, Federal Republic of Germ

Publisher

Informa UK Limited

Subject

General Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/FST92-A30108

Reference10 articles.

1. A Comparison of the Deuterium-Tritium Neutron Wall Load Distributions in Several Tokamak Fusion Reactor Designs

2. Three-Dimensional Monte Carlo Calculations of Nuclear Heating in CIT and Comparisons with Results from Simpler Models

3. J. F. BRIESMEISTER, Ed. “MCNP-A General Monte Carlo Code for Neutron and Photon Transport,” Version 3A, LA-7396-M, Rev. 2, Los Alamos National Laboratory (1986).

4. Authors

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