Neutronic Calculations for the Tokamak Fusion Test Reactor Diagnostic Penetrations
Author:
Affiliation:
1. Princeton University Plasma Physics Laboratory, Princeton, New Jersey 08544
Publisher
Informa UK Limited
Subject
General Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/FST82-A20763
Reference10 articles.
1. LONG-POE KU, “Nuclear Radiation Analysis for TFTR,” PPPL-1711, Princeton Plasma Physics Laboratory (1980).
2. K. M. YOUNG, “TFTR Diagnostics: Notes on the Impact of Operation with Tritium and High Neutron Fluxes,” TFTR Physics Group Report #37, Princeton Plasma Physics Laboratory (1981).
3. W. A. RHOADES and F. R. MYNATT, “The DOT III Two Dimensional Discrete Ordinates Code,” ORNL/TM-4280, Oak Ridge National Laboratory (1973);
4. see also ORNL/RSICCCC 276, Oak Ridge National Laboratory (1976).
5. 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/RSIC-CCC203, Oak Ridge National Laboratory (1970).
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1. TFTR Basement Radiation Fluence Calculations and Comparisons with Measurements;Fusion Technology;1986-11
2. TheDCN-SNHybrid Method for Neutron Transport Calculations in (r-z) Geometry;Nuclear Science and Engineering;1986-02
3. Analysis of a 14-MeV Neutron Streaming Through a Narrow Hole Duct Using the Monte Carlo Coupling Technique;Fusion Technology;1985-01
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