NEWLIT - A General Code for Neutron Wall Loading Distribution in Toroidal Reactors
Author:
Affiliation:
1. Fusion Technology Institute, University of Wisconsin 1500 Johnson Drive, Madison, WI 53706 (608) 263-6398 or (608) 263-5093
Publisher
Informa UK Limited
Subject
General Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/FST85-A40106
Reference6 articles.
1. “MCNP, A General Monte Carlo Code for Neutron and Photon Transport,” LA-7396-M, Los Alamos National Laboratory (1981).
2. W. DANNER, “Neutron Flux Asymmetry in Toroidal Geometries,” IPP 4/101, Max-Planck Institut für Plasmaphysik (1972).
3. W.G. PRICE, Jr. and D.L. CHAPIN, “Neutron Wall Loading Distributions in a Circular Cross Section Tokamak,” MATT-1102, Princeton Plasma Physics Laboratory (1975).
4. A Comparison of the Deuterium-Tritium Neutron Wall Load Distributions in Several Tokamak Fusion Reactor Designs
5. K.A. VERSCHUUR, “Furnace Calculations for JET Neutron Diagnostics,” ECN-146, Netherlands Energy Research Foundation (1983).
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