TheDPNSurface Flux Integral Neutron Transport Method for Slab Geometry

Author:

Stepanek Jiri1

Affiliation:

1. Swiss Federal Institute for Reactor Research CH-5303 Würenlingen, Switzerland

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Reference25 articles.

1. I. CARLVIK, “Integral Transport Theory in One-Dimensional Geometries,” AE-227, Aktiebolaget Atomenergi, Stockholm, Sweden (1966).

2. I. CARLVIK, “Calculations of Neutron Flux Distributions by Means of Integral Transport Methods,” AE-279, Aktiebolaget Atomenergi, Stockholm, Sweden (1967).

3. I. CARLVIK, “Monoenergetic Critical Parameters and Decay Constants for Small Spheres and Thin Slabs,” AE-273, Aktiebolaget Atomenergi, Stockholm, Sweden (1967).

4. The Integral Transform Method for Neutron Transport Problems

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