Neutron Temperature Distributions in a Cylinder of Hot Moderator-Reference-Cited by-同舟云学术

Neutron Temperature Distributions in a Cylinder of Hot Moderator

Published:1963-05 Issue:1 Volume:16 Page:85-100
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Bigham C. B.¹,Turner R. B.¹,Chidley B. G.¹

Affiliation:

1. Atomic Energy of Canada Ltd., Chalk River, Ontario, Canada

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE63-A26479

Reference5 articles.

1. Neutron Temperatures in a CANDU-Type Power Reactor

2. C. B. BIGHAM, B. G. CHIDLEY, AND R. B. TURNER, Experimental effective fission cross sections and neutron spectra in a uranium fuel rod, Part II CANDU-type uranium oxide clusters. Atomic Energy of Canada Ltd., Report No. AECL-1350 (1961).

3. C. H. WESTCOTT, Effective cross sections for well-moderated thermal reactor spectra (3rd ed.). Atomic Energy of Canada Ltd., Report No. AECL-1101 (1960).

4. Thermal Neutron Flux Spectrum in a Medium with a Temperature Discontinuity

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