Neutron Temperatures in a CANDU-Type Power Reactor-Reference-Cited by-同舟云学术

Neutron Temperatures in a CANDU-Type Power Reactor

Published:1963-05 Issue:1 Volume:16 Page:39-67
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Chidley B. G.¹,Turner R. B.¹,Bigham C. B.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-A26477

Reference15 articles.

1. J. M. KENNEDY AND R. M. PEARCE, Multigroup diffusion calculations of thermal neutron spectra in CANDU using a free gas model. Atomic Energy of Canada Limited, Report No. AECL 1414 (1961).

2. C. H. WESTCOTT, Effective cross sections for wellmoderated thermal reactor spectra (3rd ed.). Atomic Energy of Canada Limited, Report No. AECL 1101 (1960).

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