Fuels and Materials Fast-Reactor Dosimetry Data Development and Testing-Reference-Cited by-同舟云学术

Fuels and Materials Fast-Reactor Dosimetry Data Development and Testing

Published:1975-02 Issue:2 Volume:25 Page:180-223
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

McElroy W. N.¹,Kellogg L. S.¹

Affiliation:

1. Hanford Engineering Development Laboratory P.O. Box 1970, Richland, Washington 99352

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT75-A24364

Reference64 articles.

1. C. A. OSTER, W. N. McELROY, and J. M. MARR, “A Monte Carlo Program for SAND-II Error Analysis,” HEDLTME 73-20, Hanford Engineering Development Laboratory (1973).

2. Preparation and Characterization of Neutron Dosimeter Materials

3. Measurement of Absolute Fission Rates

4. Evaluated Decay Scheme Data

5. Nonfission Reaction Rate Measurements

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