High-Resolution Transmission Measurements of233U Using a Cooled Sample at the TemperatureT= 11 K-Reference-Cited by-同舟云学术

High-Resolution Transmission Measurements of233U Using a Cooled Sample at the TemperatureT= 11 K

Published:2001-10 Issue:2 Volume:139 Page:111-117
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Guber K. H.¹,Spencer R. R.¹,Leal L. C.¹,Koehler P. E.¹,Harvey J. A.¹,Sayer R. O.¹,Derrien H.¹,Valentine T. E.¹,Pierce D. E.¹,Cauley V. M.¹,Lewis T. A.¹

Affiliation:

1. Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, Tennessee 37921-6354

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE01-A2226

Reference7 articles.

1. CROSS SECTION EVALUATION WORKING GROUP, “ENDF/B-VI Summary Documentation,” BNL-NCS-17541 (ENDF-201), P. F. ROSE, Ed. National Nuclear Data Center, Brookhaven National Laboratory (1991).

2. Japanese Evaluated Nuclear Data Library Version 3 Revision-2: JENDL-3.2

3. New High-Resolution Fission Cross-Section Measurements of233U in the 0.4-eV to 700-keV Energy Range

4. Measurement of the Neutron Total Cross Section of U233from 0.07 to 10,000 ev

5. R-Matrix Analysis of Neutron Effective Total Cross Section, Fission Cross Section and Capture Cross Section of233U in the Energy Range from Thermal to 150eV

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