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-Reference-Cited by-同舟云学术

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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

Published:1994-05 Issue:5 Volume:31 Page:379-397
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

DERRIEN Herve

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

http://www.tandfonline.com/doi/pdf/10.1080/18811248.1994.9735169

Reference40 articles.

1. Multilevel Formula for the Fission Process

2. RMatrix Analysis of239Pu Neutron Cross Sections in the Energy Range up to 1000 eV

3. R-Matrix Analysis of239Pu Neutron Transmissions and Fission Cross Sections in Energy Range from 1.0 keV to 2.5 keV

4. RMatrix Analysis of the241Pu Neutron Cross Sections in the Thermal to 300-eV Energy Range

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2. U233 Data Evaluation for Criticality Study;Journal of Nuclear Engineering and Radiation Science;2016-06-17

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4. Excited Nuclear States for Ne-21 (Neon);Supplement to I/25 A-F;2016

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