Calculation of Prompt Fission Product Average Cross Sections for Neutron-Induced Fission of235U and239Pu-Reference-Cited by-同舟云学术

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Calculation of Prompt Fission Product Average Cross Sections for Neutron-Induced Fission of235U and239Pu

Published:2010-05 Issue:5 Volume:47 Page:478-481
ISSN:0022-3131
Container-title:Journal of Nuclear Science and Technology
language:en
Short-container-title:Journal of Nuclear Science and Technology

Author:

WATANABE Takehito,KAWANO Toshihiko,CHADWICK Mark B.,NELSON Ronald O.,HILAIRE Stephane,BAUGE Erick,DOSSANTOS-UZARRALDE Pierre

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

http://www.tandfonline.com/doi/pdf/10.1080/18811248.2010.9711638

Reference31 articles.

1. Nuclear energy generation and waste transmutation using an accelerator-driven intense thermal neutron source

2. Report by the Working Party on International Evaluation Co-operation of the NEA Nuclear Science Committee;Gruppelaar (coordinator) H.,1998

3. LA-9168-MS, Los Alamos National Laboratory;Foster D. G.,1982

4. LA-UR-06–7612;Nelson R. O.,2006

5. EMPIRE: Nuclear Reaction Model Code System for Data Evaluation

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