Study on integrated TRU multi-recycling in sodium cooled fast reactor CDFR-Reference-Cited by-同舟云学术

Study on integrated TRU multi-recycling in sodium cooled fast reactor CDFR

Published:2010-10 Issue:10 Volume:240 Page:3638-3644
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Hu Yun,Xu Mi,Wang Kan

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference17 articles.

1. A User's Manual for the ORIGEN2 Computer Code;Croff,1980

2. Spent fuel reprocessing options: melding advanced & current technology;Dobson,2007

3. Calculations of Isotopic Composition of Daya Bay NPP Spent Fuel. Technical Report of China Institute of Atomic Energy. ZYY. QT. DG. MOX1.03-WL;Fang,2003

4. PASC-1 Code System. Technical Report of China Experimental Fast Reactor. CEFR LP1. 2-CX/PASC-1;Fang,2006

5. Nuclear Reactor Core Analysis Code: CITATION, ORNL-TM-2469. Rev. 2;Fowler,1971

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