Physical mechanism analysis of burnup actinide composition in light water reactor MOX fuel and its application to uncertainty evaluation

Author:

Oizumi Akito,Jin Tomoyuki,Ishikawa Makoto,Kugo Teruhiko

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference6 articles.

1. Ando, Y., Takano, H., 1999. Estimation of LWR Spent Fuel Composition. JAERI-Research 99-004. Japan Atomic Energy Research Institute. (in Japanese).

2. Okumura, K., Sugino, K., Kojima, K., Jin, T., Okamoto, T., Katakura, J., 2012. A set of ORIGEN2 Cross Section Libraries Based on JENDL-4.0: ORLIBJ40. JAEA-Data/Code 2012-032. Japan Atomic Energy Agency (in Japanese).

3. JENDL-4.0: a new library for nuclear science and engineering;Shibata;J. Nucl. Sci. Technol.,2011

4. Burnup sensitivity analysis in a fast breeder reactor – Part I: Sensitivity calculation method with generalized perturbation theory;Takeda;Nucl. Sci. Eng.,1985

5. Development of depletion perturbation theory for coupled neutron/nuclide fields;Williams;Nucl. Sci. Eng.,1979

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