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Evaluation of Tritium Production in LiPb Blanket System Using Neutrons Analysis

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Zero-Carbon Energy Kyoto 2012

Part of the book series: Green Energy and Technology ((GREEN))

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Abstract

Tritium production in LiPb blanket was evaluated by neutronics analysis with Monte Carlo code, MCNP using nuclear cross-section data from the FENDL-2.1 libraries. The result suggests the sufficient TBR (Tritium Breeding Ratio) can be obtained without using additional neutron multiplier such as beryllium. Based on the calculation, a plan for the integral experiment of a small LiPb system to verify it with our DD fusion neutron beam source was made. An integral experiment on LiPb with DD neutrons properly, transport and absorption of the neutron in a small test module was evaluated.

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References

  1. MCNP-A (1983) General Monte Carlo N-particle transport code, version 5. Report LA-UR-03-1987, Los Alamos

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  2. Aldama DL, Trkov A (2004) FENDL-2.1: update of an evaluated nuclear data library for fusion applications. IAEA Report INDC(NDS)-467

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Acknowledgment

The authors were grateful for the support of the Ministry of Education, Culture, Sports, Science and Technology of Japan via “Energy Science in the Age of Global Warming” of Global Center of Excellence (G-COE) program (J-051).

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Correspondence to Saerom Kwon .

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© 2013 Springer Japan

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Kwon, S., Noborio, K., Kasada, R., Konishi, S. (2013). Evaluation of Tritium Production in LiPb Blanket System Using Neutrons Analysis. In: Yao, T. (eds) Zero-Carbon Energy Kyoto 2012. Green Energy and Technology. Springer, Tokyo. https://doi.org/10.1007/978-4-431-54264-3_26

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  • DOI: https://doi.org/10.1007/978-4-431-54264-3_26

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  • Publisher Name: Springer, Tokyo

  • Print ISBN: 978-4-431-54263-6

  • Online ISBN: 978-4-431-54264-3

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