17.6 Conclusion
To realize the harmonization of MA transmutation and sodium void reactivity, the
MA transmutation fast reactor core concept, with an internal blanket between the
MA-loaded core fuel region and the sodium plenum above the core fuel, was
proposed. The feature of this core concept is that sodium void reactivity can be
greatly reduced without spoiling core performance for normal operation.
To accurately evaluate neutronics parameters in a MA transmutation fast reactor,
we improved the calculation methods for estimating MA transmutation rates and
safety-related parameters such as sodium void reactivity. For the MA transmutation
rate, we introduced a definition of MA transmutation for individual MA nuclides
and a method for calculating the MA transmutation rates. To evaluate the prediction
accuracy of neutronics parameters, we proposed a new method that can eliminate
systematic errors of measurements and calculations, and introduced a method to
reduce the prediction uncertainty based on the cross-section adjustment method or
the bias factor method. Furthermore, we improved the sensitivity, which is necessary to evaluate the uncertainty, by considering the effect of self-shielding.
Acknowledgments A part of the present study is the result of “Study on minor actinide transmutation using Monju data” entrusted to University of Fukui by the Ministry of Education,
Culture, Sports, Science and Technology of Japan (MEXT).
Open Access This chapter is distributed under the terms of the Creative Commons Attribution
Noncommercial License, which permits any noncommercial use, distribution, and reproduction in
any medium, provided the original author(s) and source are credited.
References
1. Nakai R (2009) Design and assessment approach on advanced SFR safety with emphasis on
the core disruptive accident issue. In: Proceedings of the international conference on fast
reactor and related fuel cycles (FR09), Kyoto, 7–11 December, 2009
2. Aoto K, Uto N, Sakamoto Y, Ito T, Toda M, Kotake S (2011) Design study and R & D progress
on Japan sodium-cooled fast reactor. J Nucl Sci Technol 48:463–471
3. Beils S, Carluec B, Devictor N, Fiorini GL, Sauvage JF (2011) Safety approach and R & D
program for future French sodium-cooled fast reactors. J Nucl Sci Technol 48:510–515
4. Carluec B, Lo Point P, Mariteau P, Capelle S (2012) Severe accident countermeasure of SFR.
In: Proceedings of the JAEA-IAEA international workshop on prevention and mitigation of
severe accidents in sodium-cooled fast reactors, Tsuruga, 11–13 June, 2012
5. Grouiller JP et al. Transmutation in ASTRID. In: Proceedings of international conference on
fast reactors and related fuel cycles: safe technologies and sustainable scenarios. FR13, Paris,
March 4–7, paper IAEA-CN-199-140
6. Kawashima K et al (1991) Study of the advanced design for axially heterogeneous LMFBR
cores. In: Proceedings of international conference on fast reactors and related fuel cycles,
FR91, vol 1, Kyoto, October 28–November 1
7. Kawashima K et al (1992) Conceptual core design to enhance safety characteristics in MOX
fueled large LMFBRs (I). Neutronics and transient safety performance characteristics. In:
17 Method Development for Calculating Minor Actinide Transmutation in a Fast. . .
195
To realize the harmonization of MA transmutation and sodium void reactivity, the
MA transmutation fast reactor core concept, with an internal blanket between the
MA-loaded core fuel region and the sodium plenum above the core fuel, was
proposed. The feature of this core concept is that sodium void reactivity can be
greatly reduced without spoiling core performance for normal operation.
To accurately evaluate neutronics parameters in a MA transmutation fast reactor,
we improved the calculation methods for estimating MA transmutation rates and
safety-related parameters such as sodium void reactivity. For the MA transmutation
rate, we introduced a definition of MA transmutation for individual MA nuclides
and a method for calculating the MA transmutation rates. To evaluate the prediction
accuracy of neutronics parameters, we proposed a new method that can eliminate
systematic errors of measurements and calculations, and introduced a method to
reduce the prediction uncertainty based on the cross-section adjustment method or
the bias factor method. Furthermore, we improved the sensitivity, which is necessary to evaluate the uncertainty, by considering the effect of self-shielding.
Acknowledgments A part of the present study is the result of “Study on minor actinide transmutation using Monju data” entrusted to University of Fukui by the Ministry of Education,
Culture, Sports, Science and Technology of Japan (MEXT).
Open Access This chapter is distributed under the terms of the Creative Commons Attribution
Noncommercial License, which permits any noncommercial use, distribution, and reproduction in
any medium, provided the original author(s) and source are credited.
References
1. Nakai R (2009) Design and assessment approach on advanced SFR safety with emphasis on
the core disruptive accident issue. In: Proceedings of the international conference on fast
reactor and related fuel cycles (FR09), Kyoto, 7–11 December, 2009
2. Aoto K, Uto N, Sakamoto Y, Ito T, Toda M, Kotake S (2011) Design study and R & D progress
on Japan sodium-cooled fast reactor. J Nucl Sci Technol 48:463–471
3. Beils S, Carluec B, Devictor N, Fiorini GL, Sauvage JF (2011) Safety approach and R & D
program for future French sodium-cooled fast reactors. J Nucl Sci Technol 48:510–515
4. Carluec B, Lo Point P, Mariteau P, Capelle S (2012) Severe accident countermeasure of SFR.
In: Proceedings of the JAEA-IAEA international workshop on prevention and mitigation of
severe accidents in sodium-cooled fast reactors, Tsuruga, 11–13 June, 2012
5. Grouiller JP et al. Transmutation in ASTRID. In: Proceedings of international conference on
fast reactors and related fuel cycles: safe technologies and sustainable scenarios. FR13, Paris,
March 4–7, paper IAEA-CN-199-140
6. Kawashima K et al (1991) Study of the advanced design for axially heterogeneous LMFBR
cores. In: Proceedings of international conference on fast reactors and related fuel cycles,
FR91, vol 1, Kyoto, October 28–November 1
7. Kawashima K et al (1992) Conceptual core design to enhance safety characteristics in MOX
fueled large LMFBRs (I). Neutronics and transient safety performance characteristics. In:
17 Method Development for Calculating Minor Actinide Transmutation in a Fast. . .
195