TY - GEN
T1 - Effects of high burn-up operation of LWR and extended cooling period of spent fuel on high-level waste properties for vitrification and storage
AU - Kawai, Kota
AU - Sagara, Hiroshi
AU - Takeshita, Kenji
AU - Kawakubo, Masahiro
AU - Asano, Hidekazu
AU - Inagaki, Yaohiro
AU - Niibori, Yuichi
AU - Sato, Seichi
PY - 2017
Y1 - 2017
N2 - Looking ahead to final disposal of high-level radioactive waste arising from further utilization of nuclear energy, the effects of burn-up of LWR with UO2 and MOX fuel and extended cooling period of spent fuel on waste management was discussed. It was assumed that the waste loading of vitrified waste is restricted by three factors: heat generation rate, MoO3 content, and platinum group metal content. As a result of evaluation for effects of extended cooling period, the waste loading of vitrified waste generated from both UO2 and MOX fuel could be increased in the current vitrification technology. For the storage of the MOX fuel vitrified waste with higher waste loading, however, those vitrified waste require long storage period because decay heat of 241Am contributes significantly. Therefore, the evaluation of effects of Am separation on the storage period was performed. The results showed, 70 to 90% of Am separation is desirable to shorten the storage period. These results indicate that nuclides separation could be one of efficient solutions in order to cope with extension of cooling period of spent fuel.
AB - Looking ahead to final disposal of high-level radioactive waste arising from further utilization of nuclear energy, the effects of burn-up of LWR with UO2 and MOX fuel and extended cooling period of spent fuel on waste management was discussed. It was assumed that the waste loading of vitrified waste is restricted by three factors: heat generation rate, MoO3 content, and platinum group metal content. As a result of evaluation for effects of extended cooling period, the waste loading of vitrified waste generated from both UO2 and MOX fuel could be increased in the current vitrification technology. For the storage of the MOX fuel vitrified waste with higher waste loading, however, those vitrified waste require long storage period because decay heat of 241Am contributes significantly. Therefore, the evaluation of effects of Am separation on the storage period was performed. The results showed, 70 to 90% of Am separation is desirable to shorten the storage period. These results indicate that nuclides separation could be one of efficient solutions in order to cope with extension of cooling period of spent fuel.
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M3 - Conference contribution
AN - SCOPUS:85036474353
T3 - 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings
BT - 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings
PB - International Congress on Advances in Nuclear Power Plants, ICAPP
T2 - 2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017
Y2 - 24 April 2017 through 28 April 2017
ER -