Abstract
Two types of conceptual design of fusion-fission hybrid reactor are presented, which is for transmutation of actinide nuclides with nitride fuel or metallic alloy fuel blanket and transmutation of fission products, especially {sup 90}Sr, with Pu fuel blanket, respectively. Neutronics and thermal hydraulics calculation were performed to estimate the performance of the whole system. It was found that the plasma core with recently experimental parameters of plasma physics or the ones to be reached in the near future may drive the blanket which can transmute 17% of the loaded fission product {sup 90}Sr or 23% of the loaded actinides after one year operation at neutron wall loading of 1 MW/m{sup 2} and 80% load factor. thus, the present system may burn {sup 90}Sr waste from about 40 PWRs of 3 GW(t) or the actinide waste from about 65 PWRs of 3 GW(t), respectively.
Citation Formats
Yican, Wu, and Lijian, Qiu.
Study on the technical feasibility of disposal of long-lived radioactive wastes by neutron burning in fusion-fission hybrid reactors.
China: N. p.,
1993.
Web.
Yican, Wu, & Lijian, Qiu.
Study on the technical feasibility of disposal of long-lived radioactive wastes by neutron burning in fusion-fission hybrid reactors.
China.
Yican, Wu, and Lijian, Qiu.
1993.
"Study on the technical feasibility of disposal of long-lived radioactive wastes by neutron burning in fusion-fission hybrid reactors."
China.
@misc{etde_10157330,
title = {Study on the technical feasibility of disposal of long-lived radioactive wastes by neutron burning in fusion-fission hybrid reactors}
author = {Yican, Wu, and Lijian, Qiu}
abstractNote = {Two types of conceptual design of fusion-fission hybrid reactor are presented, which is for transmutation of actinide nuclides with nitride fuel or metallic alloy fuel blanket and transmutation of fission products, especially {sup 90}Sr, with Pu fuel blanket, respectively. Neutronics and thermal hydraulics calculation were performed to estimate the performance of the whole system. It was found that the plasma core with recently experimental parameters of plasma physics or the ones to be reached in the near future may drive the blanket which can transmute 17% of the loaded fission product {sup 90}Sr or 23% of the loaded actinides after one year operation at neutron wall loading of 1 MW/m{sup 2} and 80% load factor. thus, the present system may burn {sup 90}Sr waste from about 40 PWRs of 3 GW(t) or the actinide waste from about 65 PWRs of 3 GW(t), respectively.}
place = {China}
year = {1993}
month = {Jul}
}
title = {Study on the technical feasibility of disposal of long-lived radioactive wastes by neutron burning in fusion-fission hybrid reactors}
author = {Yican, Wu, and Lijian, Qiu}
abstractNote = {Two types of conceptual design of fusion-fission hybrid reactor are presented, which is for transmutation of actinide nuclides with nitride fuel or metallic alloy fuel blanket and transmutation of fission products, especially {sup 90}Sr, with Pu fuel blanket, respectively. Neutronics and thermal hydraulics calculation were performed to estimate the performance of the whole system. It was found that the plasma core with recently experimental parameters of plasma physics or the ones to be reached in the near future may drive the blanket which can transmute 17% of the loaded fission product {sup 90}Sr or 23% of the loaded actinides after one year operation at neutron wall loading of 1 MW/m{sup 2} and 80% load factor. thus, the present system may burn {sup 90}Sr waste from about 40 PWRs of 3 GW(t) or the actinide waste from about 65 PWRs of 3 GW(t), respectively.}
place = {China}
year = {1993}
month = {Jul}
}