Abstract
A new concept of hybrid reactor is introduced. It uses JET-like(Joint European Tokamak) device worked at sub-breakeven conditions, as a source of high energy neutrons to induce a blanket fission of depleted uranium. The solid breeding material and helium cooling technique are also used. It can produce 100 kg of {sup 239}Pu per year by partial fission suppressed. The energy self-sustained of the fusion core is not necessary. Plasma temperature is maintained by external 20 MW ICRF (ion cyclotron resonance frequency) and 10 MW ECRF (electron cyclotron resonance frequency) heating. A steady state plasma current at 1.5 Ma is driven by 10 MW LHCD (lower hybrid current driven). Plasma density will be kept by pellet injection. ICRF can produce a high energy tail in ion distribution function and lead to significant enhancement of D-T reaction rate by 2 {approx} 5 times so that the neutron source strength reaches to the level of 1 x 10{sup 19} n/s. This system is a passive system. It`s power density is 10 W/cm{sup 3} and the wall loading is 0.6 W/cm{sup 2} that is the lower limitation of fusion and fission technology. From the calculation of neutrons it could always be in sub-critical and
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Lijian, Qiu;
Guishi, Luan;
Qiang, Xu
[1]
- Academia Sinica, Hefei, AH (China). Inst. of Plasma Physics; and others
Citation Formats
Lijian, Qiu, Guishi, Luan, and Qiang, Xu.
Hefei experimental hybrid fusion-fission reactor conceptual design.
China: N. p.,
1992.
Web.
Lijian, Qiu, Guishi, Luan, & Qiang, Xu.
Hefei experimental hybrid fusion-fission reactor conceptual design.
China.
Lijian, Qiu, Guishi, Luan, and Qiang, Xu.
1992.
"Hefei experimental hybrid fusion-fission reactor conceptual design."
China.
@misc{etde_10145467,
title = {Hefei experimental hybrid fusion-fission reactor conceptual design}
author = {Lijian, Qiu, Guishi, Luan, and Qiang, Xu}
abstractNote = {A new concept of hybrid reactor is introduced. It uses JET-like(Joint European Tokamak) device worked at sub-breakeven conditions, as a source of high energy neutrons to induce a blanket fission of depleted uranium. The solid breeding material and helium cooling technique are also used. It can produce 100 kg of {sup 239}Pu per year by partial fission suppressed. The energy self-sustained of the fusion core is not necessary. Plasma temperature is maintained by external 20 MW ICRF (ion cyclotron resonance frequency) and 10 MW ECRF (electron cyclotron resonance frequency) heating. A steady state plasma current at 1.5 Ma is driven by 10 MW LHCD (lower hybrid current driven). Plasma density will be kept by pellet injection. ICRF can produce a high energy tail in ion distribution function and lead to significant enhancement of D-T reaction rate by 2 {approx} 5 times so that the neutron source strength reaches to the level of 1 x 10{sup 19} n/s. This system is a passive system. It`s power density is 10 W/cm{sup 3} and the wall loading is 0.6 W/cm{sup 2} that is the lower limitation of fusion and fission technology. From the calculation of neutrons it could always be in sub-critical and has intrinsic safety. The radiation damage and neutron flux distribution on the first wall are also analyzed. According to the conceptual design the application of this type hybrid reactor earlier is feasible.}
place = {China}
year = {1992}
month = {Mar}
}
title = {Hefei experimental hybrid fusion-fission reactor conceptual design}
author = {Lijian, Qiu, Guishi, Luan, and Qiang, Xu}
abstractNote = {A new concept of hybrid reactor is introduced. It uses JET-like(Joint European Tokamak) device worked at sub-breakeven conditions, as a source of high energy neutrons to induce a blanket fission of depleted uranium. The solid breeding material and helium cooling technique are also used. It can produce 100 kg of {sup 239}Pu per year by partial fission suppressed. The energy self-sustained of the fusion core is not necessary. Plasma temperature is maintained by external 20 MW ICRF (ion cyclotron resonance frequency) and 10 MW ECRF (electron cyclotron resonance frequency) heating. A steady state plasma current at 1.5 Ma is driven by 10 MW LHCD (lower hybrid current driven). Plasma density will be kept by pellet injection. ICRF can produce a high energy tail in ion distribution function and lead to significant enhancement of D-T reaction rate by 2 {approx} 5 times so that the neutron source strength reaches to the level of 1 x 10{sup 19} n/s. This system is a passive system. It`s power density is 10 W/cm{sup 3} and the wall loading is 0.6 W/cm{sup 2} that is the lower limitation of fusion and fission technology. From the calculation of neutrons it could always be in sub-critical and has intrinsic safety. The radiation damage and neutron flux distribution on the first wall are also analyzed. According to the conceptual design the application of this type hybrid reactor earlier is feasible.}
place = {China}
year = {1992}
month = {Mar}
}