Abstract
Fast reactors with a nitride fuel and a lead coolant (BREST) have low excessive in-core plutonium breeding (CBR {approx}1.05) and do not have breeding blankets. The fuel cycle of BREST reactors includes stages that are traditionally considered in a closed fuel cycle of fast reactors excluding the breeding blanket cycle, namely in-pile fuel irradiation, post-irradiation cooling of spent FAs (SFAs); SFA transportation to the recovery shop, SFA dismantling, fuel extraction and separation of the SFA steel components, radiochemical treatment, adjustment of the fuel mixture composition, manufacturing of nitride pellets, manufacturing of fuel elements and fuel assemblies, interim storage and transportation to the reactor. There is a radioactive waste storage facility at the NPP site. The fuel cycle of fast reactors with CBR of {approx}1 does not requires plutonium separation to produce 'fresh' fuel, so it should use a radiochemical technology that would not separate plutonium from the fuel in the recovery process. Besides, rough recovered fuel cleaning of fission products is permitted (the FP residue in the 'fresh' fuel is 10{sup -2}-10{sup -3} of their content in the irradiated fuel) and the presence of minor actinides therein causes high activity of the fuel (radiation barrier for fuel thefts). The fuel
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Glazov, A G;
Lopatkin, A V;
Orlov, V V;
[1]
Volk, V I;
Poluektov, P P;
[2]
Leontyev, V F;
[3]
Karimov, R S
[4]
- Research and Development Institute of Power Engineering (NIKIET), Moscow (Russian Federation)
- Research Institute of Inorganic Materials (VNIINM), Moscow (Russian Federation)
- Special State Design Institute, Moscow (Russian Federation)
- SverdNIIkhimmash, Ekaterinburg (Russian Federation)
Citation Formats
Glazov, A G, Lopatkin, A V, Orlov, V V, Volk, V I, Poluektov, P P, Leontyev, V F, and Karimov, R S.
Fuel cycle of BREST reactors. Solution of the radwaste and nonproliferation problems.
IAEA: N. p.,
2004.
Web.
Glazov, A G, Lopatkin, A V, Orlov, V V, Volk, V I, Poluektov, P P, Leontyev, V F, & Karimov, R S.
Fuel cycle of BREST reactors. Solution of the radwaste and nonproliferation problems.
IAEA.
Glazov, A G, Lopatkin, A V, Orlov, V V, Volk, V I, Poluektov, P P, Leontyev, V F, and Karimov, R S.
2004.
"Fuel cycle of BREST reactors. Solution of the radwaste and nonproliferation problems."
IAEA.
@misc{etde_20617719,
title = {Fuel cycle of BREST reactors. Solution of the radwaste and nonproliferation problems}
author = {Glazov, A G, Lopatkin, A V, Orlov, V V, Volk, V I, Poluektov, P P, Leontyev, V F, and Karimov, R S}
abstractNote = {Fast reactors with a nitride fuel and a lead coolant (BREST) have low excessive in-core plutonium breeding (CBR {approx}1.05) and do not have breeding blankets. The fuel cycle of BREST reactors includes stages that are traditionally considered in a closed fuel cycle of fast reactors excluding the breeding blanket cycle, namely in-pile fuel irradiation, post-irradiation cooling of spent FAs (SFAs); SFA transportation to the recovery shop, SFA dismantling, fuel extraction and separation of the SFA steel components, radiochemical treatment, adjustment of the fuel mixture composition, manufacturing of nitride pellets, manufacturing of fuel elements and fuel assemblies, interim storage and transportation to the reactor. There is a radioactive waste storage facility at the NPP site. The fuel cycle of fast reactors with CBR of {approx}1 does not requires plutonium separation to produce 'fresh' fuel, so it should use a radiochemical technology that would not separate plutonium from the fuel in the recovery process. Besides, rough recovered fuel cleaning of fission products is permitted (the FP residue in the 'fresh' fuel is 10{sup -2}-10{sup -3} of their content in the irradiated fuel) and the presence of minor actinides therein causes high activity of the fuel (radiation barrier for fuel thefts). The fuel cycle under consideration 'burns' uranium- 238 added to the fuel during reprocessing. And plutonium is a fuel component and circulates in a closed cycle as part of the high-level material. The radiation balance between natural uranium consumed by the nuclear power closed system and long-lived high-level radioactive waste generated in the BREST-type nuclear reactor system is provided by actinides transmutation in the fuel (U, Pu, Am, Np) and long-lived products (Tc, I) in the BREST reactor blanket and by monitored pre-disposal cooling of high-level waste for approximately 200 years. The design of the building and the entire set of the fuel cycle equipment has been completed for a BREST-OD-300 experimental demonstration reactor, which will implement the basic features of the BREST reactor fuel cycle. (author)}
place = {IAEA}
year = {2004}
month = {Sep}
}
title = {Fuel cycle of BREST reactors. Solution of the radwaste and nonproliferation problems}
author = {Glazov, A G, Lopatkin, A V, Orlov, V V, Volk, V I, Poluektov, P P, Leontyev, V F, and Karimov, R S}
abstractNote = {Fast reactors with a nitride fuel and a lead coolant (BREST) have low excessive in-core plutonium breeding (CBR {approx}1.05) and do not have breeding blankets. The fuel cycle of BREST reactors includes stages that are traditionally considered in a closed fuel cycle of fast reactors excluding the breeding blanket cycle, namely in-pile fuel irradiation, post-irradiation cooling of spent FAs (SFAs); SFA transportation to the recovery shop, SFA dismantling, fuel extraction and separation of the SFA steel components, radiochemical treatment, adjustment of the fuel mixture composition, manufacturing of nitride pellets, manufacturing of fuel elements and fuel assemblies, interim storage and transportation to the reactor. There is a radioactive waste storage facility at the NPP site. The fuel cycle of fast reactors with CBR of {approx}1 does not requires plutonium separation to produce 'fresh' fuel, so it should use a radiochemical technology that would not separate plutonium from the fuel in the recovery process. Besides, rough recovered fuel cleaning of fission products is permitted (the FP residue in the 'fresh' fuel is 10{sup -2}-10{sup -3} of their content in the irradiated fuel) and the presence of minor actinides therein causes high activity of the fuel (radiation barrier for fuel thefts). The fuel cycle under consideration 'burns' uranium- 238 added to the fuel during reprocessing. And plutonium is a fuel component and circulates in a closed cycle as part of the high-level material. The radiation balance between natural uranium consumed by the nuclear power closed system and long-lived high-level radioactive waste generated in the BREST-type nuclear reactor system is provided by actinides transmutation in the fuel (U, Pu, Am, Np) and long-lived products (Tc, I) in the BREST reactor blanket and by monitored pre-disposal cooling of high-level waste for approximately 200 years. The design of the building and the entire set of the fuel cycle equipment has been completed for a BREST-OD-300 experimental demonstration reactor, which will implement the basic features of the BREST reactor fuel cycle. (author)}
place = {IAEA}
year = {2004}
month = {Sep}
}