The GT-MHR reactor core is characterized by flexibility of neutronic characteristics at the given average power density and fixed geometrical dimensions of reactor core. Such flexibility makes it possible to start the reactor operation with one fuel cycle, and then to turn to another type of core fuel load without changes of main reactor elements: fuel block design, core and reflector size, control rod number etc. Preliminary analysis reindicates the commercial viability of the GT-MHR, part of which is due to the ability to accommodate different fuel types and cycles. This paper presents the results of studies of the neutronic characteristics of reactor cores using different fuel (low- and high-enriched uranium, MOX fuel). Comparison of different fuel cycles is carried out for a three-batch refueling option with respect to following characteristics: discharged fuel burnup, reactivity change during one partial cycle of fuel burnup, consumption of fissile isotopes per unit of produced energy, power distribution, reactivity effects, control rods worth. It is shown, that the considered options of fuel loads provide the three-year fuel campaign (with accounting of capacity factor ∼ 0,8) without change of core design, number and design of control rods at transition from the one fuel type to another.
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10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3598-7
PROCEEDINGS PAPER
Possibility of Different Fuel Cycles Usage in GT-MHR
N. Kodochigov,
N. Kodochigov
OKB Mechanical Engineering, Nizhny Novgorod, Russia
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Yu. Sukharev,
Yu. Sukharev
OKB Mechanical Engineering, Nizhny Novgorod, Russia
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E. Marova,
E. Marova
OKB Mechanical Engineering, Nizhny Novgorod, Russia
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N. Ponomarev-Stepnoy,
N. Ponomarev-Stepnoy
RRC Kurchatov Institute, Moscow, Russia
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E. Glushkov,
E. Glushkov
RRC Kurchatov Institute, Moscow, Russia
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P. Fomichenko,
P. Fomichenko
RRC Kurchatov Institute, Moscow, Russia
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N. Kodochigov
OKB Mechanical Engineering, Nizhny Novgorod, Russia
Yu. Sukharev
OKB Mechanical Engineering, Nizhny Novgorod, Russia
E. Marova
OKB Mechanical Engineering, Nizhny Novgorod, Russia
N. Ponomarev-Stepnoy
RRC Kurchatov Institute, Moscow, Russia
E. Glushkov
RRC Kurchatov Institute, Moscow, Russia
P. Fomichenko
RRC Kurchatov Institute, Moscow, Russia
C. Ellis
General Atomics
Paper No:
ICONE10-22404, pp. 339-342; 4 pages
Published Online:
March 4, 2009
Citation
Kodochigov, N, Sukharev, Y, Marova, E, Ponomarev-Stepnoy, N, Glushkov, E, Fomichenko, P, & Ellis, C. "Possibility of Different Fuel Cycles Usage in GT-MHR." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 4. Arlington, Virginia, USA. April 14–18, 2002. pp. 339-342. ASME. https://doi.org/10.1115/ICONE10-22404
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