Authors & Affiliations
National Research Centre "Kurchatov Institute", Moscow, Russia
There are separate of fissile isotopes in a fuel rod in the fuel load admit the transition to a closed fuel circle in the nuclear power industry. For this solution to consider the formation of heterogeneous fuel pellet in which the fissile and raw isotope are separate and not mixed together. The raw material iso-tope is located in the peripheral zone. Fissile isotope, placed in the center of fuel pin holds 10% of the volume. There is row isotope in the periphery.
All calculations for this research were made with UNK code. This code was complemented with a module, which allows calculating temperatures in pin cell. At present UNK allows solving of neutron-physical task of neutron transport, burn-up task (isotope composition evolution) and temperature calculation.
Initial loading is plutonium, separated from spent fuel of the same cell of previous company. Irra-diated plutonium of the central part is sent to either long term storage or final disposal.
Energy plutonium location extracted from spent fuel of VVER in the central part of fuel pellet (heterogeneous pellet) decreases plutonium loading approximately 20 % in condition of the same company duration in comparison with UOX fuel.
In case of heterogeneous location, there is depleted uranium in the periphery on the pellet. And after irradiation received plutonium isotope composition can be used repeatedly to form new loadings. This solution is qualitatively different from MOX case, which does not allow further using.
Rod, heterogeneous, homogeneous, cell, fuel, cycle, fuel, program, closed, burnout, plutonium, energy, SNF, MOX
1. Concepts of improved MOX fuel (MIX, CORAIL, APA). Available at: https://studopedia.su/5_10921_kontseptsii-usovershenstvovannogo-moh-topliva-mIX-CORAIL-APA.html (accessed 07.06.2019)
2. Davidenko V.D., Tsibulsky S.V. Efficient way of burning up of plutonium in reactors in VVER reactors. Atomic Energy, 2015, Vol. 118, no. 3, pp. 134–136.
3. Ternovykh M.U., Tikhomirov G.V., Saldikov I.S., Tsibulsky S.V. Benchmark system for calculating radial temperature fields in combined fuel cores. Proc. Scientific Session NRNU MEPhI-2013. Moscow, 2013. Pp. 47.
4. Andrianova E.A., Davidenko V.D., Tsibulskiy V.F., Tsibulskiy S.V. Variants of the nuclear fuel cycle closure. Problems of atomic science and technology. Series: Physics of Nuclear Reactors, 2014, no. 1–2, pp. 60–67.
5. Belousov N.I., Davidenko V.D., Tsibulskiy V.F. UNK Program for Detailed Calculation of the Neutron Spectrum in a Nuclear Reactor Cell. Preprint IAE-6083/4.. Moscow, 1998.
6. Davidenko V.D., Tsibulskiy V.F. Calculation of burnout in the UNK program. Proc. Conf. Neutronics-1999. Obninsk, 2000.
7. Davidenko V.D., Tsibulskiy V.F., Tsibulskiy S.V. Investigation of the influence of the approximations of the computational model on the change in the temperature coefficient of reactivity in the cell, the fuel assembly of the LWR reactor in the process of fuel burnout. Preprint IAE-6698/5. Moscow, 2012.
8. Production technology of fuel rods. Available at: http://portal.tpu.ru:7777/SHARED/p/ PMGAVRILOV/study/Tab/Lecture%205%20-%20Production%20tvel.pdf (accessed 07.06.2019).