Authors & Affiliations
National Research Center “Kurchatov Institute”, Moscow, Russia
The paper considered the features of heat transfer of two fast sodium reactors of large and low power (1000 and 190 MW(e.)), which are developed for use in the production of secondary nuclear fuel. The design of a case fuel assembly for a higher power reactor is a combination of thin fuel elements (6.1 mm) with U-Pu fuel and a wide grating (relative pitch 1.39) with spacing of the gratings. For a low-power reactor, in this paper, three fuel assemblies (diameter of fuel rod 8.1 mm, relative pitch 1.16) were considered: without a cover, with a cover 1 mm apart from the peripheral row of fuel rods and with a cover spaced 0,5 mm from the peripheral row of fuel rods. Calculations were carried out using the COBRA-IV-I code. Data were obtained on the azimuthal temperature distributions on the claddings of the corner, peripheral and central fuel rods, temperatures on the surfaces of the covers, and calculations were performed to optimize the designs of fuel assemblies in order to reduce the temperature difference on the claddings of the peripheral fuel rods. For a large-power reactor, optimization of the configuration of the corner cell was proposed in order to reduce the azimuthal temperature difference at the corner and peripheral fuel rods. For a low-power reactor, optimization of the fuel assembly design is recommended by replacing the spacer grids with wire spacing and equalizing the temperature field by mixing the coolant, as well as increasing the relative pitch of the fuel element grid from 1.16 to 1.19.
fast neutron reactor, heat transfer, sodium coolant, fuel element, secondary nuclear fuel
Article Text (PDF, in Russian)
- Blandinsky V.Yu. Vliyaniye sostava zagruzhayemogo plutoniya na izmeneniye reaktivnosti i izotopnyy sostav narabatyvayemogo topliva v reaktore na bystrykh neytronakh [The effect of the composition of charged plutonium on the change in reactivity and isotopic composition of produced fuel in a fast neutron reactor]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics of Nuclear Reactors, 2012, no. 4, pp. 62–68.
- Kotov Y.A., Alekseev P.N., Grishanin E.I., Shimkevich A.L. Modul'nyy yadernyy reaktor na bystrykh neytronakh maloy moshchnosti s zhidkometallicheskim teplonositelem i aktivnaya zona reaktora (varianty) [Modular low-power fast neutron reactor with liquid metal coolant and reactor core (options)]. Patent RF, no. 2699229, 2019.
- Wheeler C.L., Stewart C.W., Cena R.J., Rowe D.S., Sutey A.M. COBRA-IV-I: An Interim Version of COBRA for Thermal-Hydraulic Analysis of Rod Bundle Nuclear Fuel Elements and Cores. Washington, Pacific Northwest Laboratories, 1976, 283 p.
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2021, issue 4, 4:15