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Nuclear Science and Engineering Volume 196, 2022 - Issue 1
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Technical Papers

Feasibility of Sodium-Cooled Breed-and-Burn Reactor with Rotational Fuel Shuffling

Van Khanh Hoanga Vietnam Atomic Energy Institute, Institute for Nuclear Science and Technology, 179 Hoang Quoc Viet, Nghia Do, Cau Giay, Hanoi, Viet NamCorrespondence[email protected]
ORCID Iconhttps://orcid.org/0000-0002-0747-3092
ORCID Icon,
Odmaa Sambuub National University of Mongolia, School of Engineering and Applied Sciences, Building #3, Ikh Surguuliin Gudamj-3, Sukhbaatar District, Ulaanbaatar14201, Mongolia;c National University of Mongolia, Nuclear Research Center, Peace Avenue-122/1, Bayanzurkh District, Ulaanbaatar13330, MongoliaORCID Iconhttps://orcid.org/0000-0001-5896-6113
ORCID Icon,
Jun Nishiyamad Tokyo Institute of Technology, Institute of Innovative Research, Laboratory for Advanced Nuclear Energy, 2-12-1-N1-19, Ookayama, Meguro-ku, Tokyo152-8550, JapanORCID Iconhttps://orcid.org/0000-0002-0977-127X
ORCID Icon &
Toru Obarad Tokyo Institute of Technology, Institute of Innovative Research, Laboratory for Advanced Nuclear Energy, 2-12-1-N1-19, Ookayama, Meguro-ku, Tokyo152-8550, JapanORCID Iconhttps://orcid.org/0000-0002-7624-4154
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Pages 109-120 | Received 07 Feb 2021, Accepted 30 Jun 2021, Published online: 29 Jul 2021

Figures & data

Fig. 1. Fuel-shuffling pattern and position ID of fuel assemblies in the core. In this rotational-fuel-shuffling scheme, a fresh fuel assembly is loaded at position 1. The fuel assembly is moved inward after the first 25 fuel-shuffling steps and then moved outward and discharged after 17 fuel-shuffling steps at position 42

Fig. 1. Fuel-shuffling pattern and position ID of fuel assemblies in the core. In this rotational-fuel-shuffling scheme, a fresh fuel assembly is loaded at position 1. The fuel assembly is moved inward after the first 25 fuel-shuffling steps and then moved outward and discharged after 17 fuel-shuffling steps at position 42

Fig. 2. (a) Schematic core layout and (b) fuel cell model for thermal-hydraulic analyses

Fig. 2. (a) Schematic core layout and (b) fuel cell model for thermal-hydraulic analyses

Fig. 3. Metallic fuel types and P/D dependence of criticality in the B&B reactors

Fig. 3. Metallic fuel types and P/D dependence of criticality in the B&B reactors

TABLE I Summary of Analysis Results of the U-2Zr & P/D = 1.086 Core

TABLE II Summary of Analysis Results of the Core with a 200-cm Active Core Height

TABLE III Summary of Analysis Results of the 400-MW(thermal) Core with a 200-cm Active Height

Fig. 4. Radial power distribution during the equilibrium cycle

Fig. 4. Radial power distribution during the equilibrium cycle

Fig. 5. The power density in each fuel assembly: Each assembly is lined up by position ID, and the vertical axis shows the axial position

Fig. 5. The power density in each fuel assembly: Each assembly is lined up by position ID, and the vertical axis shows the axial position

Fig. 6. Average power density distributions at the BOEC and EOEC

Fig. 6. Average power density distributions at the BOEC and EOEC

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