Optimized core design and shield analysis of a medium temperature heat pipe cooled reactor
Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review
Author(s)
Detail(s)
Original language | English |
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Article number | 112605 |
Number of pages | 14 |
Journal / Publication | Nuclear Engineering and Design |
Volume | 414 |
Online published | 18 Sept 2023 |
Publication status | Published - 1 Dec 2023 |
Externally published | Yes |
Link(s)
Abstract
Medium Temperature heat pipe cooled Reactor (MTR) is a new reactor concept proposed by Li et al. in (2022). Low enriched uranium zirconium hydride fuel and mercury heat pipe are introduced in MTR. The unique advantages of MTR have been verified (Li et al., 2022), and it is considered as a potential candidate for energy supply in decentralized markets. In this work, an optimized MTR core design is proposed with detailed neutronic analysis and evaluation on mercury heat pipe, reflector and control rod arrangement, further increasing the economic efficiency and mobility of MTR. Heat transfer limit of the improved heat pipe model is further increased, contributing to a great reduction on core volume. Reflector material and thickness are analyzed in detail for mass minimization. Core physics characteristics are analyzed for four control rod arrangement schemes. The control mechanism is further simplified with only 9 control rods involved in the normal regulation of the core. Core lifetime is far more than 10 years. High inherent safety of the core is ensured. Besides, preliminary design of the shielding system is also carried out. A shieling layer of 60 cm LiH and 20 cm Pb can reduce the total dose to less than 40 % of the design limits. The total mass of the optimized core is greatly reduced and its specific power is increased by 60 % compared with that of the previous design. © 2023 Elsevier B.V.
Research Area(s)
- Mercury heat pipe, Uranium zirconium hydride, Shielding design, Neutronic analysis
Citation Format(s)
Optimized core design and shield analysis of a medium temperature heat pipe cooled reactor. / Li, S.N.; Huang, J.C.; Ma, B.B. et al.
In: Nuclear Engineering and Design, Vol. 414, 112605, 01.12.2023.
In: Nuclear Engineering and Design, Vol. 414, 112605, 01.12.2023.
Research output: Journal Publications and Reviews › RGC 21 - Publication in refereed journal › peer-review