Neutronic Design Modification of Passive Compact-Molten Salt Reactor

被引:2
作者
Dwijayanto, R. A. P. [1 ]
Harto, A. W. [2 ]
机构
[1] BJ Habibie Sci & Technol Ctr, Res Org Nucl Energy, Res Ctr Nucl Reactor Technol, Natl Res & Innovat Agcy, Bldg 80, South Tangerang 15314, Indonesia
[2] Univ Gadjah Mada, Fac Engn, Dept Nucl Engn & Phys Engn, Jl Grafika 2, Yogyakarta 55281, Indonesia
关键词
PCMSR; Temperature coefficient of reactivity; Breeding ratio; MCNP; BREEDING FUEL-CYCLE; THORIUM; OPTIMIZATION; FEATURES; MCNP6;
D O I
10.55981/aij.2024.1308
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Passive compact molten salt reactor (PCMSR) is a design concept of a molten salt reactor (MSR) currently under development in Universitas Gadjah Mada, Indonesia. It is designed as a thermal breeder reactor using thorium fuel cycle. However, our previous study shows that the original PCMSR design was incorrectly modelled, primarily overestimating its thorium breeding capability. To improve PCMSR neutronic design, we modified the core configuration by the addition of radial fuel channel layers previously nonexistent in original PCMSR core design in various configurations. Neutronic parameters of modified PCMSR geometries in the beginning of life (BOL) were simulated using MCNP6.2 radiation transport code with ENDF/B-VII.0 library. All variations of fuel layer addition show improvement in both temperature coefficient of reactivity (TCR) and breeding ratio (BR), with TCR values became more negative and BR values are larger than unity, ensuring proper breeding capability. Configuration Inner Core -Outer Blanket (IC-OB) achieves the largest BR and lowest doubling time (DT), whilst its TCR is an improvement from the original design. Therefore, IC-OB fuel layer configuration can be applied to redesign the original PCMSR and used in various design optimization scenarios. (c) 2024 Atom Indonesia. All rights reserved
引用
收藏
页码:9 / 17
页数:9
相关论文
共 50 条
  • [21] Neutronic analysis of a tokamak hybrid blanket cooled by thorium-molten salt fuel mixture
    Sahin, Haci Mehmet
    Tunc, Guven
    Karakoc, Alper
    PROGRESS IN NUCLEAR ENERGY, 2024, 174
  • [22] Equilibrium core design methods for molten salt breeder reactor based on two-cell model
    Jeong, Yongjin
    Park, Jinsu
    Lee, Hyun Chul
    Lee, Deokjung
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2016, 53 (04) : 529 - 536
  • [23] Characterization of neutronic parameters and radiation shielding design for an aqueous homogeneous reactor
    Jandaghian, B.
    Dastjerdi, M. H. Choopan
    Mokhtari, J.
    NUCLEAR ENGINEERING AND DESIGN, 2024, 417
  • [24] Implementation of an LBE spallation target in an accelerator-driven molten salt subcritical reactor
    Bak, Sang-In
    Hong, Seung-Woo
    Kadi, Yacine
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2017, 54 (08) : 862 - 870
  • [25] Assessment of Various Candidate Salts Properties for Molten Salt Reactor Application by MCNP Software
    Petrosyan, Taron
    Melyan, Elmira
    Katovsky, Karel
    2020 21ST INTERNATIONAL SCIENTIFIC CONFERENCE ON ELECTRIC POWER ENGINEERING (EPE), 2020, : 400 - 405
  • [26] The molten salt reactor (MSR) in generation IV: Overview and perspectives
    Serp, Jerome
    Allibert, Michel
    Benes, Ondrej
    Delpech, Sylvie
    Feynberg, Olga
    Ghetta, Veronique
    Heuer, Daniel
    Holcomb, David
    Ignatiev, Victor
    Kloosterman, Jan Leen
    Luzzi, Lelio
    Merle-Lucotte, Elsa
    Uhlir, Jan
    Yoshioka, Ritsuo
    Dai Zhimin
    PROGRESS IN NUCLEAR ENERGY, 2014, 77 : 308 - 319
  • [27] Depletion Calculations for an Integral Small Molten Salt Reactor With Serpent
    Wang, Xiaolin
    Nguyen, T. Sinh
    Wojtaszek, Daniel
    JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2024, 10 (02):
  • [28] A novel concept for a molten salt reactor moderated by heavy water
    Wu, Jianhui
    Chen, Jingen
    Kang, Xuzhong
    Li, Xiaoxiao
    Yu, Chenggang
    Zou, Chunyan
    Cai, Xiangzhou
    ANNALS OF NUCLEAR ENERGY, 2019, 132 : 391 - 403
  • [29] Modeling and simulation functional needs for molten salt reactor licensing
    Betzler, Benjamin R.
    Heidet, Florent
    Feng, Bo
    Rabiti, Cristian
    Sofu, Tanju
    Brown, Nicholas R.
    NUCLEAR ENGINEERING AND DESIGN, 2019, 355
  • [30] Possible scenarios for the transition to thorium fuel cycle in molten salt reactor by using enriched uranium
    Cui, D. Y.
    Li, X. X.
    Xia, S. P.
    Zhao, X. C.
    Yu, C. G.
    Chen, J. G.
    Cai, X. Z.
    PROGRESS IN NUCLEAR ENERGY, 2018, 104 : 75 - 84