• NUCLEAR TECHNIQUES
  • Vol. 47, Issue 8, 080604 (2024)
Liang CHEN1,2, Guifeng ZHU1,2, Ziye WANG1,3, Rui YAN1,2,*..., Yang ZOU1,2,** and Hongjie XU1,2,3|Show fewer author(s)
Author Affiliations
  • 1Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
  • 2University of Chinese Academy of Sciences, Beijing 100049, China
  • 3ShanghaiTech University, Shanghai 201210, China
  • show less
    DOI: 10.11889/j.0253-3219.2024.hjs.47.080604 Cite this Article
    Liang CHEN, Guifeng ZHU, Ziye WANG, Rui YAN, Yang ZOU, Hongjie XU. Evaluation of 99Mo production based on molten salt reactor off-gas extraction[J]. NUCLEAR TECHNIQUES, 2024, 47(8): 080604 Copy Citation Text show less
    References

    [1] Chuvilin D Y, Meister J D, Abalin S S et al. An interleaved approach to production of 99Mo and 89Sr medical radioisotopes[J]. Journal of Radioanalytical and Nuclear Chemistry, 257, 59-63(2003).

    [2] LIU Xiaolin, ZHOU Bo, ZOU Yang et al. Physical optimal design and analysis of 99Mo production in new type molten salt fast reactor[J]. Nuclear Techniques, 45, 060604(2022).

    [3] Chen L, Yan R, Kang X Z et al. Study on the production characteristics of 131I and 90Sr isotopes in a molten salt reactor[J]. Nuclear Science and Techniques, 32, 33(2021).

    [4] MA Zhiguo. Simulation study on medical isotope generation in photonucleus based on laser accelerated electron source[D](2020).

    [5] WANG Jieru, CHEN Dengsheng, HUANG Qinggang et al. The study on molybdenum-99 via proton-induced the fission of natural uranium[J]. Journal of Isotopes, 33, 347-355(2020).

    [6] SUN Hui, CHEN Zhiqiang, HAN Rui et al. Study of proton induced reactions on molybdenum using TALYS and EMPIRE[J]. Nuclear Physics Review, 38, 470-478(2021).

    [7] Yu C G, Zou C Y, Wu C et al. Sustainable supply of 99Mo source in a 2 MW molten salt reactor using low-enriched uranium[J]. Applied Radiation and Isotopes, 160, 109134(2020).

    [8] Kang X Z, Zhu G F, Yan R et al. Evaluation of 99Mo production in a small modular thorium based molten salt reactor[J]. Progress in Nuclear Energy, 124, 103337(2020).

    [9] Sheu R J, Chao C C, Feynberg O et al. A fuel depletion analysis of the MSRE and three conceptual small molten-salt reactors for Mo-99 production[J]. Annals of Nuclear Energy, 71, 111-117(2014).

    [10] Soppera N, Bossant M, Dupont E. JANIS 4: an improved version of the NEA java-based nuclear data information system[J]. Nuclear Data Sheets, 120, 294-296(2014).

    [11] Robertson R. MSRE design and operations report. Part I. description of reactor design[R](1965).

    [12] Price T, Chvala O, Bereznai G. A dynamic model of xenon behavior in the Molten Salt Reactor Experiment[J]. Annals of Nuclear Energy, 144, 107535(2020).

    [13] Stempniewicz M M, Roelofs F. Molten salt modelling in SPECTRA applied to MSRE[J]. Nuclear Engineering and Design, 384, 111483(2021).

    [15] ZHOU Bo, YAN Rui, ZOU Yang. Analysis of xenon dynamic characteristics in primary loop system of MSR[J]. Nuclear Power Engineering, 39, 15-20(2018).

    [16] Zhou B, Yu X H, Zou Y et al. Study on dynamic characteristics of fission products in 2 MW molten salt reactor[J]. Nuclear Science and Techniques, 31, 17(2020).

    [17] ZHOU Bo, YAN Rui, ZOU Yang et al. Analysis of decay heat in primary loop of molten salt reactor under normal conditions[J]. Nuclear Techniques, 41, 040602(2018).

    [18] ZHOU Bo, YAN Rui, ZOU Yang et al. Analysis of 16N source term in primary coolant system of FHR[J]. Atomic Energy Science and Technology, 52, 652-658(2018).

    [19] Walker S A, Ji W. Species transport analysis of noble metal fission product transport, deposition, and extraction in the molten salt reactor experiment[J]. Annals of Nuclear Energy, 158, 108250(2021).

    [20] LI Ziwei, HAN Yuncheng, WANG Xiaoyu et al. Production status and technical prospects of medical radioisotope 99Mo/99mTc[J]. Nuclear Physics Review, 36, 170-183(2019).

    Liang CHEN, Guifeng ZHU, Ziye WANG, Rui YAN, Yang ZOU, Hongjie XU. Evaluation of 99Mo production based on molten salt reactor off-gas extraction[J]. NUCLEAR TECHNIQUES, 2024, 47(8): 080604
    Download Citation