- Introduce
- Editorial Board
- Journal
- Special Source
- Excellent Articles
- Authors
- Reviewers
- Publication Statement
- 个人中心
- 退出登录
浏览全部资源
扫码关注微信
- Introduce
- Introduce
- Journal Honour
- Subscribe
- Video
- Editorial Board
- Ninth Editorial Board
- Current Editorial Board
- Past Editorial Boards
- Spirit of Scientists
- Journal
- ASAP Articles
- Current Issue
- Archive
- Virtual Issues
- Special Issues/Column
- Cover Articles
- Editorial board paper
- Special Source
- Nuclear School
- Talk to Author
- AI
- Article video
- Cover
- Animation Cover
- Nuclear News
- Entering the laborator
- Meeting Highlights
- Blessing Video
- Excellent Articles
- WANG Ganchang
- Excellent Articles
- F5000
- Bilingual Engineering
- Three high thesis
- Exhibition
- Authors
- Instructions for Author
- Manuscript Processing
- Copyright Announcement
- Preprint Policy
- Reviewers
- Guide for Reviewers
- Publication Statement
- Publishing Ethics
- Open Access Statement
Research on isotope yield calculation methodology for HFETR
- NUCLEAR TECHNIQUES Vol. 49, Issue 2, Article number: 020304(2026)
- 作者机构：
中国核动力研究设计院 成都 610213
- 作者简介：
SONG Jiyang, male, born in 1993, graduated from Harbin Engineering University with a master's degree in 2018, focusing on reactor physics analysis and thermal-hydraulics simulation, E-mail: songjiyang1993@163.com
- 基金信息：Research on Yield Calculation Methodology for Isotope Production(KJCX-2022-YC1-04)
DOI：10.3724/j.0253-3219.2026.hjs.49.240497
CLC： TL8Received：12 December 2024，
Revised：2025-06-30，
Published：15 February 2026
- 稿件说明：
移动端阅览
宋霁阳,刘畅,何宇豪等.HFETR同位素产额计算方法研究[J].核技术,2026,49(02):020304.
SONG Jiyang,LIU Chang,HE Yuhao,et al.Research on isotope yield calculation methodology for HFETR[J]. NUCLEAR TECHNIQUES,2026,49(02):020304.
宋霁阳,刘畅,何宇豪等.HFETR同位素产额计算方法研究[J].核技术,2026,49(02):020304. DOI： 10.3724/j.0253-3219.2026.hjs.49.240497. CSTR： 32193.14.hjs.CN31-1342/TL.2026.49.240497.
SONG Jiyang,LIU Chang,HE Yuhao,et al.Research on isotope yield calculation methodology for HFETR[J]. NUCLEAR TECHNIQUES,2026,49(02):020304. DOI： 10.3724/j.0253-3219.2026.hjs.49.240497. CSTR： 32193.14.hjs.CN31-1342/TL.2026.49.240497.
摘要
高通量工程试验堆（High Flux Engineering Test Reactor，HFETR）因其高中子通量密度，用于生产各种医用同位素。针对HFETR堆芯结构复杂、非均匀性强、辐照环境变化较大的特点，以“确定论燃料管理-蒙特卡罗粒子输运-产额”耦合计算的策略建立了一套适用于不同类型同位素产额精确计算模型及方法。该方法首先通过研究堆专用燃料管理程序完成堆芯装载设计与燃耗计算，获得各时间步的燃料燃耗分布及临界棒位等参数，然后利用自编程序实现自动化全堆精细化建模，并利用蒙特卡罗方法完成输运计算。通过计算获得每一时间步下样品中不同核素与中子的反应率，通过产额求解程序与三维粒子输运蒙卡程序进行耦合，计算出下一个时间步样品内关键核素的含量变化情况，并对换料停堆和从出堆到测量期间的衰变损耗进行计算。该方法综合考虑了HFETR运行期间控制棒变化、燃料燃耗变化及计算燃耗步长的影响，利用HFETR已获得的同位素生产实验结果验证该套计算程序的准确性，对辐照
88
Sr生产
89
Sr产额的计算偏差为5.41%，对辐照生产
32
P产额的计算偏差为4.90%，对辐照生产
177
Lu产额的计算偏差为5.66%，与实验结果相比同位素产额计算偏差均在6%以内，证明该方法提高了同位素产额计算的精度，能够适用于研究堆生产同位素产额准确评估问题。
Abstract
Background
2
The High Flux Engineering Test Reactor (HFETR) is used to produce various medical isotopes due to its high neutron flux density. The calculation of isotope yield of HFETR needs to consider the characteristics of complex core structure
strong heterogeneity and large changes in radiation environment.
Purpose
2
This study aims to establish a model and method for the accurate calculation of different types of isotope yields by employing a "deterministic fuel management-Monte Carlo particle transport-yield" coupled calculation strategy.
Methods
2
Firstly
the core loading design and burnup calculation through the dedicated fuel management program for the research reactor were conducted to obtain the fuel burnup distribution and control rod positions at each time step along with other parameters. Then
the acquired data was applied to establishing automated full-core refined modeling and conducting neutron transport calculations employing the Monte Carlo method. The reaction rates between various nuclides and neutrons within the sample were systematically determined at each temporal interval. Subsequently
the concentration variations of critical nuclides in subsequent time steps were calculated through iterative coupling of the yield determination algorithm with the Monte Carlo program
and comprehensive evaluations of decay losses occurring during refueling shutdown phases and throughout the post-extraction measurement period were incorporated. Finally
the accuracy of the calculation program was verified by the isotope production experimental results obtained by HFETR.
Results
2
The calculation results show that the deviation for the production yield of
89
Sr through irradiation of
88
Sr is 5.41%
the deviation for the production yield of
32
P through irradiation is 4.90%
and the deviation for the production yield of
177
Lu through irradiation is 5.66%. All devi
ations are within 6% compared with experimental results.
Conclusions
2
Results of this study demonstrate that this calculation method improves the accuracy of isotope yield calculation
hence can be used to accurately evaluate the isotope yield of the research reactor isotope production mission.
关键词
Keywords
references
向玉新 , 刘红倩 , 刘水清 , 等 . HFETR材料辐照精细中子注量率谱研究 [J ] . 核动力工程 , 2017 , 38 ( 1 ): 10 – 12 . DOI: 10.13832/j.jnpe.2017.01.0010 http://dx.doi.org/10.13832/j.jnpe.2017.01.0010 .
XIANG Yuxin , LIU Hongqian , LIU Shuiqing , et al . Study on irradiation fine neutron fluence spectrum of HFETR material [J ] . Nuclear Power Engineering , 2017 , 38 ( 1 ): 10 – 12 . DOI: 10.13832/j.jnpe.2017.01.0010 http://dx.doi.org/10.13832/j.jnpe.2017.01.0010 .
王皓 , 向玉新 , 徐涛忠 , 等 . 高通量工程试验堆(HFETR)材料辐照中子注量率计算方法验证 [J ] . 核动力工程 , 2017 , 38 ( S1 ): 154 – 156 . DOI: 10.13832/j.jnpe.2017.S1.0154 http://dx.doi.org/10.13832/j.jnpe.2017.S1.0154 .
WANG Hao , XIANG Yuxin , XU Taozhong , et al . Verification of calculation method for neutron flux rate of high flux engineering test reactor (HFETR) materials irradiation [J ] . Nuclear Power Engineering , 2017 , 38 ( S1 ): 154 – 156 . DOI: 10.13832/j.jnpe.2017.S1.0154 http://dx.doi.org/10.13832/j.jnpe.2017.S1.0154 .
刘红倩 , 刘水清 , 康长虎 , 等 . HFETR辐照孔道内中子注量率敏感性分析 [J ] . 核科学与工程 , 2021 , 41 ( 6 ): 1130 – 1137 . DOI: 10.3969/j.issn.0258-0918.2021.06.005 http://dx.doi.org/10.3969/j.issn.0258-0918.2021.06.005 .
LIU Hongqian , LIU Shuiqing , KANG Changhu , et al . Sensitivity analysis of neutron fluence rate in HFETR irradiation tunnel [J ] . Nuclear Science and Engineering , 2021 , 41 ( 6 ): 1130 – 1137 . DOI: 10.3969/j.issn.0258-0918.2021.06.005 http://dx.doi.org/10.3969/j.issn.0258-0918.2021.06.005 .
刘畅 , 夏羿 , 彭星杰 , 等 . HFETR辐照装置低温差流动换热过程热工性能分析 [J ] . 核动力工程 , 2023 , 44 ( S2 ): 184 – 187 . DOI: 10.13832/j.jnpe.2023.S2.0184 http://dx.doi.org/10.13832/j.jnpe.2023.S2.0184 .
LIU Chang , XIA Yi , PENG Xingjie , et al . Thermal performance analysis of low temperature differential flow heat transfer process in HFETR irradiation device [J ] . Nuclear Power Engineering , 2023 , 44 ( S2 ): 184 – 187 . DOI: 10.13832/j.jnpe.2023.S2.0184 http://dx.doi.org/10.13832/j.jnpe.2023.S2.0184 .
刘畅 , 刘文斌 , 戴勇 , 等 . CFETR先进小样品辐照胶囊优化与热工安全分析 [J ] . 核动力工程 , 2024 , 45 ( 2 ): 139 – 146 . DOI: 10.13832/j.jnpe.2024.02.0139 http://dx.doi.org/10.13832/j.jnpe.2024.02.0139 .
LIU Chang , LIU Wenbin , DAI Yong , et al . Optimization and thermal safety analysis of cfetr advanced small sample irradiation capsule [J ] . Nuclear power engineering , 2024 , 45 ( 2 ): 139 – 146 . DOI: 10.13832/j.jnpe.2024.02.0139 http://dx.doi.org/10.13832/j.jnpe.2024.02.0139 .
杨文华 , 童明炎 , 孙胜 . 模块式套管型随堆辐照考验装置Ansys CFX热工分析 [J ] . 核动力工程 , 2013 , 34 ( 4 ): 153 – 156 . DOI: 10.3969/j.issn.0258-0926.2013.04.035 http://dx.doi.org/10.3969/j.issn.0258-0926.2013.04.035 .
YANG Wenhua , TONG Mingyan , SUN Sheng . Ansys CFX thermal analysis of modular tube-type irradiation rig [J ] . Nuclear Power Engineering , 2013 , 34 ( 4 ): 153 – 156 . DOI: 10.3969/j.issn.0258-0926.2013.04.035 http://dx.doi.org/10.3969/j.issn.0258-0926.2013.04.035 .
杨文华 , 张亮 , 斯俊平 , 等 . 燃料试样堆内辐照温度设计与实验研究 [J ] . 核动力工程 , 2018 , 39 ( 6 ): 43 – 48 . DOI: 10.13832/j.jnpe.2018.06.0043 http://dx.doi.org/10.13832/j.jnpe.2018.06.0043 .
YANG Wenhua , ZHANG Liang , SI Junping , et al . Design and experimental study of irradiation temperature in fuel specimen [J ] . Nuclear Power Engineering , 2018 , 39 ( 6 ): 43 – 48 . DOI: 10.13832/j.jnpe.2018.06.0043 http://dx.doi.org/10.13832/j.jnpe.2018.06.0043 .
杨文华 , 赵国正 , 张亮 , 等 . 高通量工程试验堆辐照试验能力和 辐照试验技术 [J ] . 核科学与工程 , 2018 , 38 ( 6 ): 986 – 994 . DOI: 10.3969/j.issn.0258-0918.2018.06.011 http://dx.doi.org/10.3969/j.issn.0258-0918.2018.06.011 .
YANG Wenhua , ZHAO Guozheng , ZHANG Liang , et al . High-throughput engineering test reactor irradiation test capability and irradiation test technology [J ] . Nuclear Science and Engineering , 2018 , 38 ( 6 ): 986 – 994 . DOI: 10.3969/j.issn.0258-0918.2018.06.011 http://dx.doi.org/10.3969/j.issn.0258-0918.2018.06.011 .
Pan Q Q , Lv G , Zou S D , et al . Dataset of neutron energy region values for the in-reactor production of medical isotopes [J ] . Nuclear Science and Techniques , 2025 , 36 ( 8 ): 139 . DOI: 10.1007/s41365-025-01735-y http://dx.doi.org/10.1007/s41365-025-01735-y .
左亚杰 , 陈晓亮 , 张宇 , 等 . 49-2游泳池反应堆辐照生产 90 Y的可行性研究 [J ] . 同位素 , 2023 , 36 ( 3 ): 279 – 284 . DOI: 10.7538/tws.2023.36.03.0279 http://dx.doi.org/10.7538/tws.2023.36.03.0279 .
ZUO Yajie , CHEN Xiaoliang , ZHANG Yu , et al . Feasibility study for irradiation production of 90 Y by 49-2 pool reactor [J ] . Journal of Isotopes , 2023 , 36 ( 3 ): 279 – 284 . DOI: 10.7538/tws.2023.36.03.0279 http://dx.doi.org/10.7538/tws.2023.36.03.0279 .
左亚杰 , 陈晓亮 . 新型泳池式研究堆生产放射性同位素的可行性研究 [J ] . 科学技术创新 , 2023 ( 14 ): 224 – 228 . DOI: 10.3969/j.issn.1673-1328.2023.14.056 http://dx.doi.org/10.3969/j.issn.1673-1328.2023.14.056 .
ZUO Yajie , CHEN Xiaoliang . Feasibility study on production of radioisotopes in a new pool research reactor [J ] . Scientific and Technological InnovationInformation , 2023 ( 14 ): 224 – 228 . DOI: 10.3969/j.issn.1673-1328.2023.14.056 http://dx.doi.org/10.3969/j.issn.1673-1328.2023.14.056 .
范文玎 , 孙光耀 , 张彬航 , 等 . 基于切比雪夫有理逼近方法的蒙特卡罗燃耗计算研究与验证 [J ] . 核技术 , 2016 , 39 ( 4 ): 040501 . DOI: 10.11889/j.0253-3219.2016.hjs.39. 040501 http://dx.doi.org/10.11889/j.0253-3219.2016.hjs.39.040501 .
FAN Wending , SUN Guangyao , ZHANG Binhang , et al . Research and verification of Monte Carlo burnup calculations based on Chebyshev rational approximation method [J ] . Nuclear Techniques , 2016 , 39 ( 4 ): 040501 . DOI: 10.11889/j.0253-3219.2016.hjs.39.040501 http://dx.doi.org/10.11889/j.0253-3219.2016.hjs.39.040501 .
Pan Q Q , Zhao Q F , Wang L J , et al . Rapid diagnostic method for transplutonium isotope production in high flux reactors [J ] . Nuclear Science and Techniques , 2023 , 34 ( 3 ): 44 . DOI: 10.1007/s41365-023-01185-4 http://dx.doi.org/10.1007/s41365-023-01185-4 .
Pan Q Q , Zhao Q F , Wang L J , et al . High-resolution neutronics model for 238 Pu production in high-flux reactors [J ] . Nuclear Science and Techniques , 2024 , 35 ( 5 ): 88 . DOI: 10.1007/s41365-024-01461-x http://dx.doi.org/10.1007/s41365-024-01461-x .
邱立青 , 傅蓉 , 邓才玉 . 高通量工程试验堆与MCNP程序的接口程序的开发 [J ] . 核动力工程 , 2007 , 28 ( 4 ): 16 – 19 . DOI: 10.3969/j.issn.0258-0926.2007.04.005 http://dx.doi.org/10.3969/j.issn.0258-0926.2007.04.005 .
QIU Liqing , FU Rong , DENG Caiyu . Development of MCNP interface code in HFETR [J ] . Nuclear Power Engineering , 2007 , 28 ( 4 ): 16 – 19 . DOI: 10.3969/j.issn.0258-0926.2007.04.005 http://dx.doi.org/10.3969/j.issn.0258-0926.2007.04.005 .
Ian Sommerville (美) . 软件工程 [M ] . 北京 : 机械工业出版社 , 2000 .
Ian Sommerville (USA) . Software engineering [M ] . Beijing : China Machine Press , 2000 .
Malec J , Cabellos O , Kromar M , et al . Generation and validation of a new WIMS-D library based on ENDF/B-VIII.0 [J ] . Annals of Nuclear Energy , 2025 , 211 : 110989 . DOI: 10.1016/j.anucene.2024.110989 http://dx.doi.org/10.1016/j.anucene.2024.110989 .
邱立青 , 傅蓉 , 秦乐刚 , 等 . 高通量工程试验堆压力容器焊缝快中子注量计算 [J ] . 核动力工程 , 2006 , 27 ( 5 ): 58 – 60, 73 . DOI: 10.3969/j.issn.0258-0926.2006.05.012 http://dx.doi.org/10.3969/j.issn.0258-0926.2006.05.012 .
QIU Liqing , FU Rong , QIN Legang , et al . Fast neutron flux calculation of welding line in pressure vessel of high flux engineering test reactor [J ] . Nuclear Power Engineering , 2006 , 27 ( 5 ): 58 – 60, 73 . DOI: 10.3969/j.issn.0258-0926.2006.05.012 http://dx.doi.org/10.3969/j.issn.0258-0926.2006.05.012 .
杨体波 , 王敏 , 范新洋 , 等 . 屏蔽材料γ射线积累因子的MCNP模拟 [J ] . 核技术 , 2021 , 44 ( 3 ): 030503 . DOI: 10.11889/j.0253-3219.2021.hjs.44.030503 http://dx.doi.org/10.11889/j.0253-3219.2021.hjs.44.030503 .
YANG Tibo , WANG Min , FAN Xinyang , et al . MCNP simulation for gamma-ray buildup factors of shielding material [J ] . Nuclear Techniques , 2021 , 44 ( 3 ): 030503 . DOI: 10.11889/j.0253-3219.2021.hjs.44.030503 http://dx.doi.org/10.11889/j.0253-3219.2021.hjs.44.030503 .
0
Views
0
下载量
0
CSCD
- L-PDFDownload
- Meta-XMLDownload
- BibTeXDownload
- EndnoteDownload
- RefMan Download
- NoteExpressDownload
- NoteFirstDownload
Publicity Resources
Related Articles
Related Author
Related Institution
AI脑图
AI问答- Address：2019 Jialuo Road, Jiading, Shanghai, China Postal code：201800
- Tel：021-39194977 Email：LHB@sinap.ac.cn
- Technical support is provided by Beijing Founder electronics co., LTD 沪ICP备05005479号-1
京公网安备11010802024621 - It is recommended to read the content of this site in Chrome&IE9+. Please switch to extreme mode in browser 360.
- Cookies We use cookies to help provide and enhance our service and tailor content. By continuing, you agree to the use of cookies.
- Total Visits：1035494 Visits Today：44
