HFETR同位素产额计算方法研究

宋霁阳; 刘畅; 何宇豪; 康长虎; 胡映江

doi:10.3724/j.0253-3219.2026.hjs.49.240497

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HFETR同位素产额计算方法研究

核化学、放射化学、放射性药物和核医学 | 更新时间：2026-02-13

- HFETR同位素产额计算方法研究
- Research on isotope yield calculation methodology for HFETR
- 核技术 2026年49卷第2期文章编号：020304
- 作者机构：
  
  中国核动力研究设计院成都 610213
- 作者简介：
  
  宋霁阳，男，1993年出生，2018年于哈尔滨工程大学获硕士学位，研究领域为反应堆物理与热工水力，E-mail：songjiyang1993@163.com
- 基金信息：
  
  同位素制备产量计算方法研究(KJCX-2022-YC1-04)
- DOI：10.3724/j.0253-3219.2026.hjs.49.240497
  中图分类号： TL8
- 收稿：2024-12-12，
  
  修回：2025-06-30，
  
  纸质出版：2026-02-15
- 稿件说明：
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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

Sr生产

Sr产额的计算偏差为5.41%，对辐照生产

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

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

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

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

The calculation results show that the deviation for the production yield of

Sr through irradiation of

Sr is 5.41%

the deviation for the production yield of

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

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

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