XiPAF束流垃圾桶屏蔽设计及残余剂量评估

王迪; 陈伟; 吕伟; 闫逸花; 于俊英; 王敏文; 王忠明

doi:10.3724/j.0253-3219.2026.hjs.49.250021

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XiPAF束流垃圾桶屏蔽设计及残余剂量评估

加速器技术、射线技术及应用 | 更新时间：2026-01-19

- XiPAF束流垃圾桶屏蔽设计及残余剂量评估
- Radiation shielding design and residual radioactivity assessment for the beam dump at XiPAF
- 核技术 2026年49卷第1期文章编号：010203
- 作者机构：
  
  强脉冲辐射环境模拟与效应全国重点实验室（西北核技术研究所）西安 710024
- 作者简介：
  
  王迪，男，1992年出生，2016年于西北核技术研究所获硕士学位，核技术及应用专业
  王忠明，E-mail：wangzhongming@nint.ac.cn
- 基金信息：
- DOI：10.3724/j.0253-3219.2026.hjs.49.250021
  中图分类号： TL77
- 收稿：2025-01-25，
  
  修回：2025-07-06，
  
  纸质出版：2026-01-15
- 稿件说明：
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王迪,陈伟,吕伟等.XiPAF束流垃圾桶屏蔽设计及残余剂量评估[J].核技术,2026,49(01):010203.

WANG Di,CHEN Wei,LYU Wei,et al.Radiation shielding design and residual radioactivity assessment for the beam dump at XiPAF[J].NUCLEAR TECHNIQUES,2026,49(01):010203.
王迪,陈伟,吕伟等.XiPAF束流垃圾桶屏蔽设计及残余剂量评估[J].核技术,2026,49(01):010203. DOI： 10.3724/j.0253-3219.2026.hjs.49.250021. CSTR： 32193.14.hjs.CN31-1342/TL.2026.49.250021.

WANG Di,CHEN Wei,LYU Wei,et al.Radiation shielding design and residual radioactivity assessment for the beam dump at XiPAF[J].NUCLEAR TECHNIQUES,2026,49(01):010203. DOI： 10.3724/j.0253-3219.2026.hjs.49.250021. CSTR： 32193.14.hjs.CN31-1342/TL.2026.49.250021.

摘要

为了确保西安200 MeV质子应用装置（Xi'an 200 MeV Proton Application Facility，XiPAF）升级之后的辐射安全，对束流垃圾桶进行了屏蔽设计与残余剂量评估。首先分析了不同材料的中子产额特征，选择聚乙烯作为低中子产额的靶芯材料。基于FLUKA蒙特卡罗模拟设计了复合结构束流垃圾桶，主体屏蔽材料为铁，外围屏蔽材料为含硼聚乙烯。计算结果表明，束流垃圾桶尾部侧面和横向侧面的最大剂量当量率分别为4.2 mSv·h

-1

和3.2 mSv·h

-1

，满足5.5 mSv·h

-1

的设计限值。与传统石墨靶芯相比，聚乙烯靶芯在上游方向的剂量降低约75%。对连续出束1 h、1 d、1 w三种工况的残余剂量分析显示，桶入口处剂量衰减至2.5 μSv·h

-1

所需时间均为2~3 h。研究结果为中能质子加速器束流垃圾桶设计提供了重要参考，有助于确保XiPAF工作人员的辐射安全。

Abstract

Background

The Xi'an 200 MeV proton application facility (XiPAF) is planned for upgrade and transformation into a versatile experimental facility for both proton and heavy-ion applications

requiring comprehensive radiation protection design for operational safety.

Purpose

This study aims to develop a radiation-safe beam dump design ensuring compliance with operational dose limits during operation and minimizing post-irradiation residual doses.

Methods

Firstly

the neutron yield characteristics of different target materials were analyzed using FLUKA Monte Carlo simulations to determine the optimal core material with low neutron production. Then

a composite structure beam dump was designed with polyethylene as the target core material

iron as the main shielding material

and borated polyethylene as the outer shielding layer. Finally

shielding performance was quantified via ambient dose equivalent rate mapping at critical locations

and residual dose decay kinetics were modeled for three operational scenarios: 1-h

1-d

and 1-w continuous irradiation at maximum beam intensity of 1.3×10

protons per second.

Results

The computational results show that the maximum ambient dose equivalent rates at the rear and transverse sides of the beam dump are 4.2 mSv·h

-1

and 3.2 mSv·h

-1

respectively

both below the design limit of 5.5 mSv·h

-1

. Compared to traditional graphite core

polyethylene demonstrates approximately 75% lower upstream dose while maintaining equivalent downstream shielding performance. Analysis of residual dose under the three operational scenarios shows consistent decay patterns

with all cases reaching the dose constraint of 2.5 μSv·h

-1

after 2~3 h cooling time.

Conclusions

The polyethylene-core composite beam dump design provides effective radiation protection for the XiPAF facility upgrade

with significantly reduced neutron backscattering compared to conventional graphite targets. The residual radioactivity analysis indicates that facility access can be safely permitted within 2~3 h after beam shutdown for all typical operational scenarios. These results provide practical reference for radiation protection design of beam dumps at similar intermediate-energy proton accelerator facilities.

关键词

Keywords

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