The effect of pre-irradiation on deuterium retention and desorption behavior in tungsten and tungsten alloys

XUE Haiyu; ZHU Te; LIU Sheng; LUO Laima; ZHANG Peng; WU Haibiao; YUAN Daqing; CAO Xingzhong; CHENG Pinjing

doi:10.3724/j.0253-3219.2026.hjs.49.250019

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The effect of pre-irradiation on deuterium retention and desorption behavior in tungsten and tungsten alloys

NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH | 更新时间：2026-02-13

- The effect of pre-irradiation on deuterium retention and desorption behavior in tungsten and tungsten alloys
- NUCLEAR TECHNIQUES Vol. 49, Issue 2, Article number: 020501(2026)
- 作者机构：
  
  1.中国科学院高能物理研究所北京 100049
  2.南华大学核科学技术学院衡阳 421001
  3.合肥工业大学材料科学与工程学院合肥 230009
  4.南华大学附属第一医院衡阳 421001
  5.中国原子能科学研究院北京 102413
- 作者简介：
  
  XUE Haiyu, male, born in 2000, graduated from Nanhua University in 2018, master student, focusing on nuclear science and technology
  ZHU Te, E-mail: zhute@ihep.ac.cn
  WU Haibiao, E-mail: wuhaibiao@163.com
  CHENG Pinjing, E-mail: pjcheng@usc.edu.cn
- 基金信息：
  
  the Strategic Priority Research Program of Chinese Academy of Sciences(XDA0410400);National Natural Science Foundation of China(12175262;12005093);the Hunan Province Major Science and Technology Project(2023ZJ1050);the Key R&D Project of Hunan Province(2023GK2091)
- DOI：10.3724/j.0253-3219.2026.hjs.49.250019
  CLC： TL62⁺7
- Received：16 January 2025，
  
  Revised：2025-04-18，
  
  Published：15 February 2026
- 稿件说明：
移动端阅览
薛海宇,朱特,刘晟等.预辐照对钨及钨-镍-铁合金中氘滞留与脱附行为的影响[J].核技术,2026,49(02):020501.

XUE Haiyu,ZHU Te,LIU Sheng,et al.The effect of pre-irradiation on deuterium retention and desorption behavior in tungsten and tungsten alloys[J].NUCLEAR TECHNIQUES,2026,49(02):020501.
薛海宇,朱特,刘晟等.预辐照对钨及钨-镍-铁合金中氘滞留与脱附行为的影响[J].核技术,2026,49(02):020501. DOI： 10.3724/j.0253-3219.2026.hjs.49.250019. CSTR： 32193.14.hjs.CN31-1342/TL.2026.49.250019.

XUE Haiyu,ZHU Te,LIU Sheng,et al.The effect of pre-irradiation on deuterium retention and desorption behavior in tungsten and tungsten alloys[J].NUCLEAR TECHNIQUES,2026,49(02):020501. DOI： 10.3724/j.0253-3219.2026.hjs.49.250019. CSTR： 32193.14.hjs.CN31-1342/TL.2026.49.250019.

摘要

钨-镍-铁合金（W-Ni-Fe合金）具有较好的耐高温性能，被认为是具有较大潜力的聚变堆结构材料，然而复杂服役环境下辐照缺陷对其氘滞留与脱附行为的影响机理尚不明确。本工作通过铁（Fe）离子预辐照W-Ni-Fe合金（97W-2Ni-1Fe）与纯钨（W），随后注入低能等离子体氘，模拟中子辐照产生的离位损伤对氘滞留和脱附行为的影响。实验采用正电子湮没谱学技术、热脱附质谱和电镜等方法表征样品中辐照产生空位缺陷的深度分布、缺陷结构类型及热脱附行为。结果表明，纯钨及97W-2Ni-1Fe合金中预辐照缺陷捕获大量氘形成氘-空位复合体和氘泡，氘捕获量随预辐照损伤程度而增大，但增加速率逐渐减小。相比于纯钨，97W-2Ni-1Fe合金低剂量和高剂量预辐照情况下氘滞留量分别减少了65.0%和55.8%。

Abstract

Background

Tungsten (W) and tungsten alloys

such as 97W-2Ni-1Fe

are critical materials for nuclear fusion reactors due to their excellent thermal conductivity and high melting point. However

the performance of these materials can be significantly affected by irradiation-induced defects and deuterium (D) retention

which is crucial for maintaining material integrity and minimizing fuel retention in fusion environments.

Purpose

This study aims to investigate the influence of pre-irradiation defects on deuterium retention and desorption behavior in W and tungsten-nickel-iron (W-Ni-Fe) alloys.

Methods

Firstly

pure W and 97W-2Ni-1Fe alloy samples were irradiated with Fe

13+

ions at doses of 5×10

Fe·cm

-2

and 3×10

Fe·cm

-2

using the heavy ion accelerator at Lanzhou University

and SRIM simulations were conducted to model the defect and Fe ion distribution in the samples. Subsequently

D plasma irradiation was performed at Hefei University of Technology for 1 h at a constant plasma flow of 4×10

D·cm

-2

with 50 eV. Finally

the D retention and desorption behaviors were studied using Thermal Desorption Spectroscopy (TDS)

Doppler-broadening Spectroscopy (DBS) of Positron Annihilation

Transmission Electron Microscopy (TEM)

and Scanning Electron Microscopy (SEM). SRIM simulations were also conducted to model the defect and D atom distributions in the materials.

Results

Observational findings show that Fe

13+

ion irradiation induces significant vacancy-type defects in both materials

with higher defect concentrations in pure W compared to the alloy. D retention is observed to be higher in pure W

with desorption occurring at approximately 250 °C and 700 °C. In contrast

the 97W-2Ni-1Fe alloy shows reduced D retention

with desorption peaks at 200 °C and 700 °C. The TDS results reveal that pure W retained 2~3 times more D than the alloy. Pre-irradiation with Fe

13+

ions further enhances D retention

especially in pure W. TEM analysis results confirm the formation of D bubbles in the defect regions

especially under high-dose irradiation. Compared to pure tungsten

the deuterium retention of the 97W-2Ni-1Fe alloy decreases by 65.0% and 55.8% under low and high dose pre-irradiation conditions

espectively.

Conclusions

The 97W-2Ni-1Fe alloy demonstrates superior performance in minimizing D retention

with significantly lower D desorption and reduced bubble formation compared to pure W

hence is a more favorable material for applications where minimizing D retention and associated damage is critical

such as in fusion reactors. The results highlight the importance of material composition and defect structure in controlling D behavior under irradiation and plasma conditions

offering valuable insights into the design of next-generation plasma-facing materials.

关键词

Keywords

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