Kinetics of gas release from titanium beryllide irradiated to different neutron fluences

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-04-15 DOI:10.1016/j.fusengdes.2025.115069

A. Shaimerdenov , A. Akhanov , S. Askerbekov , T. Kulsartov , M. Aitkulov , D. Sairanbayev , A. Nessipbay , Zh. Bugybay , I. Kenzhina , B. Shakirov , M. Kylyshkanov , M. Podoinikov

{"title":"Kinetics of gas release from titanium beryllide irradiated to different neutron fluences","authors":"A. Shaimerdenov , A. Akhanov , S. Askerbekov , T. Kulsartov , M. Aitkulov , D. Sairanbayev , A. Nessipbay , Zh. Bugybay , I. Kenzhina , B. Shakirov , M. Kylyshkanov , M. Podoinikov","doi":"10.1016/j.fusengdes.2025.115069","DOIUrl":null,"url":null,"abstract":"<div><div>The binary intermetallic compound of beryllium and titanium (Be<sub>12</sub>Ti) is an advanced material for DEMO-type fusion reactors as a neutron multiplier in breeder blankets. Titanium beryllide has a high melting point (∼1873 K), high oxidation resistance and low swelling, which makes it attractive for use in fission and fusion reactors. The study of its behavior in a radiation field is of utmost importance from the point of view of practical application of titanium beryllide in nuclear installations.</div><div>Based on this, at the Institute of Nuclear Physics (Kazakhstan), R&D is underway to characterization of industrial fabricated titanium beryllide (Be<sub>12</sub>Ti) at JSC “Ulba Metallurgical Plant” (Kazakhstan). Titanium beryllide samples were irradiated in the WWR-K reactor core to accumulate two integral neutron fluences of 1.6 × 10<sup>2</sup><sup>5</sup> m<sup>-2</sup> and 2.3 × 10<sup>2</sup><sup>5</sup> m<sup>-2</sup>, in an inert environment and at low temperature to minimize gas migration from the samples.</div><div>The present work presents the results of post reactor studies to determine the amount of generated tritium and helium in irradiated Be<sub>12</sub>Ti samples. The studies were carried out by thermodesorption spectrometry (TDS) method with mass-spectra control of gas composition. Mass spectra of gas extraction from titanium beryllide irradiated to different neutron fluences and heated up to 1173–1223 K at different heating rates (5, 10, 20 K/min) are presented. The kinetic parameters of tritium desorption from Be<sub>12</sub>Ti were determined, and the activation energy was estimated for each fluence achieved.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115069"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625002662","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}

引用次数: 0

Abstract

The binary intermetallic compound of beryllium and titanium (Be₁₂Ti) is an advanced material for DEMO-type fusion reactors as a neutron multiplier in breeder blankets. Titanium beryllide has a high melting point (∼1873 K), high oxidation resistance and low swelling, which makes it attractive for use in fission and fusion reactors. The study of its behavior in a radiation field is of utmost importance from the point of view of practical application of titanium beryllide in nuclear installations.

Based on this, at the Institute of Nuclear Physics (Kazakhstan), R&D is underway to characterization of industrial fabricated titanium beryllide (Be₁₂Ti) at JSC “Ulba Metallurgical Plant” (Kazakhstan). Titanium beryllide samples were irradiated in the WWR-K reactor core to accumulate two integral neutron fluences of 1.6 × 10²⁵ m^-2 and 2.3 × 10²⁵ m^-2, in an inert environment and at low temperature to minimize gas migration from the samples.

The present work presents the results of post reactor studies to determine the amount of generated tritium and helium in irradiated Be₁₂Ti samples. The studies were carried out by thermodesorption spectrometry (TDS) method with mass-spectra control of gas composition. Mass spectra of gas extraction from titanium beryllide irradiated to different neutron fluences and heated up to 1173–1223 K at different heating rates (5, 10, 20 K/min) are presented. The kinetic parameters of tritium desorption from Be₁₂Ti were determined, and the activation energy was estimated for each fluence achieved.

查看原文本刊更多论文

不同中子辐照下铍化钛气体释放动力学

铍钛二元金属间化合物（Be12Ti）是用于demo型核聚变反应堆增殖包层中子倍增器的先进材料。铍化钛具有高熔点（~ 1873 K），高抗氧化性和低溶胀性，这使得它在裂变和聚变反应堆中具有吸引力。从铍化钛在核设施中的实际应用来看，研究铍化钛在辐射场中的行为具有极其重要的意义。在此基础上，核物理研究所（哈萨克斯坦）正在JSC“Ulba冶炼厂”（哈萨克斯坦）进行工业制造的铍化钛（Be12Ti）的特性研究。铍化钛样品在WWR-K堆芯中进行惰性低温辐照，积累了1.6 × 1025 m-2和2.3 × 1025 m-2的积分中子通量，以减少样品的气体迁移。本工作介绍了反应器后研究的结果，以确定辐照Be12Ti样品中产生的氚和氦的量。研究采用热解吸光谱法（TDS），质谱控制气体成分。给出了铍化钛在不同中子辐照强度下，以不同的升温速率（5、10、20 K/min）加热至1173 ~ 1223 K时的气体萃取质谱。测定了Be12Ti解吸氚的动力学参数，并对每次解吸的活化能进行了估计。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

来源期刊

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.