• 文献检索
  • 文档翻译
  • 深度研究
  • 学术资讯
  • Suppr Zotero 插件Zotero 插件
  • 邀请有礼
  • 套餐&价格
  • 历史记录
应用&插件
Suppr Zotero 插件Zotero 插件浏览器插件Mac 客户端Windows 客户端微信小程序
定价
高级版会员购买积分包购买API积分包
服务
文献检索文档翻译深度研究API 文档MCP 服务
关于我们
关于 Suppr公司介绍联系我们用户协议隐私条款
关注我们

Suppr 超能文献

核心技术专利:CN118964589B侵权必究
粤ICP备2023148730 号-1Suppr @ 2026

文献检索

告别复杂PubMed语法,用中文像聊天一样搜索,搜遍4000万医学文献。AI智能推荐,让科研检索更轻松。

立即免费搜索

文件翻译

保留排版,准确专业,支持PDF/Word/PPT等文件格式,支持 12+语言互译。

免费翻译文档

深度研究

AI帮你快速写综述,25分钟生成高质量综述,智能提取关键信息,辅助科研写作。

立即免费体验

基于硼的滤光器下的超热中子激活剂量测定-(n,γ)反应。

Epithermal neutron activation dosimetry-(n, γ) reactions under boron-based filters.

机构信息

Jožef Stefan Institute, Jamova Cesta 39, 1000, Ljubljana, Slovenia.

Faculty of Mathematics and Physics, University of Ljubljana, Jadranska Cesta 19, 1000, Ljubljana, Slovenia.

出版信息

Sci Rep. 2024 Nov 19;14(1):28604. doi: 10.1038/s41598-024-78034-w.

DOI:10.1038/s41598-024-78034-w
PMID:39562584
原文链接:https://pmc.ncbi.nlm.nih.gov/articles/PMC11576865/
Abstract

Neutron activation dosimetry is the primary method for the determination of the neutron flux or fluence, and in general, it is sensitive to the thermal and resonance energy ranges (radiative capture reactions- reactions) and the fast energy range (threshold reactions). However, there are very few nuclear reactions which are sensitive specifically to neutrons in the intermediate-epithermal-energy region. This energy region, along with the fast energy range, will become particularly important in the development and deployment of new reactor technologies (Generation IV reactors and Small Modular Reactors-SMRs), which are currently being championed as technologies enabling a meaningful contribution to decarbonization and the fight against climate change, as well as nuclear fusion. The epithermal neutron energy range is also of particular importance for Boron Neutron Capture Therapy (BNCT), a neutron-based cancer therapy, particularly effective for the treatment of head and neck cancer, malignant meningioma, melanoma and hepatocellular carcinoma. This work investigates and demonstrates the applicability of a particular set of reactions in conjunction with boron-based neutron filters to achieve sensitivity in the epithermal energy region, and discusses avenues for future research in this context.

摘要

中子活化剂量测定是确定中子通量或注量的主要方法,通常对热和共振能区(辐射俘获反应——反应)以及快能区(阈反应)敏感。然而,在中能区至超能区,仅有极少数核反应对中子具有特异性。随着新一代反应堆技术(四代反应堆和小型模块化反应堆)的发展和部署,该能区以及快能区将变得尤为重要,这些技术被认为是对脱碳和应对气候变化以及核聚变做出有意义贡献的技术。超热中子能量范围对于硼中子俘获治疗(BNCT)也非常重要,这是一种基于中子的癌症治疗方法,对头颈癌、恶性脑膜瘤、黑色素瘤和肝细胞癌的治疗特别有效。本工作研究并证明了一组特定的反应与基于硼的中子滤波器结合使用在超热区实现灵敏度的适用性,并讨论了这方面未来研究的途径。

https://cdn.ncbi.nlm.nih.gov/pmc/blobs/be6b/11576865/b8cf4ccfee02/41598_2024_78034_Fig7_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/be6b/11576865/4e9767b02fd7/41598_2024_78034_Fig1_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/be6b/11576865/b258b7c4cb45/41598_2024_78034_Fig2_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/be6b/11576865/48eeaa4bde56/41598_2024_78034_Fig3_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/be6b/11576865/62ad02accf56/41598_2024_78034_Fig4_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/be6b/11576865/5c42dad2f206/41598_2024_78034_Fig5_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/be6b/11576865/2e21cee4fe8a/41598_2024_78034_Fig6_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/be6b/11576865/b8cf4ccfee02/41598_2024_78034_Fig7_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/be6b/11576865/4e9767b02fd7/41598_2024_78034_Fig1_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/be6b/11576865/b258b7c4cb45/41598_2024_78034_Fig2_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/be6b/11576865/48eeaa4bde56/41598_2024_78034_Fig3_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/be6b/11576865/62ad02accf56/41598_2024_78034_Fig4_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/be6b/11576865/5c42dad2f206/41598_2024_78034_Fig5_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/be6b/11576865/2e21cee4fe8a/41598_2024_78034_Fig6_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/be6b/11576865/b8cf4ccfee02/41598_2024_78034_Fig7_HTML.jpg

相似文献

1
Epithermal neutron activation dosimetry-(n, γ) reactions under boron-based filters.基于硼的滤光器下的超热中子激活剂量测定-(n,γ)反应。
Sci Rep. 2024 Nov 19;14(1):28604. doi: 10.1038/s41598-024-78034-w.
2
The neutron sensitivity of dosimeters applied to boron neutron capture therapy.应用于硼中子俘获治疗的剂量计的中子敏感性。
Med Phys. 1996 Sep;23(9):1581-9. doi: 10.1118/1.597737.
3
Mixed field dosimetry of epithermal neutron beams for boron neutron capture therapy at the MITR-II research reactor.麻省理工学院R-II研究堆用于硼中子俘获治疗的超热中子束混合场剂量测定法。
Med Phys. 1994 Oct;21(10):1611-25. doi: 10.1118/1.597267.
4
Boron neutron capture therapy of brain tumors: past history, current status, and future potential.脑肿瘤的硼中子俘获疗法:过去、现状与未来潜力
Cancer Invest. 1996;14(6):534-50. doi: 10.3109/07357909609076899.
5
Rhodium self-powered neutron detector as a suitable on-line thermal neutron flux monitor in BNCT treatments.铑自供电中子探测器作为硼中子俘获治疗中在线热中子通量监测的合适选择。
Med Phys. 2011 Dec;38(12):6502-12. doi: 10.1118/1.3660204.
6
Beam port filters in a TRIGA MARK III nuclear reactor to produce epithermal neutrons for BNCT.在 TRIGA MARK III 核反应堆中使用射束端口滤波器产生用于硼中子俘获治疗的超热中子。
Appl Radiat Isot. 2022 Jan;179:110018. doi: 10.1016/j.apradiso.2021.110018. Epub 2021 Nov 4.
7
Current status of boron neutron capture therapy of high grade gliomas and recurrent head and neck cancer.高级别脑胶质瘤和复发性头颈部肿瘤硼中子俘获治疗的现状。
Radiat Oncol. 2012 Aug 29;7:146. doi: 10.1186/1748-717X-7-146.
8
Measurements of gamma dose and thermal neutron fluence in phantoms exposed to a BNCT epithermal beam with TLD-700.使用TLD-700对暴露于硼中子俘获疗法超热束的体模中的γ剂量和热中子注量进行测量。
Radiat Prot Dosimetry. 2014 Oct;161(1-4):422-7. doi: 10.1093/rpd/nct363. Epub 2014 Jan 16.
9
Determination of the thermal and epithermal neutron sensitivities of an LBO chamber.LBO腔室热中子和超热中子灵敏度的测定。
Radiat Environ Biophys. 2017 Aug;56(3):269-276. doi: 10.1007/s00411-017-0700-y. Epub 2017 Jun 21.
10
Performance characteristics of the MIT fission converter based epithermal neutron beam.
Phys Med Biol. 2003 Apr 7;48(7):943-58. doi: 10.1088/0031-9155/48/7/310.

本文引用的文献

1
Validation of absolute axial neutron flux distribution calculations with MCNP with 197Au(n,γ)198Au reaction rate distribution measurements at the JSI TRIGA Mark II reactor.在JSI TRIGA Mark II反应堆中,通过197Au(n,γ)198Au反应速率分布测量对MCNP绝对轴向中子通量分布计算进行验证。
Appl Radiat Isot. 2014 Feb;84:57-65. doi: 10.1016/j.apradiso.2013.11.027. Epub 2013 Nov 20.
2
Analysis of neutron flux distribution for the validation of computational methods for the optimization of research reactor utilization.用于验证研究堆利用优化计算方法的中子通量分布分析。
Appl Radiat Isot. 2011 Jan;69(1):136-41. doi: 10.1016/j.apradiso.2010.08.019. Epub 2010 Sep 19.