Boron shielding design for neutron and gamma detectors of a pulsed neutron tool

被引:0
|
作者
Wang, Xin-Yang [1 ]
Chen, Jun-Yan [1 ]
Zhang, Qiong [1 ]
机构
[1] Univ Elect Sci & Technol China, Chengdu 611731, Peoples R China
关键词
Nuclear well logging; Pulsed neutron tool; Boron shielding; CAPTURE; SYSTEM; RAY;
D O I
10.1007/s41365-024-01605-z
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Shielding materials are critical for downhole pulsed neutron tool design because they directly influence the accuracy of formation measurements. A well-designed shield configuration ensures that the response of the tool is maximally representative of the formation without being affected by the tool and borehole environment. This study investigated the effects of boron-containing materials on neutron and gamma detectors based on a newly designed logging-while-drilling tool that is currently undergoing manufacturing. As the boron content increased, the ability to absorb thermal neutrons increased significantly. Through simulation, it was proven that boron carbide (B4C)\documentclass[12pt]{minimal} \usepackage{amsmath} \usepackage{wasysym} \usepackage{amsfonts} \usepackage{amssymb} \usepackage{amsbsy} \usepackage{mathrsfs} \usepackage{upgreek} \setlength{\oddsidemargin}{-69pt} \begin{document}$$(\hbox {B}_4\hbox{C})$$\end{document}can be used as an effective boron shielding material for thermal neutrons, and is therefore employed in this work. To shield against thermal neutrons migrating from the mud pipes, the optimal shielding thicknesses for the near- and far-neutron detectors were determined to be 5 and 4 mm. At a porosity of 25 p.u., near-neutron sensitivity exhibited a 5.6% increase. Furthermore, to shield the capture gamma generated by thermal neutrons once they enter the tool from the mud pipe and formation, internal and external shields for the gamma detector were evaluated. The results show that the internal shield requires a boron content of 75%, whereas the external shield has a thickness of 14.2 mm thickness and a boron content of 25% to minimize the tool effect.
引用
收藏
页数:12
相关论文
共 50 条
  • [31] Gamma and Neutron Shielding Parameters of Polyester-based composites reinforced with boron and tin nanopowders
    Ogul, H.
    Polat, H.
    Akman, F.
    Kacal, M. R.
    Dilsiz, K.
    Bulut, F.
    Agar, O.
    RADIATION PHYSICS AND CHEMISTRY, 2022, 201
  • [32] High-density concrete: Exploring Ferro boron effects in neutron and gamma radiation shielding
    Roslan, Muhammad Khairi Azri
    Ismail, Mohammad
    Kueh, Ahmad Beng Hong
    Zin, Muhammad Rawi Mohamed
    CONSTRUCTION AND BUILDING MATERIALS, 2019, 215 : 718 - 725
  • [33] Shielding Effect of Boron Carbide Aluminium Metal Matrix Composite against Gamma and Neutron Radiation
    Akkas, A.
    Tugrul, A. B.
    Buyuk, B.
    Addemir, A. O.
    Marsoglu, M.
    Agacan, B.
    ACTA PHYSICA POLONICA A, 2015, 128 (2B) : B176 - B179
  • [34] Modified ultra-high-performance concrete with boron carbide for neutron and gamma radiation shielding
    Ramli, N.
    Rashid, Raizal S. M.
    Nasir, N. A. M.
    Voo, Y. L.
    Azreen, N. M.
    Karim, J. A.
    CONSTRUCTION AND BUILDING MATERIALS, 2025, 467
  • [35] Neutron Shielding Calculation for Barite-Boron-Water
    Al-Obaidi, S.
    Akyildirim, H.
    Gunoglu, K.
    Akkurt, I.
    ACTA PHYSICA POLONICA A, 2020, 137 (04) : 551 - 553
  • [36] Nomex with boron as a neutron shielding in space: Preliminary study
    Loffredo, Filomena
    Vardaci, Emanuele
    Roca, Vincenzo
    Pugliese, Mariagabriella
    NUOVO CIMENTO C-COLLOQUIA AND COMMUNICATIONS IN PHYSICS, 2018, 41 (06):
  • [37] Neutron Shielding Properties of Concrete and Ferro-Boron
    Sariyer, D.
    Kucer, R.
    Kucer, N.
    ACTA PHYSICA POLONICA A, 2015, 128 (2B) : B201 - B202
  • [38] BORON-LOADED EPOXY MATERIAL FOR NEUTRON SHIELDING
    THIBEAULT, SA
    LONG, ER
    GLASGOW, MB
    ORWOLL, RA
    KIEFER, RL
    ABSTRACTS OF PAPERS OF THE AMERICAN CHEMICAL SOCIETY, 1994, 208 : 325 - POLY
  • [39] Neutron shielding characteristics of polymer composites with boron carbide
    Tuncay Tuna
    Aysegul Akdogan Eker
    Erol Kam
    Journal of the Korean Physical Society, 2021, 78 : 566 - 573
  • [40] Neutron shielding characteristics of polymer composites with boron carbide
    Tuna, Tuncay
    Eker, Aysegul Akdogan
    Kam, Erol
    JOURNAL OF THE KOREAN PHYSICAL SOCIETY, 2021, 78 (07) : 566 - 573