Theory and Simulation Investigation of Low-Energy Neutron Shielding for Different Boron Compounds

被引:9
作者
Adeli, R. [1 ]
Shirmardi, S. P. [1 ,2 ]
Bagheri, R. [3 ]
机构
[1] NSTRI, Cent Iran Res Complex Yazd, POB 14395-836, Tehran, Iran
[2] NSTRI, Radiat Applicat Res Sch, POB 14395-836, Tehran, Iran
[3] AEOI, NSTRI, Nucl Fuel Cycle Res Sch, POB 14155-1339, Tehran 141551339, Iran
关键词
boron compound; photoneutron reaction; secondary gamma ray; thermal neutron shielding; Monte Carlo calculation; ATTENUATION; MCNP;
D O I
10.1520/JTE20160060
中图分类号
TB3 [工程材料学];
学科分类号
0805 ; 080502 ;
摘要
Neutron absorbers, especially boron, exhibit a comparatively large neutron absorption cross section, in particular, with regard to thermal neutrons. In this study, four boron compounds, including boron carbide (B4C), boron nitride (BN), boron trioxide (B2O3), and boric acid (H3BO3) were considered for shielding the thermal neutrons, both theoretically and in simulation. The shielding ability and secondary gamma-ray production of compounds were studied, using the MCNP-4C Monte Carlo code. The theory shows that B4C has the greatest and B(OH)(3) the least total neutron macroscopic cross section. Simulation results also show that B2O3 and H3BO3 create more high-energy secondary gamma rays that may cause a significant photoneutron reaction, in addition to unwanted dose radiation. Among these, BN and, especially, B4C, create secondary photons with lower energy. From a shielding point of view, we can confirm that B4C and BN in the second order have the best performance when epithermal and, particularly, thermal neutron absorption is concerned. Result shows that H3BO3 has the worst performance among the candidates considered.
引用
收藏
页码:1570 / 1576
页数:7
相关论文
共 22 条
  • [1] Effect of Boron Carbide Filler on the Curing and Mechanical Properties of an Epoxy Resin
    Abenojar, J.
    Martinez, M. A.
    Velasco, F.
    Pascual-Sanchez, V.
    Martin-Martinez, J. M.
    [J]. JOURNAL OF ADHESION, 2009, 85 (4-5) : 216 - 238
  • [2] Aleinikov V. E., 2002, METHODS PHYS RES A, V476, P378
  • [3] Amiri J., 2014, J PARAMED SCI, V5, P2008
  • [4] Booth T.E., 1985, LA-10363-MS
  • [5] BRIESMEISTER JF, 2000, RSICC COMPUTER CODE
  • [6] Calculations of neutron shielding data for 10-100 MeV proton accelerators
    Chen, CC
    Sheu, RJ
    Jiang, SH
    [J]. RADIATION PROTECTION DOSIMETRY, 2005, 116 (1-4) : 245 - 251
  • [7] Chilton A. B., 1984, PRINCIPLES RAD SHIEL, P493
  • [8] Generation of shielding data for neutron radiation produced by heavy ions
    Fehrenbacher, Georg
    Radon, Torsten
    [J]. RADIATION MEASUREMENTS, 2010, 45 (10) : 1529 - 1531
  • [9] Glasstone S., 1994, Nuclear Reactor Engineering: Reactor Systems Engineering, V4th
  • [10] Polyethylene/boron nitride composites for space radiation shielding
    Harrison, Courtney
    Weaver, Sean
    Bertelsen, Craig
    Burgett, Eric
    Hertel, Nolan
    Grulke, Eric
    [J]. JOURNAL OF APPLIED POLYMER SCIENCE, 2008, 109 (04) : 2529 - 2538