Investigation of neutron shielding properties depending on number of boron atoms for colemanite, ulexite and tincal ores by experiments and FLUKA Monte Carlo simulations

被引:75
作者
Korkut, Turgay [1 ]
Karabulut, Abdulhalik [2 ,5 ]
Budak, Gokhan [2 ]
Aygun, Bunyamin [2 ]
Gencel, Osman [3 ]
Hancerliogullari, Aybaba [4 ]
机构
[1] Ibrahim Cecen Univ Agri, Dept Phys, Fac Sci & Art, Agri, Turkey
[2] Ataturk Univ, Dept Phys, Fac Sci, Erzurum, Turkey
[3] Bartin Univ, Fac Engn, Dept Civil Engn, Bartin, Turkey
[4] Kastamonu Univ, Fac Sci & Art, Dept Phys, TR-37100 Kastamonu, Turkey
[5] Erzurum Tech Univ, Erzurum, Turkey
关键词
Boron ores; Neutron shielding; Total macroscopic cross section; FLUKA Monte Carlo code; HVL; DOSE TRANSMISSION; CROSS-SECTIONS; CONCRETE; ATTENUATION;
D O I
10.1016/j.apradiso.2011.09.006
中图分类号
O61 [无机化学];
学科分类号
070301 ; 081704 ;
摘要
Am-241-Be source and three samples including different amounts of boron atoms per unit volume called colemanite, ulexite and tincal were used in total macroscopic cross section experiments. Also FLUKA Monte Carlo code was used to simulate total macroscopic cross sections, absorbed doses and deposited energies by low energy neutron interactions. Besides half value layers of samples were calculated and compared to paraffin. As a result, ascending concentration of boron atoms can enhance neutron shielding property of samples. (C) 2011 Elsevier Ltd. All rights reserved.
引用
收藏
页码:341 / 345
页数:5
相关论文
共 25 条
[1]   Calculation of the cross-sections for fast neutrons and gamma-rays in concrete shields [J].
Abdo, AES .
ANNALS OF NUCLEAR ENERGY, 2002, 29 (16) :1977-1988
[2]   Neutron transmission through pyrolytic graphite crystals [J].
Adib, M. ;
Habib, N. ;
Fathaalla, M. .
ANNALS OF NUCLEAR ENERGY, 2006, 33 (07) :627-632
[3]   Shielding data for 100-250 MeV proton accelerators: Double differential neutron distributions and attenuation in concrete [J].
Agosteo, S. ;
Magistris, M. ;
Mereghetti, A. ;
Silari, M. ;
Zajacova, Z. .
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 2007, 265 (02) :581-598
[4]  
ALI MY, 1995, NUCL GEOPHYS, V9, P203
[5]   Investigation of hematite-serpentine and ilmenite-limonite concretes for reactor radiation shielding [J].
Bashter, II ;
Makarious, AS ;
Abdo, AES .
ANNALS OF NUCLEAR ENERGY, 1996, 23 (01) :65-71
[6]   Analysis of neutron attenuation in boron-alloyed stainless steel with neutron radiography and JEN-3 gauge [J].
Bastürk, M ;
Arztmann, J ;
Jerlich, W ;
Kardjilov, N ;
Lehmann, E ;
Zawisky, M .
JOURNAL OF NUCLEAR MATERIALS, 2005, 341 (2-3) :189-200
[7]   Comparison of radioactive transmission and mechanical properties of Portland cement and a modified cement with trommel sieve waste [J].
Boncukcuglu, R ;
Içelli, O ;
Erzeneoglu, S ;
Kocakerim, MM .
CEMENT AND CONCRETE RESEARCH, 2005, 35 (06) :1082-1087
[8]  
CSIKAI J, 1999, STUDIES NEUTRON REFL
[9]  
Czubek J. A., 1996, Progress in Nuclear Energy, V30, P295, DOI 10.1016/0149-1970(95)00091-7