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

Applied Radiation and Isotopes

Volumn 70, Issue 1, 2012, Pages 341-345

  Korkut, Turgay ^a   Karabulut, Abdulhalik ^b,e   Budak, Gökhan ^b   Aygün, Bünyamin ^b   Gencel, Osman ^c   Hançerlioĝullari, Aybaba ^d  

^a AGRI IBRAHIM CECEN UNIVERSITY   (Turkey)

^b ATATÜRK UNIVERSITY   (Turkey)

^c BARTIN UNIVERSITY   (Turkey)

^d KASTAMONU UNIVERSITY   (Turkey)

^e ERZURUM TECHNICAL UNIVERSITY   (Turkey)

Author keywords

Boron ores; FLUKA Monte Carlo code; HVL; Neutron shielding; Total macroscopic cross section

Indexed keywords

ATOMS; BORATE MINERALS; BORON; INTELLIGENT SYSTEMS; NEUTRONS; ORES; RADIATION SHIELDING;

ABSORBED DOSE; BORON ATOM; DEPOSITED ENERGY; LOW-ENERGY NEUTRONS; MONTE CARLO CODES; NEUTRON SHIELDING; PER UNIT VOLUME; TOTAL MACROSCOPIC CROSS SECTION;

MONTE CARLO METHODS;

AMERICIUM 241; BERYLLIUM; BORON; COLEMANITE; MINERAL; PARAFFIN; TINCAL; ULEXITE; UNCLASSIFIED DRUG;

ALPHA RADIATION; ARTICLE; CONTROLLED STUDY; GAMMA RADIATION; GEOMETRY; IONIZING RADIATION; MONTE CARLO METHOD; NEUTRON; NEUTRON RADIATION; PRIORITY JOURNAL; RADIATION DOSE; RADIATION ENERGY; RADIATION SHIELD;

EID: 81755173513     PISSN: 09698043     EISSN: 18729800     Source Type: Journal    
DOI: 10.1016/j.apradiso.2011.09.006     Document Type: Article

References (25)

1. Abdo A.E. Calculation of the cross sections for fast neutrons and gamma rays in concrete shields. Ann. Nucl. Eng. 2002, 29:1977-1988.
2. Adib M., Habib N., Fathaalla M. Neutron transmission through pyrolytic graphite crystals. Ann. Nucl. Eng. 2007, 33(7):627-632.
3. Agosteo S., Magistris M., Mereghetti A., Silari M., Zajacova Z. Shielding data for 100-250MeV proton accelerators: double differential neutron distributions and attenuation in concrete. Nucl. Instrum. Methods Phys. Res. B 2007, 265:581-598.
4. Bashter I.I., Makarious A.S., Abdo A.E. Investigation of hematite-serpentine and ilmenite-limonite concretes for reactor radiation shielding. Ann. Nucl. Eng. 1996, 23(1):65-71.
5. BaŞtürk M., Arztmann J., Jerlich W., Kardjilov N., Lehmann E., Zawisky M. Analysis of neutron attenuation in boron-alloyed stainless steel with neutron radiography and JEN-3 gauge. J. Nucl. Mater. 2005, 341:189-200.
6. Boncukçuoĝlu R., Içelli O., Erzeneoĝlu S., Kocakerim M.M. Comprasion of radioactive transmission and mechanical properties of Portland cement and modified cement with trommel sieve waste. Cem. Concr. Res. 2005, 35:1082-1087.
7. Csi;kai, J., Elagib, I., Buczko, Cs.M., 1999. Studies on the Neutron Reflection, Scattering and Transmission Methods Used for Bulk Hydrogen Analysis. Progress Report on IAEA CRP on Bulk Hydrogen Analysis using Neutrons.
8. Czubek J.A., Drozdowicz K., Gabanska B., Igielski A., Krynicka E., Woźnicka U. Thermal neutron macroscopic absorption cross section measurement applied for geophysics. Prog. Nucl. Energy 1996, 30-3:295-303.
9. Demir F. Determination of mass attenuation coefficients of some boron ores at 59.54keV by using scintillation detector. Appl. Radiat. Isot. 2010, 68(1):175-179.
10. Desdin L., Ceballos C. Neutron reflection method fort he fast estimation of neutron removal cross section in hydrogenous materials. J. Radioanal. Nucl. Chem. 2000, 243(3):835-837.
11. El-Khayatt A.M. Calculation of fast neutron removal cross-sections for some compounds and materials. Ann. Nucl. Energy 2010, 37-2:218-222.
12. Ferrari, A., Sala, P.R., Fasso, A., Ranft, J., 2005. FLUKA: a multi-particle transport code. CERN-2005-10 INFN/TC 05/11, SLAC-R-773.
13. Hayashi T., Tobita K., Nakamori Y., Orimo S. Advanced neutron shielding material using zirconium borohydride and zirconium hydride. J. Nucl. Mater. 2009, 386-388:121-199.
14. Içelli O., Erzeneoĝlu S., Boncukçuoĝlu R. Measurement of X-ray transmission factors of some boron compounds. Radiat. Meas. 2003, 37:613-616.
15. Karabulut A., Budak G. Radioisotope X-ray fluorescence analysis of some elements in colemanite ore. Spectrochim. Acta B: Atom. Spectrosc. 2000, 55:91-95.
16. Kase K.R., Nelson W.R., Fasso A., Liu J.C., Mao X., Jenkins T.M., Kleck J.H. Measurements of accelerator-produced leakage neutron and photon transmission through concrete. Health Phys. 2003, 84:180-187.
17. 4 . J. Radioanal. Nucl. Chem. 2010, 286:61-65.
18. Korkut T., Ün A., Demir F., Karabulut A., Budak G., şahin R., Oltulu M. Neutron dose transmission measurements for several new concrete samples including colemanite. Ann. Nucl. Energy 2010, 37:996-998.
19. Maiti M., Nandy M., Roy S.N., Sarkar P.K. Flux and dose transmission through concrete of neutrons from proton induced reactions on various target elements. Nucl. Instrum. Methods Phys. Res. B: Beam Interact. Mater. Atoms 2004, 226(4):585-594.
20. Mark S., Khomchenkoa S., Shifrin M., Haviv Y., Schwartz J.R., Orion I. TVF-NMCRC-a powerful program for writing and executing simulation inputs for the FLUKA Monte Carlo Code system. Nucl. Instrum. Methods Phys. Res. A 2007, 572:929-934.
21. Mollah A.S., Ahmad G.U., Husain S.R. Measurements of neutron shielding properties of heavy concretes using a Cf-252 source. Nucl. Eng. Des. 1992, 135(3):321-325.
22. Okuno K. Neutron shielding material based on colemanite and epoxy resin. Radiat. Prot. Dosim. 2005, 115(1-4):258-261.
23. Tschirf E. Concrete as a shielding material against x-rays, gamma and Neutron. Zement-und-Beton 1976, 21(5):240-244.
24. Woznicka U. Thermal neutron absorption cross section and clay mineral content for Miocene Carpathian samples. Appl. Radiat. Isot. 2000, (53-6):1023-1030.
25. Yousif Ali M., El-Megrab A.M., Jonah S.A., Daw May Su, Varadi M., Csikai J. Investigations of neutron fields used in elemental analysis of bulk samples. Nucl. Geophys. 1995, 9(3):203-217.