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Published: 2017-06-30
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DOI: https://doi.org/10.53747/jnst.v7i2.107
Issue
Vol. 7 No. 2 (2017)
Section
Articles
How to Cite
Tran, N. T., Chu, V. L., Bui, D. K., Nguyen, D. K., & Nguyen, . D. T. (2017). Characterization of an ²⁴¹Am-Be neutron irradiation facility at Institute for Nuclear Science and Technology. Nuclear Science and Technology, 7(2), 16-24. https://doi.org/10.53747/jnst.v7i2.107

Characterization of an ²⁴¹Am-Be neutron irradiation facility at Institute for Nuclear Science and Technology

Tran Ngoc Toan1, Chu Vu Long2, Bui Duc Ky2, Nguyen Duc Kien3, Nguyen Duc Tam3
1 Vietnam Atomic Energy Institute, 59 Ly Thuong Kiet, Hanoi, Vietnam
2 Institute for Nuclear Science and Technology, 179 Hoang Quoc Viet, Hanoi, Vietnam
3 Hanoi University of Natural Science, Nguyen Trai, Hanoi, Vietnam

Main Article Content

Abstract

An automated panoramic irradiator with a 241Am-Be neutron source of 5 Ci is installed in a bunker-type medium room at the Institute for Nuclear Science and Technology (INST) for calibration of neutron devices. Bonner Sphere Spectrometer (BSS) formed by 6 spheres plus bare detector, with cylindrical, almost point like, 6LiI(Eu) scintillator and 2 different spectral unfolding FRUIT and BUNKIUT codes are used to characterize the neutron field in different measurement points along the irradiation bench. The neutron field is also simulated by MCNP5 software and compared with measurements performed by the BSS. The paper shows the main results obtained in terms of neutron spectra at fixed distances from the source as well as their neutron fluence rate (total and direct) and ambient dose equivalent rate. These values measured by the BSS with two unfolding FRUIT and BUNKIUT codes are in good agreement with that of simulated by MCNP5 within 10%.

Article Details

Keywords

Bonner Sphere Spectrometer, unfolding code, neutron fluence rate, neutron ambient dose rate

References

[1] ISO – 8529-2, Reference neutron radiations - Part 2: Calibration fundamentals of radiation protection devices related to the basic quantities characterizing the radiation field, 2000.
[2] MCNP5-X-5 Monte Carlo Team, MCNP-A General Monte Carlo N-Particle Transport Code, Version 5, Los Alamos National Laboratory Report LA-UR-03-1987, 2003.
[3] J. McConn Jr., C. J. Gesh, R. T. Pagh, R. A. Rucker, R. G. Williams III, Compendium of Material Composition Data for Radiation Transport Modeling. p.375, Pacific North West National Laboratory, Washington, 2011.
[4] Oak Ridge National Laboratory, RSICC Computer Code Collection MCNP4C2, USA, 2000.
[5] International Atomic Energy Agency, Compendium of neutron Spectra and detector response for radiation protection purpose, Technical reports series No. 403, IAEA, Vienna, 2001.
[6] Rose, P.F., “ENDF/B-VI Summary Documentation”, report BNL-NCS-17541 (ENDF-201), 4th Edition, 1991.
[7] ICRP, Conversion coefficients for use in radiological protection against external radiation. ICRP Publication 74. Ann. ICRP 26(3/4), 1996.
[8] J.J. Doroshenko, S.N. Kraitor, T.V. Kuznetsova, K.K. Kushnereva, E.S. Leonov, Nucl. Technol. 33 296, 1997.
[9] K.A. Lowry, T.L. Johnson, Modification to iterative recursion unfolding algorithms and computer codes to find more appropriate neutron spectra, Naval Research Laboratory, NRL Memorandum Report 5340, Washington, DC, 1984.
[10] Vega-Carrillo, H.R., Ortiz-Rodríguez J.M. Martínez-Blanco M.R, NSDUAZ unfolding package for neutron spectrometry and dosimetry with Bonner spheres. The XII International Symposium/XXII National Congress on Solid State Dosimetry, September 5th to 9th, 2011. Mexico city, 2011.
[11] Bedogni,. R., Domingo, C., Esposito, A., Fernández, F, FRUIT: an operational tool for multisphere neutron spectrometry in workplaces. Nucl. Instr. and Meth. A 580, 1301-1309, 2007.