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Author(s): El-Khayatt AM (El-Khayatt, A. M.)
Title: NXcom - A program for calculating attenuation coefficients of fast neutrons and gamma-rays
Source: ANNALS OF NUCLEAR ENERGY 38 (1): 128-132
Date: 2011 JAN
Document Type: Journal : Article
DOI: 10.1016/j.anucene.2010.08.003
Language: English
Comment:
Address: Atom Energy Author, Nucl Res Ctr, Atom Reactors Div, Reactor Phys Dept, Cairo, Egypt.
Reprint: El-Khayatt, AM (reprint author), Atom Energy Author, Nucl Res Ctr, Atom Reactors Div, Reactor Phys Dept, PO 13759, Cairo, Egypt
E-mail:
Author Keywords: Removal cross sections; Attenuation coefficients; Computer program;
Shielding materials
KeyWords Plus:
Abstract: This work is concerned with a construction and use of NXcom computer program for calculating the removal and attenuation coefficients of transmitted fast neutrons and gamma-rays respectively through mixtures composites concretes and compounds The program uses only one input data file for neutrons and gamma-rays calculations For gamma-ray attenuation the program predictions were tested by comparing them with the well-known WinXcom program results and an excellent agreement was noticed Also it has been used for calculating the values of macroscopic effective removal cross-sections Sigma(R) (cm(-1)) for five new published polyamide and anhydride composites designed for shielding mixed neutron and gamma-rays The obtained values for Sigma(R) using the program and the reported attenuation thicknesses which were based on the Monte Carlo N-Particle (MCNP) code showed the same trend The NXcom program can be used as a preliminary effective tool for testing the shielding material against fast neutrons and gamma-rays (C) 2010 Elsevier Ltd All rights reserved
Cited References: El-Khayatt AM, 2010, ANN NUCL ENERGY, V37, P991, DOI 10.1016/j.anucene.2010.03.001 El-Khayatt AM, 2010, ANN NUCL ENERGY, V37, P218, DOI 10.1016/j.anucene.2009.10.022 Kurudirek M, 2009, RADIAT PHYS CHEM, V78, P751, DOI 10.1016/j.radphyschem.2009.03.070 El-Khayatt AM, 2009, ANN NUCL ENERGY, V36, P832, DOI 10.1016/j.anucene.2009.01.013 Hu HS, 2008, IEEE T NUCL SCI, V55, P2376, DOI 10.1109/TNS.2008.2000800 Jalali M, 2008, RADIAT PHYS CHEM, V77, P523, DOI 10.1016/j.radphyschem.2007.12.014 Wieser ME, 2006, PURE APPL CHEM, V78, P2051, DOI 10.1351/pac200678112051 Gerward L, 2004, RADIAT PHYS CHEM, V71, P653, DOI 10.1016/j.radphyschem.2004.04.040 Gerward L, 2001, RADIAT PHYS CHEM, V60, P23 MARTIN JE, 2000, PHYS RAD PROTECTION KAPLAN MF, 1989, CONCRETE RAD SHIELDI BERGER MJ, 1987, NBSIR, V87, P3597 GLASSTONE S, 1986, NUCL REACTOR ENG CHILTON AB, 1984, PRINCIPLES RAD SHIEL WOOD J, 1982, COMPUTATIONAL METHOD PROFIO AE, 1979, RAD SHIELDING DOSIME *NCRP, 1971, 38 NCRP GOLDSTEIN H, 1959, FUNDAMENTAL ASPECTS *NCRP, 1957, NBS HDB, V63 |