Reaction Cross Section Calculations in Neutron Induced Reactions and GEANT4 Simulation of Hadronic Interactions for the Reactor Moderator Material BeO

<span style="line-height: 115%; font-family: 'Cambria',serif; font-size: 11pt; mso-ascii-theme-font: major-latin; mso-fareast-font-family: Calibri; mso-fareast-theme-font: minor-latin; mso-hansi-theme-font: major-latin; mso-bidi-font-family: 'Times New Roman'; mso-bidi-th...

Full description

Bibliographic Details
Main Authors: Veli ÇAPALI, Mert ŞEKERCİ, Hasan ÖZDOĞAN, Abdullah KAPLAN
Format: Article
Language:English
Published: Suleyman Demirel University 2016-05-01
Series:Süleyman Demirel Üniversitesi Fen Bilimleri Enstitüsü Dergisi
Subjects:
Online Access:http://dergipark.ulakbim.gov.tr/sdufenbed/article/view/5000176110
Description
Summary:<span style="line-height: 115%; font-family: 'Cambria',serif; font-size: 11pt; mso-ascii-theme-font: major-latin; mso-fareast-font-family: Calibri; mso-fareast-theme-font: minor-latin; mso-hansi-theme-font: major-latin; mso-bidi-font-family: 'Times New Roman'; mso-bidi-theme-font: minor-bidi; mso-ansi-language: EN-US; mso-fareast-language: EN-US; mso-bidi-language: AR-SA;" lang="EN-US">BeO is one of the most common moderator material for neutron moderation; due to its high density, neutron capture cross section and physical-chemical properties that provides usage at elevated temperatures. As it’s known, for various applications in the field of reactor design and neutron capture, reaction cross–section data are required. The cross–sections of (n,α), (n,2n), (n,t), (n,EL) and (n,TOT) reactions for <sup>9</sup>Be and <sup>16</sup>O nuclei have been calculated by using TALYS 1.6 Two Component Exciton model and EMPIRE 3.2 Exciton model in this study. Hadronic interactions of low energetic neutrons and generated isotopes–particles have been investigated for a situation in which BeO was used as a neutron moderator by using GEANT4, which is a powerful simulation software. In addition, energy deposition along BeO material has been obtained. Results from performed calculations were compared with the experimental nuclear reaction data exist in EXFOR.<br /></span>
ISSN:1308-6529