Modification of the radial beam port of ITU TRIGA Mark II research reactor for BNCT applications

Zafer Akan; Mehmet Türkmen; Tahir Çakir; Iskender A. Reyhancan; Üner Çolak; Muhittin Okka; Sahip Kiziltaş

doi:10.1016/j.apradiso.2015.02.014

Modification of the radial beam port of ITU TRIGA Mark II research reactor for BNCT applications

Zafer Akan
, Mehmet Türkmen
, Tahir Çakir
, Iskender A. Reyhancan
, Üner Çolak
, Muhittin Okka
, Sahip Kiziltaş

Nuclear Reactor Technology

Research output: Contribution to journal › Article › peer-review

12 Scopus citations

Abstract

This paper aims to describe the modification of the radial beam port of ITU (Istanbul Technical University) TRIGA Mark II research reactor for BNCT applications. Radial beam port is modified with Polyethylene and Cerrobend collimators. Neutron flux values are measured by neutron activation analysis (Au-Cd foils). Experimental results are verified with Monte Carlo results. The results of neutron/photon spectrum, thermal/epithermal neutron flux, fast group photon fluence and change of the neutron fluxes with the beam port length are presented.

Original language	English
Pages (from-to)	110-116
Number of pages	7
Journal	Applied Radiation and Isotopes
Volume	99
DOIs	https://doi.org/10.1016/j.apradiso.2015.02.014
State	Published - May 1 2015

Keywords

BNCT
ITU TRIGA Mark II
Monte-Carlo simulation
PE and Cerrobend collimator
Radial beam port

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10.1016/j.apradiso.2015.02.014

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title = "Modification of the radial beam port of ITU TRIGA Mark II research reactor for BNCT applications",

abstract = "This paper aims to describe the modification of the radial beam port of ITU (Istanbul Technical University) TRIGA Mark II research reactor for BNCT applications. Radial beam port is modified with Polyethylene and Cerrobend collimators. Neutron flux values are measured by neutron activation analysis (Au-Cd foils). Experimental results are verified with Monte Carlo results. The results of neutron/photon spectrum, thermal/epithermal neutron flux, fast group photon fluence and change of the neutron fluxes with the beam port length are presented.",

keywords = "BNCT, ITU TRIGA Mark II, Monte-Carlo simulation, PE and Cerrobend collimator, Radial beam port",

author = "Zafer Akan and Mehmet T{\"u}rkmen and Tahir {\c C}akir and Reyhancan, \{Iskender A.\} and {\"U}ner {\c C}olak and Muhittin Okka and Sahip Kizilta{\c s}",

note = "Funding Information: This research was supported by grants from the Turkish National Boron Research Institute ( BOREN-2011-{\c C}0289 ). Publisher Copyright: {\textcopyright} 2015 Elsevier Ltd.",

year = "2015",

month = may,

day = "1",

doi = "10.1016/j.apradiso.2015.02.014",

language = "English",

volume = "99",

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journal = "Applied Radiation and Isotopes",

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T1 - Modification of the radial beam port of ITU TRIGA Mark II research reactor for BNCT applications

AU - Akan, Zafer

AU - Türkmen, Mehmet

AU - Çakir, Tahir

AU - Reyhancan, Iskender A.

AU - Çolak, Üner

AU - Okka, Muhittin

AU - Kiziltaş, Sahip

PY - 2015/5/1

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N2 - This paper aims to describe the modification of the radial beam port of ITU (Istanbul Technical University) TRIGA Mark II research reactor for BNCT applications. Radial beam port is modified with Polyethylene and Cerrobend collimators. Neutron flux values are measured by neutron activation analysis (Au-Cd foils). Experimental results are verified with Monte Carlo results. The results of neutron/photon spectrum, thermal/epithermal neutron flux, fast group photon fluence and change of the neutron fluxes with the beam port length are presented.

AB - This paper aims to describe the modification of the radial beam port of ITU (Istanbul Technical University) TRIGA Mark II research reactor for BNCT applications. Radial beam port is modified with Polyethylene and Cerrobend collimators. Neutron flux values are measured by neutron activation analysis (Au-Cd foils). Experimental results are verified with Monte Carlo results. The results of neutron/photon spectrum, thermal/epithermal neutron flux, fast group photon fluence and change of the neutron fluxes with the beam port length are presented.

KW - BNCT

KW - ITU TRIGA Mark II

KW - Monte-Carlo simulation

KW - PE and Cerrobend collimator

KW - Radial beam port

UR - https://www.scopus.com/pages/publications/84924147525

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SN - 0969-8043

VL - 99

SP - 110

EP - 116

JO - Applied Radiation and Isotopes

JF - Applied Radiation and Isotopes

ER -

Modification of the radial beam port of ITU TRIGA Mark II research reactor for BNCT applications

Abstract

Keywords

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