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

^*Corresponding author for this work

Energy Institute

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

10 Citations (Scopus)

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
Publication status	Published - 1 May 2015

Bibliographical note

Publisher Copyright:
© 2015 Elsevier Ltd.

Funding

This research was supported by grants from the Turkish National Boron Research Institute ( BOREN-2011-Ç0289 ).

Funders	Funder number
Turkish National Boron Research Institute	BOREN-2011-Ç0289

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

Cite this

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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.",

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AU - Akan, Zafer

AU - Türkmen, Mehmet

AU - Çakir, Tahir

AU - Reyhancan, Iskender A.

AU - Çolak, Üner

AU - Okka, Muhittin

AU - Kiziltaş, Sahip

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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

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ER -

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

Abstract

Bibliographical note

Funding

Keywords

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