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

^*Bu çalışma için yazışmadan sorumlu yazar

Enerji Enstitüsü

Manisa Celal Bayar University
Hacettepe University
Yuzuncu Yil University
Istanbul Technical University

Araştırma sonucu: Dergiye katkı › Makale › bilirkişi

11 Atıf (Scopus)

Özet

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.

Orijinal dil	İngilizce
Sayfa (başlangıç-bitiş)	110-116
Sayfa sayısı	7
Dergi	Applied Radiation and Isotopes
Hacim	99
DOI'lar	https://doi.org/10.1016/j.apradiso.2015.02.014
Yayın durumu	Yayınlandı - 1 May 2015

Bibliyografik not

Publisher Copyright:
© 2015 Elsevier Ltd.

Finansman

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

Finansörler	Finansör numarası
Turkish National Boron Research Institute	BOREN-2011-Ç0289

Belgeye Erişim

10.1016/j.apradiso.2015.02.014

Diğer Dosyalar ve Linkler

Link to publication in Scopus

Alıntı Yap

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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 = "Publisher Copyright: {\textcopyright} 2015 Elsevier Ltd.",

year = "2015",

month = may,

day = "1",

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

language = "English",

volume = "99",

pages = "110--116",

journal = "Applied Radiation and Isotopes",

issn = "0969-8043",

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TY - JOUR

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

Y1 - 2015/5/1

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

U2 - 10.1016/j.apradiso.2015.02.014

DO - 10.1016/j.apradiso.2015.02.014

M3 - Article

C2 - 25746919

AN - SCOPUS:84924147525

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

Özet

Bibliyografik not

Finansman

Belgeye Erişim

Diğer Dosyalar ve Linkler

Parmak izi

Alıntı Yap