Neutron reflector analysis for the beam-port of the Missouri S&T Reactor

Tayfun Akyurek; Warren S. Vaz; Ayodeji B. Alajo; Jeffrey C. King; Shoaib Usman; Carlos H.C. Giraldo

doi:10.1007/s10967-019-06752-x

Neutron reflector analysis for the beam-port of the Missouri S&T Reactor

Tayfun Akyurek^*, Warren S. Vaz, Ayodeji B. Alajo, Jeffrey C. King, Shoaib Usman, Carlos H.C. Giraldo

^*Bu çalışma için yazışmadan sorumlu yazar

Araştırma sonucu: ???type-name??? › Makale › bilirkişi

1 Atıf (Scopus)

Özet

A preliminary neutron reflector material selection and feasibility study of an inexpensive reflector replacement for the neutron beam-port at the 200 kW Missouri University of Science and Technology Research Reactor (MSTR) was conducted using Monte-Carlo techniques. The Monte-Carlo N-Particle transport code (MCNP6.1) was used to model the neutron beam-port of the Missouri S&T Reactor in order to study the effects of adding different reflector materials, in terms of the neutron flux reaching the radiography/tomography facility in front of MSTR’s neutron beam-port. Aluminum, beryllium, titanium, nickel, nickel-58, lead, bismuth, tungsten and stainless steel reflectors were modeled to find the best neutron reflector for the beam-port. After examining reflector materials, it was concluded that none of them were an improvement over the current design. Experimental thermal flux was measured to be 1.0 × 10⁷ ± 3.16 × 10³ cm⁻² s⁻¹ at the exit of beam port for current version of beam-port. The current ratio of beam port inlet and outlet obtained from simulations was found to be 3.37 × 10⁴. The flux of beam port inlet was determined on the order of 1.0 × 10¹¹ cm⁻² s⁻¹ which is consistent with previous findings.

Orijinal dil	İngilizce
Sayfa (başlangıç-bitiş)	975-981
Sayfa sayısı	7
Dergi	Journal of Radioanalytical and Nuclear Chemistry
Hacim	322
Basın numarası	2
DOI'lar	https://doi.org/10.1007/s10967-019-06752-x
Yayın durumu	Yayınlandı - 1 Kas 2019
Harici olarak yayınlandı	Evet

Bibliyografik not

Publisher Copyright:
© 2019, Akadémiai Kiadó, Budapest, Hungary.

Finansman

The authors wish to thank the reactor staff for providing the beam-port blueprints and other reactor related information for the preparation of this article. This study was supported by Marmara University, Scientific Research Commission (BAPKO) under the research Project FEN-A-131016-0466. The corresponding author would also like to express his appreciation to Dr. Ozgur Delice for the fruitful discussions. The authors wish to thank the reactor staff for providing the beam-port blueprints and other reactor related information for the preparation of this article. This study was supported by Marmara University, Scientific Research Commission (BAPKO) under the research Project FEN-A-131016-0466. The corresponding author would also like to express his appreciation to Dr. Ozgur Delice for the fruitful discussions.

Finansörler	Finansör numarası
BAPKO
Marmara Üniversitesi	FEN-A-131016-0466
UGC-DAE Consortium for Scientific Research, University Grants Commission

Belgeye Erişim

10.1007/s10967-019-06752-x

Diğer Dosyalar ve Linkler

Link to publication in Scopus

Alıntı Yap

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title = "Neutron reflector analysis for the beam-port of the Missouri S&T Reactor",

abstract = "A preliminary neutron reflector material selection and feasibility study of an inexpensive reflector replacement for the neutron beam-port at the 200 kW Missouri University of Science and Technology Research Reactor (MSTR) was conducted using Monte-Carlo techniques. The Monte-Carlo N-Particle transport code (MCNP6.1) was used to model the neutron beam-port of the Missouri S&T Reactor in order to study the effects of adding different reflector materials, in terms of the neutron flux reaching the radiography/tomography facility in front of MSTR{\textquoteright}s neutron beam-port. Aluminum, beryllium, titanium, nickel, nickel-58, lead, bismuth, tungsten and stainless steel reflectors were modeled to find the best neutron reflector for the beam-port. After examining reflector materials, it was concluded that none of them were an improvement over the current design. Experimental thermal flux was measured to be 1.0 × 107 ± 3.16 × 103 cm−2 s−1 at the exit of beam port for current version of beam-port. The current ratio of beam port inlet and outlet obtained from simulations was found to be 3.37 × 104. The flux of beam port inlet was determined on the order of 1.0 × 1011 cm−2 s−1 which is consistent with previous findings.",

keywords = "Inexpensive neutron reflector, Monte Carlo N-Particle (MCNP), Neutron beam-port",

author = "Tayfun Akyurek and Vaz, {Warren S.} and Alajo, {Ayodeji B.} and King, {Jeffrey C.} and Shoaib Usman and Giraldo, {Carlos H.C.}",

note = "Publisher Copyright: {\textcopyright} 2019, Akad{\'e}miai Kiad{\'o}, Budapest, Hungary.",

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doi = "10.1007/s10967-019-06752-x",

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AU - Usman, Shoaib

AU - Giraldo, Carlos H.C.

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Neutron reflector analysis for the beam-port of the Missouri S&T Reactor

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Finansman

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