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

^*Corresponding author for this work

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

2 Citations (Scopus)

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’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.

Original language	English
Pages (from-to)	975-981
Number of pages	7
Journal	Journal of Radioanalytical and Nuclear Chemistry
Volume	322
Issue number	2
DOIs	https://doi.org/10.1007/s10967-019-06752-x
Publication status	Published - 1 Nov 2019
Externally published	Yes

Bibliographical note

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

Funding

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.

Funders	Funder number
BAPKO
Marmara Üniversitesi	FEN-A-131016-0466
UGC-DAE Consortium for Scientific Research, University Grants Commission

Keywords

Inexpensive neutron reflector
Monte Carlo N-Particle (MCNP)
Neutron beam-port

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Cite this

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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",

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

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AU - Giraldo, Carlos H.C.

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AB - 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.

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

Abstract

Bibliographical note

Funding

Keywords

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