Neutron flux characterization of the beam port of the Missouri University of Science and Technology Reactor

Mubarak Albarqi; Raed Alsulami; Tayfun Akyurek; Joseph Graham

doi:10.1007/s10967-019-06561-2

Neutron flux characterization of the beam port of the Missouri University of Science and Technology Reactor

Mubarak Albarqi, Raed Alsulami, Tayfun Akyurek, Joseph Graham^*

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8 Atıf (Scopus)

Özet

Neutron activation analysis was used to determine the thermal and epithermal neutron flux and its spatial distribution at the beam port of the Missouri University of Science and Technology Research Reactor. Gold foil irradiations were conducted and the determined flux was compared to Monte Carlo radiation transport predictions using the Monte Carlo N-particle code. The average experimental thermal (E < 0.55 eV) and epithermal (0.55 eV < E < 100 keV) fluxes were (5.7 ± 0.3) × 10⁶ cm⁻² s⁻¹ and (7.3 ± 0.3) × 10⁵ cm⁻² s⁻¹, respectively and were found to be in good qualitative agreement with the MCNP simulations.

Orijinal dil	İngilizce
Sayfa (başlangıç-bitiş)	109-116
Sayfa sayısı	8
Dergi	Journal of Radioanalytical and Nuclear Chemistry
Hacim	321
Basın numarası	1
DOI'lar	https://doi.org/10.1007/s10967-019-06561-2
Yayın durumu	Yayınlandı - 15 Tem 2019
Harici olarak yayınlandı	Evet

Bibliyografik not

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

Belgeye Erişim

10.1007/s10967-019-06561-2

Diğer Dosyalar ve Linkler

Link to publication in Scopus

Alıntı Yap

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title = "Neutron flux characterization of the beam port of the Missouri University of Science and Technology Reactor",

abstract = "Neutron activation analysis was used to determine the thermal and epithermal neutron flux and its spatial distribution at the beam port of the Missouri University of Science and Technology Research Reactor. Gold foil irradiations were conducted and the determined flux was compared to Monte Carlo radiation transport predictions using the Monte Carlo N-particle code. The average experimental thermal (E < 0.55 eV) and epithermal (0.55 eV < E < 100 keV) fluxes were (5.7 ± 0.3) × 106 cm−2 s−1 and (7.3 ± 0.3) × 105 cm−2 s−1, respectively and were found to be in good qualitative agreement with the MCNP simulations.",

keywords = "Beam port, Foil activation, MCNP, Monte Carlo, Neutron activation analysis, Neutron flux characterization",

author = "Mubarak Albarqi and Raed Alsulami and Tayfun Akyurek and Joseph Graham",

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

year = "2019",

month = jul,

day = "15",

doi = "10.1007/s10967-019-06561-2",

language = "English",

volume = "321",

pages = "109--116",

journal = "Journal of Radioanalytical and Nuclear Chemistry",

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TY - JOUR

T1 - Neutron flux characterization of the beam port of the Missouri University of Science and Technology Reactor

AU - Albarqi, Mubarak

AU - Alsulami, Raed

AU - Akyurek, Tayfun

AU - Graham, Joseph

PY - 2019/7/15

Y1 - 2019/7/15

N2 - Neutron activation analysis was used to determine the thermal and epithermal neutron flux and its spatial distribution at the beam port of the Missouri University of Science and Technology Research Reactor. Gold foil irradiations were conducted and the determined flux was compared to Monte Carlo radiation transport predictions using the Monte Carlo N-particle code. The average experimental thermal (E < 0.55 eV) and epithermal (0.55 eV < E < 100 keV) fluxes were (5.7 ± 0.3) × 106 cm−2 s−1 and (7.3 ± 0.3) × 105 cm−2 s−1, respectively and were found to be in good qualitative agreement with the MCNP simulations.

AB - Neutron activation analysis was used to determine the thermal and epithermal neutron flux and its spatial distribution at the beam port of the Missouri University of Science and Technology Research Reactor. Gold foil irradiations were conducted and the determined flux was compared to Monte Carlo radiation transport predictions using the Monte Carlo N-particle code. The average experimental thermal (E < 0.55 eV) and epithermal (0.55 eV < E < 100 keV) fluxes were (5.7 ± 0.3) × 106 cm−2 s−1 and (7.3 ± 0.3) × 105 cm−2 s−1, respectively and were found to be in good qualitative agreement with the MCNP simulations.

KW - Beam port

KW - Foil activation

KW - MCNP

KW - Monte Carlo

KW - Neutron activation analysis

KW - Neutron flux characterization

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U2 - 10.1007/s10967-019-06561-2

DO - 10.1007/s10967-019-06561-2

M3 - Article

AN - SCOPUS:85067381875

SN - 0236-5731

VL - 321

SP - 109

EP - 116

JO - Journal of Radioanalytical and Nuclear Chemistry

JF - Journal of Radioanalytical and Nuclear Chemistry

IS - 1

ER -

Neutron flux characterization of the beam port of the Missouri University of Science and Technology Reactor

Özet

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Belgeye Erişim

Diğer Dosyalar ve Linkler

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