World Journal of Nuclear Science and Technology

World Journal of Nuclear Science and Technology

ISSN Print: 2161-6795
ISSN Online: 2161-6809
www.scirp.org/journal/wjnst
E-mail: wjnst@scirp.org
"Determination of Neutron Fluxes and Spectrum Shaping Factors in Irradiation Sites of Ghana’S Miniature Neutron Source Reactor (mnsr) by Activation Method After Compensation of Loss of Excess Reactivty"
written by R.B.M. Sogbadji, B.J.B. Nyarko, E.H.K. Akaho, R. G. Abrefah,
published by World Journal of Nuclear Science and Technology, Vol.1 No.2, 2011
has been cited by the following article(s):
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[1] Thermal neutron flux measurements in self-serve and tray rod facilities of Dhruva reactor
Life Cycle Reliability and Safety Engineering, 2017
[2] Thermal neutron capture cross-section and resonance integral measurements of 139La(n,)140La and 140Ce(n,)141Ce using a Am-Be neutron source
The European Physical Journal A - Hadrons and Nuclei, 2017
[3] Characterization of Ghana Research Reactor-1 Low Enriched Uranium Core Irradiation Sites Using a Theoretical Method
Doctoral dissertation, University of Ghana, 2017
[4] استفاده از دزیمتر ترمولومینسانس 100-TLD برای اندازه گیری شاریدگی نوترون های حرارتی با روش پرتوزاسازی LiF‎
2016
[5] Application of Thermoluminescence Dosimeter TLD-100 to Measure ThermalNeutron Fluence by LiF Activation Method
J. of Nucl Sci. and Tech., 2016
[6] NEUTRONICS BENCHMARK STUDIES FOR THE TRITIUM BREEDING BLANKETS
2016
[7] Application of Thermoluminescence Dosimeter TLD-100 to Measure Thermal Neutron Fluence by LiF Activation Method
Journal of Nuclear …, 2016
[8] Расчетное определение поправок на резонансное самоэкранирование активационных индикаторов из золота и тантала при облучении
Известия Томского политехнического университета, 2016
[9] Characterization of Neutron Field in a Spherical Irradiation Facility
American Journal of Modern Physics, 2015
[10] Assessment of the reliability of neutronic parameters of Ghana Research Reactor-1 control systems
Nuclear Engineering and Design, 2015
[11] Tritium breeding mock-up experiments containing lithium titanate ceramic pebbles and lead irradiated with DT neutrons
Fusion Engineering and Design, 2015
[12] THERMAL NEUTRON FLUX MAPPING ON A TARGET CAPSULE AT RABBIT FACILITY OF RSG-GAS REACTOR FOR USE IN k0-INAA
TRI DASA MEGA-Jurnal Teknologi Reaktor Nuklir, 2015
[13] Implementation of the k0-standardization Method at the Penn State Breazeale Reactor
2013
[14] Preliminary studies on the performance of Ghana's MNSR neutron fluxes in reactor neutron activation analysis after the addition of a beryllium shim
Advances in Applied Science Research, 2013
[15] Assessment of the Reliability of Thermal-Hydraulic and Neutronics Parameters of Ghana Research Reactor-1 Control Systems
Doctoral dissertation, University of Ghana, 2013
[16] Preliminary studies on the performance of Ghana s MNSR neutron fluxes in reactor neutron activation analysis after the addition of a beryllium shim
2013
[17] Neutronic study of the mono-recycling of americium in PWR and of the core conversion in MNSR using the MURE code
2012
[18] Neutronic study of the mono-recycling of americum in PWR and of the core conversion INMNSR using the MURE code
2012
[19] Robert Bright Mawuko SOGBADJI
2012
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