Zobrazeno 1 - 10
of 17
pro vyhledávání: '"Otman Jai"'
Publikováno v:
Moscow University Physics Bulletin. 74:710-716
This paper discusses the capability of the deterministic code system DRAGON-5 and DONJON-5 to reliably simulate the SLOWPOKE-2 research reactor. The characteristics of complex geometry, highly heterogeneity and large leakage of the SLOWPOKE-2 core, p
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::51b77c7ac961c50c8f377030ceff50ca
https://doi.org/10.3103/s002713491906016x
https://doi.org/10.3103/s002713491906016x
Publikováno v:
Moscow University Physics Bulletin. 74:544-550
This paper investigates the applicability of the DRAGON5 and DONJON5 code system to develop an accurate full-core model of the Moroccan 2 MW TRIGA Mark-II research reactor. The evaluated cross-section data library ENDFB.VII.1 with SHEM-295 group stru
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::abbc27eb911f2c8aff90c58b7571d333
https://doi.org/10.3103/s0027134919050084
https://doi.org/10.3103/s0027134919050084
Publikováno v:
Eurasian Journal of Physics and Functional Materials, Vol 2, Iss 4, Pp 315-325 (2018)
Neutrons are produced in accelerators by irradiating heavy targets with an electron or proton beam. Produced neutrons are of high energy. The purpose of our work is optimization the neutron flux by MCNP-6 code for production the thermal neutron flux
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::deb400990b613770aac12b6e018b1ae4
https://doi.org/10.29317/ejpfm.2018020403
https://doi.org/10.29317/ejpfm.2018020403
Autor:
Otman Jai, Abdelmajid Maghnouj, Abdessamad Didi, Hassane El Bekkouri, Jaouad Tajmouati, Ahmed Dadouch, Mohamed Bencheikh
Publikováno v:
Moscow University Physics Bulletin. 73:612-617
In this paper, we investigated a system, is composed of a natural tungsten and bismuth cylindrical targets. The target has been optimized to produce the maximum of neutrons yield with a diameter of 20 cm and varying height from 10 to 80 cm. The targe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::abd46627e07cb2240ba5be453527a2eb
https://doi.org/10.3103/s0027134918060085
https://doi.org/10.3103/s0027134918060085
Publikováno v:
Bangladesh Journal of Medical Science. 17:567-572
Background: Molybdenum- 99 is a parent isotope of Technetium-99m ( 99m Tc) as intermediate to diagnosis and radiation treatment. This production is made according to irradiation of Molybdenum-98 with thermal neutrons. The cycle comprises a complex of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::14c3e0793780be1b9be2480b4301b1ac
https://doi.org/10.3329/bjms.v17i4.38317
https://doi.org/10.3329/bjms.v17i4.38317
Publikováno v:
Results in Physics, Vol 9, Iss, Pp 1155-1160 (2018)
The MNSR is a pool type research reactor, which is difficult to model because of the importance of neutron leakage. The aim of this study is to evaluate a 2-D transport model for the reactor compatible with the latest release of the DRAGON code and 3
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::1e8c2e6d241e9075cacd91a8191de84a
https://doi.org/10.1016/j.rinp.2018.04.033
https://doi.org/10.1016/j.rinp.2018.04.033
Publikováno v:
Eurasian Journal of Physics and Functional Materials, Vol 2, Iss 2, Pp 129-139 (2018)
The production of neutrons can be carried out with the bombardment of the nuclei of heavy atoms, with accelerated and energetic particles (generally electrons). The electron collides with the target nuclei, so, 20 to 30 neutrons are produced by a pro
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2cf1d44e28cc57d45e59d9b178e27860
http://ephys.kz/files/2018-06-25_Vol2_Num2_05.pdf
http://ephys.kz/files/2018-06-25_Vol2_Num2_05.pdf
Publikováno v:
Moscow University Physics Bulletin. 72:633-637
The objective of this analysis is to present the validation study of the latest release of the reactor physics lattice transport code DRAGON5 by TRX and BAPL critical experiments of light water reactors for neutrons calculations of Moroccan 2 MW TRIG
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9001e38b349f49be21fa9074479cf5dc
https://doi.org/10.3103/s002713491706011x
https://doi.org/10.3103/s002713491706011x
Publikováno v:
Moscow University Physics Bulletin. 72:465-469
Using the Monte Carlo N-Particle code (MCNP-6), to analyze the thermal, epithermal and fast neutron fluxes, of 3 millicuries of radium–beryllium, for determine the qualitative and quantitative of many materials, using method of neutron activation a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d778d824207cb4c0d007de75a7be60dd
https://doi.org/10.3103/s0027134917050034
https://doi.org/10.3103/s0027134917050034
Publikováno v:
Moscow University Physics Bulletin. 72:460-464
The neutron activation analysis is a method of exclusively elemental analysis. Its implementation of irradiates the sample which can be analyzed by a high neutron flux, this method is widely used in developed countries with nuclear reactors or accele
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c0e940c64ebe2f2673b5e91785ae9612
https://doi.org/10.3103/s0027134917050022
https://doi.org/10.3103/s0027134917050022