The Experts below are selected from a list of 2853 Experts worldwide ranked by ideXlab platform
M Alnassar - One of the best experts on this subject based on the ideXlab platform.
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estimation of the activation of local Reactor Shielding concretes
2009Co-Authors: S Alhajali, M H Kharita, B Naoom, S Yousef, M AlnassarAbstract:Abstract Many elements in Reactor Shielding concrete become radioactive due to interaction with neutrons during the operation of a nuclear Reactor. These radioactive elements will build up over the time due to (n,γ) reaction and contribute to the radioactive waste during decommissioning of the Reactor, they will increase the dose from the inner part of the biological Shielding (concrete) surrounding a nuclear Reactor during maintenance works within Reactor containment, and their effect should be taken in the calculations of the dose behind the concrete shield. Six mixtures of local ordinary and special Shielding concretes have been investigated in this study. Their compositions were determined using X-ray diffraction and neutron activation analysis using the Syrian Miniature Neutron Source Reactor (MNSR) and consequently the dose rates. Based on the results of the analyses and comparing to the published limits in the references, it has been found that 60Co, 152Eu, 154Eu and 134Cs will be the most effective radioactive nuclides existing in the local concrete, but Dolomite aggregates contain the minimum limits of them and it has been found that Fe, Mg, and Ti the major elements existing in the local concrete.
S Alhajali - One of the best experts on this subject based on the ideXlab platform.
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appropriate concrete for nuclear Reactor Shielding
2016Co-Authors: S Alhajali, S Yousef, B NaoumAbstract:A survey for the neutron activation significant trace-minerals in limestones from different sites in Syria has been carried out. The specific saturation activation radioactivity was calculated and compared to the clearance levels. The results show that the limestone composition varies significantly from one site to another. For example Al-Tamoura site has ∑(C(i)/CL(i))≤1 at thermal neutron flux less than 10(7) (n cm(-2) s(-1)), while the limestone from other the three sites has ∑(C(i)/CL(i))≤1 at a flux less than 3×10(6) (n cm(-2) s(-1)).
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estimation of the activation of local Reactor Shielding concretes
2009Co-Authors: S Alhajali, M H Kharita, B Naoom, S Yousef, M AlnassarAbstract:Abstract Many elements in Reactor Shielding concrete become radioactive due to interaction with neutrons during the operation of a nuclear Reactor. These radioactive elements will build up over the time due to (n,γ) reaction and contribute to the radioactive waste during decommissioning of the Reactor, they will increase the dose from the inner part of the biological Shielding (concrete) surrounding a nuclear Reactor during maintenance works within Reactor containment, and their effect should be taken in the calculations of the dose behind the concrete shield. Six mixtures of local ordinary and special Shielding concretes have been investigated in this study. Their compositions were determined using X-ray diffraction and neutron activation analysis using the Syrian Miniature Neutron Source Reactor (MNSR) and consequently the dose rates. Based on the results of the analyses and comparing to the published limits in the references, it has been found that 60Co, 152Eu, 154Eu and 134Cs will be the most effective radioactive nuclides existing in the local concrete, but Dolomite aggregates contain the minimum limits of them and it has been found that Fe, Mg, and Ti the major elements existing in the local concrete.
Batet Miracle Lluís - One of the best experts on this subject based on the ideXlab platform.
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Research in plasma physics and fusion nuclear technology in the Department of Physics of UPC
2019Co-Authors: Futatani Shimpei, Mas De Les Valls Ortiz, Elisabet, Suárez Cambra Daniel, Batet Miracle LluísAbstract:Advanced Nuclear Technologies (ANT) Research Group of Universitat Politècnica de Catalunya (UPC) has diverse fields of activity; research lines in the field of Nuclear Fusion are summarized in this article. Activities of ANT group in this field encompass from Plasma Physics to Control Engineering, including studies of plasma instabilities, fluid-dynamics and heat and mass transfer analyses; and relate to a variety of subsystems, from the plasma itself to the ancillary systems, including the plasma facing components and the Breeding Blankets. Breeding Blankets are complex components that perform three functions in a fusion Reactor: Shielding the magnets, recovering the heat produced in the plasma, and producing tritium, which is one of the fuels of fusion. Most of ANT group activities are framed within the EUROFusion program (www.euro-fusion.org), in close collaboration with existing experimental fusion devices and with ITER, the large international R&D fusion project (www.iter.org)Postprint (published version
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Research in plasma physics and fusion nuclear technology in the Department of Physics of UPC
2019Co-Authors: Futatani Shimpei, Mas De Les Valls Ortiz, Elisabet, Suárez Cambra Daniel, Batet Miracle LluísAbstract:Advanced Nuclear Technologies (ANT) Research Group of Universitat Politècnica de Catalunya (UPC) has diverse fields of activity; research lines in the field of Nuclear Fusion are summarized in this article. Activities of ANT group in this field encompass from Plasma Physics to Control Engineering, including studies of plasma instabilities, fluid-dynamics and heat and mass transfer analyses; and relate to a variety of subsystems, from the plasma itself to the ancillary systems, including the plasma facing components and the Breeding Blankets. Breeding Blankets are complex components that perform three functions in a fusion Reactor: Shielding the magnets, recovering the heat produced in the plasma, and producing tritium, which is one of the fuels of fusion. Most of ANT group activities are framed within the EUROFusion program (www.euro-fusion.org), in close collaboration with existing experimental fusion devices and with ITER, the large international R&D fusion project (www.iter.org
S Yousef - One of the best experts on this subject based on the ideXlab platform.
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appropriate concrete for nuclear Reactor Shielding
2016Co-Authors: S Alhajali, S Yousef, B NaoumAbstract:A survey for the neutron activation significant trace-minerals in limestones from different sites in Syria has been carried out. The specific saturation activation radioactivity was calculated and compared to the clearance levels. The results show that the limestone composition varies significantly from one site to another. For example Al-Tamoura site has ∑(C(i)/CL(i))≤1 at thermal neutron flux less than 10(7) (n cm(-2) s(-1)), while the limestone from other the three sites has ∑(C(i)/CL(i))≤1 at a flux less than 3×10(6) (n cm(-2) s(-1)).
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estimation of the activation of local Reactor Shielding concretes
2009Co-Authors: S Alhajali, M H Kharita, B Naoom, S Yousef, M AlnassarAbstract:Abstract Many elements in Reactor Shielding concrete become radioactive due to interaction with neutrons during the operation of a nuclear Reactor. These radioactive elements will build up over the time due to (n,γ) reaction and contribute to the radioactive waste during decommissioning of the Reactor, they will increase the dose from the inner part of the biological Shielding (concrete) surrounding a nuclear Reactor during maintenance works within Reactor containment, and their effect should be taken in the calculations of the dose behind the concrete shield. Six mixtures of local ordinary and special Shielding concretes have been investigated in this study. Their compositions were determined using X-ray diffraction and neutron activation analysis using the Syrian Miniature Neutron Source Reactor (MNSR) and consequently the dose rates. Based on the results of the analyses and comparing to the published limits in the references, it has been found that 60Co, 152Eu, 154Eu and 134Cs will be the most effective radioactive nuclides existing in the local concrete, but Dolomite aggregates contain the minimum limits of them and it has been found that Fe, Mg, and Ti the major elements existing in the local concrete.
J E White - One of the best experts on this subject based on the ideXlab platform.
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production and testing of the vitamin b6 fine group and the bugle 93 broad group neutron photon cross section libraries derived from endf b vi nuclear data
1995Co-Authors: J E WhiteAbstract:A revised multigroup cross-section library based on Release 3 of ENDF/B-VI data has been produced and tested for light-water-Reactor Shielding and Reactor pressure vessel dosimetry applications. This new broad-group library, which is designated BUGLE-96, represents an improvement over the BUGLE-93 data library released in February 1994 and replaces the data package for BUGLE-93 in the Radiation Safety Information Computational Center (formerly RSIC). The processing methodology is the same as that used for producing BUGLE-93 and is consistent with ANSI/ANS 6.1.2. The ENDF data were first processed into a fine-group, pseudo-problem-independent format and then collapsed into the final broad-group format. The fine-group library, which is designated VITAMIN-B6, contains 120 nuclides. The BUGLE-96 47-neutron-group/20-gamma-ray-group library contains the same 120 nuclides processed as infinitely dilute and collapsed using a weighting spectrum typical of a concrete shield. Additionally, nuclides processed with resonance self-Shielding and weighted using spectra specific to BWR and PWR material compositions and Reactor models are available. As an added feature of BUGLE-96, cross-section sets having upscatter data for four thermal neutron groups are included. The upscattering data should improve the application of BUGLE-96 to the calculation of more accurate thermal fluences, although more computer time will be required. Several new dosimetry response functions and kerma factors for all 120 nuclides are also included in the library. The incorporation of feedback from users has resulted in a data library that addresses a wider spectrum of user needs.
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vitamin b6 a fine group cross section library based on endf b vi for radiation transport applications
1994Co-Authors: J E White, R Q Wright, D T Ingersoll, R W Roussin, N M Greene, R E MacfarlaneAbstract:A new multigroup cross-section library based on ENDF/B-VI data has been produced and tested for light water Reactor Shielding and Reactor pressure vessel dosimetry applications. This fine-group library, which is designated VITAMIN-B6, contains 120 nuclides. Several dosimetry response functions and kerma factors for all 120 nuclides are also included with the library. Significant benchmark data testing of VITAMIN-B6 was an integral part of this development work to accelerate the qualification. Over 50 benchmarks were calculated using the VITAMIN-B6 library. In general, results using the new data show significant improvements relative to earlier ENDF data.
