Results 21 to 30 of about 8,745 (215)

COMPARISON OF WASTE DUE TO IRRADIATED STEELS IN THE ESFR AND DEMO [PDF]

open access: yesEPJ Web of Conferences, 2021
For either nuclear fusion or generation IV fission reactors to be viable as a commercial energy source the decommissioning and waste disposal solutions must be considered during the design.
Reid Jack   +4 more
doaj   +1 more source

Evaluation of mass attenuation coefficient of concrete sample for different traits

open access: yesBrazilian Journal of Radiation Sciences, 2022
Concrete is widely used in the world and is the main material for civil construction. Due to its properties, it has different uses such as structural, filling and shielding. The aim of this work is to compare experimental and theoretical mass attenuation
Luan Ferreira Bastos   +7 more
doaj   +1 more source

Recent MCNP developments [PDF]

open access: yesIEEE Transactions on Nuclear Science, 1992
The authors report both the status and developments in the Monte Carlo neutron-photon (MCNP) radiation transport computer code and two items of more general interest to computational physics: the accuracy of modern physics computer codes and the performance of scientific workstations.
Hendricks, J.S., Briesmeister, J.F.
openaire   +1 more source

Validation of Neutron Evaluated Data Based on The Experimental Reactivity Worth of Tungsten Target in CiADS [PDF]

open access: yesEPJ Web of Conferences, 2020
Measurement of a cylindrical tungsten target reactivity worth has been performed on the light water zero-power reactor of VENUS-II at China Institute of Atomic Energy (CIAE) in order to verify the neutron evaluated data related to the engineering design ...
Jiang Wei   +8 more
doaj   +1 more source

Determination of neutron spectrum parameters at IREN facility using the MCNP simulation and experimental validation [PDF]

open access: yesNuclear Technology and Radiation Protection
The determination of the characteristics of neutron spectrum at different irradiation positions on the outer wall of moderator chamber of the intense resonance neutron source by simulation method using MCNP code was presented.
Nhat Le Tran Minh   +14 more
doaj   +1 more source

Localization of nuclear materials in large concrete radioactive waste packages using photofission delayed gamma rays [PDF]

open access: yesEPJ Web of Conferences, 2021
The characterization of radioactive waste packages is mandatory for their transport, interim storage and final disposal. In this framework, the Nuclear Measurement Laboratory of CEA DES IRESNE Institute, at Cadarache, France, uses a high-energy electron ...
Delarue Manon   +10 more
doaj   +1 more source

Neutron-physical parameters at the outlet of the WWR-K reactor beam tube

open access: yesEurasian Journal of Physics and Functional Materials, 2021
The paper is devoted to the neutron-physical parameters obtained via combined calculations and experimental measurements for the exit of the WWR-K reactor beam tube.
A. B. Bauyrzhan   +6 more
doaj   +1 more source

Calculation of Mass Attenuation Coefficients for Pedicle Screw by Theoretical and Monte Carlo Simulation Methods

open access: yesSüleyman Demirel Üniversitesi Fen-Edebiyat Fakültesi Fen Dergisi, 2021
Spine fixation is required in cases such as congenital spinal curvatures, vertebral fractures, sagittal collapse over time, painful kyphosis, and bone load due to tumors.
Hasan Özdoğan   +3 more
doaj   +1 more source

Bremsstrahlung conversion efficiency and gamma - neutron generation from polypropylene, aluminum, iron, and lead bombarded by 10 MeV electrons [PDF]

open access: yesNuclear Technology and Radiation Protection, 2020
An electron beam from the UELR-10-15S2 accelerator (average energy of 9.92 ± 0.48 MeV) was applied to irradiate food and medical items at the Research and Development Center for Radiation Technology, Vietnam Atomic Energy Institute, Vietnam. The
Tuan Nguyen Anh, Tao Chau Van
doaj   +1 more source

Analysis of DD, TT and DT Neutron Streaming Experiments with the ADVANTG Code [PDF]

open access: yesEPJ Web of Conferences, 2020
The paper presents an analysis of DD, TT and DT neutron streaming benchmark experiments with the recently released hybrid transport code ADVANTG (AutomateD VAriaNce reducTion Generator).
Kos Bor   +8 more
doaj   +1 more source

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