Results 31 to 40 of about 5,690 (213)

Evaluation of fast fission factor in a typical pool type research reactor [PDF]

Journal of Nuclear Research and Applications, 2022
One of the important factors of a nuclear reactor core is the fast fission factor.  This paper calculates this parameter based on space and energy-dependent method using the PTRAC card of MCNPX code. Tehran research reactor (TRR) is taken as a case study,
M. Arkani, S. Khakshournia
doaj   +1 more source

Determination of fluid dynamic parameters through imports of CFD images validated in experiments for the MCNPX code.

Brazilian Journal of Radiation Sciences, 2021
Como medições não intrusivas de transmissão de raios gama, uma contribuição significativa para os modelos de estrutura de fluxo que descrevem o sistema FCC riser multifásico.
Victor Hugo Farias Ferreira da Silva, Carlos Costa Dantas, Silvio de Barros Melo, Fernando Roberto de Andrade Lima, Pamalla Rafaelly Barbosa de Oliveira, Tennyson Accetti Resende Filho, Jorge Alexandre Gomes Lins, Eudes Bertony Vieira, Bruno Gomes Andrade, Milton Santos Viana   +9 more
doaj   +1 more source

Validation of MCNPX-PoliMi fission models [PDF]

2012 IEEE Nuclear Science Symposium and Medical Imaging Conference Record (NSS/MIC), 2012
We present new results on the measurement of correlated, outgoing neutrons from spontaneous fission events in a Cf-252 source. 16 EJ-309 liquid scintillation detectors are used to measure neutron-neutron correlations for various detector angles. Anisotropy in neutron emission is observed.
Sara A. Pozzi, Shaun D. Clarke, William J. Walsh, Eric C. Miller, Jennifer L. Dolan, Marek Flaska, Brian M. Wieger, Andreas Enqvist, Natalia Puppato, Enrico Padovani, John K. Mattingly, David L. Chichester, Paolo Peerani   +12 more
openaire   +1 more source

Simulating Proton Radiation Tolerance of Perovskite Solar Cells for Space Applications

Advanced Energy and Sustainability Research, Volume 4, Issue 12, December 2023., 2023
Dang‐Thuan and co‐authors suggest a novel approach for predicting proton‐radiated degradation in perovskite solar cells. They combine ion scattering and optoelectronic simulations to overcome experimental constraints. FAMAPbI3‐based (lighter materials) cells show higher radiation tolerance than CsPbI2Br (heavier materials).
Dang-Thuan Nguyen, Daniel Walter, Klaus J. Weber, The Duong, Thomas P. White   +4 more
wiley   +1 more source

Evaluating the induced photon contamination by different breast IOERT shields using Monte Carlo simulation

Journal of Applied Clinical Medical Physics, Volume 24, Issue 11, November 2023., 2023
Abstract Background and Objective Avoiding the underlying healthy tissue over‐exposure during breast intraoperative electron radiotherapy (IOERT) is owing to the use of some dedicated radioprotection disks during patient irradiation. The originated contaminant photons from some widely used double‐layered shielding disks including PMMA+Cu, PTFE+steel ...
Hamid Reza Baghani, Mostafa Robatjazi
wiley   +1 more source

Neutronic Evaluation of MSBR System Using MCNP Code

Brazilian Journal of Radiation Sciences, 2021
The concept of Molten Salt Reactor use Th to breed fissile 233U, where an initial source of fissile material needs to be provided. However, there is no available 233U and so; the fissile fuel supply is one of the unresolved problems.
Clarysson Alberto Mello da Silva, Alana Lima Vieira, Isabella Resende Magalhães, Claubia Pereira   +3 more
doaj   +1 more source

Validation and study of different parameters in the simulation of diagnostic X-ray spectra using the MCNPX code

Brazilian Journal of Radiation Sciences, 2023
In radiology, knowing the X-ray spectrum characteristics makes it possible to estimate the absorbed dose in the patient and to improve image quality. In this study, an X-ray generator was proposed using the MCNPX code and to validate it, the simulated ...
K.C.W. Consatti, W. S. Santos, J. V. B. Valença, M. T. Yoshizumi   +3 more
doaj   +1 more source

Status of the MCNPX Transport Code [PDF]

, 2001
The Monte Carlo particle transport code MCNPX and its associated data have been the focus of a major development effort at Los Alamos for several years. The system has reached a mature state, and has become a significant tool for many intermediate and high-energy particle transport applications.
H. G. Hughes, M. B. Chadwick, R. K. Corzine, H. W. Egdorf, F. X. Gallmeier, R. C. Little, R. E. MacFarlane, S. G. Mashnik, E. J. Pitcher, R. E. Prael, A. J. Sierk, E. C. Snow, L. S. Waters, M. C. White, P. G. Young   +14 more
openaire   +1 more source

Beta-backscattering Thickness-meter Design and Evaluation with Fuzzy TOPSIS Method

Nukleonika, 2014
An industrial gauge for measuring thickness of a gold coating layer deposited on a steel base through detection of the backscattered beta particles has been described.
Arjhangmehr Afshin, Mohammadzadeh Mohammad, Hossein Feghhi Seyed Amir, Hassanpour Saeed Tasouji   +3 more
doaj   +1 more source

The comparison of five neutron sources via 7Li(p,n) reaction for the design of a facility based on prompt gamma ray neutron activation analysis (PGNAA) in vivo detections of boron [PDF]

Acta Periodica Technologica, 2020
Prompt Gamma Ray Neutron Activation Analysis (PGNAA) is a useful nondestructive method with numerous applications. In this study neutron yield from 7Li(p,n) reaction with proton energies of 2.5, 3, 4, 4.5 and 5 MeV was used in order to provide ...
Fantidis J.G., Nicolaou G.E.
doaj   +1 more source