Search Results - "Alrwashdeh, Mohammad"

Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core by Alrwashdeh, Mohammad, Alameri, Saeed A.

“…The accident-tolerant fuel concept involves replacing the conventional cladding system (zirconium) with a new material or coating that has specific…”
Get full text

Correction: Alrwashdeh, M.; Alameri, S.A. Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core. Energies 2022, 15, 8008 by Alrwashdeh, Mohammad, Alameri, Saeed A.

“…In the original publication [...]…”
Get full text

SiC and FeCrAl as Potential Cladding Materials for APR-1400 Neutronic Analysis by Alrwashdeh, Mohammad, Alameri, Saeed A.

“…The aim of this study is to investigate the potential improvement of accident-tolerant fuels in pressurized water reactors for replacing existing reference…”
Get full text

Reactor Monte Carlo (RMC) model validation and verification in compare with MCNP for plate-type reactor by Alrwashdeh, Mohammad, Alameri, Saeed A.

“…Traditional neutronics calculations and simulation behavior of plate type research reactors pose a challenge comparing with the conventional pressurized water…”
Get full text

Neutronic Analysis of SiC/SiC Sandwich Cladding Design in APR-1400 under Normal Operation Conditions by Alaleeli, Maithah, Alameri, Saeed, Alrwashdeh, Mohammad

“…Our aim is to study the neutronic behaviour of potential accident-tolerant fuel (ATF) claddings in a pressurised water reactor under normal operations. This…”
Get full text

Unveiling the latest progresses in chromium-coated Zircaloy cladding ATF materials: Fabrication techniques, performance metrics, and beyond by Mohamed, Ghadeer Hegab, Karuppasamy, K., Alrwashdeh, Mohammad, Barsoum, Imad, Alameri, Saeed, Alfantazi, Akram

“…After the Fukushima-Daiichi event, there has been notable progress in developing accident-tolerant fuel (ATF) cladding designs to improve light-water reactor…”
Get full text

The Application of the ThroLy Risk Assessment Model to Predict Venous Thromboembolism in Patients with Diffuse Large B-Cell Lymphoma by Abdel-Razeq, Hikmat, Ma’koseh, Mohammad, Mansour, Asem, Bater, Rayan, Amarin, Rula, Abufara, Alaa, Halahleh, Khalid, Manassra, Mohammad, Alrwashdeh, Mohammad, Almomani, Mohammad, Zmaily, Mais

“…Background Patients with aggressive lymphomas are at higher risk for venous thromboembolism (VTE). ThroLy is a risk assessment model (RAM) derived to predict…”
Get full text

CONSOLIDATION OF REACTOR PHYSICS EDUCATION – THE KHALIFA UNIVERSITY STUDENT FIELD TRIPS CASE STUDY by Alameri, Saeed A., Alrwashdeh, Mohammad, Beeley, Philip, Kim, Myung-Hyun, Unlu, Kenan

“…In 2010, the Department of Nuclear Engineering at Khalifa University of Science and Technology (NUCE) established the MSc degree in Nuclear Engineering. This…”
Get full text

Covariance data evaluation for 233U by Alrwashdeh, Mohammad

“…The FITWR program was developed and applied to experimental nuclear data by using the weighted least square method with nonlinear regression for high-order…”
Get full text

Preliminary three-dimensional neutronic analysis of IFBA coated TRISO fuel particles in prismatic-core advanced high temperature reactor by Alameri, Saeed A., Alrwashdeh, Mohammad

“…•Preliminary neutronics analysis for 2D and 3D PAHTR cores.•Effectiveness of utilizing IFBA layer in TRISO fuel particles.•Homogeneous distribution of IFBA…”
Get full text

239Pu evaluation comparison study by Alrwashdeh, Mohammad

“…•The analysis of 239Pu was performed using the SAMMY Code for Neutron Transmission, Capture, and Fission cross-sections in the resolved resonance region up to…”
Get full text

Correction: Alrwashdeh, M.; Alameri, S.A. Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core. IEnergies/I 2022, I15/I, 8008 by Alrwashdeh, Mohammad, Alameri, Saeed A

Get full text

Evaluation review of the 250Cf neutron cross section by Alrwashdeh, Mohammad, Alameri, Saeed

“…This research investigated the data for the cross section of the 250Cf isotope in the unresolved resonance region, where the incident particle with a specific…”
Get full text

Preliminary neutronic analysis of alternative cladding materials for APR-1400 fuel assembly by Alrwashdeh, Mohammad, Alameri, Saeed A.

“…•Preliminary neutronics analysis for alternative fuel cladding materials.•Effectiveness of utilizing different ATF materials on the thermal neutron…”
Get full text

A Neutronics Study of the Initial Fuel Cycle Extension in APR-1400 Reactors: Examining Homogeneous and Heterogeneous Enrichment Design by Alrwashdeh, Mohammad, Alameri, Saeed A.

“…Abstract In this study, we conducted a neutronics analysis of a soluble-free-boron APR-1400 reactor core. Our goal was to explore the possibility of extending…”
Get full text

Correction: A Neutronics Study of the Initial Fuel Cycle Extension in APR-1400 Reactors: Examining Homogeneous and Heterogeneous Enrichment Design by Alrwashdeh, Mohammad, Alameri, Saeed A.

Get full text

Covariance data evaluation for 233 U by Alrwashdeh, Mohammad

“…The FITWR program was developed and applied to experimental nuclear data by using the weighted least square method with nonlinear regression for high-order…”
Get full text

Sensitivity neutronic analysis of accident tolerant fuel concepts in APR1400 by Alhattawi, Nouf T., Alrwashdeh, Mohammad, Alameri, Saeed A., Alaleeli, Maitha M.

“…Zirconium-based cladding materials used in nuclear power plants have been shown to pose safety concerns due to their susceptibility to oxidation and hydrogen…”
Get full text

Impact of in-core fuel management on the radial peaking factor in the APR-1400 with accident-tolerance fuel cladding by Alzarooni, Asma, Alrwashdeh, Mohammad, Chaudri, Khurrum Saleem, Alameri, Saeed A.

Get full text

Evaluation review of the 250 Cf neutron cross section by Alrwashdeh, Mohammad, Alameri, Saeed

“…This research investigated the data for the cross section of the Cf isotope in the unresolved resonance region, where the incident particle with a specific…”
Get full text