Differential parameters uncertainty estimation via a PCA-based monte carlo sampling approach: IRT-4M fuel type as a case study von A. Khuwaileh, Bassam, Said, Zafar

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Technology options and cost estimates of nuclear powered desalination in the United Arab Emirates von Khuwaileh, Bassam A., Alzaabi, Fatima E., Almomani, Belal, Ali, Muataz

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Gaussian process approach for dose mapping in radiation fields von Khuwaileh, Bassam A., Metwally, Walid A.

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Non-linear, time dependent target accuracy assessment algorithm for multi-physics, high dimensional nuclear reactor calculations von Khuwaileh, Bassam A., Turinsky, Paul J.

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On the over-conservatism of the 5% depletion uncertainty rule in spent fuel criticality analyses von Metwally, Walid A., Alawad, Abdulrahman S., Khuwaileh, Bassam A.

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Surrogate based model calibration for pressurized water reactor physics calculations von Khuwaileh, Bassam A., Turinsky, Paul J.

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An Extended Thermosyphon Cooling System for APR-1400 Reactor Design von Alhammadi, Saif Y., Alktebi, Abdulla A., Eldemiery, Abdelfattah E., Gillette, Victor, El Haj Assad, Mamdouh, AlShabi, Mohammad, Khuwaileh, Bassam A.

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A once-through artificial neural network approach for used nuclear fuel inverse depletion analysis: A comparative study von Khuwaileh, Bassam A., Almomani, Belal

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Gaussian process approach for dose mapping in radiation fields von Khuwaileh, Bassam A, Metwally, Walid A

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On the performance of nanofluids in APR 1400 PLUS7 assembly: Neutronics von Khuwaileh, Bassam A., Al-Hamadi, Fatima I., Hartanto, Donny, Said, Zafar, Ali, Muataz

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Artificial Neural Network based Particle Swarm Optimization solution approach for the inverse depletion of used nuclear fuel von Khuwaileh, Bassam A., Al-Shabi, Mohammad, El Haj Assad, Mamdouh

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Surrogate based model calibration for pressurized water reactor physics calculations von Khuwaileh, Bassam A, Turinsky, Paul J

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Analysis of OECD/NEA medium 1000 MWth sodium-cooled fast reactor using the Monte Carlo serpent code and ENDF/B-VIII.0 nuclear data library von Al-Hamadi, Fatima I., Khuwaileh, Bassam A., Liem, Peng Hong, Hartanto, Donny

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Verification of Reduced Order Modeling based Uncertainty/Sensitivity Estimator (ROMUSE) von Khuwaileh, Bassam, Williams, Brian, Turinsky, Paul, Hartanto, Donny

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Validation of TRACE V5.0 for intermediate break in the cold leg of the reactor with passive emergency core cooling system via the ATLAS facility von Matesha, Polina, Akram, Yumna, Khuwaileh, Bassam, Alyammahi, Nourah, Yoon, Ho Joon

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Validation of TRACE 5.0 for steam line break with passive auxiliary feedwater system via the ATLAS facility von Akram, Yumna, Matesha, Polina, Khuwaileh, Bassam, Alyammahi, Nourah, Yoon, Ho Joon

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Nuclear design of an integrated small modular reactor based on the APR-1400 for RO desalination purposes von Alnuaimi, Reem Rashed, Khuwaileh, Bassam, Zubair, Muhammad, Hartanto, Donny

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Verification of Reduced Order Modeling based Uncertainty/Sensitivity Estimator (ROMUSE) von Khuwaileh, Bassam, Williams, Brian, Turinsky, Paul, Hartanto, Donny

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Benchmarking the new ENDF/B-VIII.0 nuclear data library for OECD/NEA medium 1000 MWth sodium-cooled fast reactor von Hartanto, Donny, Khuwaileh, Bassam, Liem, Peng Hong

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Gradient-Free Construction of Active Subspaces for Dimension Reduction in Complex Models with Applications to Neutronics von Coleman, Kayla D., Lewis, Allison, Smith, Ralph C., Williams, Brian, Morris, Max, Khuwaileh, Bassam

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