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RISS 인기검색어
- 검색키워드
- 저자 : Walid A. Metwally (검색결과 2 건)
- 무료
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- 유료
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Gaussian process approach for dose mapping in radiation fields
Khuwaileh Bassam A.,Metwally Walid A. 한국원자력학회 2020 Nuclear Engineering and Technology Vol.52 No.8
In this work, a Gaussian Process (Kriging) approach is proposed to provide efficient dose mapping for complex radiation fields using limited number of responses. Given a few response measurements (or simulation data points), the proposed approach can help the analyst in completing a map of the radiation dose field with a 95% confidence interval, efficiently. Two case studies are used to validate the proposed approach. The First case study is based on experimental dose measurements to build the dose map in a radiation field induced by a D-D neutron generator. The second, is a simulation case study where the proposed approach is used to mimic Monte Carlo dose predictions in the radiation field using a limited number of MCNP simulations. Given the low computational cost of constructing Gaussian Process (GP) models, results indicate that the GP model can reasonably map the dose in the radiation field given a limited number of data measurements. Both case studies are performed on the nuclear engineering radiation laboratories at the University of Sharjah
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Sensitivity studies in spent fuel pool criticality safety analysis for APR-1400 nuclear power plants
Abdulrahman S. Al Awad,Abdalla Habashy,Walid A. Metwally 한국원자력학회 2018 Nuclear Engineering and Technology Vol.50 No.5
A criticality safety analysis was performed for the APR-1400 spent fuel pool region-II to ensure the safestorage of spent fuel, with credit taken for depletion and in-rack neutron absorbers (Metamic panels). PLUS7 fuel assembly was modeled using TRITON-NEWT of SCALE-6.1. The burnup-dependent crosssectionlibrary was generated under limiting core-operating conditions with 5%-w U-235 initialenrichment. MCNP5 was used to evaluate the neutron multiplication factor in an infinite array of rackcells with the axially nonuniformly burnt PLUS7 assemblies under normal, abnormal, and accidentconditions; including all biases and uncertainties. The main purpose of this study is to investigatereactivity variations due to the critical depletion and reactor operation parameters. The approach, assumptions,and modeling methods were verified by analyzing the contents of the most important fissileand the associated reactivity effects. The Nuclear Regulatory Commission (NRC) guidance on k-eff beingless than 1.0 for spent fuel pools filled with unborated water was the main criterion used in this study. Itwas found that assemblies with 49.0 GWd/MTU and 5.0 w/o U-235 initial enrichment loaded in Region-IIsatisfy this criterion. Moreover, it was found that the end effect resulted in a positive bias, thus ensuringits consideration
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