• Title/Summary/Keyword: McMaster model

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Sorption of Pd on illite, MX-80 bentonite and shale in Na-Ca-Cl solutions

  • Goguen, Jared;Walker, Andrew;Racette, Joshua;Riddoch, Justin;Nagasaki, Shinya
    • Nuclear Engineering and Technology
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    • v.53 no.3
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    • pp.894-900
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    • 2021
  • This paper examines sorption of Pd(II) onto illite, MX-80 bentonite, and Queenston shale in Na-Ca-Cl solutions of varying ionic strength (IS) from 0.01 to 6.0 mol/L (M) and pHc ranging from 3 to 9 under atmospheric conditions. A 2-site protolysis non-electrostatic surface complexation and cation exchange model was applied to the Pd sorption onto illite and MX-80 using PHREEQC, and the model results were compared to the experimental ones obtained in this work. Surface complexation and cation exchange constants were estimated for both illite and MX-80 through the optimization process to bring the predicted distribution coefficients from the model into alignment with the experimentally derived values. These optimized surface complexation constants were compared to existing linear free energy relationships (LFER).

Artificial neural network for predicting nuclear power plant dynamic behaviors

  • El-Sefy, M.;Yosri, A.;El-Dakhakhni, W.;Nagasaki, S.;Wiebe, L.
    • Nuclear Engineering and Technology
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    • v.53 no.10
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    • pp.3275-3285
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    • 2021
  • A Nuclear Power Plant (NPP) is a complex dynamic system-of-systems with highly nonlinear behaviors. In order to control the plant operation under both normal and abnormal conditions, the different systems in NPPs (e.g., the reactor core components, primary and secondary coolant systems) are usually monitored continuously, resulting in very large amounts of data. This situation makes it possible to integrate relevant qualitative and quantitative knowledge with artificial intelligence techniques to provide faster and more accurate behavior predictions, leading to more rapid decisions, based on actual NPP operation data. Data-driven models (DDM) rely on artificial intelligence to learn autonomously based on patterns in data, and they represent alternatives to physics-based models that typically require significant computational resources and might not fully represent the actual operation conditions of an NPP. In this study, a feed-forward backpropagation artificial neural network (ANN) model was trained to simulate the interaction between the reactor core and the primary and secondary coolant systems in a pressurized water reactor. The transients used for model training included perturbations in reactivity, steam valve coefficient, reactor core inlet temperature, and steam generator inlet temperature. Uncertainties of the plant physical parameters and operating conditions were also incorporated in these transients. Eight training functions were adopted during the training stage to develop the most efficient network. The developed ANN model predictions were subsequently tested successfully considering different new transients. Overall, through prompt prediction of NPP behavior under different transients, the study aims at demonstrating the potential of artificial intelligence to empower rapid emergency response planning and risk mitigation strategies.

Rasch Analysis of the Korean Western Ontario McMaster (KWOMAC): In the Out-Patients Over 65 Years With Osteoarthritis of the Knee (한국판 Western Ontario MacMaster(WOMAC)의 Rasch분석)

  • Koh, Eun-Kyung;Yi, Chung-Hwi
    • Physical Therapy Korea
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    • v.14 no.1
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    • pp.82-89
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    • 2007
  • The Western Ontario and McMaster Universities Osteoarthritis Index (WOMAC) is a valid and widely used instrument for the assessment of osteoarthritis patients. In this study, data was obtained from the out-patients with painful osteoarthritis of the knee. One hundred-three out-patients were interviewed by physical therapists. In an exploratory way, a Korean version of the KWOMAC was analyzed for unidimensionality, item separation, and item difficulty using the Winsteps programs. Ninety-five patients with osteoarthritis of the knee over 65 years were analyzed for Rash analysis. In the analysis several functional items poorly fit to the model. These items included "heavy domestic duties" and "standing". In the pain domain, one item ("at night while in bed") did not fit the model. In the stiffness domain one item ("after sitting, lying, or resting later in the day") did not fit the model. Although 4 items from the 3 domains (pain, stiffness, function domain) do not fit well, the KWOMAC domains were confirmed by Rasch analysis. Thus the KWOMAC needs to be further examined before it can be used to properly determine the health status of the elderly with OA.

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Development of Incident Detection Algorithm Using Naive Bayes Classification (나이브 베이즈 분류기를 이용한 돌발상황 검지 알고리즘 개발)

  • Kang, Sunggwan;Kwon, Bongkyung;Kwon, Cheolwoo;Park, Sangmin;Yun, Ilsoo
    • The Journal of The Korea Institute of Intelligent Transport Systems
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    • v.17 no.6
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    • pp.25-39
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    • 2018
  • The purpose of this study is to develop an efficient incident detection algorithm by applying machine learning, which is being widely used in the transport sector. As a first step, network of the target site was constructed with micro-simulation model. Secondly, data has been collected under various incident scenarios produced with combination of variables that are expected to affect the incident situation. And, detection results from both McMaster algorithm, a well known incident detection algorithm, and the Naive Bayes algorithm, developed in this study, were compared. As a result of comparison, Naive Bayes algorithm showed less negative effect and better detect rate (DR) than the McMaster algorithm. However, as DR increases, so did false alarm rate (FAR). Also, while McMaster algorithm detected in four cycles, Naive Bayes algorithm determine the situation with just one cycle, which increases DR but also seems to have increased FAR. Consequently it has been identified that the Naive Bayes algorithm has a great potential in traffic incident detection.

A Preliminary Study on Family Function Components Affecting Individual Health and Disease: A Delphi Study (개인의 건강과 질병에 영향을 미치는 가족기능 구성요소에 관한 사전연구: 델파이 연구)

  • Kim, Ah-Ram;Jeong, Seong-Woo;Jeong, Jiin;Kim, Jung-Ran
    • Therapeutic Science for Rehabilitation
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    • v.10 no.3
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    • pp.83-96
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    • 2021
  • Objective : This study aimed to determine Korea-type family function factors that affect individual growth and social activities, and examine check the appropriate contents and domestic culture components based on the McMaster model, a family function evaluation tool, through the Delphi technique. Methods : The Delphi technique was applied to 12 expert panels in fields related to family function. The period lasted 9 weeks, from May to June 2020. The Delphi survey was conducted twice. In the first survey, the domestic culture and appropriate contents of the McMaster model were selected and localized, and expert' opinions about the components were collected using closed and open-ended questions. In the second survey, the fitness and importance of the components were investigated. Results : As a result of the first Delphi investigation, 18 items were deleted from the 53 items presented. After adding 11 items and excluding any overlapping items, a total of 40 items were selected. Subsequently, sentences that were difficult to understand were revised to familiar vocabulary. A second survey was constructed, with an example sentence. In the second Delphi investigation, 33 items were selected. The average content validity ratio for the final selected component was 0.76, and the stability was 0.28. Conclusion : Family function and the factors influencing domestic family function identified though this study can be used to conduct family function evaluations and interventions in clinical sites or relevant research studies.

Comparison of proliferation resistance among natural uranium, thorium-uranium, and thorium-plutonium fuels used in CANada Deuterium Uranium in deep geological repository by combining multiattribute utility analysis with transport model

  • Nagasaki, Shinya;Wang, Xiaopan;Buijs, Adriaan
    • Nuclear Engineering and Technology
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    • v.50 no.5
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    • pp.794-800
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    • 2018
  • The proliferation resistance (PR) of Th/U and Th/Pu fuels used in CANada Deuterium Uranium for the deep geological repository was assessed by combining the multiattribute utility analysis proposed by Chirayath et al., 2015 with the transport model of radionuclides in the repository and comparing with that of the used natural U fuel case. It was found that there was no significant advantage for Th/U and Th/Pu fuels from the viewpoint of the PR in the repository. It was also found that the PR values for used nuclear fuels in the repository of Th/U, Th/Pu, and natural U was comparable with those for enrichment and reprocessing facilities in the pressurized water reactor (PWR) nuclear fuel cycle. On the other hand, the PR values considering the transport of radionuclides in the repository were found to be slightly smaller than those without their transport after the used nuclear fuels started dissolving after 1,000 years.

Sorption of Eu on MX-80 Bentonite in Na-Ca-Cl Brine Solutions

  • Yang, Jieci;Racette, Joshua;Garcia, Fabiola Guido;Nagasaki, Shinya;Yang, Tammy
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.20 no.2
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    • pp.151-160
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    • 2022
  • The sorption of Eu on MX-80 bentonite in Na-Ca-Cl solutions is investigated at a molal proton concentration (pHm) range of 3 to 10 and an ionic strength (I) range of 0.1 to 6 m (mol·kgw-1). The sorption equilibrium of Eu on MX-80 is achieved within 14 to 21 d at I = 0.1 and 6 m. The sorption distribution coefficient (Kd) values of Eu for MX-80 increase as pHm increases from 3 to 6 for all I values, and they are independent of pHm between 8 and 10 at I ≥ 0.5 m. Meanwhile, at I = 0.1 m, the Kd value at pHm = 10 is slightly lower than those at pHm = 8 and 9. The Kd values are not affected by the I values between 0.5 m and 6 m, whereas the Kd value at I = 0.1 m is greater than those at I ≥ 0.5 m, except at pHm = 10. A two-site protolysis nonelectrostatic surface complexation and cation exchange sorption model is applied to the Eu sorption data for I ≤ 4 m, and the equilibrium constants of the sorption reactions are estimated.

System dynamics simulation of the thermal dynamic processes in nuclear power plants

  • El-Sefy, Mohamed;Ezzeldin, Mohamed;El-Dakhakhni, Wael;Wiebe, Lydell;Nagasaki, Shinya
    • Nuclear Engineering and Technology
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    • v.51 no.6
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    • pp.1540-1553
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    • 2019
  • A nuclear power plant (NPP) is a highly complex system-of-systems as manifested through its internal systems interdependence. The negative impact of such interdependence was demonstrated through the 2011 Fukushima Daiichi nuclear disaster. As such, there is a critical need for new strategies to overcome the limitations of current risk assessment techniques (e.g. the use of static event and fault tree schemes), particularly through simulation of the nonlinear dynamic feedback mechanisms between the different NPP systems/components. As the first and key step towards developing an integrated NPP dynamic probabilistic risk assessment platform that can account for such feedback mechanisms, the current study adopts a system dynamics simulation approach to model the thermal dynamic processes in: the reactor core; the secondary coolant system; and the pressurized water reactor. The reactor core and secondary coolant system parameters used to develop system dynamics models are based on those of the Palo Verde Nuclear Generating Station. These three system dynamics models are subsequently validated, using results from published work, under different system perturbations including the change in reactivity, the steam valve coefficient, the primary coolant flow, and others. Moving forward, the developed system dynamics models can be integrated with other interacting processes within a NPP to form the basis of a dynamic system-level (systemic) risk assessment tool.

Sorption of Se(-II) on illite, MX-80 bentonite, shale, and limestone in Na-Ca-Cl solutions

  • Walker, Andrew;Racette, Joshua;Saito, Takumi;Yang, Tammy (Tianxiao);Nagasaki, Shinya
    • Nuclear Engineering and Technology
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    • v.54 no.5
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    • pp.1616-1622
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    • 2022
  • Selenium has been identified as an element of interest for the safety assessment of a deep geological repository (DGR) for used nuclear fuel. In Canada, groundwaters at DGR depths in sedimentary rocks have been observed to have a high ionic strength. This paper examines the sorption behavior of Se(-II) onto illite, MX-80 bentonite, Queenston shale, and argillaceous limestone in Na-Ca-Cl solutions of varying ionic strength (0.1-6 mol/kgw (m)) and across a pH range of 4-9. Little ionic strength dependence for Se(-II) sorption onto all solids was observed except that sorption at high ionic strength (6 m) was generally slightly lower than sorption at low ionic strength (0.1 m). Illite and MX-80 exhibited the expected results for anion sorption, while shale and limestone exhibited more constant sorption across the pH range tested. A non-electrostatic surface complexation model successfully predicted sorption of Se(-II) onto illite and MX-80 using the formation of an inner-sphere surface complex and an outer-sphere surface complex. Optimized values for the formation reactions of these surface species were proposed.

Modelling of shear deformation and bond slip in reinforced concrete joints

  • Biddah, Ashraf;Ghobarah, A.
    • Structural Engineering and Mechanics
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    • v.7 no.4
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    • pp.413-432
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    • 1999
  • A macro-element model is developed to account for shear deformation and bond slip of reinforcement bars in the beam-column joint region of reinforced concrete structures. The joint region is idealized by two springs in series, one representing shear deformation and the other representing bond slip. The softened truss model theory is adopted to establish the shear force-shear deformation relationship and to determine the shear capacity of the joint. A detailed model for the bond slip of the reinforcing bars at the beam-column interface is presented. The proposed macro-element model of the joint is validated using available experimental data on beam-column connections representing exterior joints in ductile and nonductile frames.