Development and verification of a new nuclear data processing system FRENDY

Tada, Kenichi; Nagaya, Yasunobu; Kunieda, Satoshi; Suyama, Kenya; Fukahori, Tokio

doi:10.1080/00223131.2017.1309306

Cited by 58 publications

(11 citation statements)

References 14 publications

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“…To get the adsorption capacity model of the prepared adsorbent for As 5+ removal, the DPS-7.05 (Data Processing System) was used to choose the quadratic polynomial stepwise regression method to achieve regression analysis. The data processing system (DPS) is a comprehensive and user-friendly platform for experimental designs, statistical analysis, and data mining that provides uniform design and calculation benefits [ 20 ]. Equation (3) was used to examine the final values of Y‘, which are the predicted values of equilibrium adsorption capacities, and results are mentioned in Table 4 .…”

Section: Resultsmentioning

confidence: 99%

Synthesis of Fe3O4@mZrO2-Re (Re = Y/La/Ce) by Using Uniform Design, Surface Response Methodology, and Orthogonal Design & Its Application for As3+ and As5+ Removal

et al. 2021

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In this study, iron oxide (Fe3O4) was coated with ZrO2, and doped with three rare earth elements((Y/La/Ce), and a multi-staged rare earth doped zirconia adsorbent was prepared by using uniform design U14, Response Surface methodology, and orthogonal design, to remove As3+ and As5+ from the aqueous solution. Based on the results of TEM, EDS, XRD, FTIR, and N2-adsorption desorption test, the best molar ratio of Fe3O4:TMAOH:Zirconium butoxide:Y:La:Ce was selected as 1:12:11:1:0.02:0.08. The specific surface area and porosity was 263 m2/g, and 0.156 cm3/g, respectively. The isothermal curves and fitting equation parameters show that Langmuir model, and Redlich Peterson model fitted well. As per calculations of the Langmuir model, the highest adsorption capacities for As3+ and As5+ ions were recorded as 68.33 mg/g, 84.23 mg/g, respectively. The fitting curves and equations of the kinetic models favors the quasi second order kinetic model. Material regeneration was very effective, and even in the last cycle the regeneration capacities of both As3+ and As5+ were 75.15%, and 77.59%, respectively. Adsorption and regeneration results suggest that adsorbent has easy synthesis method, and reusable, so it can be used as a potential adsorbent for the removal of arsenic from aqueous solution.

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Section: Resultsmentioning

confidence: 99%

Synthesis of Fe3O4@mZrO2-Re (Re = Y/La/Ce) by Using Uniform Design, Surface Response Methodology, and Orthogonal Design & Its Application for As3+ and As5+ Removal

et al. 2021

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“…Cells in Fig. 1 For the pointwise cross sections used in the present method, the ACE formatted cross sections, which are generated by the FRENDY code [11] using JENDL-4.0 [12], are adopted. The generated ACE cross sections are also used for ultra-fine group (UFG) reference calculations by MOC.…”

Section: Calculation Conditionsmentioning

confidence: 99%

A Resonance Calculation Method Using Energy Expansion Based on a Reduced Order Model: Use of Ultra-Fine Group Spectrum Calculation and Application to Heterogeneous Geometry

et al. 2021

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A Resonance calculation using energy Spectral Expansion (RSE) method has been recently proposed in order to efficiently treat complicated heterogeneous geometry and resonance interference effect. In the RSE method, ultra-fine group spectra are generated from ultra-fine group calculations in homogeneous geometry, and the spectra are expanded by the orthogonal basis on energy based on the singular value decomposition. Then the transport calculation for expansion coefficients is numerically performed, and the ultra-fine group spectra in the target heterogeneous regions are reconstructed by the expansion coefficients and the orthogonal basis. In this study, the RSE method is applied to multi-cell geometries including UO2, MOX and water cells, in which the resonance interference effect between UO2 and MOX fuel cells appears. The validity of the RSE method is confirmed through comparison with the reference effective multi-group cross sections obtained from the direct ultra-fine group calculation in the target heterogeneous geometry.

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“…The evaluated nuclear data files, JENDL-4.0, ENDF/B-VIII.0 and JEFF-3.3, are used in the present work. These data files are processed by the FRENDY code [10] to generate the ACE-formatted files including the probability tables for the unresolved resonance treatment, and then 211-energy group libraries are generated by the FRENDY/MG code [11]. Neutron slowing-down calculation capability of FRENDY/MG is used to calculate multi-group data in the resolved resonance range.…”

Section: Numerical Procedures and Toolmentioning

confidence: 99%

Experimental analysis of small sample reactivity measured in the SEG experiment by a deterministic reactor physics code system CBZ

Chiba

Fan

2021

Journal of Nuclear Science and Technology

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Experimental analysis of the sample reactivity measured in the SEG experiment is carried out with the deterministic reactor physics code system CBZ with the recent evaluated nuclear data files, JENDL-4.0, ENDF/B-VIII.0 and JEFF-3.3.Since the systems to be analysed are fast-thermal coupled ones, 211-energy group neutron reaction cross section libraries applicable to both the fast and thermal neutron systems are generated and utilized. In the multi-group library generation, the recentlydeveloped FRENDY and FRENDY/MG codes are used. Forward and adjoint neutron fluxes at the sample position are calculated by solving the neutron transport equation, and the sample reactivity is obtained by the first-order perturbation calculations. In order to simplify the systems calculated, two-dimensional cylinder model is prepared based on the previous work.Whereas the simplified model is employed, generally the reactivity of many different samples is well predicted by the calculations in comparison with the experimental uncertainties. On some of the samples, large discrepancies of the C/E values from unity are observed, and also relatively large differences in the C/E values among different nuclear data files are observed. These information are still useful for future development of the 1

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Development and verification of a new nuclear data processing system FRENDY

Cited by 58 publications

References 14 publications

Synthesis of Fe3O4@mZrO2-Re (Re = Y/La/Ce) by Using Uniform Design, Surface Response Methodology, and Orthogonal Design & Its Application for As3+ and As5+ Removal

Synthesis of Fe3O4@mZrO2-Re (Re = Y/La/Ce) by Using Uniform Design, Surface Response Methodology, and Orthogonal Design & Its Application for As3+ and As5+ Removal

A Resonance Calculation Method Using Energy Expansion Based on a Reduced Order Model: Use of Ultra-Fine Group Spectrum Calculation and Application to Heterogeneous Geometry

Experimental analysis of small sample reactivity measured in the SEG experiment by a deterministic reactor physics code system CBZ

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