ENDF-201: ENDF/B-VI summary documentation

Rose, P.F.

doi:10.2172/10132931

Cited by 131 publications

(58 citation statements)

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“…The cross section covariance matrix was taken from JENDL-3.3. However, the covariance matrix for Er is not present in JENDL-3.3, ENDF/B-IV, 10) ENDF/B-VI R8 11) or JEFF-3.0. 12) Thus, we compared the 167 Er capture cross sections of JENDL-3.3, ENDF/B-IV, ENDF/B-VI R8, and JEFF-3.0 in Fig.…”

Section: Numerical Results 1 Calculational Modelmentioning

confidence: 99%

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A New Uncertainty Reduction Method for Fuel Fabrication Process with Erbia-Bearing Fuel

Sano

Takeda

Yamasaki³

2009

Journal of Nuclear Science and Technology

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A new uncertainty reduction method is proposed to evaluate the prediction accuracy of neutronics characteristics by combining the generalized bias factor method and the cross section adjustment method. The present method is applied to a fuel fabrication process with erbia-bearing fuel. The cross section uncertainty of erbium is improved by means of cross section adjustment using experimental data of the erbia worths. For a blending machine (H=U ¼ 0) used in the fuel fabrication process, the uncertainty reduction, which shows the rate of reduction of uncertainty, of the k eff is 0.604 for the present method and 0.555 for the conventional bias factor method. Thus, the prediction uncertainties are reduced by the present method compared with by the bias factor method.

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Section: Numerical Results 1 Calculational Modelmentioning

confidence: 99%

“…(15)), because the bias factor is directly applied only to the k eff using Eq. (11). In the bias factor method, the Er cross section uncertainties are set to 10%.…”

Section: Calculation Results For the Blending Machinementioning

confidence: 99%

A New Uncertainty Reduction Method for Fuel Fabrication Process with Erbia-Bearing Fuel

Sano

Takeda

Yamasaki³

2009

Journal of Nuclear Science and Technology

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“…These data are based on ENDF/B-VI. 7) Figure 1 shows that the scattering occurred in the energy range lower than 10 keV is almost isotropic. The purpose of the ultrafine-group calculations is to evaluate effective cross-sections in the resolved resonance energy range (lower than 5 keV).…”

Section: Neutron Slowing-down Equation In the Aegis Codementioning

confidence: 97%

Resonance Treatment Based on Ultra-fine-group Spectrum Calculation in the AEGIS Code

Sugimura¹,

Yamamoto

2007

J. Nucl. Sci. Technol.

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The resonance calculation method using the ultra-fine-group spectrum calculations in the AEGIS code is explained in detail. By a simple benchmark problem, it is verified that the effect of anisotropic scattering on effective cross-sections is not very large and the isotropic scattering source approximation is adequate in practical resonance calculations in LWRs. Furthermore, some efficient numerical algorithms in the ultra-fine-group calculations to reduce the computation time without large degeneration of accuracy are presented. In addition, the SPH method for energy collapsing of cross-sections is adopted in the AEGIS code to reduce the error of energy collapsing.Through the comparison with continuous-energy Monte-Calro calculation in the pin-cell geometry, the validity of the resonance treatment in the AEGIS code is verified.

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“…The characteristics of the proton beams were investigated through both numerical and experimental analyses using Monte Carlo calculations (MCNPX 11) with ENDF/B-VI 12) and SRIM 13) codes) and a specific film (the Gafchromic 14) film), respectively. In the numerical analysis, 150 MeV proton beams were assumed to be injected onto the tungsten target shown in the experimental settings (Fig.…”

Section: Proton Beam Characteristicsmentioning

confidence: 99%

Reaction Rate Analysis of Nuclear Spallation Reactions Generated by 150, 190, and 235MeV Protons

Pyeon

Shiga

Abe

et al. 2010

Journal of Nuclear Science and Technology

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At the National Cancer Center, proton irradiation experiments have been conducted using the cyclotron accelerator to measure the neutron spectrum by the foil activation method. The experimental results demonstrate that high-energy neutrons are bombarded by injecting high-energy protons onto the tungsten target. The agreement between the results of the experiments and the MCNPX calculations with ENDF/ B-VI is around 20% in the relative difference of the C/E (calculation/experiment) values in some of the 209 Bi(n, xn) 210Àx Bi reactions. Here, the activation foil 209 Bi is useful in obtaining experimental neutron spectrum information on nuclear spallation reactions of the tungsten target by the high-energy protons ranging between 150 and 235 MeV. The current experimental data could contribute to evaluating the accuracy of the numerical simulation methodology of reaction rates and the uncertainties of cross sections of 209 Bi, as experimental benchmarks.

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ENDF-201: ENDF/B-VI summary documentation

Cited by 131 publications

References 0 publications

A New Uncertainty Reduction Method for Fuel Fabrication Process with Erbia-Bearing Fuel

A New Uncertainty Reduction Method for Fuel Fabrication Process with Erbia-Bearing Fuel

Resonance Treatment Based on Ultra-fine-group Spectrum Calculation in the AEGIS Code

Reaction Rate Analysis of Nuclear Spallation Reactions Generated by 150, 190, and 235MeV Protons

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