• Title/Summary/Keyword: Karlsruhe

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Total Cross Sections for Kilovolt Neutrons of Even-Odd Nuclei in the Region of the 3s Strength-Function Resonances

  • Mann-Cho;Bak, Hae-Ill;F.H. Frohner;K.N. Muller
    • Nuclear Engineering and Technology
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    • v.2 no.4
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    • pp.241-248
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    • 1970
  • Neutron total cross sections of seperated isotopes were measured with the time-of-flight spectrometer at the 3 MeV Karlsruhe Van do Graaff Accelerator. The neutron energy ranged from 10 to 250 keV. The energy resolution was between 0.2 and 0.5 nsce/m. The measured cross sections were-shape-analyzed in terms of an R-matrix multilevel formula. Thus neutron widths and spins for up to 50 resonances per isotope could be determined. Average neutron widths, level densities and strength functions were derived. The spin dependence of strength functions and the distribution of widths and spacings were investigated.

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Large eddy simulation of turbulent flow using the parallel computational fluid dynamics code GASFLOW-MPI

  • Zhang, Han;Li, Yabing;Xiao, Jianjun;Jordan, Thomas
    • Nuclear Engineering and Technology
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    • v.49 no.6
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    • pp.1310-1317
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    • 2017
  • GASFLOW-MPI is a widely used scalable computational fluid dynamics numerical tool to simulate the fluid turbulence behavior, combustion dynamics, and other related thermal-hydraulic phenomena in nuclear power plant containment. An efficient scalable linear solver for the large-scale pressure equation is one of the key issues to ensure the computational efficiency of GASFLOW-MPI. Several advanced Krylov subspace methods and scalable preconditioning methods are compared and analyzed to improve the computational performance. With the help of the powerful computational capability, the large eddy simulation turbulent model is used to resolve more detailed turbulent behaviors. A backward-facing step flow is performed to study the free shear layer, the recirculation region, and the boundary layer, which is widespread in many scientific and engineering applications. Numerical results are compared with the experimental data in the literature and the direct numerical simulation results by GASFLOW-MPI. Both time-averaged velocity profile and turbulent intensity are well consistent with the experimental data and direct numerical simulation result. Furthermore, the frequency spectrum is presented and a -5/3 energy decay is observed for a wide range of frequencies, satisfying the turbulent energy spectrum theory. Parallel scaling tests are also implemented on the KIT/IKET cluster and a linear scaling is realized for GASFLOW-MPI.

Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from the Temelín II VVER-1000 reactor

  • Garcia, Manuel;Vocka, Radim;Tuominen, Riku;Gommlich, Andre;Leppanen, Jaakko;Valtavirta, Ville;Imke, Uwe;Ferraro, Diego;Uffelen, Paul Van;Milisdorfer, Lukas;Sanchez-Espinoza, Victor
    • Nuclear Engineering and Technology
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    • v.53 no.10
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    • pp.3133-3150
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    • 2021
  • This work deals with the validation of a high-fidelity multiphysics system coupling the Serpent 2 Monte Carlo neutron transport code with SUBCHANFLOW, a subchannel thermalhydraulics code, and TRANSURANUS, a fuel-performance analysis code. The results for a full-core pin-by-pin burnup calculation for the ninth operating cycle of the Temelín II VVER-1000 plant, which starts from a fresh core, are presented and assessed using experimental data. A good agreement is found comparing the critical boron concentration and a set of pin-level neutron flux profiles against measurements. In addition, the calculated axial and radial power distributions match closely the values reported by the core monitoring system. To demonstrate the modeling capabilities of the three-code coupling, pin-level neutronic, thermalhydraulic and thermomechanic results are shown as well. These studies are encompassed in the final phase of the EU Horizon 2020 McSAFE project, during which the Serpent-SUBCHANFLOW-TRANSURANUS system was developed.

Atomic displacement cross-sections for neutron irradiation of materials from Be to Bi calculated using the arc-dpa model

  • Konobeyev, A. Yu.;Fischer, U.;Simakov, S.P.
    • Nuclear Engineering and Technology
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    • v.51 no.1
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    • pp.170-175
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    • 2019
  • Displacement cross-sections for an advanced assessment of radiation damage rates were obtained for a number of materials using the arc-dpa model at neutron incident energies from $10^{-5}eV$ to 10 GeV. Evaluated data files, CEM03 and ECIS codes, and an approximate approach were applied for the calculation of recoil energy distributions in neutron induced reactions. Three sets of displacement cross-sections based on the use of low-energy data from JEFF-3.3, ENDF/B-VIII.0, and JENDL-4.0u were prepared. Files contain also cross-sections calculated using the standard NRT model. Special efforts were made to estimate the uncertainty of obtained displacement cross-sections.

Research on Rradiochemistry and Geochemistry at KIT-INE, Germany, in Support of the Nuclear Waste Disposal Safety Case

  • Altmaier, Marcus;Geckeis, Horst
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2018.11a
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    • pp.567-568
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    • 2018
  • Within this contribution, an overview of recent research performed in the radiochemistry division at KIT-INE is given. Examples are taken from R&D activities performed within the HGF NUSAFE programme, but also from studies performed within collaborations on the national and international level. It finally may contribute to increased interaction and exchange of KIT-INE with Korean research groups interested in nuclear waste disposal topics.

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Gas detonation cell width prediction model based on support vector regression

  • Yu, Jiyang;Hou, Bingxu;Lelyakin, Alexander;Xu, Zhanjie;Jordan, Thomas
    • Nuclear Engineering and Technology
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    • v.49 no.7
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    • pp.1423-1430
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    • 2017
  • Detonation cell width is an important parameter in hydrogen explosion assessments. The experimental data on gas detonation are statistically analyzed to establish a universal method to numerically predict detonation cell widths. It is commonly understood that detonation cell width, ${\lambda}$, is highly correlated with the characteristic reaction zone width, ${\delta}$. Classical parametric regression methods were widely applied in earlier research to build an explicit semiempirical correlation for the ratio of ${\lambda}/{\delta}$. The obtained correlations formulate the dependency of the ratio ${\lambda}/{\delta}$ on a dimensionless effective chemical activation energy and a dimensionless temperature of the gas mixture. In this paper, support vector regression (SVR), which is based on nonparametric machine learning, is applied to achieve functions with better fitness to experimental data and more accurate predictions. Furthermore, a third parameter, dimensionless pressure, is considered as an additional independent variable. It is found that three-parameter SVR can significantly improve the performance of the fitting function. Meanwhile, SVR also provides better adaptability and the model functions can be easily renewed when experimental database is updated or new regression parameters are considered.