Marcus Seidl
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View article: Neutron activation analysis of metal foils placed inside an ex-core instrumentation channel of a Siemens/KWU PWR
Neutron activation analysis of metal foils placed inside an ex-core instrumentation channel of a Siemens/KWU PWR Open
View article: Evaluation of the in- and ex-vessel neutron fluence distributions in a Siemens/KWU PWR
Evaluation of the in- and ex-vessel neutron fluence distributions in a Siemens/KWU PWR Open
View article: Investigation of Two-Phase Critical Flow Phenomena during a Large-Break LOCA in a German PWR with the System Code ATHLET
Investigation of Two-Phase Critical Flow Phenomena during a Large-Break LOCA in a German PWR with the System Code ATHLET Open
View article: Application of Statistical Learning Methods to a Data Set of Measured Heat Transfer Coefficients for Continuous Casting
Application of Statistical Learning Methods to a Data Set of Measured Heat Transfer Coefficients for Continuous Casting Open
The heat transfer coefficient (HTC) between water and air/water sprays and the strand surface is a major parameter to simulate solidification in continuous casting processes. The HTC can be calculated via various equations from literature.…
View article: An introduction to Spent Nuclear Fuel decay heat for Light Water Reactors: a review from the NEA WPNCS
An introduction to Spent Nuclear Fuel decay heat for Light Water Reactors: a review from the NEA WPNCS Open
This paper summarized the efforts performed to understand decay heat estimation from existing spent nuclear fuel (SNF), under the auspices of the Working Party on Nuclear Criticality Safety (WPNCS) of the OECD Nuclear Energy Agency. Needs …
View article: Estimation of neutron fluence distribution within German PWR components for decommissioning studies
Estimation of neutron fluence distribution within German PWR components for decommissioning studies Open
On 15 April 2023, the last German NPPs were shut down. The final shutdown is followed by a post-operational phase in which measures can be carried out to prepare for the NPPs dismantling and decommissioning. One of the tasks in preparation…
View article: Editorial: Unique safety features and licensing requirements of small modular reactors
Editorial: Unique safety features and licensing requirements of small modular reactors Open
EDITORIAL article Front. Energy Res., 06 September 2023Sec. Nuclear Energy Volume 11 - 2023 | https://doi.org/10.3389/fenrg.2023.1273294
View article: Note on the potential to increase the accuracy of source term calculations for spent nuclear fuel
Note on the potential to increase the accuracy of source term calculations for spent nuclear fuel Open
The accuracy of source term predictions is an important factor which determines the efficiency of interim and final storage of spent nuclear fuel. To minimize the required number of storage containers and to minimize the volume and mass of…
View article: Note on the performance of parametrization strategies to determine the decay heat of PWR fuel
Note on the performance of parametrization strategies to determine the decay heat of PWR fuel Open
The behavior of fuel assembly safety properties such as decay heat is often parametrized by a set of proxy variables such as burnup and by categorical variables like UOX or MOX. The standards ANS5.1 and DIN-25463 are examples of this strat…
View article: On the estimation of nuclide inventory and decay heat: a review from the EURAD European project
On the estimation of nuclide inventory and decay heat: a review from the EURAD European project Open
In this work, a study dedicated to the characterization of the neutronics aspect of the Spent Nuclear Fuel (SNF), as part of the European project EURAD (Work Package 8), is presented. Both measured nuclide concentrations from Post Irradiat…
View article: Spent nuclear fuel management, characterisation, and dissolution behaviour: progress and achievement from SFC and DisCo
Spent nuclear fuel management, characterisation, and dissolution behaviour: progress and achievement from SFC and DisCo Open
SFC is a work package in Eurad that investigates issues related to the properties of the spent nuclear fuel in the back-end of the nuclear fuel cycle. Decay heat, nuclide inventory, and fuel integrity (mechanical and otherwise), and not le…
View article: The H2020 McSAFER Project: Main Goals, Technical Work Program, and Status
The H2020 McSAFER Project: Main Goals, Technical Work Program, and Status Open
This paper describes the main objectives, technical content, and status of the H2020 project entitled “High-performance advanced methods and experimental investigations for the safety evaluation of generic Small Modular Reactors (McSAFER)”…
View article: NEUTRON NOISE PATTERNS FROM COUPLED FUEL-ASSEMBLY VIBRATIONS
NEUTRON NOISE PATTERNS FROM COUPLED FUEL-ASSEMBLY VIBRATIONS Open
The neutron flux fluctuation magnitude of KWU-built PWRs shows a hitherto unexplained correlation with the types of loaded fuel assemblies. Also, certain measured long-range neutron flux fluctuation patterns in neighboring core quadrants s…
View article: Improvement of PIE analysis with a full core simulation: The U1 case
Improvement of PIE analysis with a full core simulation: The U1 case Open
In this paper the isotopic content of the U1 sample is re-analyzed taking into account the full irradiation environment with a 3-dimensional core simulator. It is found that by accounting for the neighboring assemblies as well as the vario…
View article: Neutron physics of the liquid‐fuel heat‐pipe reactor concept with molten salt fuel—Static calculations
Neutron physics of the liquid‐fuel heat‐pipe reactor concept with molten salt fuel—Static calculations Open
A liquid-fuel heat-pipe reactor (LFHPR) is a novel fast heterogeneous reactor developed by Harbin Engineering University, China, on the basis of liquid-fuel reactor designs and the heat-pipe reactor concept. In the concept, the reactor aba…
View article: IMPLEMENTATION OF PIN POWER FACTORS IN THE ANSYS CFX/PARCS COULPLING SYSTEM FOR LOCAL ANALYSIS OF NEUTRON OSCILLATION
IMPLEMENTATION OF PIN POWER FACTORS IN THE ANSYS CFX/PARCS COULPLING SYSTEM FOR LOCAL ANALYSIS OF NEUTRON OSCILLATION Open
Neutron noise analysis has been done over the last decades to predict fuel assembly and pressure vessel vibrations to evaluate safety related issues. In order to have a better insight of the neutron noise, a fluid mechanics and neutronics …
View article: McSAFE- High performance monte Carlo Methods for SAFETy Demonstration
McSAFE- High performance monte Carlo Methods for SAFETy Demonstration Open
View article: NEUTRON PHYSICAL FEASIBILITY OF SMALL MODULAR DESIGN OF DUAL FLUID REACTOR
NEUTRON PHYSICAL FEASIBILITY OF SMALL MODULAR DESIGN OF DUAL FLUID REACTOR Open
The Dual Fluid Reactor (DFR) is a fast reactor concept proposed by the Institute of Solid-state- and Nuclear physics (IFK) in Berlin. The design of DFR aims to combine the GenIV Molten Salt Reactor (MSR) and the Liquid-Metal Cooled Reactor…
View article: Mechanical analysis of the bow deformation of a row of fuel assemblies in a PWR core
Mechanical analysis of the bow deformation of a row of fuel assemblies in a PWR core Open
View article: Bowing effects on isotopic concentrations for simplified PWR assemblies and full cores
Bowing effects on isotopic concentrations for simplified PWR assemblies and full cores Open
View article: Development of a Multiphysics Approach With ANSYS CFX and PARCS for Local Analysis of Neutron Oscillation
Development of a Multiphysics Approach With ANSYS CFX and PARCS for Local Analysis of Neutron Oscillation Open
Neutron noise analysis has been done over the decades to predict fuel assembly vibrations and to evaluate safety related issues. Neutron noise occurs due to several reasons: the vibration of the fuel rods, flow obstacles such as rod bendin…
View article: McSAFE - High performance Monte Carlo methods for SAFEty demonstration, From proof of concept to industry-like applications
McSAFE - High performance Monte Carlo methods for SAFEty demonstration, From proof of concept to industry-like applications Open
View article: Study of the uncertainties due to position change of the PWR aeroball measurement system
Study of the uncertainties due to position change of the PWR aeroball measurement system Open
The aeroball measurement system (AMS) is an important in-core instrumentation in German pressurized water reactors. Therefore, it is essential to know the possible uncertainties of this system. One is the lack of knowledge of the positions…
View article: Hcsmr fuel assembly computations with apollo2 and Tripoli-4® codes
Hcsmr fuel assembly computations with apollo2 and Tripoli-4® codes Open
View article: ICONE23-1700 SIMULATION OF THE SYSTEM DYNAMICS FOR THE MOLTEN SALT REACTOR EXPERIMENT USING MODIFIED TRACE
ICONE23-1700 SIMULATION OF THE SYSTEM DYNAMICS FOR THE MOLTEN SALT REACTOR EXPERIMENT USING MODIFIED TRACE Open
The aim of this work is to use a modified version of TRACE for a preliminary study of a molten salt reactor (MSR) system behavior for the steady-state, transient and accidental conditions so as to demonstrate the suitability of the TRACE c…