Characterization and quantification of numerical errors in threshold displacement energy calculated by molecular dynamics in bcc-Fe (original) (raw)

Evaluation of the threshold displacement energy in tungsten by molecular dynamics calculations

Journal of Nuclear Materials, 2017

The threshold displacement energy of tungsten was determined by molecular dynamics calculations to be 85 eV, which reasonably agree with the ASTM recommendation, 90 eV. A possible error was estimated to be 4.5% by systematic investigations on the effects of calculation settings such as the system size and the number of sampled recoil directions. We explained the reasons why large discrepancies in the threshold displacement energy were observed in previous studies.

The primary damage in Fe revisited by Molecular Dynamics and its binary collision approximation

MRS Proceedings, 2000

Molecular Dynamics (MD) is a very powerful tool for studying displacement cascades initiated by the neutrons when they interact with matter and thus evaluate the primary damage. The mean number of point defects created can be obtained with a fair standard error with a reasonable number of cascade simulations (10 to 20 [1]), however other cascades characteristics (spatial distribution, size and amount of defect clusters ...) display a huge variability. Therefore, they may need to be studied using faster methods such as the Binary Collision Approximation (BCA) which is several order of magnitude less time consuming. We have investigated the point defect distributions subsequent to atomic collision cascades by both MD (using EAM potentials for Fe) and its BCA. MD and its BCA lead to comparable point defect predictions. The significant similarities and differences are discussed.

Collision Cascade and Primary Radiation Damage in Silicon Carbide: A Molecular Dynamics Study

JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA

Silicon carbide (SiC) is a competitive candidate material to be used in several advanced and Generation-IV nuclear reactor designs as neutron moderator, fuel coating, cladding, or core structural material. Many studies have been performed to investigate the durability of SiC in severe environment in nuclear reactor. However, the nature and behavior of defect induced by neutron irradiation are still not fully understood. This paper is aimed to study collision cascade and primary radiation damage in SiC using molecular dynamics simulation. The potential being used was a hybrid Tersoff potential modified with Ziegler-Biersack-Littmark (ZBL) screening function. The collision cascade was let evolved for 10 ps from a Si or C primary knocked atom (PKA) located initially at the top center of a system containing 960000 atoms. The simulation was carried out at room temperature as well as at several advanced fission reactor-relevant temperatures. It was obtained that the number of C point defe...

Influence of the interatomic potentials on molecular dynamics simulations of displacement cascades

Journal of Nuclear Materials, 2000

Molecular dynamics (MD) is a powerful tool to study the displacement cascades initiated by the neutrons when they interact with matter. Key components of this technique are the interatomic potentials which model the binding of the dierent constitutive atoms. There exist many interatomic potentials dedicated to a-Fe and we have tested three of them for the study of radiation damage. We have found that the primary damage is potential sensitive. From our study, it appears that some characteristics of the potentials, not always considered, can be correlated to the type of damage produced by displacement cascades. The repulsive part of the potential has a strong in¯uence on the cascade morphology. Moreover, equilibrium properties such as the atoms mean square displacements, the vacancy migration and vacancy±vacancy binding energies also appear to have some in¯uence and should be investigated carefully when simulating radiation damage. It is therefore very important to use extreme care when trying to obtain quantitative results from MD simulations. Ó

Validation of induced radioactivity calculations for candidate fusion materials through measurements in a graphite-centered assembly

Fusion Engineering and Design, 1998

Induced radioactivity measurements were carried out jointly by the USA and Japan in a graphite-centered assembly, in the framework of ITER Task T-218 entitled 'Shielding Blanket Neutronics Experiments'. An intense, accelerator-based D-T rotating target neutron source at JAERI, with a nominal intensity of 5 × 10 12 s − 1 , was used. Two locations, providing different neutron energy spectra, were chosen for irradiating samples of a range of materials of interest to ITER. Three independent experimental campaigns were conducted so as to accommodate a large number of samples, on one hand, and as many short and long half-life products as possible, on the other. The total neutron fluence ranged from 4.7 × 10 11 to 1.5× 10 14 n cm − 2 . Altogether, samples of Mg, Al, SiO 2 , Ti, V, Cr, Mn, Fe, Co, Ni, FH82 steel, SS316LN steel (ITER grade), Cu, Zn, KCl, Zr, Nb, Mo, Ag, In, Sn, Dy, Ta, Hf, Re, Au, Ir, and Pb were irradiated. The irradiated samples were cooled for variable periods ranging from 30 s to 250 days before their decay gamma-ray spectra were counted on high purity intrinsic germanium detectors. The half lives of the observed radioisotopes have ranged from 18.7 s ( 46m Sc from Ti) to 5.3 years ( 60 Co from Ni). The neutron energy spectra for the two locations were calculated using Monte Carlo code MCNP with FENDL-1 and ENDF/B-VI data libraries. The analysis of isotopic activities, expressed in Bq cc − 1 , of the irradiated materials has been carried out using REAC-3 radioactivity code, with FENDL-2A and FENDL-1A activation cross-section and decay data libraries. Typically, C/E lies in a band of 0.5-1.5 for the results being reported.

Challenging fission cross section simulation with long standing macro-microscopic model of nucleus potential energy surface

Université de Bordeaux, 2015

Titre : De la phénoménologie à la microscopie, une nouvelle approche pour l'évaluation des sections efficaces de fission Résumé : Les travaux présentés visent à améliorer les modèles de physique nucléaire utilisés dans l'évaluation des sections efficaces neutroniques de fission. Le résultat de ces travaux donne les clefs pour une percée significative dans ce domaine et a permis d'étendre fortement les capacités du code d'évaluation CONRAD. Les sections partielles étant naturellement corrélées entre-elles pour respecter la valeur de la section totale, ces améliorations bénéficient à l'ensemble des sections partielles. Un cadre solide pour la modélisation des processus concurrent à la fission a dû être établi sur le modèle du code de référence TALYS. Après s'être assuré de la fiabilité et de la cohérence du cadre, les investigations spécifiques concernant la fission ont pu être réalisées. Les perspectives d'applications offertes par les modèles macro-microscopiques FRDM et FRLDM ont été analysées. Ces modèles ont été implémentés et validés sur des données expérimentales et des benchmarks. Afin d'obtenir des temps de calcul compatibles avec les besoins de l'évaluation, des méthodes numériques sophistiquées ont été sélectionnées et une partie des calculs a été portée sur GPU. Ces modèles macro-microscopiques peuvent être utilisés pour construire des surfaces d'énergie potentielle qui sont à leur tour traitées afin d'obtenir des barrières de fission à une dimension, puis des coefficients de transmission fission. Ces derniers sont alors utilisés dans le cadre de modélisation des sections efficaces moyennes du domaine statistique sur la base d'un modèle Hauser-Feshbach. Les résultats de cette approche seront présentés sur le cas du 239 Pu(n,f).

Calculation of radiation damage induced by neutrons in compound materials

Journal of Nuclear Materials, 2006

Many years have been devoted to study the behaviour of solids submitted to impinging particles like ions or neutrons. The nuclear evaluations describe more and more accurately the various neutron-atom interactions. Anisotropic neutronatom cross-sections are now available for many elements. Moreover, clear mathematical formalism now allows to calculate the number of displacements per atom in polyatomic targets in a realistic way using the binary collision approximation (BCA) framework. Even if these calculations do not take into account relaxation processes at the end of the displacement spike, they can be used to compare damages induced by different facilities like pressurized water reactors (PWR), fast breeder reactors (FBR), high temperature reactors (HTR) and fusion facilities like the European Spallation Source (ESS) and the International Fusion Material Irradiation Facility (IFMIF) on a defined material. In this paper, a formalism is presented to describe the neutron-atom cross-section and primary recoil spectra taking into account the anisotropy of nuclear reactions extracted from nuclear evaluations. Such a formalism permitted to compute displacement per atom production rate, primary and weighted recoil spectra within the BCA. The multigroup approximation has been used to calculate displacement per atom production rate and recoil spectra for a define nuclear reactor. All these informations are useful to compare recoil spectra and displacement per atom production rate produced by particle accelerator and nuclear reactor.

Modelling irradiation effects in fusion materials

Fusion Engineering and Design, 2007

We review the current status of the European fusion materials modelling programme. We describe recent findings and outline potential areas for future development. Large-scale density functional theory (DFT) calculations reveal the structure of the point defects in ␣-Fe, and highlight the crucial part played by magnetism. The calculations give accurate migration energies of point defects and the strength of their interaction with He atoms. Kinetic models based on DFT results reproduce the stages of radiation damage recovery in iron, and stages of He-desorption from pre-implanted iron. Experiments aimed at validating the models will be carried out in the future using a multi-beam ion irradiation facility chosen for its versatility and rapid feedback.