Kodeli, Ivan Aleksander
Kodeli, Ivan Alexander
Ivan Aleksander Kodeli
VIAF ID: 313566747 (Personal)
Permalink: http://viaf.org/viaf/313566747
Preferred Forms
- 100 0 _ ‡a Ivan Aleksander Kodeli
- 100 1 _ ‡a Kodeli, Ivan Aleksander
- 100 1 _ ‡a Kodeli, Ivan Alexander
4xx's: Alternate Name Forms (4)
Works
Title | Sources |
---|---|
Amélioration de la modélisation des protections neutroniques des rnr-na et évaluation des biais et incertitudes sur leur dimensionnement | |
Analysis of QUADOS problem on TLD-Albedo personal dosemeter responses using discrete ordinates and Monte Carlo methods | |
Application of perturbation theory methods to nuclear data uncertainty propagation using the collision probability method | |
Benchmark for uncertainty analysis in modeling (UAM) for design, operation and safety analyis of LWRs : Version 2.0 | |
Calculations to support In situ neutron yield calibrations at the joint European torus | |
Development of computation schemes for small-sized boron-free PWR. | |
Développement d’un code neutronique stochastique dynamique pour l’analyse de réacteurs nucléaires conventionnels et hybrides. | |
Développement d'un schéma de calcul neutronique pour la modélisation du pilotage des SMR (Small Modular Reactors) sans bore soluble | |
Developpment of qualification and uncertainty quantification method for ASTRID's end-of-cycle neutronic quantities. | |
Efficient generation of energetic ions in multi-ion plasmas by radio-frequency heating | |
Equatorial electron cyclotron port plug neutronic analyses for the EU DEMO | |
ETUDES DES INCERTITUDES SUR LA FLUENCE DANS LES CUVES DES REP. AJUSTEMENT DES DONNEES DE BASE | |
Evaluation and uncertainty analysis of the KRITZ-2 critical benchmark experiments | |
Exploitation du corpus de données expérimentales pour la puissance résiduelle des combustibles de réacteurs à eau pressurisée afin d'accroître la maîtrise des biais et incertitudes de calcul avec l'OCS DARWIN2.3 | |
Exploitation of a corpus of experimental data for the decay heat of pressurized water reactor fuels in order to increase the control of calculation biases and uncertainties with the DARWIN2.3 code. | |
The F4E programme on nuclear data validation and nuclear instrumentation techniques for TBM in ITER | |
FNG copper benchmark evaluation for the SINBAD database | |
Improvement of the modelisation of neutron shielding in sfr and quantification of biases and uncertainties on their design. | |
ITER oriented neutronics benchmark experiments on neu- tron streaming and shutdown dose rate at JET | |
Méthodes de dimensionnement des incertitudes d'une chaine industrielle de calcul cœur | |
Methodology investigations on uncertainties propagation in nuclear data evaluation | |
Modélisation neutronique de coeurs complexes en cinétique multidimensionnelle : application au coeur astrid faible vidange et à la préparation d'expériences de validation | |
The 'neutron deficit' in the JET tokamak | |
Neutronic modeling of complex cores in multidimentional kinetics : application to the low void worth core ASTRID and to the preparation of a validation experiment. | |
Nuclear data adjustment exercise combining information from shielding, critical and kinetics benchmark experiments ASPIS-Iron 88, Popsy and SNEAK-7A/7B | |
Nuclear data sensitivity, uncertainty and target accuracy assessment for future nuclear systems | |
Nuclear well logging modeling using deterministic and Monte Carlo transport computer codes | |
On the universality of power laws for tokamak plasma predictions | |
Pitfalls and modelling incosistencies in computational radiation dosimetry : lessons learnt from the QUADOS intercomparison | |
Plasma cleaning of beryllium coated mirrors | |
Plasma isotopic changeover experiments in JET under carbon and ITER-like wall conditions | |
Plasma position measurement with collimated neutron flux monitor diagnostics on JET | |
Preliminary independent evaluation report of document SSR-NEK-12, Rev. 0 | |
Processed covariance matrices for Ni-60 evaluation | |
Processing of EFF-3 co-variance matrices with extended options and application tests with SUSD3D uncertainty calculations | |
QUADOS intercomparison : a summary of photon and charged particle problems | |
Quantification de l'incertitude du flux neutronique rapide reçu par la cuve d'un réacteur à eau pressurisée. | |
Računska ocena zadostnosti betonske radiološke zaščite pred žarki gama z uporabo "point-kernel" metode | |
Real-Time Implementation in JET of the SPAD Disruption Predictor Using MARTe | |
Report on comparison of evaluated libraries and identification of existing experimental data : Euratom project CHANDA, solving challenges in nuclear data for the safety of European nuclear facilities | |
Resolidification-controlled melt dynamics under fast transient tokamak plasma loads | |
Results of EURADOS Exercise On Neutron Spectrum Unfolding in Bonner Sphere Spectrometry Using GRUPINT | |
ROESTI | |
Role de la banque de donnees de l'AEN dans le domaine des codes de calcul en radioprotection, radiophysique et dosimetrie | |
Role of NBI fuelling in contributing to density peaking between the ICRH and NBI identity plasmas on JET | |
Runaway electron beam control | |
Search for mobilised dust during operations with equipment for remote handling in JET with ITER-like wall | |
Self-consistent coupling of DSMC method and SOLPS code for modeling tokamak particle exhaust | |
Self-consistent pedestal prediction for JET-ILW in preparation of the DT campaign | |
Sensitivity and uncertainty analysis performed on a 14-MeV neutron streaming experiment | |
Shattered pellet injection experiments at JET in support of the ITER disruption mitigation system design | |
Shielding experimental Benchmark storage, retrieval and display system | |
Simulating the nitrogen migration in Be/W tokamaks with WallDYN | |
Simulation of JET ITER-Like Wall pulses at high neon seeding rate | |
SINBAD - a shielding experiments database for data and radiation transport codes validation : Recent data and perspectives | |
SINBAD shielding integral Benchmark archive and database | |
Special section NENE 2011 | |
Stabilization of sawteeth with third harmonic deuterium ICRF-accelerated beam in JET plasmas | |
Stacking of predictors for the automatic classification of disruption types to optimize the control logic | |
Statistical validation of predictive TRANSP simulations of baseline discharges in preparation for extrapolation to JET D-T | |
Studies of dust from JET with the ITER-Like Wall : Composition and internal structure | |
Study of the triton-burnup process in different JET scenarios using neutron monitor based on CVD diamond | |
SUSD3D, a multi-dimensional, discrete ordinates based cross section sensitivity and uncertainty code | |
Synthetic spectra of BeH, BeD and BeT for emission modeling in JET plasmas | |
Technological exploitation of the JET neutron environment : progress in ITER materials irradiation and nuclear analysis | |
Testing of tritium breeder blanket activation foil spectrometer during JET operations | |
TLD calibration for neutron fluence measurements at JET fusion facility | |
Transmission of neutrons and photons generated by 65 MeV protons | |
Uncertainties evaluation methods on an industrial core calculation chain. | |
Uncertainty of the delayed neutron fraction in fuel assembly depletion calculations | |
Uncertainty quantification of the fast flux calculation for a PWR vessel | |
UNCERTAINTY STUDY OF THE PWR PRESSURE VESSEL FLUENCE. ADJUSTMENT OF THE NUCLEAR DATA BASE. | |
Upgrade of the tangential gamma-ray spectrometer beam-line for JET DT experiments | |
The upgraded JET gamma-ray cameras based on high resolution/high count rate compact spectrometers | |
Use of fusion benchmark experiments to validate nuclear data, calculational methods and fusion design | |
Validation of a NTM model using databases of disruptive plasmas at JET | |
Validation of DT source term modelling in MCNP and MCUNED codes against SINBAD fusion benchmarks | |
Validation of IRDF F - v1.04(&v1.05) dosimetry library using SINBAD shielding benchmark experiments | |
Validation of the JEFF-3.1 Nuclear Data Library | |
Variance reduction of fusion and fission neutron transport problems using the ADVANTG hybrid code | |
Verification of oxygen cross section data for oil well logging applications | |
W transport and accumulation control in the termination phase of JET H-mode discharges and implications for ITER | |
Wall conditioning in fusion devices with superconducting coils | |
Water level monitoring after shutdown using neutron and gamma flux measurements in PWR |