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Licensed Unlicensed Requires Authentication Published by De Gruyter August 27, 2019

Contents

From the journal Kerntechnik
https://doi.org/10.3139/124.019042
Published Online: 2019-08-27
Published in Print: 2019-09-16

© 2019, Carl Hanser Verlag, München

From the journal
Kerntechnik
Kerntechnik
Volume 84 Issue 4

Journal and Issue

Articles in the same Issue

Contents/Inhalt
Contents
Editorial
Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2018
Technical Contributions/Fachbeiträge
Development of CASMO5 for VVER-1000/1200 analysis and preliminary validation using critical experiments
C-PORCA 7: a nodal diffusion reactor calculation code to support off-line and on-line core analysis at Paks nuclear power plant
Adaptation of the gas gap simplified model in DYN3D code to new types of fuel
A procedure for verification of Studsvik's spent nuclear fuel code SNF
Extension of nodal diffusion solver of Ants to hexagonal geometry
VVER-1000 fuel assembly model in CAD-based unstructured mesh for MCNP6
Fuel cycles with PK-3+ FAs for VVER-440 reactors
Prospects for implementation of VVER nuclear fuel enriched above 5%
Core loading optimisation in Slovak VVER-440 reactors
Statistical evaluation of C-15 cycles in Paks NPP, based on measured in-core data
Optimized 18-months low-leakage core loadings for uprated VVER-1000
Leningrad NPP-2 start-up loss of power test and its simulation with use of KORSAR/GP code
Assessment of the fuel assembly pin-by-pin model in the KORSAR/GP code
Comparative thermohydraulic analyses of VVER 1000 active core for two different construction types of assemblies
Analysis of uncontrolled dilution of boric acid concentration in the reactor VVER-1000/320
Applied study on optimizing the final disposal of Loviisa NPP spent fuel assemblies
Criticality safety analysis for GNS IQ® – The Integrated Quiver System for damaged fuel
Neutron balance in two-component nuclear energy system
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