Development of AC2 for the simulation of advanced reactor design of Generation 3/3+ and light water cooled SMRs
来源期刊:KerntechnikDOI:10.3139/124.190068
Validation of the AC2 Codes ATHLET and ATHLET-CD
来源期刊:KerntechnikDOI:10.3139/124.190069
Natural radioactive risk assessment in top soil and possible health effect in Minim and Martap villages, Cameroon: using radioactive risk index and statistical analysis
来源期刊:KerntechnikDOI:10.3139/124.110927
New research reactor protection system
来源期刊:KerntechnikDOI:10.3139/124.110935
Core loading optimisation in Slovak VVER-440 reactors
来源期刊:KerntechnikDOI:10.3139/124.190024
Statistical evaluation of C-15 cycles in Paks NPP, based on measured in-core data
来源期刊:KerntechnikDOI:10.3139/124.190028
ATWS severe accident analysis in the loss of flow scenario using the MELCOR code in Bushehr nuclear Power Plant
来源期刊:KerntechnikDOI:10.3139/124.110914
Validation and Application of the AC2 Code COCOSYS
来源期刊:KerntechnikDOI:10.3139/124.190066
Effect of reactor operator intervention during unprotected LOFA in a typical MTR
来源期刊:KerntechnikDOI:10.3139/124.110874
Numerical study on cut-off diameter of aerosol particle for filtered containment venting system in nuclear power plant
来源期刊:KerntechnikDOI:10.3139/124.110971
Seasonally gross alpha and beta activity concentration in bottom and mid-depth water in Sır Dam Pond (Kahramanmaras, Turkey)
来源期刊:KerntechnikDOI:10.3139/124.110984
Numerical prediction of single-phase flow mixing characteristics in a 1/12th of the cross segment of a 54-rod bundle
来源期刊:KerntechnikDOI:10.3139/124.110977
Method based on directed graph and binary decision diagram to break logic loops
来源期刊:KerntechnikDOI:10.3139/124.110921
Analysis of uncontrolled dilution of boric acid concentration in the reactor VVER-1000/320
来源期刊:KerntechnikDOI:10.3139/124.190015
Experimental study on penetration characteristic of submerged steam jet in quiescent water
来源期刊:KerntechnikDOI:10.3139/124.190036
Validation of COCOSYS 2.4v4 AIM module on various single effect and integral experiments
来源期刊:KerntechnikDOI:10.3139/124.190045
Adaptation of the gas gap simplified model in DYN3D code to new types of fuel
来源期刊:KerntechnikDOI:10.3139/124.190029
CFD code-to-code benchmarking on simulation of fire and smoke propagation for nuclear applications
来源期刊:KerntechnikDOI:10.3139/124.190060
Prospects for implementation of VVER nuclear fuel enriched above 5%
来源期刊:KerntechnikDOI:10.3139/124.190023
Reanalysis of environmental qualification radiation parameters for Kuosheng nuclear power plant
来源期刊:KerntechnikDOI:10.3139/124.110961
Ultimate response guideline strategy evaluation for Maanshan power plant
来源期刊:KerntechnikDOI:10.3139/124.110891
C-PORCA 7: a nodal diffusion reactor calculation code to support off-line and on-line core analysis at Paks nuclear power plant
来源期刊:KerntechnikDOI:10.3139/124.190021
Flow and heat transfer characteristics in rough micro-channels
来源期刊:KerntechnikDOI:10.3139/124.190001
VVER-1000 fuel assembly model in CAD-based unstructured mesh for MCNP6
来源期刊:KerntechnikDOI:10.3139/124.190041
Criticality safety analysis for GNS IQ® – The Integrated Quiver System for damaged fuel
来源期刊:KerntechnikDOI:10.3139/124.190032
Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2018
来源期刊:KerntechnikDOI:10.3139/124.019041
Analysis of the melt spreading and MCCI during the ex-vessel phase of a severe accident in WWER-1000
来源期刊:KerntechnikDOI:10.3139/124.190010
CFD code-to-code benchmarking on simulation of fire and smoke propagation for nuclear applications
来源期刊:KerntechnikDOI:10.3139/kern-2019-840607
Flow and heat transfer characteristics in rough micro-channels
来源期刊:KerntechnikDOI:10.3139/kern-2019-840609
Control rod material effect on safety parameters of research reactors
来源期刊:KerntechnikDOI:10.3139/124.110989
Benchmark study of OPAL research reactor using MCNP codes
来源期刊:KerntechnikDOI:10.3139/124.190037
Comparative analysis of simulations of LIVE-L10 and -L11 experiments using different lower head modules of AC2
来源期刊:KerntechnikDOI:10.3139/124.190034
Benchmark study of OPAL research reactor using MCNP codes
来源期刊:KerntechnikDOI:10.3139/kern-2019-840605
Method based on directed graph and binary decision diagram to break logic loops
来源期刊:KerntechnikDOI:10.3139/kern-2019-840606
Operating experience feedback from incidental fluctuations of the power measurement channel at ETRR-2
来源期刊:KerntechnikDOI:10.3139/kern-2019-840604
Assessment of the fuel assembly pin-by-pin model in the KORSAR/GP code
来源期刊:KerntechnikDOI:10.3139/124.190027
TRACE simulations of IIST cooldown experiments
来源期刊:KerntechnikDOI:10.3139/kern-2019-840608
TRACE simulations of IIST cooldown experiments
来源期刊:KerntechnikDOI:10.3139/124.190090
Thermal hydraulic characteristics of two-phase natural circulation for secondary side passive residual heat removal system
来源期刊:KerntechnikDOI:10.3139/kern-2019-840610
Fuel cycles with PK-3+ FAs for VVER-440 reactors
来源期刊:KerntechnikDOI:10.3139/124.190022
Assessment of the health damage costs of radionuclides releases from Muğla provinces lignite-fired power plants
来源期刊:KerntechnikDOI:10.3139/124.110924
GRS Code System AC2
来源期刊:KerntechnikDOI:10.3139/124.019051
Operating experience feedback from incidental fluctuations of the power measurement channel at ETRR-2
来源期刊:KerntechnikDOI:10.3139/124.190053
Thermal hydraulic characteristics of two-phase natural circulation for secondary side passive residual heat removal system
来源期刊:KerntechnikDOI:10.3139/124.190062
The core shroud leakage analysis and study for Kuosheng nuclear power plant
来源期刊:KerntechnikDOI:10.3139/124.110986
Leningrad NPP-2 start-up loss of power test and its simulation with use of KORSAR/GP code
来源期刊:KerntechnikDOI:10.3139/124.190026
Coupling simulation of neutron kinetics core model with CFD of IPWR steam line break accident
来源期刊:KerntechnikDOI:10.3139/124.110979
New developments in the thermal hydraulic module THY of the COCOSYS program, part of the AC2 software package: turbulence in gaseous countercurrent flows
来源期刊:KerntechnikDOI:10.3139/124.190078
Research on multi-scale simulation model for single-phase water pipe networks
来源期刊:KerntechnikDOI:10.3139/124.110997
Comparative thermohydraulic analyses of VVER 1000 active core for two different construction types of assemblies
来源期刊:KerntechnikDOI:10.3139/124.190019