nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
A causal model explaining Chinese university students' acceptance of nuclear power
|
Wang, Yongxiang |
|
2016 |
88 |
C |
p. 165-174 10 p. |
artikel |
2 |
Adaptive burnup stepsize selection using control theory for 2-D lattice depletion simulations
|
Walter, Daniel J. |
|
2016 |
88 |
C |
p. 218-230 13 p. |
artikel |
3 |
Analyses of ACME integral test results on CAP1400 small-break loss-of-coolant-accident transient
|
Li, Yu Quan |
|
2016 |
88 |
C |
p. 375-397 23 p. |
artikel |
4 |
An approach based on Support Vector Machines and a K-D Tree search algorithm for identification of the failure domain and safest operating conditions in nuclear systems
|
Di Maio, Francesco |
|
2016 |
88 |
C |
p. 297-309 13 p. |
artikel |
5 |
An evaluation of nuclide release from a trench-type LILW repository
|
Lee, Youn-Myoung |
|
2016 |
88 |
C |
p. 95-103 9 p. |
artikel |
6 |
Application of vadose zone approach for prediction of radionuclide transfer from near-surface disposal facility
|
Jakimavičiūtė-Maselienė, Vaidotė |
|
2016 |
88 |
C |
p. 53-57 5 p. |
artikel |
7 |
Are shocks to nuclear energy consumption per capita permanent or temporary? A global perspective
|
Zhu, Huiming |
|
2016 |
88 |
C |
p. 156-164 9 p. |
artikel |
8 |
A sensitivity analysis of thermal lattices kinetic parameters with respect to the spectral weighting function using ultrafine BN method
|
Fallah, Vahid Farhang |
|
2016 |
88 |
C |
p. 310-320 11 p. |
artikel |
9 |
Benchmarking verification of the control rod effects on the MTR core parameters using the MTR-PC and MCNP codes throughout 3D core modeling and rod-drop experiment
|
Hedayat, Afshin |
|
2016 |
88 |
C |
p. 183-190 8 p. |
artikel |
10 |
Calculation of radial burnup and nuclides atom density distributions in a VVER-1000 fuel rod using Monte Carlo method
|
Pirouzmand, Ahmad |
|
2016 |
88 |
C |
p. 321-331 11 p. |
artikel |
11 |
Calculation of six-group importance weighted delayed neutron fractions and prompt neutron lifetime of MTR research reactors based on Monte Carlo method
|
Arkani, Mohammad |
|
2016 |
88 |
C |
p. 352-363 12 p. |
artikel |
12 |
Composition, decomposition and analysis of reactor antineutrino and electron spectra based on gross theory of β-decay and summation method
|
Yoshida, Tadashi |
|
2016 |
88 |
C |
p. 175-182 8 p. |
artikel |
13 |
Considerations for severe accident management under extended station blackout conditions in nuclear power plants
|
Park, Jong Woon |
|
2016 |
88 |
C |
p. 245-256 12 p. |
artikel |
14 |
Control rod drop hydrodynamic analysis for a pressurized water reactor
|
Rabiee, Ataollah |
|
2016 |
88 |
C |
p. 191-197 7 p. |
artikel |
15 |
Corrosion mitigation in coolant systems in nuclear power plants
|
Chajduk, Ewelina |
|
2016 |
88 |
C |
p. 1-9 9 p. |
artikel |
16 |
Dancoff factor analysis for pebble bed fluoride salt cooled high temperature reactor
|
Qin, Wei |
|
2016 |
88 |
C |
p. 332-339 8 p. |
artikel |
17 |
3D in-core fuel management optimization for breed-and-burn reactors
|
Hou, Jason (Jia) |
|
2016 |
88 |
C |
p. 58-74 17 p. |
artikel |
18 |
Drying kinetics of thorium oxalate: Experimental investigation and modeling
|
Beigi, Sadegh |
|
2016 |
88 |
C |
p. 240-244 5 p. |
artikel |
19 |
Editorial Board
|
|
|
2016 |
88 |
C |
p. IFC- 1 p. |
artikel |
20 |
Effect of compensation error in drift-flux parameters on predictions of thermal-hydraulic parameters in nuclear safety system analysis codes
|
Ozaki, Tetsuhiro |
|
2016 |
88 |
C |
p. 398-411 14 p. |
artikel |
21 |
Estimation of the fast neutron fluence in Laguna Verde RPV-Steel specimens simulating their irradiation in a TRIGA reactor
|
Galicia-Aragón, Juan |
|
2016 |
88 |
C |
p. 264-276 13 p. |
artikel |
22 |
Forced convection condensation in the presence of noncondensable gas in a horizontal tube; experimental and theoretical study
|
Xu, Huiqiang |
|
2016 |
88 |
C |
p. 340-351 12 p. |
artikel |
23 |
Implementation of cyber security for safety systems of nuclear facilities
|
Park, JaeKwan |
|
2016 |
88 |
C |
p. 88-94 7 p. |
artikel |
24 |
Implementation of the batch composition preserving genetic algorithm for burn up extension of a typical PWR
|
Ilyas, Muhammad |
|
2016 |
88 |
C |
p. 257-263 7 p. |
artikel |
25 |
Implicitly solving phase appearance and disappearance problems using two-fluid six-equation model
|
Zou, Ling |
|
2016 |
88 |
C |
p. 198-210 13 p. |
artikel |
26 |
Lumped pseudo fission products during burnup step in MCNP5-ORIGEN coupling system
|
Benkharfia, Hocine |
|
2016 |
88 |
C |
p. 277-284 8 p. |
artikel |
27 |
Microstructural evolution of as-cast Th–U alloys
|
Das, Santanu |
|
2016 |
88 |
C |
p. 285-296 12 p. |
artikel |
28 |
Modeling analyses of radioactive aerosol flow and collection in mesoscopic impactor filters
|
Niu, Fenglei |
|
2016 |
88 |
C |
p. 147-155 9 p. |
artikel |
29 |
Modeling and simulation of radio-iodine released inside the containment as result of an accident
|
Mehboob, Khurram |
|
2016 |
88 |
C |
p. 75-87 13 p. |
artikel |
30 |
Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code system
|
Margulis, Marat |
|
2016 |
88 |
C |
p. 118-133 16 p. |
artikel |
31 |
Neutronic evaluation of coating and cladding materials for accident tolerant fuels
|
Younker, Ian |
|
2016 |
88 |
C |
p. 10-18 9 p. |
artikel |
32 |
Nuclear energy, renewable energy, CO2 emissions, and economic growth for nine developed countries: Evidence from panel Granger causality tests
|
Saidi, Kais |
|
2016 |
88 |
C |
p. 364-374 11 p. |
artikel |
33 |
On an improved box-scheme finite difference method based on the relative event probabilities
|
Vagheian, Mehran |
|
2016 |
88 |
C |
p. 33-42 10 p. |
artikel |
34 |
On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology
|
Alhassan, E. |
|
2016 |
88 |
C |
p. 43-52 10 p. |
artikel |
35 |
Preliminary safety analysis on loss of flow accidents and external source transients for LBE cooled ADSR core
|
Lu, Tianyu |
|
2016 |
88 |
C |
p. 134-146 13 p. |
artikel |
36 |
Pressure distribution in the containment of VVER-1000 during the first seconds of large break LOCA
|
Rahgoshay, M. |
|
2016 |
88 |
C |
p. 211-217 7 p. |
artikel |
37 |
PWR few-group constants parameterization analysis
|
Li, Yunzhao |
|
2016 |
88 |
C |
p. 104-117 14 p. |
artikel |
38 |
Reactivity temperature coefficients for the HEU and LEU fuel of the MNSR reactor
|
Dawahra, S. |
|
2016 |
88 |
C |
p. 28-32 5 p. |
artikel |
39 |
Safety analysis of LBLOCA in BDBA scenarios for the Bushehr's VVER-1000 nuclear power plant
|
Pirouzmand, Ahmad |
|
2016 |
88 |
C |
p. 231-239 9 p. |
artikel |
40 |
Space independent xenon oscillations control in VVER reactor: A bifurcation analysis approach
|
Zarei, M. |
|
2016 |
88 |
C |
p. 19-27 9 p. |
artikel |