| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Activation cross sections for the (γ,n) reactions on zirconium isotopes
|
Akkurt, İskender
|
|
2014
|
65 |
C |
p. 181-183
3 p.
|
artikel
|
| 2 |
A development of a quantitative situation awareness measurement tool: Computational Representation of Situation Awareness with Graphical Expressions (CoRSAGE)
|
Yim, Ho Bin
|
|
2014
|
65 |
C |
p. 144-157
14 p.
|
artikel
|
| 3 |
Advanced surveillance of Resistance Temperature Detectors in Nuclear Power Plants
|
Montalvo, C.
|
|
2014
|
65 |
C |
p. 35-40
6 p.
|
artikel
|
| 4 |
A general method for developing friction factor formulas under supercritical conditions and in different geometries
|
Zang, Jinguang
|
|
2014
|
65 |
C |
p. 262-271
10 p.
|
artikel
|
| 5 |
A method for on-line reactivity monitoring in nuclear reactors
|
Dulla, S.
|
|
2014
|
65 |
C |
p. 433-440
8 p.
|
artikel
|
| 6 |
A multi layer core catcher concept for future sodium cooled fast reactors
|
Jasmin Sudha, A.
|
|
2014
|
65 |
C |
p. 253-261
9 p.
|
artikel
|
| 7 |
An investigation on unintended reactor trip events in terms of human error hazards of Korean nuclear power plants
|
Kim, Sa Kil
|
|
2014
|
65 |
C |
p. 223-231
9 p.
|
artikel
|
| 8 |
A note on the mixture viscosity using the Shannak definition
|
Awad, M.M.
|
|
2014
|
65 |
C |
p. 239-240
2 p.
|
artikel
|
| 9 |
A preliminary neutronic evaluation of the high temperature nuclear reactor (HTTR) using reprocessed fuel
|
Sousa, R.V.
|
|
2014
|
65 |
C |
p. 232-238
7 p.
|
artikel
|
| 10 |
Assessment of the performance of the spectral element method applied to neutron transport problems
|
Barbarino, A.
|
|
2014
|
65 |
C |
p. 190-198
9 p.
|
artikel
|
| 11 |
Benchmark analysis of SPERT-IV reactor with Monte Carlo code MVP
|
Motalab, M.A.
|
|
2014
|
65 |
C |
p. 365-369
5 p.
|
artikel
|
| 12 |
Bivariate empirical mode decomposition applied to the estimation of out-of-phase oscillations in BWR
|
Prieto-Guerrero, Alfonso
|
|
2014
|
65 |
C |
p. 247-252
6 p.
|
artikel
|
| 13 |
CAB models for water: A new evaluation of the thermal neutron scattering laws for light and heavy water in ENDF-6 format
|
Márquez Damián, J.I.
|
|
2014
|
65 |
C |
p. 280-289
10 p.
|
artikel
|
| 14 |
Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: Analytical, deterministic and Monte Carlo approaches
|
Aufiero, Manuele
|
|
2014
|
65 |
C |
p. 78-90
13 p.
|
artikel
|
| 15 |
Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code
|
Leppänen, Jaakko
|
|
2014
|
65 |
C |
p. 272-279
8 p.
|
artikel
|
| 16 |
CFD investigating the flow characteristics in a triangular-pitch rod bundle using Reynolds stress turbulence model
|
Lin, Chih-Hung
|
|
2014
|
65 |
C |
p. 357-364
8 p.
|
artikel
|
| 17 |
Coarse mesh finite difference formulation for accelerated Monte Carlo eigenvalue calculation
|
Lee, Min Jae
|
|
2014
|
65 |
C |
p. 101-113
13 p.
|
artikel
|
| 18 |
Conceptual design study of Hyb-WT as fusion–fission hybrid reactor for waste transmutation
|
Siddique, Muhammad Tariq
|
|
2014
|
65 |
C |
p. 299-306
8 p.
|
artikel
|
| 19 |
Core designs based on research reactors for neutron transmutation doping of silicon
|
Komeda, Masao
|
|
2014
|
65 |
C |
p. 338-344
7 p.
|
artikel
|
| 20 |
Core loading pattern optimization of a typical two-loop 300MWe PWR using Simulated Annealing (SA), novel crossover Genetic Algorithms (GA) and hybrid GA(SA) schemes
|
Zameer, Aneela
|
|
2014
|
65 |
C |
p. 122-131
10 p.
|
artikel
|
| 21 |
Corrigendum to “Experimental study on onset of nucleate boiling in narrow rectangular channel under static and heaving conditions” [Ann. Nucl. Energy 39 (2012) 26–34]
|
Hong, Gang
|
|
2014
|
65 |
C |
p. 307-
1 p.
|
artikel
|
| 22 |
Coupled neutronic/thermo-hydraulic analysis of water/Al2O3 nanofluids in a VVER-1000 reactor
|
Safarzadeh, O.
|
|
2014
|
65 |
C |
p. 72-77
6 p.
|
artikel
|
| 23 |
Cyber security issues imposed on nuclear power plants
|
Kim, Do-Yeon
|
|
2014
|
65 |
C |
p. 141-143
3 p.
|
artikel
|
| 24 |
Delayed neutron measurements with a natural uranium fission product source in Fast Breeder Test Reactor
|
Srinivasan, G.
|
|
2014
|
65 |
C |
p. 314-319
6 p.
|
artikel
|
| 25 |
D–T neutron generators as a feasibility tool for landmine detection based on neutron backscattering method
|
Masoudi, S. Farhad
|
|
2014
|
65 |
C |
p. 441-445
5 p.
|
artikel
|
| 26 |
Editorial board
|
|
|
2014
|
65 |
C |
p. IFC-
1 p.
|
artikel
|
| 27 |
Effect of physical, chemical and electro-kinetic properties of pumice samples on radiation shielding properties of pumice material
|
Tapan, Mücip
|
|
2014
|
65 |
C |
p. 290-298
9 p.
|
artikel
|
| 28 |
Excitation functions of the 90,91,92,94,96Zr(n,p) reactions from reaction threshold to 20MeV
|
Suchiang, Damewan
|
|
2014
|
65 |
C |
p. 97-100
4 p.
|
artikel
|
| 29 |
Experimental studies in water for safety grade decay heat removal of prototype fast breeder reactor
|
Mente, V.M.
|
|
2014
|
65 |
C |
p. 114-121
8 p.
|
artikel
|
| 30 |
Experimental study of bypass flow in near wall gaps of a pebble bed reactor using hot wire anemometry technique
|
Amini, Noushin
|
|
2014
|
65 |
C |
p. 60-71
12 p.
|
artikel
|
| 31 |
FSN-based fault modeling in CANDU® stations
|
Nasimi, Elnara
|
|
2014
|
65 |
C |
p. 325-337
13 p.
|
artikel
|
| 32 |
Global environmental transfer of 129I
|
Sunny, Faby
|
|
2014
|
65 |
C |
p. 320-324
5 p.
|
artikel
|
| 33 |
In vessel detection of delayed neutron emitters from clad failure in sodium cooled nuclear reactors: Information treatment
|
Filliatre, P.
|
|
2014
|
65 |
C |
p. 385-389
5 p.
|
artikel
|
| 34 |
Investigation of microstructure and mechanical properties of low dose neutron irradiated HT-9 steel
|
Sarkar, A.
|
|
2014
|
65 |
C |
p. 91-96
6 p.
|
artikel
|
| 35 |
Modeling and system analysis of fuel cycles for nuclear power sustainability (I): Uranium consumption and waste generation
|
Gao, Fanxing
|
|
2014
|
65 |
C |
p. 10-23
14 p.
|
artikel
|
| 36 |
Modeling of control rod ejection transient for WWER-1000-model 446 using RELAP5m3.3/PARCSv2.6 coupled codes
|
Pesaran, Farshad
|
|
2014
|
65 |
C |
p. 411-420
10 p.
|
artikel
|
| 37 |
Motion and volume change of tumor tissue depending on patient position in liver cancer treatment with use of tomotherapy
|
Kim, Young-Jae
|
|
2014
|
65 |
C |
p. 174-180
7 p.
|
artikel
|
| 38 |
Natural radioactivity distribution of southern part of Jordan (Ma′an) Soil
|
Saleh, H.
|
|
2014
|
65 |
C |
p. 184-189
6 p.
|
artikel
|
| 39 |
Non-linear time series analysis on flow instability of natural circulation under rolling motion condition
|
Zhang, Wenchao
|
|
2014
|
65 |
C |
p. 1-9
9 p.
|
artikel
|
| 40 |
Numerical simulation of molten droplet deformation and disintegration under sudden accelerations
|
Mingjun, Zhong
|
|
2014
|
65 |
C |
p. 199-206
8 p.
|
artikel
|
| 41 |
On the stability of the Discrete Generalized Multigroup method
|
Gibson, Nathan A.
|
|
2014
|
65 |
C |
p. 421-432
12 p.
|
artikel
|
| 42 |
Photon transport effect on intra-subassembly thermal power distribution in fast reactor
|
Chiba, Go
|
|
2014
|
65 |
C |
p. 41-46
6 p.
|
artikel
|
| 43 |
Practical application of the MARSSIM process to the site release of a Uranium Conversion Plant following decommissioning
|
Hong, Sang Bum
|
|
2014
|
65 |
C |
p. 241-246
6 p.
|
artikel
|
| 44 |
Prediction of wall friction factor in horizontal annular flow using the asymptotic method
|
Awad, M.M.
|
|
2014
|
65 |
C |
p. 308-313
6 p.
|
artikel
|
| 45 |
Predictions of hydrodynamic characteristics and corrosion rates using CFD in the piping systems of pressurized-water reactor power plant
|
Lin, Chih Hung
|
|
2014
|
65 |
C |
p. 214-222
9 p.
|
artikel
|
| 46 |
Preliminary safety evaluation for CSR1000 with passive safety system
|
Wu, Pan
|
|
2014
|
65 |
C |
p. 390-401
12 p.
|
artikel
|
| 47 |
Radiation protection protocol for environmental defense using nano-scopic water spray in nuclear accident
|
Woo, Tae Ho
|
|
2014
|
65 |
C |
p. 30-34
5 p.
|
artikel
|
| 48 |
Research on two-phase flow instability in parallel rectangular channels
|
Qian, Libo
|
|
2014
|
65 |
C |
p. 47-59
13 p.
|
artikel
|
| 49 |
Review and comparison of effective delayed neutron fraction calculation methods with Monte Carlo codes
|
Bécares, V.
|
|
2014
|
65 |
C |
p. 402-410
9 p.
|
artikel
|
| 50 |
Severe accident research at the Transuranium Institute Karlsruhe: A review of past experience and its application to future challenges
|
Bottomley, P.D.W.
|
|
2014
|
65 |
C |
p. 345-356
12 p.
|
artikel
|
| 51 |
Simulation and dose analysis of a hypothetical accident in Sanmen nuclear power plant
|
Zhu, Yangmo
|
|
2014
|
65 |
C |
p. 207-213
7 p.
|
artikel
|
| 52 |
Simulation of rod ejection accident in a WWER-1000 Nuclear Reactor by using PARCS code
|
Noori-Kalkhoran, Omid
|
|
2014
|
65 |
C |
p. 132-140
9 p.
|
artikel
|
| 53 |
Solving the static-neutron diffusion equation in 2D-Cartesian geometry with Lagrange interpolation
|
Quintero-Leyva, Barbaro
|
|
2014
|
65 |
C |
p. 370-375
6 p.
|
artikel
|
| 54 |
Spherical shields perturbed to ellipsoids in transport theory
|
Favorite, Jeffrey A.
|
|
2014
|
65 |
C |
p. 376-384
9 p.
|
artikel
|
| 55 |
The Direct-Zeff software for direct calculation of mass attenuation coefficient, effective atomic number and effective electron number
|
Un, Adem
|
|
2014
|
65 |
C |
p. 158-165
8 p.
|
artikel
|
| 56 |
The effect of strongly anisotropic scattering on the critical size of a slab in one-speed neutron transport theory: Modified U N method
|
Öztürk, Hakan
|
|
2014
|
65 |
C |
p. 24-29
6 p.
|
artikel
|
| 57 |
Topographical global optimization applied to nuclear reactor core design: Some preliminary results
|
Sacco, Wagner F.
|
|
2014
|
65 |
C |
p. 166-173
8 p.
|
artikel
|
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