| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A fuzzy-based reliability approach to evaluate basic events of fault tree analysis for nuclear power plant probabilistic safety assessment
|
Purba, Julwan Hendry
|
|
2014
|
70 |
C |
p. 21-29
9 p.
|
artikel
|
| 2 |
Analysis of advanced European nuclear fuel cycle scenarios including transmutation and economic estimates
|
Rodríguez, Iván Merino
|
|
2014
|
70 |
C |
p. 240-247
8 p.
|
artikel
|
| 3 |
An evaluation on alternative cutting technologies for decommissioning of the components in a NPP
|
Jeong, Kwan-Seong
|
|
2014
|
70 |
C |
p. 44-47
4 p.
|
artikel
|
| 4 |
A novel approach in optimization problem for research reactors fuel plate using a synergy between cellular automata and quasi-simulated annealing methods
|
Barati, Ramin
|
|
2014
|
70 |
C |
p. 56-63
8 p.
|
artikel
|
| 5 |
Bayesian statistics applied to neutron activation data for reactor flux spectrum analysis
|
Chiesa, Davide
|
|
2014
|
70 |
C |
p. 157-168
12 p.
|
artikel
|
| 6 |
Benchmarking RSG-GAS reactor thermal hydraulic data using RELAP5 code
|
Abdelrazek, I.D.
|
|
2014
|
70 |
C |
p. 36-43
8 p.
|
artikel
|
| 7 |
Comparative study on the effect of reactor internal structure geometry modeling methods on the prediction accuracy for PWR internal flow distribution
|
Lee, Gong Hee
|
|
2014
|
70 |
C |
p. 208-215
8 p.
|
artikel
|
| 8 |
Comparison of fission barrier and level density models for (α,f) reaction of some heavy nuclei
|
Sarpün, İsmail H.
|
|
2014
|
70 |
C |
p. 175-179
5 p.
|
artikel
|
| 9 |
Comparison of flow instabilities under static condition and marine motion conditions based on experiments
|
Tang, Yu
|
|
2014
|
70 |
C |
p. 11-20
10 p.
|
artikel
|
| 10 |
Current status of CHF predictions using CFD modeling technique and review of other techniques especially for non-uniform axial and circumferential heating profiles
|
Habib, M.A.
|
|
2014
|
70 |
C |
p. 188-207
20 p.
|
artikel
|
| 11 |
Development of a code FITWR for nuclear cross section statistical analysis
|
Alrwashdeh, Mohammad
|
|
2014
|
70 |
C |
p. 130-134
5 p.
|
artikel
|
| 12 |
Editorial board
|
|
|
2014
|
70 |
C |
p. IFC-
1 p.
|
artikel
|
| 13 |
Effects of Ni, Fe chemicals and hydrogen on deposits formed on Zirlo fuel cladding material in nuclear primary water chemistry conditions at 325°C
|
Baek, S.H.
|
|
2014
|
70 |
C |
p. 233-239
7 p.
|
artikel
|
| 14 |
Feasibility of shock attenuation by simple obstacles in mitigating severe accident explosive loads
|
Park, Jong-Woon
|
|
2014
|
70 |
C |
p. 109-121
13 p.
|
artikel
|
| 15 |
Implementation of hybrid simulation schemes in COBAYA3/SUBCHANFLOW coupled codes for the efficient direct prediction of local safety parameters
|
Calleja, M.
|
|
2014
|
70 |
C |
p. 216-229
14 p.
|
artikel
|
| 16 |
Issues of operating systems usage for nuclear power plants
|
Andryushin, Alexander
|
|
2014
|
70 |
C |
p. 87-89
3 p.
|
artikel
|
| 17 |
Modeling space–time evolution of flux in a traveling wave reactor
|
Shrestha, Rijan
|
|
2014
|
70 |
C |
p. 90-95
6 p.
|
artikel
|
| 18 |
Modification and analysis of load follow control without boron adjustment for CPR1000
|
Wang, Li
|
|
2014
|
70 |
C |
p. 317-328
12 p.
|
artikel
|
| 19 |
Molten metal and water direct contact interaction research – II. Numerical analysis
|
Lin, Meng
|
|
2014
|
70 |
C |
p. 256-265
10 p.
|
artikel
|
| 20 |
Molten metal and water direct contact interaction research – I. Photographic experiment study
|
Zhou, Yuan
|
|
2014
|
70 |
C |
p. 248-255
8 p.
|
artikel
|
| 21 |
Non-classical particle transport with angular-dependent path-length distributions. II: Application to pebble bed reactor cores
|
Vasques, Richard
|
|
2014
|
70 |
C |
p. 301-311
11 p.
|
artikel
|
| 22 |
Non-classical particle transport with angular-dependent path-length distributions. I: Theory
|
Vasques, Richard
|
|
2014
|
70 |
C |
p. 292-300
9 p.
|
artikel
|
| 23 |
On prompt fission neutron spectrum in spontaneous fission of 252 Cf
|
Koçak, M.
|
|
2014
|
70 |
C |
p. 82-86
5 p.
|
artikel
|
| 24 |
On the numerical solution of the neutron fractional diffusion equation
|
Maleki Moghaddam, Nader
|
|
2014
|
70 |
C |
p. 1-10
10 p.
|
artikel
|
| 25 |
Optimization of automation: I. Estimation method of cognitive automation rates reflecting the effects of automation on human operators in nuclear power plants
|
Lee, Seung Min
|
|
2014
|
70 |
C |
p. 48-55
8 p.
|
artikel
|
| 26 |
Predictive modeling of coupled multi-physics systems: II. Illustrative application to reactor physics
|
Cacuci, Dan Gabriel
|
|
2014
|
70 |
C |
p. 279-291
13 p.
|
artikel
|
| 27 |
Predictive modeling of coupled multi-physics systems: I. Theory
|
Cacuci, Dan Gabriel
|
|
2014
|
70 |
C |
p. 266-278
13 p.
|
artikel
|
| 28 |
Remarks on the extension and validity of an empirical formula for the fast-neutron removal cross-section: The effective atomic weight
|
Kurudirek, M.
|
|
2014
|
70 |
C |
p. 230-232
3 p.
|
artikel
|
| 29 |
Safety analysis and optimization of the core fuel reloading for the Moroccan TRIGA Mark-II reactor
|
Nacir, B.
|
|
2014
|
70 |
C |
p. 312-316
5 p.
|
artikel
|
| 30 |
Safety evaluation of the modified auxiliary feedwater system for the Chinese improved PWR
|
Tong, L.L.
|
|
2014
|
70 |
C |
p. 169-174
6 p.
|
artikel
|
| 31 |
Simulation of leaking fuel rods in a VVER reactor
|
Hózer, Zoltán
|
|
2014
|
70 |
C |
p. 122-129
8 p.
|
artikel
|
| 32 |
Simulation of the behaviour of nuclear fuel under high burnup conditions
|
Soba, Alejandro
|
|
2014
|
70 |
C |
p. 147-156
10 p.
|
artikel
|
| 33 |
Software FMEA analysis for safety-related application software
|
Park, Gee-Yong
|
|
2014
|
70 |
C |
p. 96-102
7 p.
|
artikel
|
| 34 |
System–CFD coupled simulations of flow instability in steam generator U tubes
|
Watanabe, Tadashi
|
|
2014
|
70 |
C |
p. 141-146
6 p.
|
artikel
|
| 35 |
The effect of inner ring modification of standard 37-element fuel on CHF enhancement
|
Park, Joo Hwan
|
|
2014
|
70 |
C |
p. 135-140
6 p.
|
artikel
|
| 36 |
Thermal hydraulic effect of porous blockage in fuel subassembly of sodium cooled fast reactor
|
Govindha Rasu, N.
|
|
2014
|
70 |
C |
p. 64-81
18 p.
|
artikel
|
| 37 |
Two-dimensional Haar wavelet Collocation Method for the solution of Stationary Neutron Transport Equation in a homogeneous isotropic medium
|
Patra, A.
|
|
2014
|
70 |
C |
p. 30-35
6 p.
|
artikel
|
| 38 |
Uncertainty analysis using Beta-Bayesian approach in nuclear safety code validation
|
Deng, Chengcheng
|
|
2014
|
70 |
C |
p. 103-108
6 p.
|
artikel
|
| 39 |
Upper limits to americium concentration in large sized sodium-cooled fast reactors loaded with metallic fuel
|
Zhang, Youpeng
|
|
2014
|
70 |
C |
p. 180-187
8 p.
|
artikel
|
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