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 |