| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Adjoint eigenvalue correction for elliptic and hyperbolic neutron transport problems
|
Merton, S.R.
|
|
2014
|
76 |
C |
p. 1-16
16 p.
|
artikel
|
| 2 |
A new hybrid method for multi-objective fuel management optimization using parallel PSO-SA
|
Khoshahval, F.
|
|
2014
|
76 |
C |
p. 112-121
10 p.
|
artikel
|
| 3 |
A study of bubble behaviors in the volumetrically heated packed bed
|
Xu, Guangzhan
|
|
2014
|
76 |
C |
p. 100-105
6 p.
|
artikel
|
| 4 |
Calculation of the NEA C5G7 MOX benchmark with MCNP5
|
Reda, Sonia M.
|
|
2014
|
76 |
C |
p. 244-254
11 p.
|
artikel
|
| 5 |
Characteristics of slug flow in a narrow rectangular channel under inclined conditions
|
Wang, Yang
|
|
2014
|
76 |
C |
p. 24-35
12 p.
|
artikel
|
| 6 |
Developing a practical optimization of the refueling program for ordinary research reactors using a modified simulated annealing method
|
Hedayat, Afshin
|
|
2014
|
76 |
C |
p. 191-205
15 p.
|
artikel
|
| 7 |
Drift flux modeling of the VVER-1000 horizontal nuclear steam generator
|
Ghazanfari, V.
|
|
2014
|
76 |
C |
p. 36-43
8 p.
|
artikel
|
| 8 |
Editorial Board
|
|
|
2014
|
76 |
C |
p. IFC-
1 p.
|
artikel
|
| 9 |
Experimental and numerical study of the laminar flow in helically coiled pipes
|
De Amicis, Jacopo
|
|
2014
|
76 |
C |
p. 206-215
10 p.
|
artikel
|
| 10 |
Fuzzy probability on reliability study of nuclear power plant probabilistic safety assessment: A review
|
Purba, Julwan Hendry
|
|
2014
|
76 |
C |
p. 73-80
8 p.
|
artikel
|
| 11 |
Hybrid-transport point kinetics for initially-critical multiplying systems
|
Picca, Paolo
|
|
2014
|
76 |
C |
p. 232-243
12 p.
|
artikel
|
| 12 |
Improvement of fault diagnosis efficiency in nuclear power plants using hybrid intelligence approach
|
Liu, Yong-kuo
|
|
2014
|
76 |
C |
p. 122-136
15 p.
|
artikel
|
| 13 |
Investigations on single-phase natural circulation loop dynamics part 1: Model for simulating start-up from rest
|
Naveen, Kumar
|
|
2014
|
76 |
C |
p. 148-159
12 p.
|
artikel
|
| 14 |
Modified Bi-parametric Method for optimization of BWR fuel reload patterns
|
Perusquía, Raúl
|
|
2014
|
76 |
C |
p. 255-268
14 p.
|
artikel
|
| 15 |
Nuclear criticality accident safety, near misses and classification
|
Hodges, Matthew S.
|
|
2014
|
76 |
C |
p. 88-99
12 p.
|
artikel
|
| 16 |
Reducing axial offset and improving stability in PWRs by using uranium–thorium fuel
|
Lau, Cheuk Wah
|
|
2014
|
76 |
C |
p. 137-147
11 p.
|
artikel
|
| 17 |
Salinity independent volume fraction prediction in annular and stratified (water–gas–oil) multiphase flows using artificial neural networks
|
Salgado, César M.
|
|
2014
|
76 |
C |
p. 17-23
7 p.
|
artikel
|
| 18 |
Strategy, culture and safety
|
Garcés, Mª Isabel
|
|
2014
|
76 |
C |
p. 81-87
7 p.
|
artikel
|
| 19 |
Study of XeF2 fluorination potential against Rh2O3, RuO2, ZrO2, and U3O8 for use in reactive gas recycle of used nuclear fuel
|
Inabinett, D.
|
|
2014
|
76 |
C |
p. 106-111
6 p.
|
artikel
|
| 20 |
The development of Module In-vessel degraded severe accident Analysis Code MIDAC and the relevant research for CPR1000 during the station blackout scenario
|
Wang, Jun
|
|
2014
|
76 |
C |
p. 44-54
11 p.
|
artikel
|
| 21 |
Theory and implementation of nuclear safety system codes – Part I: Conservation equations, flow regimes, numerics and significant assumptions
|
Roth, Glenn A.
|
|
2014
|
76 |
C |
p. 160-182
23 p.
|
artikel
|
| 22 |
Theory and implementation of nuclear safety system codes – Part II: System code closure relations, validation, and limitations
|
Roth, Glenn A.
|
|
2014
|
76 |
C |
p. 55-72
18 p.
|
artikel
|
| 23 |
Thermal-hydraulic and neutronic experimental research in the TRIGA reactor of Brazil
|
Mesquita, Amir Zacarias
|
|
2014
|
76 |
C |
p. 183-190
8 p.
|
artikel
|
| 24 |
Thermal-hydraulics and safety analyses of the Solid Core-Sectored Compact Reactor (SC-SCoRe) and power system
|
Schriener, Timothy M.
|
|
2014
|
76 |
C |
p. 216-231
16 p.
|
artikel
|
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