nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
Age-dating uranium metal using microstructural damage
|
Loveless, Amanda M. |
|
2015 |
83 |
C |
p. 298-301 4 p. |
artikel |
2 |
Analysis of parallel channel instabilities in the CANDU supercritical water reactor
|
Dutta, Goutam |
|
2015 |
83 |
C |
p. 264-273 10 p. |
artikel |
3 |
Analysis of 149 Sm time evolution and the reactivity contribution in nuclear reactors
|
Moreira, O. |
|
2015 |
83 |
C |
p. 87-93 7 p. |
artikel |
4 |
Analysis of the accident in the Fukushima Daiichi nuclear power station Unit 3 with MELCOR_2.1
|
Fernandez-Moguel, L. |
|
2015 |
83 |
C |
p. 193-215 23 p. |
artikel |
5 |
An analytical investigation of direct vessel injection line break accidents of the ATLAS facility
|
Kim, Yeon-Sik |
|
2015 |
83 |
C |
p. 398-407 10 p. |
artikel |
6 |
An evaluation on the cutting technologies for decommissioning of the tube bundles in the RPV of NPPs
|
Jeong, KwanSeong |
|
2015 |
83 |
C |
p. 342-345 4 p. |
artikel |
7 |
Applications of high-resolution spatial discretization scheme and Jacobian-free Newton–Krylov method in two-phase flow problems
|
Zou, Ling |
|
2015 |
83 |
C |
p. 101-107 7 p. |
artikel |
8 |
Burnup performance of OTTO cycle pebble bed reactors with ROX fuel
|
Ho, Hai Quan |
|
2015 |
83 |
C |
p. 1-7 7 p. |
artikel |
9 |
CATHARE 2 simulations of steady state air/water tests performed in a 1:1 scale SFR sub-assembly mock-up
|
Perez, J. |
|
2015 |
83 |
C |
p. 283-297 15 p. |
artikel |
10 |
Comparative study of the hydrogen generation during short term station blackout (STSBO) in a BWR
|
Polo-Labarrios, M.A. |
|
2015 |
83 |
C |
p. 274-282 9 p. |
artikel |
11 |
Comparison of fast neutron spectra in graphite and FLINA salt inserted in well-defined core assembled in LR-0 reactor
|
Košťál, Michal |
|
2015 |
83 |
C |
p. 216-225 10 p. |
artikel |
12 |
Coupling a CFD code with neutron kinetics and pin thermal models for nuclear reactor safety analyses
|
Chen, Zhao |
|
2015 |
83 |
C |
p. 41-49 9 p. |
artikel |
13 |
Criticality Safety Evaluation of a Swiss wet storage pool using a global uncertainty analysis methodology
|
Pecchia, Marco |
|
2015 |
83 |
C |
p. 226-235 10 p. |
artikel |
14 |
Development of high-immersive simulation system for designing maintenance strategy and its application to CLEAR-I
|
Yang, Zihui |
|
2015 |
83 |
C |
p. 309-315 7 p. |
artikel |
15 |
Development of magnetic flux leakage technique for examination of steam generator tubes of prototype fast breeder reactor
|
Singh, W. Sharatchandra |
|
2015 |
83 |
C |
p. 57-64 8 p. |
artikel |
16 |
Development of reliability and probabilistic safety assessment program RiskA
|
Wu, Yican |
|
2015 |
83 |
C |
p. 316-321 6 p. |
artikel |
17 |
Dimensional measurements on 112GWd/t irradiated MOX fuel pins using X-ray radiography
|
Saravanan, T. |
|
2015 |
83 |
C |
p. 8-13 6 p. |
artikel |
18 |
1/3D modeling of the core coolant circuit of a PHWR nuclear power plant
|
Corzo, Santiago |
|
2015 |
83 |
C |
p. 386-397 12 p. |
artikel |
19 |
Editorial board
|
|
|
2015 |
83 |
C |
p. IFC- 1 p. |
artikel |
20 |
Effect of rolling motion on two-phase frictional pressure drop of boiling flows in a rectangular narrow channel
|
Chen, Chong |
|
2015 |
83 |
C |
p. 125-136 12 p. |
artikel |
21 |
Estimate of the reactivity of the VENUS-F subcritical configuration using a Monte Carlo MSM method
|
Lecouey, J.L. |
|
2015 |
83 |
C |
p. 65-75 11 p. |
artikel |
22 |
Experimental and numerical void fraction measurement for modeled two-phase flow inside a vertical pipe
|
Adineh, Mahtab |
|
2015 |
83 |
C |
p. 188-192 5 p. |
artikel |
23 |
Experimental assessment of the kinetic parameters of the JSI TRIGA reactor
|
Filliatre, P. |
|
2015 |
83 |
C |
p. 236-245 10 p. |
artikel |
24 |
Experimental investigation and CFD analysis on cross flow in the core of PMR200
|
Lee, Jeong-Hun |
|
2015 |
83 |
C |
p. 422-435 14 p. |
artikel |
25 |
Experimental study on heat pipe heat removal capacity for passive cooling of spent fuel pool
|
Xiong, Zhenqin |
|
2015 |
83 |
C |
p. 258-263 6 p. |
artikel |
26 |
Few-group condensation via two-material coexisting ring model for fast reactor core analysis
|
Won, Jong Hyuck |
|
2015 |
83 |
C |
p. 172-180 9 p. |
artikel |
27 |
Fuel cladding integrity analysis during beam trip transients for China lead-based demonstration reactor
|
Xue, Sha |
|
2015 |
83 |
C |
p. 94-100 7 p. |
artikel |
28 |
Heat transfer to supercritical water in a 2×2 rod bundle
|
Gu, H.Y. |
|
2015 |
83 |
C |
p. 114-124 11 p. |
artikel |
29 |
High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW
|
Daeubler, Miriam |
|
2015 |
83 |
C |
p. 352-375 24 p. |
artikel |
30 |
Inventory calculation and nuclear data uncertainty propagation on light water reactor fuel using ALEPH-2 and SCALE 6.2
|
Fiorito, L. |
|
2015 |
83 |
C |
p. 137-146 10 p. |
artikel |
31 |
Investigation of the pulse energy noise dynamics of IBR-2M using cluster analysis
|
Pepelyshev, Yu.N. |
|
2015 |
83 |
C |
p. 50-56 7 p. |
artikel |
32 |
Locally manufactured films for neutron flux measurement in the MNSR type reactor
|
Nassan, L. |
|
2015 |
83 |
C |
p. 108-113 6 p. |
artikel |
33 |
Methods for reconstruction of the density distribution of nuclear power
|
Pessoa, Paulo O. |
|
2015 |
83 |
C |
p. 76-86 11 p. |
artikel |
34 |
Minimizing MTR reactor uranium load with the use of MOX fuel by employing ORIGEN-S and MCNP4C codes
|
Shaaban, Ismail |
|
2015 |
83 |
C |
p. 34-40 7 p. |
artikel |
35 |
Minimum dose method for walking-path planning of nuclear facilities
|
Liu, Yong-kuo |
|
2015 |
83 |
C |
p. 161-171 11 p. |
artikel |
36 |
Modeling and simulation of bubbling hot well deaerator in condensers of ships
|
Xue, Ruo-Jun |
|
2015 |
83 |
C |
p. 346-351 6 p. |
artikel |
37 |
Molecular dynamics analysis of incoherent neutron scattering from light water via the Van Hove space–time self-correlation function with a new quantum correction
|
Abe, Y. |
|
2015 |
83 |
C |
p. 302-308 7 p. |
artikel |
38 |
Monte Carlo simulation for calculation of kinetic parameters in an Accelerator Driven Subcritical TRIGA reactor
|
Hassanzadeh, M. |
|
2015 |
83 |
C |
p. 322-327 6 p. |
artikel |
39 |
Numerical and experimental investigation on the transient heat transfer characteristics of C-shape rod bundles used in Passive Residual Heat Removal Heat Exchangers
|
Zhang, Yuhao |
|
2015 |
83 |
C |
p. 147-160 14 p. |
artikel |
40 |
ROP margin improvement options for CANDU reactors
|
Kastanya, D. |
|
2015 |
83 |
C |
p. 181-187 7 p. |
artikel |
41 |
SCALE and SERPENT solutions of the OECD VVER-1000 LEU and MOX burnup computational benchmark
|
Mercatali, L. |
|
2015 |
83 |
C |
p. 328-341 14 p. |
artikel |
42 |
Shortening transmutation time by using the molten salt reactor
|
Biss, Klaus Hendrik |
|
2015 |
83 |
C |
p. 25-33 9 p. |
artikel |
43 |
Simulation of unprotected LOFA in MTR reactors using a mix CFD and one-d computation tool
|
Khater, Hany |
|
2015 |
83 |
C |
p. 376-385 10 p. |
artikel |
44 |
Survey of prediction capabilities of three nuclear data libraries for a PWR application
|
Vanhanen, R. |
|
2015 |
83 |
C |
p. 408-421 14 p. |
artikel |
45 |
Sustainability of the Chinese nuclear expansion: Natural uranium resources availability, Pu cycle, fuel utilization efficiency and spent fuel management
|
Fiori, F. |
|
2015 |
83 |
C |
p. 246-257 12 p. |
artikel |
46 |
Theoretical approach to study the light particles induced production routes of 22Na
|
Eslami, M. |
|
2015 |
83 |
C |
p. 14-24 11 p. |
artikel |