nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
A framework for a flexible cutting-process simulation of a nuclear facility decommission
|
Kim, Ikjune |
|
2016 |
97 |
C |
p. 204-207 4 p. |
artikel |
2 |
A nonstiff solution for the stochastic neutron point kinetics equations
|
Wollmann da Silva, M. |
|
2016 |
97 |
C |
p. 47-52 6 p. |
artikel |
3 |
Assembly Discontinuity Factors for the Neutron Diffusion Equation discretized with the Finite Volume Method. Application to BWR
|
Bernal, A. |
|
2016 |
97 |
C |
p. 76-85 10 p. |
artikel |
4 |
A systematic investigation on flow characteristics of impeller passage in a nuclear centrifugal pump under cavitation state
|
Fu, Qiang |
|
2016 |
97 |
C |
p. 190-197 8 p. |
artikel |
5 |
Calculation of the power and absolute flux of a source driven subcritical assembly using Monte Carlo MCNP code
|
Xoubi, Ned |
|
2016 |
97 |
C |
p. 96-101 6 p. |
artikel |
6 |
CFD modelling of turbulent flows through 5×5 fuel rod bundles with spacer-grids
|
Podila, Krishna |
|
2016 |
97 |
C |
p. 86-95 10 p. |
artikel |
7 |
Development of 3D neutron noise simulator based on GFEM with unstructured tetrahedron elements
|
Hosseini, Seyed Abolfazl |
|
2016 |
97 |
C |
p. 132-141 10 p. |
artikel |
8 |
Development of sensitivity analysis capabilities of generalized responses to nuclear data in Monte Carlo code RMC
|
Qiu, Yishu |
|
2016 |
97 |
C |
p. 142-152 11 p. |
artikel |
9 |
Development, verification, and validation of a fuel thermal conductivity degradation model in CTF
|
Yilmaz, Mine O. |
|
2016 |
97 |
C |
p. 246-261 16 p. |
artikel |
10 |
Editorial board
|
|
|
2016 |
97 |
C |
p. IFC- 1 p. |
artikel |
11 |
Estimation of total fusion reactivity and contribution from supra-thermal tail using 3-parameter Dagum ion speed distribution
|
Majumdar, Rudrodip |
|
2016 |
97 |
C |
p. 66-75 10 p. |
artikel |
12 |
Evaluation of the Americium transmutation performance in high flux reactors
|
Houas, Mounira |
|
2016 |
97 |
C |
p. 198-203 6 p. |
artikel |
13 |
Experimental and numerical study of a printed circuit heat exchanger
|
Chen, Minghui |
|
2016 |
97 |
C |
p. 221-231 11 p. |
artikel |
14 |
Experimental investigation of the bubble separation route for an axial gas–liquid separator for TMSR
|
Yin, Junlian |
|
2016 |
97 |
C |
p. 1-6 6 p. |
artikel |
15 |
Experimental investigation on the second dominant frequency of supersonic steam jet condensation oscillation and its propagation characteristic
|
Chen, Weixiong |
|
2016 |
97 |
C |
p. 122-131 10 p. |
artikel |
16 |
Implementation of an integrated real-time process surveillance and diagnostic system for nuclear power plants
|
Wang, Wenlin |
|
2016 |
97 |
C |
p. 7-26 20 p. |
artikel |
17 |
Neutronic and thermo hydraulic analysis of a modeled subcritical uranyl nitrate aqueous reactor driven by 30-MeV protons
|
Mirvakili, S.M. |
|
2016 |
97 |
C |
p. 171-178 8 p. |
artikel |
18 |
Neutronics and thermal hydraulics analysis of a small modular reactor
|
Kitcher, Evans D. |
|
2016 |
97 |
C |
p. 232-245 14 p. |
artikel |
19 |
Numerical simulation of a 374tons/h water-tube steam boiler following a feedwater line break
|
Deghal Cheridi, Amina Lyria |
|
2016 |
97 |
C |
p. 27-35 9 p. |
artikel |
20 |
Preliminary design and thermal analysis of a liquid metal heat pipe radiator for TOPAZ-II power system
|
Zhang, Wenwen |
|
2016 |
97 |
C |
p. 208-220 13 p. |
artikel |
21 |
Selective sorption of uranium (IV) from hydrochloric acid media by agro-industrial byproducts
|
Monji, Akbar Boveiri |
|
2016 |
97 |
C |
p. 115-121 7 p. |
artikel |
22 |
Simulation on the hydraulic characteristics of SFR SG using “single-hole plate+tube bundles” (SHTB) hybrid porous media model
|
Lu, Daogang |
|
2016 |
97 |
C |
p. 36-46 11 p. |
artikel |
23 |
Supercritical water heat transfer for nuclear reactor applications: A review
|
Rahman, Mohammad Mizanur |
|
2016 |
97 |
C |
p. 53-65 13 p. |
artikel |
24 |
The impacts of thermal neutron scattering effect and resonance elastic scattering effect on FHRs
|
Li, Zhifeng |
|
2016 |
97 |
C |
p. 102-114 13 p. |
artikel |
25 |
Twofold application of nanofluids as the primary coolant and reactivity controller in a PWR reactor: Case study VVER-1000 in normal operation
|
Hadad, Kamal |
|
2016 |
97 |
C |
p. 179-182 4 p. |
artikel |
26 |
Validation of Monte Carlo based burnup codes against LWR-PROTEUS Phase-II experimental data
|
Pecchia, Marco |
|
2016 |
97 |
C |
p. 153-164 12 p. |
artikel |
27 |
Validation of Monte-Carlo methods for generation time and delayed neutron fraction predictions
|
Perret, Grégory |
|
2016 |
97 |
C |
p. 165-170 6 p. |
artikel |
28 |
XPZ: Development of a lattice code for HTR
|
She, Ding |
|
2016 |
97 |
C |
p. 183-189 7 p. |
artikel |