nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
A code development for leak before break (LBB) leakage from supercritical to subcritical conditions
|
Zhang, J. |
|
2018 |
103 |
C |
p. 217-228 |
artikel |
2 |
Adaptive simulation for failure identification in the Advanced Lead Fast Reactor European Demonstrator
|
Turati, Pietro |
|
2018 |
103 |
C |
p. 176-190 |
artikel |
3 |
A new study on Uranium (VI) stripping from loaded Alamine 336 using some of alkaline solutions
|
Mir-mohammadi, S.L. |
|
2018 |
103 |
C |
p. 229-235 |
artikel |
4 |
Assessment of radiation dose received by nuclear plant personnel through a video-based surveillance system
|
Jorge, Carlos Alexandre F. |
|
2018 |
103 |
C |
p. 51-59 |
artikel |
5 |
Conceptual design and comprehensive optimization analysis of a fusion-fission hybrid reactor water-cooled pressure tube blanket
|
Cui, Shijie |
|
2018 |
103 |
C |
p. 8-19 |
artikel |
6 |
Construction of minor actinides reduction scenario in Japan utilizing fusion reactors
|
Furudate, Yuki |
|
2018 |
103 |
C |
p. 28-32 |
artikel |
7 |
Design and performance analysis of passive residual heat removal system for a lead-cooled fast reactor
|
Wu, Guowei |
|
2018 |
103 |
C |
p. 236-242 |
artikel |
8 |
Development and verification of the high-fidelity neutronics and thermal-hydraulic coupling code system NECP-X/SUBSC
|
Liu, Zhouyu |
|
2018 |
103 |
C |
p. 114-125 |
artikel |
9 |
Development of an efficient tightly coupled method for multiphysics reactor transient analysis
|
Senecal, Jaron P. |
|
2018 |
103 |
C |
p. 33-44 |
artikel |
10 |
Editorial Board
|
|
|
2018 |
103 |
C |
p. ii |
artikel |
11 |
Experimental investigation on natural circulation characteristics of emergency passive residual heat removal system in HPR1000
|
Sun, D.C. |
|
2018 |
103 |
C |
p. 1-7 |
artikel |
12 |
Flow regime transition criteria for co-current downward two-phase flow
|
Lokanathan, Manojkumar |
|
2018 |
103 |
C |
p. 165-175 |
artikel |
13 |
Formulation of a fully implicit numerical scheme for simulation of two-phase flow in a vertical channel using the Drift-Flux Model
|
Hajizadeh, A. |
|
2018 |
103 |
C |
p. 91-105 |
artikel |
14 |
Improvement and optimization of the pseudo-resonant-nuclide subgroup method in NECP-X
|
Liu, Zhouyu |
|
2018 |
103 |
C |
p. 60-73 |
artikel |
15 |
Laminar fluid flow and heat transfer in non-circular sub-channel geometries of nuclear fuel bundle
|
Moorthi, Annamalai |
|
2018 |
103 |
C |
p. 243-253 |
artikel |
16 |
Optimization of fuel loading pattern for a material test reactor using swarm intelligence
|
Ahmad, Ammar |
|
2018 |
103 |
C |
p. 45-50 |
artikel |
17 |
Optimization of regression model using principal component regression method in passive system reliability assessment
|
Solanki, R.B. |
|
2018 |
103 |
C |
p. 126-134 |
artikel |
18 |
Parametric study of CSR1000 thermal hydraulic stability
|
Shahzad, Muhammad Ali |
|
2018 |
103 |
C |
p. 106-113 |
artikel |
19 |
Preliminary post-closure safety assessment for a borehole-type repository for disused sealed radioactive sources in Brazil
|
Cota, Stela |
|
2018 |
103 |
C |
p. 74-80 |
artikel |
20 |
Prospects in China for nuclear development up to 2050
|
Chen, Yanxin |
|
2018 |
103 |
C |
p. 81-90 |
artikel |
21 |
Removal of cobalt ions from simulated radioactive wastewater by vacuum membrane distillation
|
Jia, Fei |
|
2018 |
103 |
C |
p. 20-27 |
artikel |
22 |
Review on heat transfer and flow characteristics of liquid sodium (2): Two-phase
|
Wu, Yingwei |
|
2018 |
103 |
C |
p. 151-164 |
artikel |
23 |
Simulation of hydrogen generated from fuel bundles and verification of a semi-empirical cladding oxidation model by PWR type CORA tests
|
Ni, Xinghe |
|
2018 |
103 |
C |
p. 191-208 |
artikel |
24 |
The thermodynamic and cost-benefit-analysis of miniaturized lead-cooled fast reactor with supercritical CO2 power cycle in the commercial market
|
Li, Ming-Jia |
|
2018 |
103 |
C |
p. 135-150 |
artikel |
25 |
Three-dimensional experiment of heat transfer for molten oxidic pool
|
Chen, Lian |
|
2018 |
103 |
C |
p. 209-216 |
artikel |