nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
Analysis for fuel rod performance under LOCA based on the FROBA-ROD 2.0 code
|
Liao, Haoyu |
|
|
3 |
C |
p. 54-65 |
artikel |
2 |
Calculation of flow heat transfer characteristics of liquid gallium
|
Zhou, Jian |
|
|
3 |
C |
p. 175-183 |
artikel |
3 |
Calculation of neutron flux and neutron visualization in a spherical reactor core applying a conceptual approach and drawing a comparison with the results obtained by the CITATION code
|
Mousavi Shirazi, Seyed Alireza |
|
|
3 |
C |
p. 166-174 |
artikel |
4 |
Determination of the neutron and gamma ray dose rates of the irradiating beam tubes of a pool-type research reactor by using Monte Carlo simulation and experimental detectors regarding radiation protection issues
|
Hedayat, Afshin |
|
|
3 |
C |
p. 27-43 |
artikel |
5 |
Development of a three-dimensional method for thermal-hydraulics/neutronics coupling analysis and its application on CFETR helium-cooled solid breeder blanket
|
Lian, Qiang |
|
|
3 |
C |
p. 154-165 |
artikel |
6 |
Effect of LaB6 addition on mechanical properties and irradiation resistance of 316L stainless steels processed by selective laser melting
|
Xu, Dexin |
|
|
3 |
C |
p. 74-79 |
artikel |
7 |
Experimental investigation on heat transfer characteristics of high temperature air in round tube
|
Qin, Hao |
|
|
3 |
C |
p. 200-205 |
artikel |
8 |
Heat-transfer characteristics of screw tube in one-side high heat load condition for fusion reactor divertor application
|
Lim, Ji Hwan |
|
|
3 |
C |
p. 213-225 |
artikel |
9 |
Influence of zinc injection on deposition of corrosion products on inner wall of heat transfer tube
|
Ma, Yan |
|
|
3 |
C |
p. 139-144 |
artikel |
10 |
Investigation of kaolin - Granite composite bricks for gamma radiation shielding
|
Echeweozo, E.O. |
|
|
3 |
C |
p. 194-199 |
artikel |
11 |
IVR design and review of advanced NPPs in China: Issues and perspectives
|
Zhiyi, Yang |
|
|
3 |
C |
p. 97-101 |
artikel |
12 |
Low temperature overpressurization analysis for CPR1000
|
Liang, Yu |
|
|
3 |
C |
p. 145-153 |
artikel |
13 |
Neutron density waves versus temperature waves
|
Haidar, Nassar H.S. |
|
|
3 |
C |
p. 206-212 |
artikel |
14 |
Neutrons diffusion variable coefficient advection in nuclear reactors
|
El-Nabulsi, Rami Ahmad |
|
|
3 |
C |
p. 102-107 |
artikel |
15 |
Reactor dynamic simulation to analyze possible scenarios after a spurious opening of the safety flapper valve of TRR during the normal operation regarding the inherently safety features and Design Extension Conditions (DEC) by using the RELAP5 code
|
Hedayat, Afshin |
|
|
3 |
C |
p. 119-133 |
artikel |
16 |
Simulation of hydrogen deflagrations with the lumped parameter code COCOSYS
|
Hoffrichter, Johannes |
|
|
3 |
C |
p. 18-26 |
artikel |
17 |
Steady-state thermal fluids analysis for the HTR-PM equilibrium core
|
Chen, Fubing |
|
|
3 |
C |
p. 11-17 |
artikel |
18 |
Studies on post-dryout heat transfer in R-134a vertical flow
|
Köckert, Ludwig |
|
|
3 |
C |
p. 44-53 |
artikel |
19 |
Study on the thermal and geometrical parameters of helical coil once-through steam generator system
|
Yao, Hao |
|
|
3 |
C |
p. 80-96 |
artikel |
20 |
Supersonic shear layer characteristics of two fluids with a splitter plate
|
Bai, Yuping |
|
|
3 |
C |
p. 1-10 |
artikel |
21 |
Thermal-hydraulic performance evaluation of annular fuel based on modified FROBA-ANNULAR
|
Li, Chenxi |
|
|
3 |
C |
p. 108-118 |
artikel |
22 |
Transient thermal analysis of IVR strategy under a LB-LOCA based on ASTEC code
|
Chen, Peng |
|
|
3 |
C |
p. 66-73 |
artikel |
23 |
Uncertainty analysis and its application of radioactive source term of HPR1000 under severe accident
|
Shi, Xueyao |
|
|
3 |
C |
p. 134-138 |
artikel |
24 |
Virtual reactor laboratory integrated with cyber security from Bangladesh perspective
|
Das, Anik |
|
|
3 |
C |
p. 184-193 |
artikel |