| no |
title |
author |
magazine |
year |
volume |
issue |
page(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
|
article
|
| 2 |
Calculation of flow heat transfer characteristics of liquid gallium
|
Zhou, Jian
|
|
|
3 |
C |
p. 175-183
|
article
|
| 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
|
article
|
| 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
|
article
|
| 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
|
article
|
| 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
|
article
|
| 7 |
Experimental investigation on heat transfer characteristics of high temperature air in round tube
|
Qin, Hao
|
|
|
3 |
C |
p. 200-205
|
article
|
| 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
|
article
|
| 9 |
Influence of zinc injection on deposition of corrosion products on inner wall of heat transfer tube
|
Ma, Yan
|
|
|
3 |
C |
p. 139-144
|
article
|
| 10 |
Investigation of kaolin - Granite composite bricks for gamma radiation shielding
|
Echeweozo, E.O.
|
|
|
3 |
C |
p. 194-199
|
article
|
| 11 |
IVR design and review of advanced NPPs in China: Issues and perspectives
|
Zhiyi, Yang
|
|
|
3 |
C |
p. 97-101
|
article
|
| 12 |
Low temperature overpressurization analysis for CPR1000
|
Liang, Yu
|
|
|
3 |
C |
p. 145-153
|
article
|
| 13 |
Neutron density waves versus temperature waves
|
Haidar, Nassar H.S.
|
|
|
3 |
C |
p. 206-212
|
article
|
| 14 |
Neutrons diffusion variable coefficient advection in nuclear reactors
|
El-Nabulsi, Rami Ahmad
|
|
|
3 |
C |
p. 102-107
|
article
|
| 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
|
article
|
| 16 |
Simulation of hydrogen deflagrations with the lumped parameter code COCOSYS
|
Hoffrichter, Johannes
|
|
|
3 |
C |
p. 18-26
|
article
|
| 17 |
Steady-state thermal fluids analysis for the HTR-PM equilibrium core
|
Chen, Fubing
|
|
|
3 |
C |
p. 11-17
|
article
|
| 18 |
Studies on post-dryout heat transfer in R-134a vertical flow
|
Köckert, Ludwig
|
|
|
3 |
C |
p. 44-53
|
article
|
| 19 |
Study on the thermal and geometrical parameters of helical coil once-through steam generator system
|
Yao, Hao
|
|
|
3 |
C |
p. 80-96
|
article
|
| 20 |
Supersonic shear layer characteristics of two fluids with a splitter plate
|
Bai, Yuping
|
|
|
3 |
C |
p. 1-10
|
article
|
| 21 |
Thermal-hydraulic performance evaluation of annular fuel based on modified FROBA-ANNULAR
|
Li, Chenxi
|
|
|
3 |
C |
p. 108-118
|
article
|
| 22 |
Transient thermal analysis of IVR strategy under a LB-LOCA based on ASTEC code
|
Chen, Peng
|
|
|
3 |
C |
p. 66-73
|
article
|
| 23 |
Uncertainty analysis and its application of radioactive source term of HPR1000 under severe accident
|
Shi, Xueyao
|
|
|
3 |
C |
p. 134-138
|
article
|
| 24 |
Virtual reactor laboratory integrated with cyber security from Bangladesh perspective
|
Das, Anik
|
|
|
3 |
C |
p. 184-193
|
article
|
Journal description