| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A criticality assessment through user's routines in FLUKA
|
Vanoni, F.
|
|
|
|
1 |
p. 9-16
|
artikel
|
| 2 |
A movable boundary model for helical coiled once-through steam generator using preconditioned JFNK method
|
Wu, Yingjie
|
|
|
|
1 |
p. 1-8
|
artikel
|
| 3 |
Analysis of radiation shielding effectiveness of hydride and borohydride metals for nuclear industry
|
Osman, A.M.
|
|
|
|
1 |
p. 30-43
|
artikel
|
| 4 |
Analysis on containment thermal hydraulic behaviour under passive containment heat removal system operation condition for HPR1000
|
Sun, Jing
|
|
|
|
1 |
p. 36-42
|
artikel
|
| 5 |
Corrigendum to “Heat-transfer characteristics of screw tube in one-side high heat load condition for fusion reactor divertor application”[Int. J. Adv. Nucl. Reactor. Des. Technol. 3 (2021) 213–225]
|
Lim, Ji Hwan
|
|
|
|
1 |
p. 25
|
artikel
|
| 6 |
Heat transfer characteristics of single-layer and two-layer corium pool in elliptical lower head
|
Zhang, Y.P.
|
|
|
|
1 |
p. 13-24
|
artikel
|
| 7 |
Improvement and evaluation of ATWS Protective Signal and mitigation system for ACPR1000 nuclear power plant
|
Zhang, Juanhua
|
|
|
|
1 |
p. 9-12
|
artikel
|
| 8 |
Influence analysis of alloy elements on irradiation embrittlement of RPV steel based on deep neural network
|
Bing, Bai
|
|
|
|
1 |
p. 44-51
|
artikel
|
| 9 |
Numerical investigation on transverse flow of helical cruciform fuel rod assembly in a lead-bismuth cooled fast reactor
|
Zeng, Yue
|
|
|
|
1 |
p. 17-29
|
artikel
|
| 10 |
Study on startup characteristics of prototype once-through steam generator for China fast reactor
|
Min, Xin
|
|
|
|
1 |
p. 26-35
|
artikel
|
| 11 |
The evaporation of nanoscale sodium liquid film on the non-ideal nanostructure surface: A molecular dynamics study
|
Wang, Zetao
|
|
|
|
1 |
p. 1-8
|
artikel
|
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