| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor
|
Lee, Kwi Lim
|
|
2016
|
48 |
5 |
p. 1071-1082
12 p.
|
artikel
|
| 2 |
Computer Modeling, Characterization, and Applications of Gallium Arsenide Gunn Diodes in Radiation Environments
|
Abd El-Basit, Wafaa
|
|
2016
|
48 |
5 |
p. 1219-1229
11 p.
|
artikel
|
| 3 |
Development of Highly Reliable Power and Communication System for Essential Instruments Under Severe Accidents in NPP
|
Choi, Bo Hwan
|
|
2016
|
48 |
5 |
p. 1206-1218
13 p.
|
artikel
|
| 4 |
Effect of DUPIC Cycle on CANDU Reactor Safety Parameters
|
Mohamed, Nader M.A.
|
|
2016
|
48 |
5 |
p. 1109-1119
11 p.
|
artikel
|
| 5 |
Estimation of Leak Rate Through Cracks in Bimaterial Pipes in Nuclear Power Plants
|
Park, Jai Hak
|
|
2016
|
48 |
5 |
p. 1264-1272
9 p.
|
artikel
|
| 6 |
Estimation of Probability Density Functions of Damage Parameter for Valve Leakage Detection in Reciprocating Pump Used in Nuclear Power Plants
|
Lee, Jong Kyeom
|
|
2016
|
48 |
5 |
p. 1280-1290
11 p.
|
artikel
|
| 7 |
Experimental Investigation of Clay Fly Ash Bricks for Gamma-Ray Shielding
|
Mann, Harjinder Singh
|
|
2016
|
48 |
5 |
p. 1230-1236
7 p.
|
artikel
|
| 8 |
Experimental Investigation of the Thermal Hydraulics in Lead Bismuth Eutectic-Helium Experimental Loop of an Accelerator-Driven System
|
Xi, Wenxuan
|
|
2016
|
48 |
5 |
p. 1154-1161
8 p.
|
artikel
|
| 9 |
Field Programmable Gate Array Reliability Analysis Using the Dynamic Flowgraph Methodology
|
McNelles, Phillip
|
|
2016
|
48 |
5 |
p. 1192-1205
14 p.
|
artikel
|
| 10 |
Implementation of Strength Pareto Evolutionary Algorithm II in the Multiobjective Burnable Poison Placement Optimization of KWU Pressurized Water Reactor
|
Gharari, Rahman
|
|
2016
|
48 |
5 |
p. 1126-1139
14 p.
|
artikel
|
| 11 |
Investigating Dynamic Parameters in HWZPR Based on the Experimental and Calculated Results
|
Nasrazadani, Zahra
|
|
2016
|
48 |
5 |
p. 1120-1125
6 p.
|
artikel
|
| 12 |
Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor
|
Dehjourian, Mehdi
|
|
2016
|
48 |
5 |
p. 1174-1183
10 p.
|
artikel
|
| 13 |
Metal Fuel Development and Verification for Prototype Generation IV Sodium-Cooled Fast Reactor
|
Lee, Chan Bock
|
|
2016
|
48 |
5 |
p. 1096-1108
13 p.
|
artikel
|
| 14 |
Modeling of Hydrodynamic Processes at a Large Leak of Water into Sodium in the Fast Reactor Coolant Circuit
|
Perevoznikov, Sergey
|
|
2016
|
48 |
5 |
p. 1162-1173
12 p.
|
artikel
|
| 15 |
Numerical Ductile Tearing Simulation of Circumferential Cracked Pipe Tests under Dynamic Loading Conditions
|
Nam, Hyun-Suk
|
|
2016
|
48 |
5 |
p. 1252-1263
12 p.
|
artikel
|
| 16 |
On the Safety and Performance Demonstration Tests of Prototype Gen-IV Sodium-Cooled Fast Reactor and Validation and Verification of Computational Codes
|
Kim, Jong-Bum
|
|
2016
|
48 |
5 |
p. 1083-1095
13 p.
|
artikel
|
| 17 |
Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea
|
Yoo, Jaewoon
|
|
2016
|
48 |
5 |
p. 1059-1070
12 p.
|
artikel
|
| 18 |
Potentiality of Using Vertical and Three-Dimensional Isolation Systems in Nuclear Structures
|
Zhou, Zhiguang
|
|
2016
|
48 |
5 |
p. 1237-1251
15 p.
|
artikel
|
| 19 |
Simulation of Containment Pressurization in a Large Break-Loss of Coolant Accident Using Single-Cell and Multicell Models and CONTAIN Code
|
Noori-Kalkhoran, Omid
|
|
2016
|
48 |
5 |
p. 1140-1153
14 p.
|
artikel
|
| 20 |
Transient Diagnosis and Prognosis for Secondary System in Nuclear Power Plants
|
Park, Sangjun
|
|
2016
|
48 |
5 |
p. 1184-1191
8 p.
|
artikel
|
| 21 |
Validation of a New Design of Tellurium Dioxide-Irradiated Target
|
Fllaoui, Aziz
|
|
2016
|
48 |
5 |
p. 1273-1279
7 p.
|
artikel
|
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