| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A Concise Design for the Irradiation of U–10Zr Metallic Fuel at a Very Low Burnup
|
Guo, Haibing
|
|
2017
|
49 |
4 |
p. 734-743
10 p.
|
artikel
|
| 2 |
An Assessment of the Secondary Neutron Dose in the Passive Scattering Proton Beam Facility of the National Cancer Center
|
Han, Sang-Eun
|
|
2017
|
49 |
4 |
p. 801-809
9 p.
|
artikel
|
| 3 |
Application of CR-39 Microfilm for Rapid Discrimination Between Alpha-Particle Sources
|
Dwaikat, Nidal
|
|
2017
|
49 |
4 |
p. 881-885
5 p.
|
artikel
|
| 4 |
A Simple Parameterization for the Rising Velocity of Bubbles in a Liquid Pool
|
Park, Sung Hoon
|
|
2017
|
49 |
4 |
p. 692-699
8 p.
|
artikel
|
| 5 |
A software tool for integrated risk assessment of spent fuel transportation and storage
|
Yun, Mirae
|
|
2017
|
49 |
4 |
p. 721-733
13 p.
|
artikel
|
| 6 |
Big Data Analysis of Public Acceptance of Nuclear Power in Korea
|
Roh, Seungkook
|
|
2017
|
49 |
4 |
p. 850-854
5 p.
|
artikel
|
| 7 |
Building a Graphite Calorimetry System for the Dosimetry of Therapeutic X-ray Beams
|
Kim, In Jung
|
|
2017
|
49 |
4 |
p. 810-816
7 p.
|
artikel
|
| 8 |
Comparison of Image Uniformity with Photon Counting and Conventional Scintillation Single-Photon Emission Computed Tomography System: A Monte Carlo Simulation Study
|
Kim, Ho Chul
|
|
2017
|
49 |
4 |
p. 776-780
5 p.
|
artikel
|
| 9 |
Corrosion behavior induced by LiCl-KCl in type 304 and 316 stainless steel and copper at low temperature
|
Sim, Jee-Hyung
|
|
2017
|
49 |
4 |
p. 769-775
7 p.
|
artikel
|
| 10 |
Design response spectra-compliant real and synthetic GMS for seismic analysis of seismically isolated nuclear reactor containment building
|
Ali, Ahmer
|
|
2017
|
49 |
4 |
p. 825-837
13 p.
|
artikel
|
| 11 |
Drop Performance Test of Conceptually Designed Control Rod Assembly for Prototype Generation IV Sodium-Cooled Fast Reactor
|
Lee, Young-Kyu
|
|
2017
|
49 |
4 |
p. 855-864
10 p.
|
artikel
|
| 12 |
EELS and electron diffraction studies on possible bonaccordite crystals in pressurized water reactor fuel CRUD and in oxide films of alloy 600 material
|
Chen, Jiaxin
|
|
2017
|
49 |
4 |
p. 668-674
7 p.
|
artikel
|
| 13 |
Effect of Kinetic Parameters on Simultaneous Ramp Reactivity Insertion Plus Beam Tube Flooding Accident in a Typical Low Enriched U3Si2-Al Fuel-Based Material Testing Reactor-Type Research Reactor
|
Nasir, Rubina
|
|
2017
|
49 |
4 |
p. 700-709
10 p.
|
artikel
|
| 14 |
Effect of Oxidation on the Fatigue Crack Propagation Behavior of Z3CN20.09M Duplex Stainless Steel in High Temperature Water
|
Wu, Huan Chun
|
|
2017
|
49 |
4 |
p. 744-751
8 p.
|
artikel
|
| 15 |
Estimation of residual stress in welding of dissimilar metals at nuclear power plants using cascaded support vector regression
|
Koo, Young Do
|
|
2017
|
49 |
4 |
p. 817-824
8 p.
|
artikel
|
| 16 |
Fatigue crack growth characteristics of nitrogen-alloyed type 347 stainless steel under operating conditions of a pressurized water reactor
|
Min, Ki-Deuk
|
|
2017
|
49 |
4 |
p. 752-759
8 p.
|
artikel
|
| 17 |
High-power fiber laser cutting parameter optimization for nuclear Decommissioning
|
Lopez, Ana Beatriz
|
|
2017
|
49 |
4 |
p. 865-872
8 p.
|
artikel
|
| 18 |
Neutron activation analysis: Modelling studies to improve the neutron flux of Americium–Beryllium source
|
Didi, Abdessamad
|
|
2017
|
49 |
4 |
p. 787-791
5 p.
|
artikel
|
| 19 |
Numerical analysis of two experiments related to thermal fatigue
|
Bieder, Ulrich
|
|
2017
|
49 |
4 |
p. 675-691
17 p.
|
artikel
|
| 20 |
On the effect of temperature on the threshold stress intensity factor of delayed hydride cracking in light water reactor fuel cladding
|
Alvarez Holston, Anna-Maria
|
|
2017
|
49 |
4 |
p. 663-667
5 p.
|
artikel
|
| 21 |
Proposal of the Penalty Factor Equations Considering Weld Strength Over-Match
|
Kim, Jong-Sung
|
|
2017
|
49 |
4 |
p. 838-849
12 p.
|
artikel
|
| 22 |
γ-Ray Shielding Behaviors of Some Nuclear Engineering Materials
|
Mann, Kulwinder Singh
|
|
2017
|
49 |
4 |
p. 792-800
9 p.
|
artikel
|
| 23 |
Statistical analysis on the fluence factor of surveillance test data of Korean nuclear power plants
|
Lee, Gyeong-Geun
|
|
2017
|
49 |
4 |
p. 760-768
9 p.
|
artikel
|
| 24 |
Study on Quantification Method Based on Monte Carlo Sampling for Multiunit Probabilistic Safety Assessment Models
|
Oh, Kyemin
|
|
2017
|
49 |
4 |
p. 710-720
11 p.
|
artikel
|
| 25 |
Thermal characteristics of spent activated carbon generated from air cleaning units in korean nuclear power plants
|
So, Ji-Yang
|
|
2017
|
49 |
4 |
p. 873-880
8 p.
|
artikel
|
| 26 |
TOC
|
|
|
2017
|
49 |
4 |
p. i-iii
nvt p.
|
artikel
|
| 27 |
Visualization of Crust in Metallic Piping Through Real-Time Neutron Radiography Obtained with Low Intensity Thermal Neutron Flux
|
Luiz, Leandro C.
|
|
2017
|
49 |
4 |
p. 781-786
6 p.
|
artikel
|
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