|
| 1 |
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;Stjarnsater, Johan;
/
Korean Nuclear Society
, v.49, no.4, pp.663-667,
|
|
| 2 |
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;Lindberg, Fredrik;Wells, Daniel;Bengtsson, Bernt;
/
Korean Nuclear Society
, v.49, no.4, pp.668-674,
|
|
| 3 |
Numerical analysis of two experiments related to thermal fatigue
Bieder, Ulrich;Errante, Paolo;
/
Korean Nuclear Society
, v.49, no.4, pp.675-691,
|
|
| 4 |
A Simple Parameterization for the Rising Velocity of Bubbles in a Liquid Pool
Park, Sung Hoon;Park, Changhwan;Lee, JinYong;Lee, Byungchul;
/
Korean Nuclear Society
, v.49, no.4, pp.692-699,
|
|
| 5 |
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;Mirza, Sikander M.;Mirza, Nasir M.;
/
Korean Nuclear Society
, v.49, no.4, pp.700-709,
|
|
| 6 |
Study on Quantification Method Based on Monte Carlo Sampling for Multiunit Probabilistic Safety Assessment Models
Oh, Kyemin;Han, Sang Hoon;Park, Jin Hee;Lim, Ho-Gon;Yang, Joon Eon;Heo, Gyunyoung;
/
Korean Nuclear Society
, v.49, no.4, pp.710-720,
|
|
| 7 |
A software tool for integrated risk assessment of spent fuel transportation and storage
Yun, Mirae;Christian, Robby;Kim, Bo Gyung;Almomani, Belal;Ham, Jaehyun;Lee, Sanghoon;Kang, Hyun Gook;
/
Korean Nuclear Society
, v.49, no.4, pp.721-733,
|
|
| 8 |
A Concise Design for the Irradiation of U-10Zr Metallic Fuel at a Very Low Burnup
Guo, Haibing;Zhou, Wei;Sun, Yong;Qian, Dazhi;Ma, Jimin;Leng, Jun;Huo, Heyong;Wang, Shaohua;
/
Korean Nuclear Society
, v.49, no.4, pp.734-743,
|
|
| 9 |
Effect of Oxidation on the Fatigue Crack Propagation Behavior of Z3CN20.09M Duplex Stainless Steel in High Temperature Water
Wu, Huan Chun;Yang, Bin;Chen, Yue Feng;Chen, Xu Dong;
/
Korean Nuclear Society
, v.49, no.4, pp.744-751,
|
|
| 10 |
Fatigue crack growth characteristics of nitrogen-alloyed type 347 stainless steel under operating conditions of a pressurized water reactor
Min, Ki-Deuk;Hong, Seokmin;Kim, Dae-Whan;Lee, Bong-Sang;Kim, Seon-Jin;
/
Korean Nuclear Society
, v.49, no.4, pp.752-759,
|
|
| 11 |
Statistical analysis on the fluence factor of surveillance test data of Korean nuclear power plants
Lee, Gyeong-Geun;Kim, Min-Chul;Yoon, Ji-Hyun;Lee, Bong-Sang;Lim, Sangyeob;Kwon, Junhyun;
/
Korean Nuclear Society
, v.49, no.4, pp.760-768,
|
|
| 12 |
Corrosion behavior induced by LiCl-KCl in type 304 and 316 stainless steel and copper at low temperature
Sim, Jee-Hyung;Kim, Yong-Soo;Cho, Il-Je;
/
Korean Nuclear Society
, v.49, no.4, pp.769-775,
|
|
| 13 |
Comparison of Image Uniformity with Photon Counting and Conventional Scintillation Single-Photon Emission Computed Tomography System: A Monte Carlo Simulation Study
Kim, Ho Chul;Kim, Hee-Joung;Kim, Kyuseok;Lee, Min-Hee;Lee, Youngjin;
/
Korean Nuclear Society
, v.49, no.4, pp.776-780,
|
|
| 14 |
Visualization of Crust in Metallic Piping Through Real-Time Neutron Radiography Obtained with Low Intensity Thermal Neutron Flux
Luiz, Leandro C.;Ferreira, Francisco J.O.;Crispim, Verginia R.;
/
Korean Nuclear Society
, v.49, no.4, pp.781-786,
|
|
| 15 |
Neutron activation analysis: Modelling studies to improve the neutron flux of Americium-Beryllium source
Didi, Abdessamad;Dadouch, Ahmed;Jai, Otman;Tajmouati, Jaouad;Bekkouri, Hassane El;
/
Korean Nuclear Society
, v.49, no.4, pp.787-791,
|
|
| 16 |
γ-Ray Shielding Behaviors of Some Nuclear Engineering Materials
Mann, Kulwinder Singh;
/
Korean Nuclear Society
, v.49, no.4, pp.792-800,
|
|
| 17 |
An Assessment of the Secondary Neutron Dose in the Passive Scattering Proton Beam Facility of the National Cancer Center
Han, Sang-Eun;Cho, Gyuseong;Lee, Se Byeong;
/
Korean Nuclear Society
, v.49, no.4, pp.801-809,
|
|
| 18 |
Building a Graphite Calorimetry System for the Dosimetry of Therapeutic X-ray Beams
Kim, In Jung;Kim, Byoung Chul;Kim, Joong Hyun;Chung, Jae-Pil;Kim, Hyun Moon;Yi, Chul-Young;
/
Korean Nuclear Society
, v.49, no.4, pp.810-816,
|
|
| 19 |
Estimation of residual stress in welding of dissimilar metals at nuclear power plants using cascaded support vector regression
Koo, Young Do;Yoo, Kwae Hwan;Na, Man Gyun;
/
Korean Nuclear Society
, v.49, no.4, pp.817-824,
|
|
| 20 |
Design response spectra-compliant real and synthetic GMS for seismic analysis of seismically isolated nuclear reactor containment building
Ali, Ahmer;Abu-Hayah, Nadin;Kim, Dookie;Cho, Sung Gook;
/
Korean Nuclear Society
, v.49, no.4, pp.825-837,
|
|
| 21 |
Proposal of the Penalty Factor Equations Considering Weld Strength Over-Match
Kim, Jong-Sung;Jeong, Jae-Wook;Lee, Kang-Yong;
/
Korean Nuclear Society
, v.49, no.4, pp.838-849,
|
|
| 22 |
Big Data Analysis of Public Acceptance of Nuclear Power in Korea
Roh, Seungkook;
/
Korean Nuclear Society
, v.49, no.4, pp.850-854,
|
|
| 23 |
Drop Performance Test of Conceptually Designed Control Rod Assembly for Prototype Generation IV Sodium-Cooled Fast Reactor
Lee, Young-Kyu;Lee, Jae-Han;Kim, Hoe-Woong;Kim, Sung-Kyun;Kim, Jong-Bum;
/
Korean Nuclear Society
, v.49, no.4, pp.855-864,
|
|
| 24 |
High-power fiber laser cutting parameter optimization for nuclear Decommissioning
Lopez, Ana Beatriz;Assuncao, Eurico;Quintino, Luisa;Blackburn, Jonathan;Khan, Ali;
/
Korean Nuclear Society
, v.49, no.4, pp.865-872,
|
|
| 25 |
Thermal characteristics of spent activated carbon generated from air cleaning units in korean nuclear power plants
So, Ji-Yang;Cho, Hang-Rae;
/
Korean Nuclear Society
, v.49, no.4, pp.873-880,
|
|
| 26 |
Application of CR-39 Microfilm for Rapid Discrimination Between Alpha-Particle Sources
Dwaikat, Nidal;Al-Karmi, Anan M.;
/
Korean Nuclear Society
, v.49, no.4, pp.881-885,
|
|