| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Analysis of fission product reduction strategy in SGTR accident using CFVS
|
Shin, Hoyoung
|
|
|
53 |
3 |
p. 812-824
|
artikel
|
| 2 |
A novel approach for analyzing the nuclear supply chain cyber-attack surface
|
Eggers, Shannon
|
|
|
53 |
3 |
p. 879-887
|
artikel
|
| 3 |
Application of cohesive zone model to large scale circumferential through-wall and 360° surface cracked pipes under static and dynamic loadings
|
Moon, Ji-Hee
|
|
|
53 |
3 |
p. 974-987
|
artikel
|
| 4 |
Applications of online simulation supporting PWR operations
|
Wang, Chunbing
|
|
|
53 |
3 |
p. 842-850
|
artikel
|
| 5 |
Core analysis of accident tolerant fuel cladding for SMART reactor under normal operation and rod ejection accident using DRAGON and PARCS
|
Pourrostam, A.
|
|
|
53 |
3 |
p. 741-751
|
artikel
|
| 6 |
Design and operation of the transparent integral effect test facility, URI-LO for nuclear innovation platform
|
Kim, Kyung Mo
|
|
|
53 |
3 |
p. 776-792
|
artikel
|
| 7 |
Design of the flexible switching controller for small PWR core power control with the multi-model
|
Zeng, Wenjie
|
|
|
53 |
3 |
p. 851-859
|
artikel
|
| 8 |
Determination of burnup limit for CANDU 6 fuel using Monte-Carlo method
|
Lee, Eun-ki
|
|
|
53 |
3 |
p. 901-910
|
artikel
|
| 9 |
Determining PGAA collimator plug design using Monte Carlo simulation
|
Jalil, A.
|
|
|
53 |
3 |
p. 942-948
|
artikel
|
| 10 |
Development of de-noised image reconstruction technique using Convolutional AutoEncoder for fast monitoring of fuel assemblies
|
Choi, Se Hwan
|
|
|
53 |
3 |
p. 888-893
|
artikel
|
| 11 |
Electrochemical corrosion study of helium ions implanted Zircaloy-4 in chloride media
|
Rafique, Mohsin
|
|
|
53 |
3 |
p. 927-931
|
artikel
|
| 12 |
Establishment of the design stress intensity value for the plate-type fuel assembly using a tensile test
|
Kim, Hyun-Jung
|
|
|
53 |
3 |
p. 911-919
|
artikel
|
| 13 |
Estimation of radiostrontium, radiocesium and radiobarium transfer from arid soil to plant: A case study from Kuwait
|
Aba, Abdulaziz
|
|
|
53 |
3 |
p. 960-966
|
artikel
|
| 14 |
Finite element analysis of high-density polyethylene pipe in pipe gallery of nuclear power plants
|
Shi, Jianfeng
|
|
|
53 |
3 |
p. 1004-1012
|
artikel
|
| 15 |
Fracture simulation of SFR metallic fuel pin using finite element damage analysis method
|
Jung, Hyun-Woo
|
|
|
53 |
3 |
p. 932-941
|
artikel
|
| 16 |
Investigation of photon, neutron and proton shielding features of H3BO3–ZnO–Na2O–BaO glass system
|
Mhareb, M.H.A.
|
|
|
53 |
3 |
p. 949-959
|
artikel
|
| 17 |
Investigation of seismic responses of reactor vessel and internals for beyond-design basis earthquake using elasto-plastic time history analysis
|
Lee, Sang-Jeong
|
|
|
53 |
3 |
p. 988-1003
|
artikel
|
| 18 |
Measuring thermal conductivity and water suction for variably saturated bentonite
|
Yoon, Seok
|
|
|
53 |
3 |
p. 1041-1048
|
artikel
|
| 19 |
Methodology of seismic-response-correlation-coefficient calculation for seismic probabilistic safety assessment of multi-unit nuclear power plants
|
Eem, Seunghyun
|
|
|
53 |
3 |
p. 967-973
|
artikel
|
| 20 |
Model of the onset of liquid entrainment in large branch T-junction with the consideration of surface tension
|
Liu, Ping
|
|
|
53 |
3 |
p. 804-811
|
artikel
|
| 21 |
MPS eutectic reaction model development for severe accident phenomenon simulation
|
Zhu, Yingzi
|
|
|
53 |
3 |
p. 833-841
|
artikel
|
| 22 |
Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt
|
Ezell, N. Dianne Bull
|
|
|
53 |
3 |
p. 920-926
|
artikel
|
| 23 |
Numerical and analytical predictions of nuclear steam generator secondary side flow field during blowdown due to a feedwater line break
|
Jo, Jong Chull
|
|
|
53 |
3 |
p. 1029-1040
|
artikel
|
| 24 |
Numerical simulation on LMR molten-core centralized sloshing benchmark experiment using multi-phase smoothed particle hydrodynamics
|
Jo, Young Beom
|
|
|
53 |
3 |
p. 752-762
|
artikel
|
| 25 |
On the equivalence of reaction rate in energy collapsing of fast reactor code SARAX
|
Xiao, Bowen
|
|
|
53 |
3 |
p. 732-740
|
artikel
|
| 26 |
Perception-based analytical technique of evacuation behavior under radiological emergency: An illustration of the Kori area
|
Kim, Jeongsik
|
|
|
53 |
3 |
p. 825-832
|
artikel
|
| 27 |
Quantification of predicted uncertainty for a data-based model
|
Chai, Jangbom
|
|
|
53 |
3 |
p. 860-865
|
artikel
|
| 28 |
Recent trends of supercritical CO2 Brayton cycle: Bibliometric analysis and research review
|
Yu, Aofang
|
|
|
53 |
3 |
p. 699-714
|
artikel
|
| 29 |
Research on non-uniform pressure pulsation of the diffuser in a nuclear reactor coolant pump
|
Zhou, Qiang
|
|
|
53 |
3 |
p. 1020-1028
|
artikel
|
| 30 |
Scaling analysis of the pressure suppression containment test facility for the small pressurized water reactor
|
Liu, Xinxing
|
|
|
53 |
3 |
p. 793-803
|
artikel
|
| 31 |
Sentiment analysis of nuclear energy-related articles and their comments on a portal site in Rep. of Korea in 2010–2019
|
Jeong, So Yun
|
|
|
53 |
3 |
p. 1013-1019
|
artikel
|
| 32 |
Sorption of Pd on illite, MX-80 bentonite and shale in Na–Ca–Cl solutions
|
Goguen, Jared
|
|
|
53 |
3 |
p. 894-900
|
artikel
|
| 33 |
Syntactic and semantic information extraction from NPP procedures utilizing natural language processing integrated with rules
|
Choi, Yongsun
|
|
|
53 |
3 |
p. 866-878
|
artikel
|
| 34 |
The development of high fidelity Steam Generator three dimensional thermal hydraulic coupling code: STAF-CT
|
Zhao, Xiaohan
|
|
|
53 |
3 |
p. 763-775
|
artikel
|
| 35 |
Uncertainty quantification of PWR spent fuel due to nuclear data and modeling parameters
|
Ebiwonjumi, Bamidele
|
|
|
53 |
3 |
p. 715-731
|
artikel
|
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