|
Loss of power accident analysis for the HCCR blanket
|
Hyung Gon Jin, Suk-Kwon Kim, Sungbo Moon, Mu-Young Ahn
|
p. 4947-4950
|
|
|
|
|
|
Effects of electrode configuration on the current density distribution of the electrolytic reducer
|
Jin-Mok Hur, Sangkwon Lee, Jae Soo Ryu
|
p. 4951-4958
|
|
|
|
|
|
Study on quantitative interpretation of uranium spectral gamma-ray logging based on machine learning algorithm
|
Yan Zhang, Yujin Ye, Jun Qiu, Chunqing Fu, Haolong Huang, Renbo Wang, Bin Tang
|
p. 4959-4965
|
|
|
|
|
|
Assessment of environmental hazard impacts in building materials (Marble), Gabal El-Galala El-Bahariya, Northeastern Desert, Egypt
|
M.Y. Hanfi, R.M. Abd El Rahman, Mohammad S. Alqahtani
|
p. 4966-4974
|
|
|
|
|
|
Confirmation bias, information selection, and belief reinforcement about the safety/risk of nuclear spent fuel storage facilities
|
Daeyoun Lee, Woo J. Kim, Young Rok Choi
|
p. 4975-4982
|
|
|
|
|
|
Continuous mapping of nuclear reactor core power using artificial neural network even in the presence of inactive detectors
|
João D. Talon, Aquilino S. Martinez, Alessandro C. Gonçalves
|
p. 4983-4996
|
|
|
|
|
|
Hydrodynamics coupled circulating : fuel reactor equations in comoving frame and their analytical solutions for molten salt reactors
|
Ayhan Yılmazer, Gökhan Pediz
|
p. 4997-5013
|
|
|
|
|
|
Analysis of the atomic ratio of H and Zr effect on the neutronics parameters of ZrH moderated space nuclear reactor
|
Xiaoliang Zou, Yanting Sun, Bo Yang, Yibao Liu
|
p. 5014-5021
|
|
|
|
|
|
Measurement of production cross : sections of [nat]Ti(p,x)43K,43,44m,44g,46g,47,48Sc,48V reactions up to 50 MeV
|
Dal-Ho Moon, Myung-Hwan Jung, Young Seok Hwang, Sung-Chul Yang
|
p. 5022-5027
|
|
|
|
|
|
Microstructure response and sodium corrosion behavior of ferritic-martensitic steel after proton irradiation
|
Jeonghyeon Lee, Taeho Kim, Taeyong Kim, Ji Hyun Kim
|
p. 5028-5036
|
|
|
|
|
|
Analysis of radiation conditions in the CFETR ion cyclotron resonance heating antenna
|
Gaoxiang Wang, Shanliang Zheng, Chengming Qin, Kun Xu, Yongsheng Wang, Huiqiang Ma
|
p. 5037-5042
|
|
|
|
|
|
Preparation and radiation shielding features of high density, transparent borosilicate glasses with different Bi2O3 contents
|
M.I. Sayyed, M. Rashad, Chaitali V. More, Anjan Kumar
|
p. 5043-5047
|
|
|
|
|
|
Optimizing spent nuclear fuel cask loading for VVER-440 fuel
|
M. Lovecký, J. Závorka
|
p. 5048-5054
|
|
|
|
|
|
Imbalanced data fault diagnosis method for nuclear power plants based on convolutional variational autoencoding Wasserstein generative adversarial network and random forest
|
Jun Guo, Yulong Wang, Xiang Sun, Shiqiao Liu, Baigang Du
|
p. 5055-5067
|
|
|
|
|
|
Design of the 500 MHz 2-cell superconducting cavity for the SILF
|
Yanbing Sun, Wei Ma, Yulin Ge, Nan Yuan, Liping Zou, Zhen Yang, Liang Lu
|
p. 5068-5077
|
|
|
|
|
|
(A) simplified SP3 NEM solver within a unified formulation for pin-by-pin core multi-group calculations
|
Sicheng Wang, Ser Gi Hong
|
p. 5078-5095
|
|
|
|
|
|
Methodology for estimating the contribution of forest fires in loss of offsite power events
|
Joonseok Lim, Seungsu Han, Hyungdae Kim, Gyunyoung Heo
|
p. 5096-5105
|
|
|
|
|
|
Numerical study on the size effect on the mixing in 2×1, 3×3 and 5×5 rod bundle subchannels
|
Bin Han, Yuanyuan Yin, Xiaoliang zhu, Bao-Wen Yang, Aiguo Liu, Shenghui Liu
|
p. 5106-5117
|
|
|
|
|
|
Improvement of macroscopic turbulence model for subchannel analysis in the rod bundle array
|
Seok Kim, Jee Min Yoo, Sang-Ki Moon
|
p. 5118-5135
|
|
|
|
|
|
Assessing the Phebus FPT-1 experiment : insights from MELCOR 2.2 and ASYST codes
|
Peter Mician, Tomas Cerny, Taron Petrosyan, Stepan Foral, Karel Katovsky, Michal Ptacek
|
p. 5136-5144
|
|
|
|
|
|
Thermal dynamics aspect identification of loop heat pipe with capillary tube wick using nonlinear autoregressive exogenous neural network
|
Yoyok Dwi Setyo Pambudi, Giarno, Sumantri Hatmoko, Anhar Riza Antariksawan, Mukhsinun Hadi Kusuma
|
p. 5145-5153
|
|
|
|
|
|
Impact of choice of fragility approaches on seismic risk quantification of nuclear power plants
|
Baris Kasapoglu, Halil Sezen, Tunc Aldemir, Richard Denning
|
p. 5154-5174
|
|
|
|
|
|
(A) novel irradiation module for ANICCA fuel cycle code based on multi-task learning
|
Victor J. Casas-Molina, Nerea Aguilera-Gómez, Pablo Romojaro, Iván Merino-Rodríguez, Augusto Hernández-Solis
|
p. 5175-5181
|
|
|
|
|
|
Experimental study on practical application of optical fiber sensor (OFS) for high-temperature system
|
Byeongyeon Kim, Youngwoong Kim, YunSook Lee, Ki-Ean Nam, Jung Yoon, Yong-Hoon Shin, Hyeonil Kim, Jewhan Lee, BongWan Lee
|
p. 5182-5189
|
|
|
|
|
|
Applicability analysis of induction bending process to P91 piping of PGSFR by high-temperature fatigue test
|
Tae-Won Na, Nak-Hyun Kim, Chang-Gyu Park, Junehyung Kim, Jong-Bum Kim, Il-Kwon Oh
|
p. 5190-5200
|
|
|
|
|
|
Al–B4C-(Gd, Gd2O3) composite materials : synthesis and characterization for neutron shielding applications
|
Yasin Gaylan, Barış Avar
|
p. 5201-5211
|
|
|
|
|
|
Study of circulating liquid fuel in a 1D critical system with thermal feedback
|
Mathis Caprais, Daniele Tomatis, André Bergeron
|
p. 5212-5221
|
|
|
|
|
|
Effect of thermal neutron flux on borate and silicate glasses : experimental and theoretical investigation for distribution, decay period, and absorbed dose rate of produced isotopes
|
O.L. Tashlykov, K.A. Mahmoud, D.O. Kaskov, T.P. Volozheninov
|
p. 5222-5230
|
|
|
|
|
|
Feasibility of a position-sensitive Cherenkov radiation detector using a reflector-coated liquid light guide
|
Sangjun Lee, Siwon Song, Jae Hyung Park, Seunghyeon Kim, Hyungi Byun, Jinhong Kim, Seokhyeon Jegal, Bongsoo Lee
|
p. 5231-5238
|
|
|
|
|
|
Heavy metal loading effects on special nuclear material and waste of an uprated Indonesian Reaktor Daya Eksperimental
|
Dany Mulyana, Topan Setiadipura, I Wayan Ngarayana
|
p. 5239-5247
|
|
|
|
|
|
Mesh morphing-based pre-processing and numerical simulation of blockage accident in lead–bismuth fast reactor fuel assembly
|
Hao Sun, Yong Ouyang, Zihua Liu, Huo Liang, Hanyan Luo, Zhikang Lin
|
p. 5248-5256
|
|
|
|
|
|
Study on the effect of geometry and material property on collapse pressure of a helical steam generator tube under external pressure
|
Gyo-Geun Youn, Kwanghyun Ahn, Myeong-Woo Lee
|
p. 5257-5268
|
|
|
|
|
|
(A) three-dimensional CFD simulation of corium jet breakup in intensive vapor generation condition
|
Jeong-Hyun Eom, Ji-Won Choi, Gi-Young Tak, In-Sik Ra, Huu Tiep Nguyen, Hae-Yong Jeong
|
p. 5269-5280
|
|
|
|
|
|
(A) review of COHRISK : multihazard risk quantification software for nuclear power plants
|
Eujeong Choi, Shinyoung Kwag, Jung-Han Kim, Jeong-Gon Ha, Daegi Hahm, Minkyu Kim
|
p. 5281-5290
|
|
|
|
|
|
Two-dimensional distribution reconstruction and emittance diagnostics of proton beam phase space using tomography
|
Jeong-Jeung Dang, Seunghyun Lee, Han-sung Kim, Hyeok-jung Kwon
|
p. 5291-5296
|
|
|
|
|
|
Neutron balance approach for inline critical rod position search calculation in Monte Carlo reactor analysis
|
YuGwon Jo, Jaewoon Yoo, Jae-Yong Lim
|
p. 5297-5304
|
|
|
|
|
|
Improving tally efficiency and accuracy of multi-group scattering matrix calculations in the Monte Carlo code NECP-MCX
|
Hongchun Wu, Shuai Qin, Yunzhao Li, Jinkang Shi, Qingming He, Liangzhi Cao
|
p. 5305-5312
|
|
|
|
|
|
Uranium quantification in radioactive waste drums using In-Situ Object Counting System (ISOCS) for safeguards purposes
|
Jihyun Ahn, Seungmin Lee, Hee Seo
|
p. 5313-5319
|
|
|
|
|
|
Lifetime thermal analysis of the CANDU spent fuel storage canister at the Wolsung site
|
Tae Gang Lee, Taehyung Na, Byongjo Yun, Jae Jun Jeong
|
p. 5320-5329
|
|
|
|
|
|
Preliminary neutronics design and analysis of lithium heat pipe cooled space reactor with low-enriched uranium
|
Xiaoliang Zou, Yanting Sun, Qiusun Zeng, Xiaojian Wen, Xiaogang Cao, Xi Huang, Yibao Liu
|
p. 5330-5338
|
|
|
|
|
|
(A) PHITS based-computational model of a TRIGA-fueled subcritical reactor for gamma dose mapping
|
Jowi Rapha P. Cruz, Alvie A. Astronomo, Gil Nonato Santos, Ryan U. Olivares
|
p. 5339-5345
|
|
|
|
|
|
Assessment of look-up tables for the prediction of heat transfer coefficient distribution in rod bundles cooled by supercritical water
|
Rashed MD. Sardar, Akhmed M. Baisov
|
p. 5346-5356
|
|
|
|
|
|
CFD simulation of thermal stratification and mixing in a Nordic BWR pressure suppression pool
|
Xicheng Wang, Govatsa Acharya, Dmitry Grishchenko, Pavel Kudinov
|
p. 5357-5376
|
|
|
|
|
|
Analysis of double-ended guillotine break accident of surge line in ACP100 based on coupling method : development and validation of the coupling method
|
Fan Miao, Bin Zhang, Tianci Xie, Hao Yang, Jianqiang Shan
|
p. 5377-5385
|
|
|
|
|
|
Evaluation of particle-capturing ability of a hydrogel-based surface decontamination agent using simulated nuclear fallout particles
|
Sung-Wook Kim, Hee-Man Yang, Hyung-Ju Kim
|
p. 5386-5395
|
|
|
|
|
|
Leveraging physics-informed neural computing for transport simulations of nuclear fusion plasmas
|
J. Seo, I.H. Kim, H. Nam
|
p. 5396-5404
|
|
|
|
|
|
Defect monitoring system of the internal structures of a sodium fast reactor using an artificial intelligence model
|
Hyungi Byun, Han Gil Lee, Beom Kyu Kim, Geun Dong Song, Bongsoo Lee
|
p. 5405-5413
|
|
|
|
|
|
Comparative analysis of machine learning-based dose assessment algorithms for TL dosimetry
|
Soohyeok Lee, Hyoungtaek Kim, Hwijoon Jung, Kyung Taek Lim
|
p. 5414-5421
|
|
|
|
|
|
Research on magnetostrictive liquid level gauge for water level measurement of steam generator
|
Shuiqiang Duan, Minggang Li, Jiaming Li, Tongxi Li, Changhua Nie, Zumao Yang, Jun Hu
|
p. 5422-5427
|
|
|
|
|
|
Towards accurate dose assessment for emergency industrial radiography source retrieval operations : a preliminary study of 4D Monte Carlo dose calculations
|
Sungho Moon, Haegin Han, Chansoo Choi, Bangho Shin, Gahee Son, Hyeonil Kim, Suhyeon Kim, Jaehyo Kim, In Gyu Yoon, Kyung Hwan Lee, Chan Hyeong Kim
|
p. 5428-5436
|
|
|
|
|
한국학술지인용색인(NRF)
