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1 |
Adaptive group of ink drop spread: a computer code to unfold neutron noise sources in reactor cores
Hosseini, Seyed Abolfazl;Afrakoti, Iman Esmaili Paeen;
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Korean Nuclear Society
, v.49, no.7, pp.1369-1378,
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2 |
APOLLO3 homogenization techniques for transport core calculations-application to the ASTRID CFV core
Vidal, Jean-Francois;Archier, Pascal;Faure, Bastien;Jouault, Valentin;Palau, Jean-Marc;Pascal, Vincent;Rimpault, Gerald;Auffret, Fabien;Graziano, Laurent;Masiello, Emiliano;Santandrea, Simone;
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Korean Nuclear Society
, v.49, no.7, pp.1379-1387,
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3 |
Development of a computer code for thermal-hydraulic design and analysis of helically coiled tube once-through steam generator
Zhang, Yaoli;Wang, Duo;Lin, Jianshu;Hao, Junwei;
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Korean Nuclear Society
, v.49, no.7, pp.1388-1395,
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4 |
Magnetohydrodynamic peristalsis of variable viscosity Jeffrey liquid with heat and mass transfer
Farooq, S.;Awais, M.;Naseem, Moniza;Hayat, T.;Ahmad, B.;
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Korean Nuclear Society
, v.49, no.7, pp.1396-1404,
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5 |
Two- and three-dimensional experiments for oxide pool in in-vessel retention of core melts
Kim, Su-Hyeon;Park, Hae-Kyun;Chung, Bum-Jin;
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Korean Nuclear Society
, v.49, no.7, pp.1405-1413,
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6 |
A new approach to quantify safety benefits of disaster robots
Kim, Inn Seock;Choi, Young;Jeong, Kyung Min;
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Korean Nuclear Society
, v.49, no.7, pp.1414-1422,
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7 |
Gas detonation cell width prediction model based on support vector regression
Yu, Jiyang;Hou, Bingxu;Lelyakin, Alexander;Xu, Zhanjie;Jordan, Thomas;
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Korean Nuclear Society
, v.49, no.7, pp.1423-1430,
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8 |
The concept of the innovative power reactor
Lee, Sang Won;Heo, Sun;Ha, Hui Un;Kim, Han Gon;
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Korean Nuclear Society
, v.49, no.7, pp.1431-1441,
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9 |
Investigation of molten fuel coolant interaction phenomena using real time X-ray imaging of simulated woods metal-water system
Acharya, Avinash Kumar;Sharma, Anil Kumar;Avinash, Ch.S.S.S.;Das, Sanjay Kumar;Gnanadhas, Lydia;Nashine, B.K.;Selvaraj, P.;
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Korean Nuclear Society
, v.49, no.7, pp.1442-1450,
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10 |
A preliminary study of pilot-scale electrolytic reduction of UO2 using a graphite anode
Kim, Sung-Wook;Heo, Dong Hyun;Lee, Sang Kwon;Jeon, Min Ku;Park, Wooshin;Hur, Jin-Mok;Hong, Sun-Seok;Oh, Seung-Chul;Choi, Eun-Young;
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Korean Nuclear Society
, v.49, no.7, pp.1451-1456,
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11 |
Unsteady heat exchange at the dry spent nuclear fuel storage
Alyokhina, Svitlana;Kostikov, Andrii;
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Korean Nuclear Society
, v.49, no.7, pp.1457-1462,
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12 |
High-temperature ultrasonic thickness monitoring for pipe thinning in a flow-accelerated corrosion proof test facility
Cheong, Yong-Moo;Kim, Kyung-Mo;Kim, Dong-Jin;
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Korean Nuclear Society
, v.49, no.7, pp.1463-1471,
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13 |
The effect of neutron irradiation on hydride reorientation and mechanical property degradation of zirconium alloy cladding
Jang, Ki-Nam;Kim, Kyu-Tae;
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Korean Nuclear Society
, v.49, no.7, pp.1472-1482,
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14 |
Beta particle energy spectra shift due to self-attenuation effects in environmental sources
Alton, Thomas Theakston;Monk, Stephen David;Cheneler, David;
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Korean Nuclear Society
, v.49, no.7, pp.1483-1488,
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15 |
Large-volume and room-temperature gamma spectrometer for environmental radiation monitoring
Coulon, Romain;Dumazert, Jonathan;Tith, Tola;Rohee, Emmanuel;Boudergui, Karim;
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Korean Nuclear Society
, v.49, no.7, pp.1489-1494,
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16 |
Implications of using a 50-μm-thick skin target layer in skin dose coefficient calculation for photons, protons, and helium ions
Yeom, Yeon Soo;Nguyen, Thang Tat;Choi, Chansoo;Han, Min Cheol;Lee, Hanjin;Han, Haegin;Kim, Chan Hyeong;
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Korean Nuclear Society
, v.49, no.7, pp.1495-1504,
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17 |
Evaluation of the medical staff effective dose during boron neutron capture therapy using two high resolution voxel-based whole body phantoms
Golshanian, Mohadeseh;Rajabi, Ali Akbar;Kasesaz, Yaser;
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Korean Nuclear Society
, v.49, no.7, pp.1505-1512,
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18 |
Dynamic characteristics assessment of reactor vessel internals with fluid-structure interaction
Je, Sang Yun;Chang, Yoon-Suk;Kang, Sung-Sik;
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Korean Nuclear Society
, v.49, no.7, pp.1513-1523,
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19 |
Identification of nonregular indication according to change of grain size/surface geometry in nuclear power plant (NPP) reactor vessel (RV)-upper head alloy 690 penetration
Kim, Kyungcho;Kim, Changkuen;Kim, Hunhee;Kim, Hak-Joon;Kim, Jin-Gyum;Jhung, Myungjo;
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Korean Nuclear Society
, v.49, no.7, pp.1524-1536,
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20 |
Contribution of thermal-hydraulic validation tests to the standard design approval of SMART
Park, Hyun-Sik;Kwon, Tae-Soon;Moon, Sang-Ki;Cho, Seok;Euh, Dong-Jin;Yi, Sung-Jae;
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Korean Nuclear Society
, v.49, no.7, pp.1537-1546,
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21 |
Corium melt researches at VESTA test facility
Kim, Hwan Yeol;An, Sang Mo;Jung, Jaehoon;Ha, Kwang Soon;Song, Jin Ho;
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Korean Nuclear Society
, v.49, no.7, pp.1547-1554,
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22 |
Markov chain-based mass estimation method for loose part monitoring system and its performance
Shin, Sung-Hwan;Park, Jin-Ho;Yoon, Doo-Byung;Han, Soon-Woo;Kang, To;
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Korean Nuclear Society
, v.49, no.7, pp.1555-1562,
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23 |
Effectiveness of the neutron-shield nanocomposites for a dual-purpose cask of Bushehr's Water-Water Energetic Reactor (VVER) 1000 nuclear-power-plant spent fuels
Rezaeian, Mahdi;Kamali, Jamshid;Ahmadi, Seyed Javad;Kiani, Mohammad Amin;
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Korean Nuclear Society
, v.49, no.7, pp.1563-1570,
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24 |
Experimental investigation of effective atomic numbers for some binary alloys
Sharma, Renu;Sharma, J.K.;Kaur, Taranjot;Singh, Tejbir;Sharma, Jeewan;Singh, Parjit S.;
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Korean Nuclear Society
, v.49, no.7, pp.1571-1574,
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