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NUCLEAR ENERGY MATERIALS PREDICTION: APPLICATION OF THE MULTI-SCALE MODELLING PARADIGM
Samaras, Maria;Victoria, Maximo;Hoffelner, Wolfgang;
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Korean Nuclear Society
, v.41, no.1, pp.1-10,
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| 2 |
MULTISCALE MODELING OF RADIATION EFFECTS ON MATERIALS: PRESSURE VESSEL EMBRITTLEMENT
Kwon, Jun-Hyun;Lee, Gyeong-Geun;Shin, Chan-Sun;
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Korean Nuclear Society
, v.41, no.1, pp.11-20,
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| 3 |
METALLIC INTERFACES IN HARSH CHEMO-MECHANICAL ENVIRONMENTS
Yildiz, Bilge;Nikiforova, Anna;Yip, Sidney;
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Korean Nuclear Society
, v.41, no.1, pp.21-38,
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MULTI-SCALE MODELS AND SIMULATIONS OF NUCLEAR FUELS
Stan, Marius;
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Korean Nuclear Society
, v.41, no.1, pp.39-52,
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EXPERIMENTS ON THE PERFORMANCE SENSITIVITY OF THE PASSIVE RESIDUAL HEAT REMOVAL SYSTEM OF AN ADVANCED INTEGRAL TYPE REACTOR
Park, Hyun-Sik;Choi, Ki-Yong;Choi, Seok;Yi, Sung-Jae;Park, Choon-Kyung;Chung, Moon-Ki;
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Korean Nuclear Society
, v.41, no.1, pp.53-62,
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| 6 |
APPLICATION OF SEVERE ACCIDENT MANAGEMENT GUIDANCE IN THE MANAGEMENT OF AN SGTR ACCIDENT AT THE WOLSONG PLANTS
Jin, Young-Ho;Park, Soo-Yong;Song, Yong-Mann;
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Korean Nuclear Society
, v.41, no.1, pp.63-70,
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| 7 |
DESIGN OF DELAY-TOLERANT CONTROLLER FOR REMOTE CONTROL OF NUCLEAR REACTOR POWER
Lee, Yoon-Joon;Na, Man-Gyun;
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Korean Nuclear Society
, v.41, no.1, pp.71-78,
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| 8 |
VERIFICATION OF PLC PROGRAMS WRITTEN IN FBD WITH VIS
Yoo, Jun-Beom;Cha, Sung-Deok;Jee, Eun-Kyung;
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Korean Nuclear Society
, v.41, no.1, pp.79-90,
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| 9 |
"3+3 PROCESS" FOR SAFETY CRITICAL SOFTWARE FOR I&C SYSTEM IN NUCLEAR POWER PLANTS
Jung, Jae-Cheon;Chang, Hoon-Sun;Kim, Hang-Bae;
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Korean Nuclear Society
, v.41, no.1, pp.91-98,
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| 10 |
DETERMINATION OF THE TRANSURANIC ELEMENTS INVENTORY IN HIGH BURNUP PWR SPENT FUEL SAMPLES BY ALPHA SPECTROMETRY-II
Joe, Kih-Soo;Song, Byung-Chul;Kim, Young-Bok;Jeon, Young-Shin;Han, Sun-Ho;Jung, Euo-Chang;Song, Kyu-Seok;
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Korean Nuclear Society
, v.41, no.1, pp.99-106,
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| 11 |
CORROSION BEHAVIOR OF NI-BASE ALLOYS IN SUPERCRITICAL WATER
Zhang, Qiang;Tang, Rui;Li, Cong;Luo, Xin;Long, Chongsheng;Yin, Kaiju;
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Korean Nuclear Society
, v.41, no.1, pp.107-112,
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| 12 |
ANALYSIS OF DOPPLER-BROADENED PEAK IN THERMAL NEUTRON INDUCED 10B(n,α γ)7Li REACTION USING HYPERGAM
Choi, Hee-Dong;Jung, Nam-Suk;Park, Byung-Gun;
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Korean Nuclear Society
, v.41, no.1, pp.113-124,
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| 13 |
DEVELOPMENT OF A STEAM GENERATOR TUBE INSPECTION ROBOT WITH A SUPPORTING LEG
Shin, Ho-Cheol;Jeong, Kyung-Min;Jung, Seung-Ho;Kim, Seung-Ho;
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Korean Nuclear Society
, v.41, no.1, pp.125-134,
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| 14 |
EXPERIMENTAL APPROACHES FOR WATER DISCHARGE CHARACTERISTICS IN PEMFC USING NEUTRON IMAGING TECHNIQUE AT CONRAD, HMI
Kim, Tae-Joo;Kim, Jong-Rok;Sim, Cheul-Muu;Lee, Sung-Ho;Son, Young-Jin;Kim, Moo-Hwan;
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Korean Nuclear Society
, v.41, no.1, pp.135-142,
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