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| 1 |
OVERVIEW OF RECENT EFFORTS THROUGH ROSA/LSTF EXPERIMENTS
Nakamura, Hideo;Watanabe, Tadashi;Takeda, Takeshi;Maruyama, Yu;Suzuki, Mitsuhiro;
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Korean Nuclear Society
, v.41, no.6, pp.753-764,
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| 2 |
INTEGRAL EFFECT TESTS IN THE PKL FACILITY WITH INTERNATIONAL PARTICIPATION
Umminger, Klaus;Mull, Thomas;Brand, Bernhard;
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Korean Nuclear Society
, v.41, no.6, pp.765-774,
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| 3 |
LBLOCA AND DVI LINE BREAK TESTS WITH THE ATLAS INTEGRAL FACILITY
Baek, Won-Pil;Kim, Yeon-Sik;Choi, Ki-Yong;
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Korean Nuclear Society
, v.41, no.6, pp.775-784,
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| 4 |
DEVELOPMENT OF A SIMPLIFIED MODEL FOR ANALYZING THE PERFORMANCE OF KALIMER-600 COUPLED WITH A SUPERCRITICAL CARBON DIOXIDE BRAYTON ENERGY CONVERSION CYCLE
Seong, Seung-Hwan;Lee, Tae-Ho;Kim, Seong-O;
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Korean Nuclear Society
, v.41, no.6, pp.785-796,
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| 5 |
DEVELOPMENT OF THE MATRA-LMR-FB FOR FLOW BLOCKAGE ANALYSIS IN A LMR
Ha, Kwi-Seok;Jeong, Hae-Yong;Chang, Won-Pyo;Kwon, Young-Min;Cho, Chung-Ho;Lee, Yong-Bum;
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Korean Nuclear Society
, v.41, no.6, pp.797-806,
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| 6 |
DISTRIBUTED CONTROL SYSTEM FOR KSTAR ICRF HEATING
Wang, Son-Jong;Kwak, Jong-Gu;Bae, Young-Dug;Kim, Sung-Kyu;Hwang, Churl-Kew;
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Korean Nuclear Society
, v.41, no.6, pp.807-812,
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| 7 |
CHARACTERISTICS OF A NEW PNEUMATIC TRANSFER SYSTEM FOR A NEUTRON ACTIVATION ANALYSIS AT THE HANARO RESEARCH REACTOR
Chung, Yong-Sam;Kim, Sun-Ha;Moon, Jong-Hwa;Baek, Sung-Yeol;Kim, Hark-Rho;Kim, Young-Jin;
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Korean Nuclear Society
, v.41, no.6, pp.813-820,
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| 8 |
MODAL TESTING AND MODEL UPDATING OF A REAL SCALE NUCLEAR FUEL ROD
Park, Nam-Gyu;Rhee, Hui-Nam;Moon, Hoy-Ik;Jang, Young-Ki;Jeon, Sang-Youn;Kim, Jae-Ik;
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Korean Nuclear Society
, v.41, no.6, pp.821-830,
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| 9 |
A DYNAMIC SIMULATION OF THE SULFURIC ACID DECOMPOSITION PROCESS IN A SULFUR-IODINE NUCLEAR HYDROGEN PRODUCTION PLANT
Shin, Young-Joon;Chang, Ji-Woon;Kim, Ji-Hwan;Park, Byung-Heung;Lee, Ki-Young;Lee, Won-Jae;Chang, Jong-Hwa;
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Korean Nuclear Society
, v.41, no.6, pp.831-840,
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| 10 |
A SIMPLE ANALYTICAL METHOD FOR NONLINEAR DENSITY WAVE TWO-PHASE INSTABILITY IN A SODIUM-HEATED AND HELICALLY COILED STEAM GENERATOR
Kim, Seong-O;Choi, Seok-Ki;Kang, Han-Ok;
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Korean Nuclear Society
, v.41, no.6, pp.841-848,
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| 11 |
AN OVERVIEW OF RISK QUANTIFICATION ISSUES FOR DIGITALIZED NUCLEAR POWER PLANTS USING A STATIC FAULT TREE
Kang, Hyun-Gook;Kim, Man-Cheol;Lee, Seung-Jun;Lee, Ho-Jung;Eom, Heung-Seop;Choi, Jong-Gyun;Jang, Seung-Cheol;
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Korean Nuclear Society
, v.41, no.6, pp.849-858,
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| 12 |
DESIGN AND CONSTRUCTION OF AN ADVANCED SPENT FUEL CONDITIONING PROCESS FACILITY (ACPF)
You, Gil-Sung;Choung, Won-Myung;Ku, Jeong-Hoe;Cho, Il-Je;Kook, Dong-Hak;Kwon, Kie-Chan;Lee, Eun-Pyo;Lee, Won-Kyung;
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Korean Nuclear Society
, v.41, no.6, pp.859-866,
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| 13 |
COMPARISON BETWEEN EXPERIMENTALLY MEASURED AND THERMODYNAMICALLY CALCULATED SOLUBILITIES OF UO2 AND THO2 IN KURT GROUND WATER
Kim, Seung-Soo;Baik, Min-Hoon;Kang, Kwang-Cheol;Choi, Jong-Won;
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Korean Nuclear Society
, v.41, no.6, pp.867-874,
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