Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Title 

Showing results 1761 to 1780 of 10301

1761
Aqueous self-assembly of amphiphilic nanocrystallo-polymers and their surface-active properties

Jang, Kwang-Suk; Lee, Hyun-Jin; Yang, Hee-Man; An, Eun-Jung; Kim, Tae-Hwan; Choi, Sung-Min; Kim, Jong-Duk, SOFT MATTER, v.4, no.2, pp.349 - 356, 2008

1762
ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets

Sorbom, B. N.; Ball, J.; Palmer, T. R.; Mangiarotti, F. J.; Sierchio, J. M.; Bonoli, P.; Kasten, C.; et al, FUSION ENGINEERING AND DESIGN, v.100, pp.378 - 405, 2015-11

1763
Argon Impurity Transport Study with Resonant Magnetic Perturbation in KSTAR

Lee, Hyunyong; Hong, Joohwan; Jang, Juhyeok; Bak, Jun Gyo; Kim, Kimin; Ko, Wonha; Lee, Jae Hyun; et al, 2016 KSTAR Conference, 국가핵융합연구소, 2016-02-25

1764
Argon Impurity Transport Study with Resonant Magnetic Perturbation in KSTAR

Lee, Hyunyong; Hong, Joohwan; Jang, Juhyeok; Bak, Jun Gyo; Kim, Kimin; Ko, Wonha; Lee, Jae Hyun; et al, 2016 KSTAR Conference, 국가핵융합연구소, 2016-02-25

1765
Argon-seeded detachment during ELM control by RMPs in KSTAR

Shin, H; Hwang, J; Han, Y; Shin, G; Lee, H; Chai, KB; Choe, Wonho, NUCLEAR FUSION, v.63, no.4, 2023-04

1766
Arrangement of Single-walled Carbon Nanotubes in Binary/Ternary Polymer System : Small-angle Scattering Study

장형식; 도창우; 김태환; Kline, Steven R.; 이민재; 최성민, The 12th Pacific Polymer Conference, 2011-11

1767
Artifact reduction using segmentation constrained RPCA for CT

Kim, Yejin; Choi, Dain; Lim, Sunho; Cho, Seungryong, International Forum on Medical Imaging in Asia, IWAIT-IFMIA, 2019-01-07

1768
Artifacts associated with implementation of the Grangeat formula

Lee, SW; Cho, Gyuseong; Wang, G, MEDICAL PHYSICS, v.29, no.12, pp.2871 - 2880, 2002-12

1769
Artificial neural network modeling for 2-group pin-wise group constants

Yu, HwanYeal; Ur Rehman, Haseeb; Kim, Yonghee, Transactions of the American Nuclear Society, ANS 2017, pp.1107 - 1110, American Nuclear Society, 2017-06

1770
Assesment and Improvement of Condensation Models in RELAP5/MOD3.2

No, Hee Cheon; Choi, Ki Yong; Park, Hyun Sik; Kim, Sang Jae, 한국원자력학회 추계발표회, pp.585 - 590, 한국원자력학회, 1997

1771
Assesment on Toxicity of Radioactive Wastes from PEACER in Korea

Lee, Kun Jai, Global 2003, 2003

1772
Assessement of HTGR He Compressor Analysis Tool based on Newton-Raphson Numerical Application to Throughflow Analysis

No, Hee Cheon; Kim, JH; Kim, HM, ICONE14 Int. Conf. on Nuclear Eng., 2006

1773
Assessing Intangible Technology Transfer in North Korea’s Nuclear International Collaboration Network

Baxter, Philip; Hastings, Justin V.; Kim, Philseo; Yim, Man-Sung, Strategic Trade Review, v.9, no.10, pp.51 - 78, 2023-02

1774
Assessing proliferation uncertainty in civilian nuclear cooperation under new power dynamics of the international nuclear trade

Kim, Philseo; Kim, Jihee; Yim, Man-Sung, ENERGY POLICY, v.163, 2022-04

1775
Assessing the potential of small modular reactors (SMRs) in spent nuclear fuel management: A review of the generation IV reactor progress

Park, Hong June; Chang, Sun Young; Kim, Kyung Soo; Levrd, Pascal Cluade; Moon, Joo Hyun; Yun, Jong-Il, JOURNAL OF NUCLEAR FUEL CYCLE AND WASTE TECHNOLOGY, v.21, no.4, pp.571 - 576, 2023-12

1776
Assessing the proliferation resistance of nuclear fuel cycle systems using a fuzzy logic-based barrier method

Jun Li; Yim, Man-Sung; McNelis, David, NUCLEAR TECHNOLOGY, v.162, no.3, pp.293 - 307, 2008-06

1777
Assessment and improvement of condensation models in RELAP5/MOD3.2

Choi, KY; Park, HS; Kim, SJ; No, Hee Cheon; Bang, YS, NUCLEAR TECHNOLOGY, v.124, no.2, pp.103 - 117, 1998-11

1778
Assessment and improvement of direct-contact condensation models with/without noncondensible gases in RELAP5/MOD3.2

No, Hee Cheon; Choi, KY; Bang, YS, 3rd ASME/JSME Joint Fluids Engineering Conference, 1999

1779
Assessment of 13~19Cr Ferritic Oxide Dispersion Strengthened Steels for Fuel Cladding Applications

김인섭, Korean Nuclear Society Autumn Meeting, 2004

1780
Assessment of a DNB-type theoretical critical heat flux model for rod bundles with non-uniform axial power shapes

Han, KH; Hwang, DH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.236, no.3, pp.223 - 231, 2006-02

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