Browse "NE-Conference Papers(학술회의논문)" by Author Kim, Yonghee

Showing results 1 to 60 of 96

1
A comparative study on CMFD and p-CMFD acceleration in the Monte Carlo analysis

Kim, Inhyung; Kim, Yonghee, 2017 Transactions of the American Nuclear Society, ANS 2017, pp.675 - 678, American Nuclear Society, 2017-10

2
A diffusion-based 3D FEM analysis for assessment of reactivity change due to support plate expansion and localized flowering in an SFR

Heo, Woong; Kim, Yonghee, 2018 Transactions of the American Nuclear Society, ANS 2018, pp.1245 - 1248, American Nuclear Society, 2018-11

3
A fully passive daily load-follow operation in a small PWR system

Abdelhameed, Ahmed Amin E; Kim, Yonghee, 2017 Transactions of the American Nuclear Society, ANS 2017, pp.1217 - 1220, American Nuclear Society, 2017-06

4
A High-Performance Soluble-Boron-Free Small Modular Reactor Core

Kim, Yonghee; 모드슈크리빈야야, International Technical Meeting on Small Reactors, International Technical Meeting on Small Reactors, 2016-02-03

5
A Hybrid (?,n) and (n,?) Transmutation Study for Long-living Fission Products

Rehman, Haseeb Ur; Lee, Jiyoung; Kim, Yonghee, 2017 Transactions of the American Nuclear Society, ANS 2017, pp.1306 - 1309, American Nuclear Society, 2017-10

6
A leakage correction with SPH factors for two-group cross-section in get-based pin-by-pin core analysis

Yu, Hwan Yeal; Kim, Woosong; Kim, Yonghee, 2018 Transactions of the American Nuclear Society, ANS 2018, pp.1229 - 1232, American Nuclear Society, 2018-11

7
A neutronics study on annular fuel filled with burnable absorber

Yahya, Mohd Syukri; Hartanto, Donny; Kim, Yonghee, 2015 Transactions of the American Nuclear Society, ANS 2015, pp.1262 - 1264, American Nuclear Society, 2015-11

8
A new deterministic truncation of Monte Carlo solution using decoupled fine-mesh finite difference method

Kim, Inhyimg; Kim, Yonghee, 2020 Transactions of the American Nuclear Society Winter Meeting, ANS 2020, pp.690 - 693, American Nuclear Society, 2020-11

9
A New Stochastic Acceleration Scheme for the Monte Carlo Method

Kim, Inhyung; Kim, Yonghee, PHYSOR 2016, PHYSOR 2016, 2016-05-02

10
A new two-step framework with improved nodal equivalence for PWR depletion analysis

Lee, Kyunghoon; Kim, Woosong; Kim, Yonghee, 2019 Transactions of the American Nuclear Society, ANS 2019, pp.855 - 859, American Nuclear Society, 2019-06

11
A Physics Study for Passively-Autonomous Daily Load-Follow Operation in Soluble-Boron-Free SMR

ABDELHAMEED AHMED; Kim, Yonghee; HASEEB UR, ICAPP 2017, ANS, 2017-04-28

12
A physics study on alternative reflectors in a compact sodium-cooled breed-and-burn fast reactor

Hartanto, Donny; Kim, Yonghee, International Congress on Advances in Nuclear Power Plants: Nuclear Power - A Safe and Sustainable Choice for Green Future, ICAPP 2013, Held with the 28th KAIF/KNS Annual Conference, pp.1754 - 1760, Korean Nuclear Society, 2013-04

13
A Point Design for a LEU Composite NTP system: Superb Use of Low Enriched Uranium (SULEU)

Kim, Yonghee; VENNERI PAOLO, Nuclear and Emerging Technologies for Space, American Nuclear Society, 2016-02-22

14
A Potential Way of Co-60 Production in CANDU6 Reactions

Kim, Yonghee; Lyu, Jinqi, PBNC 2016, PBNC 2016, 2016-04-06

15
A preliminary application of the GPS correction to pin-by-pin 2-step PWR depletion

Yu, Hwanyeal; Jeong, Hae Sun; Kim, Yonghee, 2019 Transactions of the American Nuclear Society, ANS 2019, pp.1327 - 1330, American Nuclear Society, 2019-11

16
A preliminary study on the self-sustainability of a sodium-cooled breed-and-burn fast reactor (B&BR)

Hartanto, Donny; Kim, Yonghee, 2015 Transactions of the American Nuclear Society, ANS 2015, pp.1111 - 1114, American Nuclear Society, 2015-11

17
A Study of Leakage-corrected Two-step Method based on the Nodal Equivalence Theory for Fast Reactor Analysis

Jang, Seongdong; Kim, Yonghee, Physics of reactor (PHYSOR 2020), American Nuclear Society, 2020-03

18
A study on deterministic truncation of Monte Carlo transport solution

Kim, Inhyung; Kim, Yonghee, 2018 International Conference on Physics of Reactors: Reactor Physics Paving the Way Towards More Efficient Systems, PHYSOR 2018, pp.2534 - 2545, Sociedad Nuclear Mexicana, A.C., 2018-04

19
A Study on Reconstruction of Intra-Pin Information in Pin-Wise Reactor Analysis

Nguyen Xuan Ha; Kim, Yonghee, ANS Winter Meeting, ANS Winter Meeting, 2016-11-07

20
A study on the optimal position for the secondary neutron source in pwrs

Sun, Jungwon; Yahya, Mohd Syukri; Kim, Yonghee, 2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016, pp.1456 - 1465, American Nuclear Society, 2016-04

21
Advancements in the Development of Low Enriched Uranium Nuclear Thermal Rockets

Venneri, Paolo; Kim, Yonghee, 5th International Symposium on Innovative Nuclear Energy Systems, INES-5 2016, pp.53 - 60, Elsevier BV, 2016-10

22
Albedo-corrected Parameterized Equivalence Constants for Cross-section Correction in Nodal Calculation

Kim, Woosong; Kim, Yonghee, International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, ANS, 2017-04-20

23
An investigation on the homogenization of fast reactor fuel assembly

Heo, Woong; Kim, Yonghee, 2014 ANS Winter Meeting and Nuclear Technology Expo, pp.1282 - 1284, American Nuclear Society, 2014-11

24
Application of APEC method in CANDU analysis

Motalab, Mohammad Abdul; Kim, Woosong; Kim, Yonghee, International Conference on Physics of Reactors: Reactor Physics Paving the Way Towards More Efficient Systems, PHYSOR 2018, pp.3127 - 3141, Sociedad Nuclear Mexicana, A.C., 2018-04

25
Application of NEM-Based Pin-by-Pin HCMFD Algorithm to 3-D Core Analysis

Kim, Jaeha; Kim, Yonghee, ANS Winter Meeting, ANS Winter Meeting, 2016-11-09

26
Application of the APEC method to MOx fuel loaded PWR cores

Kim, Woosong; Kim, Yonghee, 2018 Transactions of the American Nuclear Society, ANS 2018 and Embedded Topical Meeting Nuclear Fuels and Structural Materials, pp.933 - 936, American Nuclear Society, 2018-06

27
Application of the BigT burnable absorber to AP1000 core for a soluble boron free operation

Yahya, Mohd Syukri; Kim, Yonghee, 2014 ANS Winter Meeting and Nuclear Technology Expo, pp.1208 - 1210, American Nuclear Society, 2014-11

28
Application of the BigT burnable absorber to AP1000 first core

Yahya, Mohd Syukri; Kim, Yonghee, 2015 ANS Annual Meeting, pp.811 - 813, American Nuclear Society, 2015-06

29
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

30
Burnable Absorber Optimization in a Super-Flux Research Reactor Utilizing Plate-Type Fuel

Kim, Yonghee; Nguyen Xuan Ha; VENNERI PAOLO, RRFM/IGORR 2016, RRFM/IGORR 2016, 2016-03-15

31
Burnup-dependenl GPS method with leakage correction and spectral weighting in core depletion analysis

Jeong, Hae Sun; Yu, Hwanyeal; Kim, Yonghee, 2020 Transactions of the American Nuclear Society Winter Meeting, ANS 2020, pp.1319 - 1322, American Nuclear Society, 2020-11

32
CANDU6 PCR evaluation with a detailed 3-D Monte Carlo analysis

Motalab, Mohammad Abdul; Kim, Woosong; Kim, Yonghee, 35th Annual Conference of the Canadian Nuclear Society and 38th CNS/CNA Student Conference 2015, pp.580 - 590, Canadian Nuclear Society, 2015-05

33
Centrally-Shielded Burnable Absorber for LWR Fuel

Yahya, Mohd Syukri; Kim, Yonghee, ICAPP 2017, ANS, 2017-04-28

34
Characterization of Xenon Induced Reactivity Changes in Low Enriched Nuclear Thermal Propulsion Cores

Kim, Yonghee; VENNERI PAOLO, Nuclear and Emerging Technologies for Space, American Nuclear Society, 2016-02-23

35
Comprehensive analysis of low- and high-enriched uranium nuclear thermal propulsion for manned mars missions

Rawlins, Samantha B; Kim, Yonghee, 53rd AIAA/SAE/ASEE Joint Propulsion Conference, 2017, American Institute of Aeronautics and Astronautics Inc, AIAA, 2017-07

36
Concepts and characteristics of a soluble-boron-free small modular reactor with centrally-shielded burnable absorbers

Nguyen, Xuan Ha; Rahman, Anisur; Kim, Yonghee, 2018 International Conference on Physics of Reactors: Reactor Physics Paving the Way Towards More Efficient Systems, PHYSOR 2018, pp.3356 - 3365, Sociedad Nuclear Mexicana, A.C., 2018-04

37
Conceptual Design of S-CO2 Cooled Micro Modular Reactor

김민길; 이정익; Kim, Yonghee; Hartano, D, 2013 한국원자력학회 춘게학술대회, 한국원자력학회, 2013-05-30

38
Conceptual System Design of a Supercritical CO2 cooled Micro Modular Reactor

Kim, Seong Gu; Baik, Seung Joon; Moon, Jangsik; Yu, Hwanyeal; Jeong, Yong Hoon; Kim, Yonghee; Jeong-Ik Lee, ICAPP 2015, American Nuclear Society, 2015-05

39
Convergence of sequential and parallel one-node CMFD accelerations for neutron transport analysis

Kim, Hyeon Tae; Kim, Yonghee, 2018 Transactions of the American Nuclear Society, ANS 2018 and Embedded Topical Meeting Nuclear Fuels and Structural Materials, pp.361 - 364, American Nuclear Society, 2018-06

40
Core reactivity control for a soluble boron free small modular reactor

Kim, Hyeong Heon; Chung, Chang Kyu; Yahya, Mohd-Syukri; Kim, Yonghee, 2017 Transactions of the American Nuclear Society, ANS 2017, pp.1027 - 1029, American Nuclear Society, 2017-06

41
Criticality Control of a High-Performance Soluble-Boron-Free Small Modular Reactor Core

모드슈크리빈야야; Kim, Yonghee, ANS Winter Meeting, ANS Winter Meeting, 2016-11-08

42
Development of the 900 second specific impulse carbide low enriched uranium nuclear thermal rocket

Venneri, Paolo F; Kim, Yonghee; Husemeyer, Peter; Howe, Stephen, 2014 International Conference on Physics of Reactors, PHYSOR 2014, Japan Atomic Energy Agency, JAEA, 2014-09

43
ERBIA-LOADED CANDU FUEL FOR MINIMIZATION OF THE COOLANT VOID REACTIVITY

MOHAMMAD ABDUL; Kim, Yonghee; Kim, Woosong, International Conference on CANDU Fuel, International Conference on CANDU Fuel, 2016-08-16

44
Erbium Burnable Absorber to Improvement Safety Parameters of CANDU Loaded With Recovered Uranium

MOHAMMAD ABDUL; Kim, Yonghee; Kim, Woosong, ICAPP 2017, ANS, 2017-04-28

45
Extreme performance multibatch research reactor based on simple plate fuel

Venneri, Paolo; Kim, Yonghee, 2015 Transactions of the American Nuclear Society, ANS 2015, pp.1067 - 1069, American Nuclear Society, 2015-11

46
Fabrication of Neutron Absorber Containing Ceramic Composite Pellets by using Microwave Sintering

Mistarihi, Qusai; Ryu, Ho Jin; Yahya, Mohd Syukri; Kim, Yonghee, 한국원자력학회 2016 추계학술대회, 한국원자력학회, 2016-10-27

47
Fabrication of neutron absorber inserted oxide fuel pellet

MISTARIHI QUSA; Ryu, Ho Jin; Kim, Yonghee; Yahya, Nigd-Sykuri, 12th Pacific Rim Conference on Ceramic and Glass Technology (PACRIM 12), The American Ceramic society, 2017-05-24

48
FAST (Floating Absorber for Safety at Transient) for the improved safety of metallic-fuel-loaded sodium-cooled fast reactors

Kim, Chihyung; Kim, Yonghee, Transactions of the American Nuclear Society, ANS 2019, pp.1545 - 1548, American Nuclear Society, 2019-11

49
FEASIBILITY ASSESSMENT OF AIR-COOLING SYSTEM AS AN ULTIMATE HEAT SINK OF THE ATOM SYSTEM

Shin, Doyoung; Seo, Gwang Hyeok; Na, Min Wook; Kim, Sung Joong; Kim, Yonghee; Lee, Jeongik, 26th International Conference on Nuclear Engineering (ICONE-26), AMER SOC MECHANICAL ENGINEERS, 2018-07

50
Feasibility of a very-low-boron core design for APR1400 with 24-month cycle length

Do, Manseok; Nguyen, Xuan Ha; Kim, Yonghee, 2018 International Conference on Physics of Reactors: Reactor Physics Paving the Way Towards More Efficient Systems, PHYSOR 2018, pp.4048 - 4057, Sociedad Nuclear Mexicana, A.C., 2018-04

51
Feasibility of Albedo-corrected parameterized equivalence constants for nodal equivalence theory

Kim, Woosong; Kim, Yonghee, Mathematics and Computations, Supercomputing in Nuclear Applications and Monte Carlo International Conference, M and C+SNA+MC 2015, pp.3198 - 3208, American Nuclear Society, 2015-04

52
Feasibility of low thrust, low-enriched uranium nuclear thermal propulsion

Rawlins, Samantha; Kim, Yonghee, Nuclear and Emerging Technologies for Space, NETS 2018, pp.349 - 351, American Nuclear Society, 2018-02

53
FEM-based Estimation of Reactivity Change due to Core Deformation in SFR

Heo, Woong; Kim, Yonghee, International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, ANS, 2016-04-20

54
FEM-based Estimation of Reactivity Change due to Core Deformation in SFR

Heo, Woong; Kim, Yonghee, International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, ANS, 2017-04-20

55
First-order perturbation for uncertainty quantification in the deterministic truncation of Monte Carlo method

Kim, HyeonTae; Kim, Inhyung; Kim, Yonghee, Tech 2018 Iron and Steel Technology Conference and Exposition, pp.430 - 432, American Nuclear Society, 2018-06

56
Full submersion criticality accident for low enriched uranium nuclear thermal rockets

Venneri, Paolo; Kim, Yonghee; Husemeyer, Peter; Howe, Stephen, 2014 ANS Winter Meeting and Nuclear Technology Expo, pp.1425 - 1428, American Nuclear Society, 2014-11

57
Full submersion criticality accident mitigation in the Carbide LEU-NTR

Venneri, Paolo F; Kim, Yonghee, 2015 Nuclear and Emerging Technologies for Space, NETS 2015, pp.299 - 306, American Nuclear Society, 2015-02

58
Improved discontinuity factor modeling for the in-situ APEC leakage correction in nodal analysis

Jang, Seongdong; Kim, Yonghee, Transactions of the American Nuclear Society, ANS 2019, pp.1335 - 1338, American Nuclear Society, 2019-11

59
Improved modelling for the assembly discontinuity factors in the APEC method

Kim, Woosong; Kim, Yonghee, 2017 Transactions of the American Nuclear Society, ANS 2017, pp.1093 - 1095, American Nuclear Society, 2017-06

60
Improvement of safety parameters by using erbium-loaded canflex fuel bundle in the candu reactor

Kim, Woosong; Kim, Yonghee, International Congress on Advances in Nuclear Power Plants: Nuclear Power - A Safe and Sustainable Choice for Green Future, ICAPP 2013, Held with the 28th KAIF/KNS Annual Conference, pp.1812 - 1820, Korean Nuclear Society, 2013-04

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