International (2010~2025)

[언푸름]

36. Cho, D.H., Woo, S.W., Chang, Y.S., Choi, J.B., Kim, Y.J., Jhung, M.J., Choi, Y.H., 2010, "Enhancement of J estimation for typical nuclear pipes with a circumferential surface crack under tensile load," Journal of Mechanical Science and Technology, Vol.24, No.3, pp.681-686.

37. Choi, S.B., Chang, Y.S., Choi, J.B., Kim, Y.J., Jhung, M.J., Choi, Y.H., 2010, "Fatigue life assessment of reactor coolant system components by using transfer functions of integrated FE model," Nuclear Engineering and Technology, Vol.42, No.5, pp.590-599.

38. Jhung, M.J., Ryu, Y.H., 2010, "Study on Dynamic Response of Mechanical Component due to Earthquake," Journal of Nuclear Science and Technology, Vol.47, No.11, pp.1065-1074.

39. Jhung, M.J., Kim, S.H., Choi, Y.H., Chang, Y.S., Xu, X., Kim, J.M., Kim, J.W., Jang, C., 2010, "Probabilistic Fracture Mechanics Round Robin Analysis on Reactor Pressure Vessels during Pressurized Thermal Shock," Journal of Nuclear Science and Technology, Vol.47, No.12, pp.1131-1139.

40. Kang, D.G., Jhung, M.J., Chang, S.H., 2011, "Fluid-structure interaction analysis for pressurizer surge line subjected to thermal stratification," Nuclear Engineering and Design, Vol.241, Issue 1, pp.257-269.

41. Jhung, M.J., Choi, Y.H., Chang, Y.S., 2011, "Comparison of Vessel Failure Probabilities during PTS," Structural Engineering and Mechanics, Vol.37, No.3, pp.257-265.

42. Jhung, M.J., Yu, S.O., Lim, Y.T., 2011, "Dynamic characteristics of a partially fluid-filled cylindrical shell," Nuclear Engineering and Technology, Vol.43, No.2, pp.167-174.

43. Cho, D.H., Seo, H.B., Kim, Y.J., Chang, Y.S., Jhung, M.J., Choi, Y.H., 2011, "Advances in J-integral estimation of circumferentially surface cracked pipes," Fatigue and Fracture of Engineering Materials and Structures, Vol.34, No.9, pp.667-681.

44. Jhung, M.J., Yu, S.O., 2011, "Study on modal characteristics of perforated shell using effective Young’s modulus," Nuclear Engineering and Design, Vol.241, Issue 6, pp.2026-2033.

45. Kim, Y.W., Jhung, M.J., 2011, "Mathematical analysis using two modelling techniques for dynamic responses of a structure subjected to a ground acceleration time history," Nuclear Engineering and Technology, Vol.43, No.4, pp.361-374.

46. Jhung, M.J., Kim, Y.B., 2012, "A study on modal characteristics of flow skirt using effective Young’s modulus," Nuclear Engineering and Technology, Vol.44, No.5, pp.501-506.

47. Jhung, M.J., 2012, "Fatigue analysis of a reactor pressure vessel for SMART," Nuclear Engineering and Technology, Vol.44, No.6, pp.683-688.

48. Kanto, Y., Jhung, M.J., Ting, K., He, Y.B., Onizawa, K., Yoshimura, S., 2012, "Summary of international PFM round robin analysis among Asian countries on reactor pressure vessel integrity during pressurized thermal shock," International Journal of Pressure Vessels and Piping, Vol.90, pp.46-55.

50. Jhung, M.J., 2013, "Assessment of thermal fatigue in mixing tee by FSI analysis," Nuclear Engineering and Technology, Vol.45, No.1, pp.99-106.

51. Kim, Y-W., Jhung, M.J., 2014, "A study on large mass method for dynamic problem of multiple degree-of-freedom system excited by ground acceleration time history," Journal of Mechanical Science and Technology, Vol.28, No.1, pp.25-41.

52. Koh, H-O., Jhung, M.J., Choi, J-B., 2014, "Development of Green's Function Approach Considering Temperature-dependent Material Properties and its Application," Nuclear Engineering and Technology, Vol.46, No.1, pp.101-108.

53. Kim, D-H., Chang, Y-S, Jhung, M.J., 2014, "Numerical study on fluid flow by hydrodynamic loads in reactor internals," Structural Engineering and Mechanics, Vol.51, No.6, pp.1005-1016.

54. Lee, K-H., Jhung, M.J., Kim, M-C., Lee, B-S., 2014, "Effects of Temperating and PWHT on Microstructures and Mechanical Properties of SA508 GR.4N Steel," Nuclear Engineering and Technology, Vol.46, No.3, pp.413-422.

55. Jhung, M.J., Jeong, K.H., 2015, "Free vibration analysis of perforated plate with square penetration pattern using equivalent material properties," Nuclear Engineering and Technology, Vol.47, No.4, pp.500-511.

56. Lee, K-H., Kang, S.S., Jhung, M.J., 2015, "Integrity Analysis of Upper Guide Structure Flange," Nuclear Engineering and Technology, Vol.47, No.6, pp.766-775.

57. Jhung, M.J., Jeong, K.H., 2015, "Modal characterictics of partially perforated rectangular plate with triangular penetration pattern," Structural Engineering and Mechanics, Vol.55, No.3, pp.583-603

58. Kim, S.H., Chang, Y-S., Cho, Y.J., Jhung, M.J., 2016, "Modeling of reinforced concrete for reactor cavity analysis under energetic steam explosion condition," Nuclear Engineering and Technology, Vol.48, No.1, pp.218-227.

59. Park, J.S., Choi, Y.H., Jhung, M.J., 2016, "Probabilistic fracture mechanics analysis of boiling water reactor vessel for cool-down and low temperature over-pressurization transients," Nuclear Engineering and Technology, Vol.48, No.2, pp.545-553.

49. Kim, J.S., Oh, K.H., Lee, K.W., Jhung, M.J., 2012, "Development and Application of the Added Fluid Mass and Substructure Techniques for Integrated Pressurized Water Reactor Assembly," Nuclear Engineering and Design, Vol.250, pp.68-80.

60. Jeong, K.H., Jhung, M.J., 2017, "Added mass estimation of square sections coupled with a liquid using finite element method," Nuclear Engineering and Technology, Vol.49, No.1, pp.234-244.

61. Kim, K.C., Kim, J.G., Kang, S.S., Jhung, M.J., 2017, "Korean round-robin tests result for new international program to assess the reliability of emerging nondestructive techniques," Nuclear Engineering and Technology, Vol.49, No.3, pp.651-661.

62. Jeong, K.H., Jhung, M.J., 2017, "Free vibration analysis of partially perforated circular plates," Procedia Engineering, Vol.199, pp.182-187.

63. Kim, K.C., Kim, C.K., Kim, H.H., Kim, H.J., Kim, J.G, Jhung, M.J., 2017, "Identification of nonregular indication according to change of grain size/surface geometry in nuclear power plant reactor vessel-upper head alloy 690 penetration," Nuclear Engineering and Technology, Vol.49, No.7, pp.1524-1536.

64. Kim, K.C., Min, K.M., Kim, C.K., Kim, J.G, Jhung, M.J., 2018, "Detectability eval‎uation of the loose parts in steam generator by eddy current testing techniques," Nuclear Engineering and Technology, Vol.50, No.7, pp.1160-1167.

65. Jhung, M.J., Kang, S.S., 2019, "Fluid effect on the modal characteristics of a square tank," Nuclear Engineering and Technology, Vol.51, No.4, pp.1117-1131.

66. Jhung, M.J., Oh, C.S., Choi, Y.I., Kang, S.S., 2020, "Vessel failure sensitivities of an advanced reactor for SBLOCA," Nuclear Engineering and Technology, Vol.52, No.1, pp.185-191.

67. Jhung, M.J., Oh, C.S., Choi, Y.I., Kang, S.S., Kim, M., Kim, T-H., Kim, J-M., Kim, M.C., Lee B.S., Kim, J-M., Kim, K., 2020, "Round robin analysis of vessel failure probabilities for PTS events in Korea," Nuclear Engineering and Technology, Vol.52, No.8, pp.1871-1880.

68. Lee, G., Jhung, M.J., Bae, J., Kang, S., 2021, "Numerical study on the cavitation flow and its effect on the structural integrity of multi-stage orifice," Energies, Vol.14, 1518.

69. Jhung, M.J., Choi, Y.I., Oh, C.S., 2021, "Earthquake response of a core shroud for APR1400," Nuclear Engineering and Technology, Vol.53, No.8, pp.2716-2727.

70. Oh, C., Lee, S., Jhung, M.J., 2022, "Analytical method to estimate cross-section stress profiles for reactor vessel nozzle corners under internal pressure," Nuclear Engineering and Technology, Vol.54, Issue 1, pp.401-413.

71. Oh, C., Lee, S., Jhung, M.J., Huh, N.S., 2022, "Analyitical approach to estimate the thermal stress distribution of reactor pressure vessel nozzle corners with a constant cooldown rate," International Journal of Pressure Vessels and Piping, Vol.197, 104608.

72. Jhung, M.J., Choi, Y., Oh, C., 2022, "Dynamic response of a fuel assembly for a KSNP design earthquake," Nuclear Engineering and Technology, Vol.54, Issue 9, pp.3353-3360.

73. Jhung, M.J., Choi, Y., Oh, C., Shin, G., Park, C.I., 2023, "Seismic analysis of a steam generator for Gyeongju and Pohang earthquakes" Nuclear Engineering and Technology, Vol.55, Issue 5, pp.1577-1586.

- The End -