화학공학소재연구정보센터

International Journal of Energy Research

International Journal of Energy Research, Vol.42, No.1 Entire volume, number list
ISSN: 0363-907X (Print) 

In this Issue (30 articles)

3 - 3 PREFACE for the special issue on "progress in novel nuclear energy technologies"
Sahin S
4 - 8 Overview of ITER TBM program objectives and management
Hong BG
9 - 26 Fusion energy development status in Korea
Jung KJ, Lee HG, Yun SH, Oh YK, Park HK
27 - 52 Advancements in DEMO WCLL breeding blanket design and integration
Martelli E, Del Nevo A, Arena P, Bongiovi G, Caruso G, Di Maio PA, Eboli M, Mariano G, Marinari R, Moro F, Mozzillo R, Giannetti F, Di Gironimo G, Tarallo A, Tassone A, Villari R
53 - 67 New high-performance light water reactor core concept with mixed cycle length operation
Jeong E, Choe J, Zhang P, Shin HC, Lee D
68 - 72 Development of high intensity D-T fusion neutron generator HINEG
Wu YC
73 - 81 An innovative core design for a soluble-boron-free small pressurized water reactor
Yahya MS, Kim Y
82 - 90 A new hybrid filter based on differential current control method for low-order harmonic suppression in Tokamak power system
Lu J, Fu P, Li J, Mao HF, Shen XS, Xu LW, Wu YA
91 - 103 Assessment and analysis of hydrogen and electricity production from a Generation IV lead-cooled nuclear reactor integrated with a copper-chlorine thermochemical cycle
Al-Zareer M, Dincer I, Rosen MA
104 - 116 Analysis of hydrogen and dust explosion after vacuum vessel rupture: Preliminary safety analysis of Korean fusion demonstration reactor using MELCOR
Moon SB, Lim SM, Bang IC
117 - 133 Thorium breeder reactors as a power source for 21st century and beyond
Jagannathan V
134 - 150 Full-core coupled neutronic/thermal-hydraulic modelling of the EBR-II SHRT-45R transient
Caron D, Bonifetto R, Dulla S, Mascolino V, Ravetto P, Savoldi L, Valerio D, Zanino R
151 - 162 A comparative physics study for an innovative sodium-cooled fast reactor (iSFR)
Hartanto D, Kim C, Kim Y
163 - 170 Design of self-sustainable small modular reactor with multiple fissile and fertile layers
Park CJ, Park MG, Jung W, Jeong HY, Kim G, Kim J
171 - 177 Void reactivity aspect and fuel conversion potential of heavy water cooled thorium reactor
Permana S, Waris A, Suud Z, Sekimoto H
178 - 187 Reactivity and kinetic parameter evolutions for the core height and boron concentration of the fixed bed nuclear reactor
Thong HV, Minh DTN, Sahin S, Hoang TH, Sefidvash F
188 - 197 A circumferentially non-uniform fuel model and its application to thermal-hydraulic code
Yang T, Liu XJ, Cheng X
198 - 206 Evaluation of the radiation damage parameters of ODS steel alloys in the first wall of deuterium-tritium fusion-fission (hybrid) reactors
Tunc G, Sahin HM, Sahin S
207 - 213 Preliminary sustainable and economic analysis of nuclear fuel cycle with subcritical system
Wang MH, Fu XW, Zhang WL, Lian C, Chen DH
214 - 220 Comparison of uranium plutonium nitride (U-Pu-N) and thorium nitride (Th-N) fuel for 500 MWth gas-cooled fast reactor (GFR) long life without refueling
Syarifah RD, Su'ud Z, Basar K, Irwanto D, Pattipawaej SC, Ilham M
221 - 235 Modification and application of Relap5 Mod3 code to several types of nonwater-cooled advanced nuclear reactors
Liu LM, Zhang DL, Song J, Wang CL, Gao XL, Tian WX, Qiu SZ, Su GH
236 - 244 Comparison of the laser-Compton scattering and the conventional Bremsstrahlung X-rays for photonuclear transmutation
Rehman HU, Lee J, Kim Y
245 - 254 Steady-state thermal simulations of the liquid-salt-cooled high-temperature reactor
Ramos MC, Scari ME, Costa AL, Pereira C, Velasquez CE, Veloso MAF
255 - 260 Temperature sensitivity analysis for an ADS system using different nuclear data libraries
Velasquez CE, Barros GD, Pereira C, Veloso MAF, Costa AL
261 - 275 Transient analysis for liquid-fuel molten salt reactor based on MOREL2.0 code
Cao LZ, Zhuang K, Zheng YQ, Hu TL, Wu HC
276 - 283 Numerical simulation of large bubble-rising behavior in nuclear reactor using diffuse interface method
Wang Y, Cai JJ, Li Q
284 - 292 Effects of delta-hydride precipitated at a crack tip on crack instability in Zircaloy-4
Suman S, Khan MK, Pathak M, Singh RN
293 - 302 Numerical simulation of tritiated bubble trajectory in a gas-liquid separator
Qian YL, Li JJ, Ma YF, Yin JL, Wang DZ, Li H, Liu W
303 - 313 Natural convection of melted core at the bottom of nuclear reactor vessel in a severe accident
Park HK, Kim SH, Chung BJ
314 - 320 A K-Epsilon RANS turbulence model for incompressible MHD flow at high Hartmann number in fusion liquid metal blankets
Meng Z, Zhang SC, Jia JT, Chen ZB, Ni MY