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 |