A STUDY OF A NUCLEAR HYDROGEN PRODUCTION DEMONSTRATION PLANT

The current energy supply system is burdened by environmental and supply problems. The concept of a hydrogen economy has been actively discussed worldwide. KAERI has set up a plan to demonstrate massive production of hydrogen using a VHTR by the early 2020s. The technological gap to meet this goal was identified during the past few years. The hydrogen production process, a process heat exchanger, the efficiency of an I/S thermochemical cycle, the manufacturing of components, the analysis tools of VHTR, and a coated particle fuel are key areas that require urgent development. Candidate NHDD plant designs based on a 200 MWth VHTR core and I/S thermochemical process have been studied and some of analysis results are presented in this paper.

[1]  J. Kaae,et al.  Irradiation behavior of experimental fuel particles containing chemically vapor deposited zirconium carbide coatings , 1976 .

[2]  P. Wagner High-temperature fuel technology for nuclear process heat: ZrC-containing coated particle fuels and high-density graphite fuel matrices , 1977 .

[3]  Y. Kurata,et al.  The effect of heat treatment on density and structure of SiC , 1980 .

[4]  G. Besenbruch,et al.  General Atomic sulfur-iodine thermochemical water-splitting process , 1982 .

[5]  K. Ikawa,et al.  Diffusion of metal fission products in ZrC1.0 , 1982 .

[6]  H. Nabielek,et al.  The Performance of High-Temperature Reactor Fuel Particles at Extreme Temperatures , 1989 .

[7]  Kazuo Minato,et al.  Fission product palladium-silicon carbide interaction in htgr fuel particles , 1990 .

[8]  H. Nabielek,et al.  Development of advanced HTR fuel elements , 1990 .

[9]  Shusaku Shiozawa,et al.  Research and Development of HTTR Coated Particle Fuel , 1991 .

[10]  U. Ohlig,et al.  V. S. O. P. ('94) Computer Code System for Reactor Physics and Fuel Cycle Simulation , 1994 .

[11]  Shusaku Shiozawa,et al.  Safety criteria and quality control of HTTR fuel , 2001 .

[12]  Jihong Li,et al.  Design and manufacture of the fuel element for the 10 MW high temperature gas-cooled reactor , 2002 .

[13]  Jacopo Buongiorno,et al.  Key Differences in the Fabrication, Irradiation, and Safety Testing of U.S. and German TRISO-coated Particle Fuel and Their Implications on Fuel Performance , 2002 .

[14]  K. R. Schultz,et al.  Initial Screening of Thermochemical Water-Splitting Cycles for High Efficiency Generation of Hydrogen Fuels Using Nuclear Power , 1999 .

[15]  Jonghwa Chang,et al.  DEVELOPMENT OF MARS-GCR/V1 FOR THERMAL-HYDRAULIC SAFETY ANALYSIS OF GAS- COOLED REACTOR SYSTEMS , 2005 .

[16]  Seung Wook Lee,et al.  Preliminary Sensitivity Study on Gas-Cooled Reactor for NHDD System Using MARS-GCR , 2005 .

[17]  Jean-Marc Borgard,et al.  Upper bound and best estimate of the efficiency of the iodine sulphur cycle , 2005 .

[18]  Willem Kriel,et al.  Revised Capital and Operating HyS Hydrogen Production Costs , 2006 .

[19]  Jae Man Noh,et al.  Development of a Computer Code System for the Analysis of VHTR Cores , 2006 .

[20]  Hong SungDeok,et al.  Design of a Small Scale High Temperature Gas Loop for Process Heat Exchanger Design Tests , 2006 .

[21]  Woo-Gon Kim,et al.  Creep Properties of Hastelloy-X Alloy for the High Temperature Gas-Cooled Reactor , 2006 .

[22]  Hee Cheon No,et al.  GAMMA Multidimensional Multicomponent Mixture Analysis to Predict Air Ingress Phenomena in an HTGR , 2006 .

[23]  J. Noh,et al.  Development of Two-Step Procedure for the Prismatic VHTR Physics Analysis , 2006 .

[24]  Jonghwa Chang,et al.  Effects of ion beam mixing of silicon carbide film deposited onto metallic materials for application to nuclear hydrogen production , 2007 .

[25]  A. Shenoy,et al.  H2-MHR PRE-CONCEPTUAL DESIGN SUMMARY FOR HYDROGEN PRODUCTION , 2007 .

[26]  K. S. Bang,et al.  HEAT REMOVAL TEST USING A HALF SCALE STORAGE CASK , 2007 .

[27]  Myung Seung Yang,et al.  EVALUATION OF PROLIFERATION RESISTANCE USING THE INPRO METHODOLOGY , 2007 .