Nuclear Production of Hydrogen, Fourth Information Exchange ...
Nuclear Production of Hydrogen, Fourth Information Exchange ... Nuclear Production of Hydrogen, Fourth Information Exchange ...
STATUS OF THE KOREAN NUCLEAR HYDROGEN PRODUCTION PROJECT Figure 2: Design tools Design Analysis Codes Nuclear Design Codes PSA PSA PSA-AIMS PSA-AIMS Temp. Fuel & Graphite COPA FP to coolant Coolant Activity HyPEP-FP/T/Dust System System Layout Layout & Efficiency Efficiency HyPEP HyPEP Sys. Configuration Sys. Performance Thermo-Fluid & Safety GAMMA+/CAPP (DBA, BDBA) MARS-GCR/MASTER (2-φ Tran.) GAMMA-TF/CAPP (RPV TF) CFX (Component TF, H 2 Explosion) Mass & energy discharge FPs Corroded source Fission Products & Containment GAMMA-FP/T/Dust mass SI SI Dynamics Dynamics DySCO DySCO T, P Thermo-Mechanical Graphite Seismic ANSYS/ABAQUS Graphite Corrosion GAMMA+, COPA Library MCNP DH Treatment Reference Verification Library HELIOS/LIBERTE Output HOPE/PROLOG CX Tableset MASTER-GCR (PMR) CAPP (PBR) Transport Lattice Calculation - Fuel Block, Pebble, Reflector CX Tablesets - Burnup, Temperatures, … Diffusion Core Calculation - Physics Analysis Activity release Atmospheric Atmospheric dispersion dispersion & Public Public dose dose TBD TBD thermo-fluid transport. An upgraded version of GAMMA, GAMMA+. will be coupled with a new reactor physics code CAPP (Lee, H.C., 2008). The CAPP code fully utilises modern computer programming standard C++. Helium flow in the complex geometries such as inlet plenum, outlet plenum, and pebbles (In, 2008; Lee, S.Y, 2008), is modelled by computational fluid dynamics (CFD) codes. There are several computer code to look at consequences of reactor incident such as COPA (Kim, Y-M., 2008) for fuel performance, and others for radioactivity transportation analysis. For mechanical analysis, a methodology using ANSYS and ABACUS is under development (Kim, D-O., 2008). For the transient analysis of sulphur iodine thermochemical process, a computer program named DySCO (Shin, 2008a) is under development. Some of the experimental activities are undergoing to verify design tools such as the pebble heat transfer (Lee, J-J., 2007), the reactor cavity cooling system heat transfer (Cho, 2006). Materials and components Most of the material research is in collaboration with Generation-IV VHTR research activities. Properties of the nuclear graphite, the metallic material such as A617 and 9Cr1Mo, the ceramic composite are under investigation by measuring specimens. Corrosion resistant material is a key issue for success of sulphuric thermochemical cycle. Silicon carbide, hastelloy, gold and Fe-Si alloys have a good corrosion rate less than 1 mm per year. However, long-term behaviour is different from that of short-term behaviour due to a protective layer (Kim, H.P., 2008). A long-term corrosion in realistic environment is required for selecting suitable material for large scale SI chemical plant. Since the process heat exchanger (PHE) is the most challenging component to couple VHTR with the sulphur decomposition section of the SI thermochemical process where high temperature and corrosion requirement is the most severe, KAERI is investigating the possibility of using a noble approach to use the ion beam mixing on the surface of a ceramic-coated metallic layer (Park, 2007). The corrosion resistance in the boiling sulphuric acid and thermal cycling environment was satisfactory so that a test PHE is manufactured (Kim, Y-W., 2008). A small gas loop of 10 kW (Hong, 2008) was built to test the performance of the IBM PHE. The initial test will be published in the near future. Coated fuel Fuel manufacturing technology in KAERI is concentrated on fabricating a quality TRISO. Currently a 20 gram per batch UO 2 kernel fabrication apparatus and a 20 gram per batch SiC coater are installed at KAERI (Lee, Y-W., 2008). Properties of the fabricated TRISO particle are investigated using various characterisation methods such as the particle size analyser, the density analyser, the density gradient 62 NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010
STATUS OF THE KOREAN NUCLEAR HYDROGEN PRODUCTION PROJECT Figure 3: A process heat exchanger assembled from ion beam mixed plates column, the anisotropy photometer, the nano indentation, etc. One of the special methods to analyse the coated layer is to use the phase contrast X-ray micro-radiography. As shown in Figure 4, the coating layers of TRISO particle can be clearly distinguished. The radiography has the benefit of non-destructive test of many samples. Figure 4: X-ray micro-radiography and images of TRISO particle KAERI is joining the PYCASSO experiment to investigate coating behaviour under irradiation (Groot, 2008). The objective of the experiment for KAERI is to analyse the porosity and property changes of a pyrolytic carbon buffer layer as a function of neutron fluence and temperature. Approximately 10 000 coated particles of four different coating layer densities were provided for PYCASSO. Hydrogen production process A small scale sulphur iodine process loop made of Pyrex glass was built and operated. The sulphuric acid section and Bunsen reaction section was operated successfully in 2006. In 2008, hydrogen iodide decomposition aided by electro-dialysis (EED) (Hong, 2007) was demonstrated to produce 3.5 litres per NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010 63
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STATUS OF THE KOREAN NUCLEAR HYDROGEN PRODUCTION PROJECT<br />
Figure 3: A process heat exchanger assembled from ion beam mixed plates<br />
column, the anisotropy photometer, the nano indentation, etc. One <strong>of</strong> the special methods to analyse<br />
the coated layer is to use the phase contrast X-ray micro-radiography. As shown in Figure 4, the coating<br />
layers <strong>of</strong> TRISO particle can be clearly distinguished. The radiography has the benefit <strong>of</strong> non-destructive<br />
test <strong>of</strong> many samples.<br />
Figure 4: X-ray micro-radiography and images <strong>of</strong> TRISO particle<br />
KAERI is joining the PYCASSO experiment to investigate coating behaviour under irradiation<br />
(Groot, 2008). The objective <strong>of</strong> the experiment for KAERI is to analyse the porosity and property changes<br />
<strong>of</strong> a pyrolytic carbon buffer layer as a function <strong>of</strong> neutron fluence and temperature. Approximately<br />
10 000 coated particles <strong>of</strong> four different coating layer densities were provided for PYCASSO.<br />
<strong>Hydrogen</strong> production process<br />
A small scale sulphur iodine process loop made <strong>of</strong> Pyrex glass was built and operated. The sulphuric<br />
acid section and Bunsen reaction section was operated successfully in 2006. In 2008, hydrogen iodide<br />
decomposition aided by electro-dialysis (EED) (Hong, 2007) was demonstrated to produce 3.5 litres per<br />
NUCLEAR PRODUCTION OF HYDROGEN – © OECD/NEA 2010 63
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