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- W242236041 abstract "A tritium permeation analyses code (TPAC) has been developed by Idaho National Laboratory for the purpose of analyzing tritium distributions in Very High Temperature Reactor (VHTR) systems, including integrated hydrogen production systems. A MATLAB SIMULINK software package was used for development of the code. The TPAC is based on the mass balance equations of tritium-containing species and various forms of hydrogen coupled with a variety of tritium sources, sinks, and permeation models. In the TPAC, ternary fission and neutron capture reactions with Li, Li B, He were taken into considerations as tritium sources. Purification and leakage models were implemented as main tritium sinks. Permeation of tritium and H2 through pipes, vessels, and heat exchangers were considered as main tritium transport paths. In addition, electroyzer and isotope exchange models were developed for analyzing hydrogen production systems including high temperature electrolysis and sulfur-iodine (SI) processes. Tritium behaviors in a very high temperature reactor/high temperature steam electrolysis (HTSE) system have been analyzed by the TPAC based on the reference indirect parallel configuration investigated by INL in a related VHTR study. This preliminary analysis showed that only 3.5% of tritium released from the core is transferred to the product hydrogen. In this case, the tritium concentration in the hydrogen product is estimated to be 1.04x10 Bq/cm, which is less than the regulatory effluent limit (=3.7x10 Bq/cm) by a factor of 3 to 4. This tritium concentration level can be even reduced further by improved system designs and novel tritium permeation barrier methods. The TPAC has unlimited flexibility for system configurations and provides an easy method to create models by using a “drag-and-drops” graphical user interface described in this study. Verification of the code was performed by comparisons with analytical solutions and the experimental data from the Peach Bottom Reactor Unit 1 design. Calculations from the THYTAN code developed in Japan and adopted by Japan Atomic Energy Agency were also compared with TPAC results." @default.
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- W242236041 date "2010-06-01" @default.
- W242236041 modified "2023-09-24" @default.
- W242236041 title "Development of Tritium Permeation Analysis Code and Tritium Transport in a High Temperature Gas-Cooled Reactor Coupled with Hydrogen Production System" @default.
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