2007
DOI: 10.3327/jnst.44.1407
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Numerical Study on Tritium Behavior by Using Isotope Exchange Reactions in Thermochemical Water-Splitting Iodine–Sulfur Process

Abstract: One potential problem in the hydrogen production system coupled with the high-temperature gascooled reactor (HTGR) is transmission of tritium from the primary coolant to the product hydrogen by permeation through the heat transfer tubes. Tritium accumulation in the process chemicals in the components of a hydrogen plant, a thermochemical water-splitting iodine-sulfur (IS) process, will also be a critical issue in seeking to license the hydrogen plant as a non-nuclear plant in the future. A numerical analysis m… Show more

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Cited by 6 publications
(3 citation statements)
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“…The RELAP5 code [23] was used to calculate short-term transient behavior for the rupture of concentric hot gas duct in the primary cooling system and transient behavior for the SG tube rupture. The graphite oxidation behavior of core internal structure was calculated using the THYTAN code [24], which was originally developed for the calculation of mass balance of tritium and hydrogen in the HTGR hydrogen production system using the flow network. The THYTAN code has been modified to calculate the mass balance of the graphite oxidation reaction and the gas concentration in the primary circuit and containment structure.…”
Section: Acceptance Criteriamentioning
confidence: 99%
“…The RELAP5 code [23] was used to calculate short-term transient behavior for the rupture of concentric hot gas duct in the primary cooling system and transient behavior for the SG tube rupture. The graphite oxidation behavior of core internal structure was calculated using the THYTAN code [24], which was originally developed for the calculation of mass balance of tritium and hydrogen in the HTGR hydrogen production system using the flow network. The THYTAN code has been modified to calculate the mass balance of the graphite oxidation reaction and the gas concentration in the primary circuit and containment structure.…”
Section: Acceptance Criteriamentioning
confidence: 99%
“…Six reports were published by JAERI/JAEA in 2007. The first was an evaluation study on tritium activity concentration, Ohashi H. et al (2007). This was done to check the permeability of tritium through heat transfer tubes and to check deuterium and tritium concentrations in the secondary helium coolant.…”
Section: Thermo-chemical Cyclesmentioning
confidence: 99%
“…In the nuclear reactor core, tritium is released to the coolant as T 2 , but will quickly undergo isotope exchange reactions with molecular hydrogen, present as a contaminant in the helium stream, to form tritiated hydrogen [27], as shown in Equation 13.…”
Section: Permeationmentioning
confidence: 99%