Permeation analysis of tritium through the titanium hydride storage vessel
- 1. Korea Atomic Energy Research Inst., Daejeon (Korea, Republic of)
Description
A preliminary design of a stainless steel vessel for the long-term storage of hydrogen isotopes has been proposed. The immobilized hydrogen as a titanium hydride could be used in a stainless steel vessel for this application. The vessel as a primary package is designed to form titanium hydride and to contain the hydrogen isotopes and helium-3 produced from the tritium decay. In order to predict against the possibility of a contamination and the deterioration of the mechanical properties, a numerical calculation was carried out for a diffusion analysis of the hydrogen isotopes and helium inside the stainless steel vessel. Numerical results showed that a negligible amount of tritium would be released by a permeation through the vessel wall of a 0.7cm thickness at normal conditions over the entire period of the storage. In the case that the vessel was heated up to a temperature of 600 C for the routine condition of an activation or exothermic hydriding, it would be of little concern regarding a tritium loss or a contamination. However, when the vessel was exposed to a fire condition with a temperature of 800 C, permeation of the hydrogen through the vessel wall resulted in a serious increase in the amount of tritium escaping, in a very short time
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Additional details
Publishing Information
- Imprint Title
- PATRAM 2004 - The 14th international symposium on the packaging and transportation of radioactive materials. Conference proceedings
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- 6 p.
- Report number
- INIS-DE--0129
Conference
- Title
- 14. international symposium on the packaging and transportation of radioactive materials
- Acronym
- PATRAM 2004
- Dates
- 20-24 Sep 2004
- Place
- Berlin (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 37088654
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FINITE ELEMENT METHOD; FIRES; HEAT TREATMENTS; HELIUM 3; NUMERICAL ANALYSIS; PRESSURE VESSELS; RISK ASSESSMENT; STAINLESS STEELS; STORAGE; TITANIUM HYDRIDES; TRITIUM
- Descriptors DEC
- ALLOYS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CALCULATION METHODS; CARBON ADDITIONS; CONTAINERS; EVEN-ODD NUCLEI; HELIUM ISOTOPES; HIGH ALLOY STEELS; HYDRIDES; HYDROGEN COMPOUNDS; HYDROGEN ISOTOPES; IRON ALLOYS; IRON BASE ALLOYS; ISOTOPES; LIGHT NUCLEI; MATHEMATICAL SOLUTIONS; MATHEMATICS; NUCLEI; NUMERICAL SOLUTION; ODD-EVEN NUCLEI; RADIOISOTOPES; STABLE ISOTOPES; STEELS; TITANIUM COMPOUNDS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENT COMPOUNDS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- Paper No. 146