Published June 2000
| Version v1
Journal article
Thermal iodine release of surface-implanted iodine in zirconia and its affect on hull disposal
Description
During the reactor processing fission products, among which iodine is one, are implanted by recoil inside the Zircaloy cladding tube, most of them being distributed within the first 2 μm. At the same time, oxidation of the cladding tubes occurs and therefore in the waste disposal phase zirconia will act as the first migration barrier. In order to analyse the mechanisms involved in iodine migration, stable and radioactive iodine atoms were introduced in oxidised zirconium samples by means of ion implantation at the near surface (mean range around 50 nm). Iodine thermal-release was measured either by Rutherford backscattering spectrometry (RBS) or γ-spectroscopy
Additional details
Identifiers
- PII
- S0022311500000209;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 279
- Journal Issue
- 2-3
- Journal Page Range
- p. 153-161
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 34036915
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- CLADDING; FISSION PRODUCTS; FUEL-CLADDING INTERACTIONS; GAMMA SPECTROSCOPY; IODINE; MIGRATION; OXIDATION; RADIOACTIVE WASTE DISPOSAL; RUTHERFORD BACKSCATTERING SPECTROSCOPY; ZIRCALOY
- Descriptors DEC
- ALLOYS; CHEMICAL REACTIONS; DEPOSITION; ELEMENTS; HALOGENS; ISOTOPES; MANAGEMENT; MATERIALS; NONMETALS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; SPECTROSCOPY; SURFACE COATING; TRANSITION ELEMENT ALLOYS; WASTE DISPOSAL; WASTE MANAGEMENT; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Copyright
- Copyright (c) 2000 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.