Published June 1996
| Version v1
Journal article
Radiation resistance of zirconium hydride
Description
Using the method of incoherent scattering of thermal neutrons a study was made into hydrogen concentration variation in the sample of zirconium hydride irradiated by fast neutron fluence of 2x1027 n/m2 at 400 deg C. The irradiation was carried out in NB-600 nuclear reactor. There is no evidence of hydrogen loss under irradiation. The stability of zirconium hydride concentration is assumed to be provided by the protective coating. The advantages of the method of thermal neutron incoherent scattering for investigating irradiated materials are pointed out. Zirconium hydrides are considered as promising fast neutron moderators. 4 refs., 4 figs., 2 tabs
Additional details
Additional titles
- Original title (Russian)
- Радиационная стойкост' гидрида циркония
Publishing Information
- Journal Title
- Fizika Metallov i Metallovedenie
- Journal Volume
- 81
- Journal Issue
- 6
- Journal Page Range
- p. 134-138.
- ISSN
- 0015-3230
- CODEN
- FMMEA9
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Russian Federation
- INIS RN
- 28041103
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BELOYARSK-3 REACTOR; CHEMICAL COMPOSITION; NEUTRON DIFFRACTION; NEUTRON SPECTRA; PHYSICAL RADIATION EFFECTS; PROTECTIVE COATINGS; STABILITY; ZIRCONIUM HYDRIDES
- Descriptors DEC
- BREEDER REACTORS; COATINGS; COHERENT SCATTERING; DIFFRACTION; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HYDRIDES; HYDROGEN COMPOUNDS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; POWER REACTORS; RADIATION EFFECTS; REACTORS; SCATTERING; SODIUM COOLED REACTORS; SPECTRA; TRANSITION ELEMENT COMPOUNDS; ZIRCONIUM COMPOUNDS