Published November 1990
| Version v1
Journal article
Radiation annealing of reactor graphite after neutron irradiation
Creators
Description
The reactor graphite specimens initially irradiated at 310-450 K by the fluences 5x1021, 9x1021, 1,3x1022 n/sm2 (E>0,18 MeV) were repeatedly irradiated at 620-1200 K by the fluences up to 2,5x1021 n/sm2. Simultaneously the control specimens of reactor graphite and nongraphitized half finished product were irradiated. It is shown that irradiation annealing of preirradiated specimens leads to the more considerable shrinkage that of the control specimens
Additional details
Additional titles
- Original title (Russian)
- Радиационный отжиг реакторного графита после воздействия нейтронного облучения
Publishing Information
- Journal Title
- Fizika i Khimiya Obrabotki Materialov
- Journal Issue
- no.6
- Series
- Fiz. Khim. Obrab. Mater.
- ISSN
- 0015-3214
- CODEN
- FKOMA
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- USSR
- INIS RN
- 22072065
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- ANNEALING; GRAPHITE; HIGH TEMPERATURE; KEV RANGE 100-1000; MECHANICAL PROPERTIES; NEUTRON FLUENCE; PHYSICAL RADIATION EFFECTS; REACTOR MATERIALS; SHRINKAGE; VERY HIGH TEMPERATURE
- Descriptors DEC
- CARBON; ELEMENTS; ENERGY RANGE; HEAT TREATMENTS; KEV RANGE; MATERIALS; NONMETALS; RADIATION EFFECTS