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In situ tritium recovery behavior from Li2TiO3 pebble bed under neutron pulse operation
- Source :
- Journal of Nuclear Materials. :1248-1251
- Publication Year :
- 2004
- Publisher :
- Elsevier BV, 2004.
-
Abstract
- A binary pebble bed of lithium titanate (Li 2 TiO 3 ) was irradiated in the Japan Materials Testing Reactor (JMTR), and its tritium recovery characteristics bed was studied under pulsed neutron operations. The temperature at the outside edge of the pebble bed increased from 300 to 350 °C immediately after the window of hafnium (Hf) neutron absorber was turned toward the reactor core, while the tritium recovery rate increased gradually. The ratio of tritium recovery rate to generation rate at the high-power, ( R / G ) high , approached the saturated value of unity at about 20 h of operation. Overall tritium recovery behavior under the pulsed operation was similar to that under the steady state power operation. An estimated time constant of about 3 h for the tritium recovery was much longer than the thermal time constant of about 100 s.
- Subjects :
- Nuclear and High Energy Physics
Materials testing reactor
Nuclear engineering
Radiochemistry
Neutron poison
Nuclear reactor
Fusion power
law.invention
chemistry.chemical_compound
Nuclear Energy and Engineering
chemistry
Nuclear reactor core
law
General Materials Science
Neutron
Tritium
Lithium titanate
Subjects
Details
- ISSN :
- 00223115
- Database :
- OpenAIRE
- Journal :
- Journal of Nuclear Materials
- Accession number :
- edsair.doi...........20ca04102879ccae6a14cb4f5463e6aa
- Full Text :
- https://doi.org/10.1016/j.jnucmat.2004.04.238