O/m-ratio measurement techniques
Revision of exp-fus-10201. critic-1 - a proposal to measure tritium release during irradiation of li2o in the NRU reactor
Critic-i - a proposal to measure tritium release during irradiation of li2o in the NRU reactor
Irradiation of Lithium-based Ceramics for Fusion Blanket Application
Critic-iii - a proposal to measure tritium release during irradiation of li2tio3 in the NRU reactor
Neutron flux measurements for the lithium-tritium sweep gas tests
A proposal for a program of in-reactor irradiation testing of solid breeder blanket materials
Task 1.4 simfuel preparation and testing. final report on work carried out by AECL research for the belgonucleaire high burnup chemistry program
Preliminary study and cost estimate for a neutron irradiation device in the enea-casaccia triga reactor for testing fusion breeder materials
The effect of material characteristics on tritium release from lithium oxide
Uses of CRL's electron accelerators for fuel research
Migration behaviour of iodine in nuclear fuel
Post-irradiation tritium recovery from lialo2 - create-ii results
Post-irradiation Examination of BEATRIX-II Phase-II Li↓2ZrO↓3 Pebble-bed
Create-vii : proposal to irradiate japanese lithium aluminate in NRX self-serve facility under international beatrix program
Post-irradiation tritium recovery from lithium ceramic breeder materials
Tritium Release from Lithium Ceramics at Constant Temperature
Create-vii : proposal to irradiate anl lithium oxide in NRX self-serve facility under international beatrix program
Tritium Release from Lithium Ceramics at Constant Temperature
Iodine, rubidium, and krypton release and bubble formation in oxide fuels