@article{oai:repo.qst.go.jp:00084919,
 author = {Makoto, Oyaizu and Masayuki, Ota and Kentaro, Ochiai and Atsushi, Kasugai and Makoto, Oyaizu and Masayuki, Ota and Kentaro, Ochiai and Atsushi, Kasugai},
 issue = {7-8},
 journal = {Fusion sciece and technology},
 month = {Nov},
 note = {In A-FNS, an accelerator-driven fusion-relevant neutron source, a few grams (3.5 g at full power operation) of tritium will be generated every year mainly in lithium target system. Since the generated tritium would migrate out of lithium target system, it is necessary to estimate the tritium migration in and out of the lithium target system for the design of detritiation systems for A-FNS, and therefore, a preliminary estimation is performed in the present study. As the results, it is found that almost all of the generated tritium in lithium target system would be trapped in impurity removal system, while less than 0.5% of that would migrate out. It is also indicated that the amount of tritium that would migrate out of lithium target system would be able to process with the existing techniques so far.},
 title = {Preliminary Estimation of Tritium Migration for A-FNS Lithium Target System},
 volume = {77},
 year = {2021}
}