Abstract
The Summary Report - Part III of the Tenth Annual Meeting of the IAEA International Working Group on Fast Reactors - contains the discussions on the commercial development of FBRs according to national plans, mostly related to technology problems of containment design, fuel fabrication, fuel failures, sodium pressure, fuel-sodium interaction, computer codes needed for licensing. Most of the discussions were related to the existing reactors: BN-600, BN-350, BN-1600, BOR-60, RAPSODIE, PHENIX.
Citation Formats
None.
Tenth annual meeting, Vienna, Austria, 29 March - 1 April 1977. Summary report. Part III.
IAEA: N. p.,
1977.
Web.
None.
Tenth annual meeting, Vienna, Austria, 29 March - 1 April 1977. Summary report. Part III.
IAEA.
None.
1977.
"Tenth annual meeting, Vienna, Austria, 29 March - 1 April 1977. Summary report. Part III."
IAEA.
@misc{etde_20139411,
title = {Tenth annual meeting, Vienna, Austria, 29 March - 1 April 1977. Summary report. Part III}
author = {None}
abstractNote = {The Summary Report - Part III of the Tenth Annual Meeting of the IAEA International Working Group on Fast Reactors - contains the discussions on the commercial development of FBRs according to national plans, mostly related to technology problems of containment design, fuel fabrication, fuel failures, sodium pressure, fuel-sodium interaction, computer codes needed for licensing. Most of the discussions were related to the existing reactors: BN-600, BN-350, BN-1600, BOR-60, RAPSODIE, PHENIX.}
place = {IAEA}
year = {1977}
month = {Nov}
}
title = {Tenth annual meeting, Vienna, Austria, 29 March - 1 April 1977. Summary report. Part III}
author = {None}
abstractNote = {The Summary Report - Part III of the Tenth Annual Meeting of the IAEA International Working Group on Fast Reactors - contains the discussions on the commercial development of FBRs according to national plans, mostly related to technology problems of containment design, fuel fabrication, fuel failures, sodium pressure, fuel-sodium interaction, computer codes needed for licensing. Most of the discussions were related to the existing reactors: BN-600, BN-350, BN-1600, BOR-60, RAPSODIE, PHENIX.}
place = {IAEA}
year = {1977}
month = {Nov}
}