Published July 2008 | Version v1
Miscellaneous

Strategy of safety evaluation of water cooled solid breeder test blanket module

  • 1. Japan Atomic Energy Agency, Fusion Research and Development Directorate, Naka, Ibaraki (Japan)

Description

Representative events selected by the result of Failure Mode Effect Analysis (FMEA) are summarized into three groups, i.e., release of Radioactive Isotopes (RI), pressurization and heatup. With respect to events about release of RI, the maximum released RI is evaluated for three RI inventories, i.e., RI in Vacuum Vessel (VV) (tritium and radioactive dust), RI in purge gas (tritium) and RI in coolant (tritium and ACP). With respect to the events about pressurization, the maximum pressures of the compartments nearby the pipes of cooling system are evaluated. With respect to the events about heatup, preliminary thermal analyses have been carried out on three hypothetical cases, i.e., the case of loss of cooling, the case of ingress of coolant into the module and loss of offsite power after ingress of coolant. (author)

Part of:
Proceedings of the 5th annual meeting of Japan Society of Maintenology

Additional details

Additional titles

Original title (Japanese)
Nippon hozen gakkai dai-5-kai gakujutsu koenkai yoshishu

Publishing Information

Imprint Title
Proceedings of the 5th annual meeting of Japan Society of Maintenology
Imprint Pagination
551 p.
Journal Page Range
p. 32-33

Conference

Title
5. annual meeting of Japan Society of Maintenology
Dates
10-12 Jul 2008
Place
Mito, Ibaraki (Japan)

Optional Information

Notes
Imprint:Nippon hozen gakkai dai-5-kai gakujutsu koenkai yoshishu