Published July 1993 | Version v1
Report

Design and characteristics of annulus ventilation and HVAC system for prototype FBR MONJU

  • 1. Power Reactor ampersand Nuclear Fuel Development Corp., Tsuruga-shi, Fukui-ken (Japan)
  • 2. Mitsubishi Heavy Industries Ltd., Hyogo-ku, Kobe-shi (Japan)
  • 3. Mitsubishi Atomic Power Industries Inc., Shibakoen, Minato-ku, Tokyo (Japan)
  • 4. Shinryo Corp., Hyogo-ku, Kobe-shi (Japan)

Description

The MONJU annulus ventilation system described in this paper keeps the annulus below a pressure of -15 mmAq as a secondary containment during reactor operation to assure -6 mmAq even in the case of accident. To minimize release of radioactive substances, the system adopts a charcoal filter with a thickness of 20 cm whose efficiency of iodine removal is over 99%. Rooms for components containing radioactive sodium are maintained in a nitrogen atmosphere during ordinary operation by the inert gas cooling system, and form gastight cells for which atmospheric leakage is designed to achieve below 100%vol/day at a pressure differential of 100mmAq. Design specifications of annulus ventilation and HVAC system are determined by experimental data and computer analyses for the accident. Function and performance of the annulus ventilation and HVAC system have been confirmed by pre-operational tests. 5 refs., 10 figs., 5 tabs

Part of:
Proceedings of the 22nd DOE/NRC Nuclear Air Cleaning Conference, Sessions 9--16

Additional details

Publishing Information

Imprint Title
Proceedings of the 22nd DOE/NRC Nuclear Air Cleaning Conference, Session 9--16
Imprint Pagination
527 p.
Journal Page Range
p. 791-807.
Report number
NUREG/CP--0130-Vol.2

Conference

Title
22. Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) nuclear air cleaning and treatment conference.
Dates
24-27 Aug 1992.
Place
Denver, CO (United States).

Optional Information

Secondary number(s)
CONF-920823--Vol.2.