Published 1992 | Version v1
Book

ALMR containment evaluation

  • 1. General Electric Co., San Jose, CA (United States)

Description

The Advanced Liquid Metal Reactor containment has been evaluated using four hypothetical severe accident scenarios, different leak areas, and different decay heat distribution assumptions. In all cases, the containment pressure was found to increase with time to a maximum value, then decrease to atmospheric pressure, at which point release from the containment stops. The maximum pressure and time at which release stops were found to depend on the accident scenario, leak area and decay heat distribution. For the reference design and leak area, site doses accumulated during the first 36 hours of release were found to be substantially less than the Protective Action Guideline lower limits for evacuation. The analysis also shows that the ALMR can tolerate significant increases in leak areas without exceeding the above dose limits. (author)

Part of:
ANP'92 international conference on design and safety of advanced nuclear power plants

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan.
Imprint Place
Tokyo (Japan)
Imprint Title
ANP'92 international conference on design and safety of advanced nuclear power plants
Imprint Pagination
[2182 p.].
Journal Page Range
v. 4 p. 41.2/1-41.2/6.

Conference

Title
international conference on design and safety of advanced nuclear power plants.
Acronym
ANP'92
Dates
25-29 Oct 1992.
Place
Tokyo (Japan).

INIS

Optional Information

Notes
Imprint:Composed of four volumes.