Published 1991 | Version v1
Report Restricted

Analysis of depressurized loss-of-forced cooling transients by HERA

Description

The Modular High-Temperature Gas-Cooled Reactor (MHTGR) is one of the next generation reactors, which has passive safety features. Among these safety features is the ability to withstand a depressurized, loss-of-forced cooling of the reactor without release of fission products from the primary containment. In order to assess the capability of the MHTGR to withstand this type of accident condition, the thermal behavior of the reactor core must be well understood. To accomplish this, we have employed the HElium cooled Reactor Analysis code (HERA) to study the MHTGR under these conditions. Our analysis will demonstrate that the MHTGR is capable of withstanding a depressurized loss-of-forced cooling, even under worst case circumstances. 7 refs., 14 figs., 5 tabs

Availability note (English)

MF available from INIS under the Report Number; OSTI as DE91013040; NTIS; INIS; US Govt. Printing Office Dep.

Files

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Additional details

Publishing Information

Imprint Pagination
18 p.
Report number
LA-UR--91-1471

Conference

Title
Winter meeting of the American Nuclear Society (ANS).
Dates
10-15 Nov 1991.
Place
San Francisco, CA (United States).

Optional Information

Contract/Grant/Project number
Contract W-7405-ENG-36
Funding organization
USDOE, Washington, DC (United States).
Secondary number(s)
CONF-911107--2.