LOFC fission product release and circulating activity calculations for gas-cooled reactors [electronic resource].
- Published
- Los Alamos, N.M. : Los Alamos Scientific Laboratory, 1977.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: 17 : digital, PDF file
- Additional Creators
- Los Alamos Scientific Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- The inventories of fission products in a gas-cooled reactor under accident and normal steady state conditions are time and temperature dependent. To obtain a reasonable estimate of these inventories it is necessary to consider fuel failure, a temperature dependent variable, and radioactive decay, a time dependent variable. Using arbitrary radioactive decay chains and published fuel failure models for the High Temperature Gas-Cooled Reactor (HTGR), methods have been developed to evaluate the release of fission products during the Loss of Forced Circulation (LOFC) accident and the circulating and plateout fission product inventories during steady state non-accident operation. The LARC-2 model presented here neglects the time delays in the release from the HTGR due to diffusion of fission products from particles in the fuel rod through the graphite matrix. It also neglects the adsorption and evaporation process of metallics at the fuel rod-graphite and graphite-coolant hole interfaces. Any time delay due to the finite time of transport of fission products by convection through the coolant to the outside of the prestressed concrete reactor vessel (PCRV) is also neglected. This model assumes that all fission products released from fuel particles are immediately deposited outside the PCRV with no time delay.
- Report Numbers
- E 1.99:la-ur-77-1569
E 1.99: conf-770708-10
conf-770708-10
la-ur-77-1569 - Subject(s)
- Other Subject(s)
- Note
- Published through SciTech Connect.
01/01/1977.
"la-ur-77-1569"
" conf-770708-10"
Thermal reactor safety meeting, Sun Valley, ID, USA, 31 Jul 1977.
Lee, C.E.; Carruthers, L.M.; Apperson, C.E. Jr. - Funding Information
- W-7405-ENG-36
View MARC record | catkey: 14801934