The effect of carbon crystal structure on treat reactor physics calculations [electronic resource].
- Published:
- Argonne, Ill. : Argonne National Laboratory, 1988.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description:
- Pages: 9 : digital, PDF file
- Additional Creators:
- Argonne National 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 Transient Reactor Test Facility (TREAT) at Argonne National Laboratory-West (ANL-W) is fueled with urania in a graphite and carbon mixture. This fuel was fabricated from a mixture of graphite flour, thermax (a thermatomic carbon produced by ''cracking'' natural gas), coal-tar resin and U/sub 3/O/sub 8/. During the fabrication process, the fuel was baked to dissociate the resin, but the high temperature necessary to graphitize the carbon in the thermax and in the resin was avoided. Therefore, the carbon crystal structure is a complex mixture of graphite particles in a nongraphitized elemental carbon matrix. Results of calculations using macroscopic carbon cross sections obtained by mixing bound-kernel graphite cross sections for the graphitized carbon and free-gas carbon cross sections for the remainder of the carbon and calculations using only bound-kernel graphite cross sections are compared to experimental data. It is shown that the use of the hybridized cross sections which reflect the allotropic mixture of the carbon in the TREAT fuel results in a significant improvement in the accuracy of calculated neutronics parameters for the TREAT reactor. 6 refs., 2 figs., 3 tabs.
- Report Numbers:
- E 1.99:conf-880911-23
conf-880911-23 - Subject(s):
- Other Subject(s):
- Alloy Nuclear Fuels
- Testing
- Carbon
- Experimental Data
- Graphite
- Neutronic Damage Functions
- Reactor Accidents
- Reactor Experimental Facilities
- Reactor Physics
- Treat Reactor
- Uranium Oxides U3o8
- Accidents
- Actinide Compounds
- Air Cooled Reactors
- Chalcogenides
- Data
- Elemental Minerals
- Elements
- Energy Sources
- Enriched Uranium Reactors
- Experimental Reactors
- Fuels
- Functions
- Gas Cooled Reactors
- Graphite Moderated Reactors
- Homogeneous Reactors
- Information
- Materials
- Minerals
- Nonmetals
- Nuclear Fuels
- Numerical Data
- Oxides
- Oxygen Compounds
- Physics
- Reactor Components
- Reactor Materials
- Reactors
- Research And Test Reactors
- Solid Fuels
- Solid Homogeneous Reactors
- Test Reactors
- Thermal Reactors
- Uranium Compounds
- Uranium Oxides
- Note:
- Published through SciTech Connect.
01/01/1988.
"conf-880911-23"
"DE89003625"
International reactor physics conference, Jackson Hole, WY, USA, 18 Sep 1988.
Harrison, L.J.; Swanson, R.W. - Funding Information:
- W-31109-ENG-38
View MARC record | catkey: 14666989