| Bibliographic Citation | |
| Full Text |  1000 K |
|---|---|
| Title | Alterative LEU designs for the FRM-II with power levels of 20-22 MW. |
| Creator/Author | Hanan, N. A. ; Smith, R. S. ; Matos, J. E. |
| Publication Date | 1999 Sep 27 |
| OSTI Identifier | OSTI ID: 750514 |
| Report Number(s) | ANL/TD/CP-100109 |
| DOE Contract Number | W-31-109-ENG-38 |
| Other Number(s) | TRN: US200221%%551 |
| Resource Type | Conference |
| Resource Relation | Conference: 1999 International Meeting on Reduced Enrichment for Research and Test Reactors, Budapest (HU), 10/03/1999--10/08/1999; Other Information: PBD: 27 Sep 1999 |
| Research Org | Argonne National Lab., IL (US) |
| Sponsoring Org | US Department of Energy (US) |
| Subject | 72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; ANL; COLD NEUTRONS; DESIGN; NATIONAL GOVERNMENT; RESEARCH AND TEST REACTORS; SILICIDES; THERMAL NEUTRONS; URANIUM |
| Description/Abstract | Alternative LEU Designs for the FRM-II have been developed by the RERTR Program at Argonne National Laboratory (ANL) at the request of an FRM-II Expert Group established by the German Federal Government in January 1999 to evaluate the options for using LEU fuel instead of HEU fuel in cores with power levels of 20 MW. The ANL designs would use the same building structure and maintain as many of the HEU design features as practical. The range of potential LEU fuels was expanded from previous studies to include already-tested silicide fuels with uranium densities up to 6.7 g/cm{sup 3} and the new U-Mo fuels that show excellent prospects for achieving uranium densities in the 8-9 g/cm{sup 3} range. For each of the LEU cores; the design parameters were chosen to match the 50 day cycle length of the HEU core and to maximize the thermal neutron flux in the Cold Neutron Source and beam tubes. The studies concluded that an LEU core with a diameter of about 29 cm instead of 24 cm in HEU design and operating at a power level of 20 MW would have thermal neutron fluxes that are 0.85 times that of the HEU design at the center of the Cold Neutron Source. With a potential future upgrade to a power of 22 MW, this ratio would increase to 0.93. |
| Country of Publication | United States |
| Language | English |
| Format | Medium: P; Size: 15 pages |
| Availability | INIS; OSTI as DE00750514 To purchase this media from NTIS, click here |
| System Entry Date | 2008 Feb 05 |
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Last Updated: 03/16/2009