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Description: A nondestructive assay instrument that measures large quantities of low-enriched uranium metal is described. The assay is based on the spontaneous totals neutron signal.
Date: January 1, 1983
Creator: Sprinkle, J. K. Jr.
Partner: UNT Libraries Government Documents Department
open access

Comparison of the Aerospace Systems Test Reactor loss-of-coolant test data with predictions of the 3D-AIRLOCA code

Description: This paper compares the predictions of the revised 3D-AIRLOCA computer code to those data available from the Aerospace Systems Test Reactor's (ASTR's) loss-of-coolant-accident (LOCA) tests run in 1964. The theoretical and experimental hot-spot temperature responses compare remarkably well. In the thirteen cases studied, the irradiation powers varied from 0.4 to 8.87 MW; the irradiation times were 300, 1540, 1800, and 10/sup 4/ s. The degrees of agreement between the data and predictions provide… more
Date: January 1, 1983
Creator: Warinner, D. K.
Partner: UNT Libraries Government Documents Department
open access

Recent developments of the US RERTR program

Description: The status of the US Reduced Enrichment Research and Test Reactor (RERTR) Program is reviewed. After a brief outline of the RERTR Program objectives, goals and past accomplishments, emphasis is placed on the developments which took place during 1983 and on current program plans and schedules. Most program activities have proceeded as planned and a combination of two silicide fuels (U/sub 3/Si/sub 2/-Al and U/sub 3/Si-Al) was found to hold excellent promise for achieving the long-term program go… more
Date: January 1, 1983
Creator: Travelli, A.
Partner: UNT Libraries Government Documents Department
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RERTR program activities related to the development and application of new LEU fuels. [Reduced Enrichment Research and Test Reactor; low-enriched uranium]

Description: The statue of the U.S. Reduced Enrichment Research and Test Reactor (RERTR) Program is reviewed. After a brief outline of RERTR Program objectives and goals, program accomplishments are discussed with emphasis on the development, demonstration and application of new LEU fuels. Most program activities have proceeded as planned, and a combination of two silicide fuels (U/sub 3/Si/sub 2/-Al and U/sub 3/Si-Al) holds excellent promise for achieving the long-term program goals. Current plans and sche… more
Date: January 1, 1983
Creator: Travelli, A.
Partner: UNT Libraries Government Documents Department
open access

Nuclear criticality assessment of LEU and HEU element storage

Description: Criticality aspects of storing LEU (20%) and HEU (93%) fuel elements have been evaluated as a function of /sup 235/U loading, element geometry, and fuel type. Silicide, oxide, and aluminide fuel types have been evaluated ranging in /sup 235/U loading from 180 to 620 g per element and from 16 to 23 plates per element. Storage geometry considerations have been evaluated for fuel element separations ranging from closely packed formations to spacings of several centimeters between elements. Data ar… more
Date: January 1, 1983
Creator: Pond, R.B. & Matos, J.E.
Partner: UNT Libraries Government Documents Department
open access

Comparison of safety parameters and transient behavior of a generic 10 MW reactor with HEU and LEU fuels

Description: Key safety parameters are compared for equilibrium cores of the IAEA generic 10 MW reactor with HEU and LEU fuels. These parameters include kinetics parameters, reactivity feedback coefficients, control rod worths, power peaking factors, and shutdown margins. Reactivity insertion and loss-of-flow transients are compared. Results indicate that HEU and LEU cores will behave in a very similar manner.
Date: January 1, 1983
Creator: Matos, J.E.; Freese, K.E. & Woodruff, W.L.
Partner: UNT Libraries Government Documents Department
open access

High-density reduced-enrichment fuels for Research and Test Reactors

Description: Development and irradiation testing of high-density fuels have been conducted by the US RERTR Program in order to provide the technical means to reduce the enrichment of fuels for research and test reactors. The traditional aluminum dispersion fuel technology has been extended to include the highest practical loadings of uranium-aluminide (UAl/sub x/, 2.3 MgU/m/sup 3/), uranium-oxide (U/sub 3/O/sub 8/, 3.2 MgU/m/sup 3/), and uranium-silicide (U/sub 3/Si/sub 2/, 5.5 MgU/m/sup 3/; U/sub 3/Si, 7.0… more
Date: January 1, 1983
Creator: Snelgrove, J. L.; Hofman, G. L. & Copeland, G. L.
Partner: UNT Libraries Government Documents Department
open access

Fuel development activities of the US RERTR Program. [Reduced Enrichment Research and Test Reactor]

Description: Progress in the development and irradiation testing of high-density fuels for use with low-enriched uranium in research and test reactors is reported. Swelling and blister-threshold temperature data obtained from the examination of miniature fuel plates containing UAl/sub x/, U/sub 3/O/sub 8/, U/sub 3/Si/sub 2/, or U/sub 3/Si dispersed in an aluminum matrix are presented. Combined with the results of metallurgical examinations, these data show that these four fuel types will perform adequately … more
Date: January 1, 1983
Creator: Snelgrove, J. L.; Domagala, R. F.; Wiencek, T. C. & Copeland, G. L.
Partner: UNT Libraries Government Documents Department
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