32 Matching Results

Search Results

Advanced search parameters have been applied.
in creator/contributor: "Osborne, M.F."  
prev Results: 25 - 32
open access

Characterization and chemistry of fission products released from LWR fuel under accident conditions

Description: Segments from commercial LWR fuel rods have been tested at temperatures between 1400 and 2000/sup 0/C in a flowing steam-helium atmosphere to simulate severe accident conditions. The primary goals of the tests were to determine the rate of fission product release and to characterize the chemical behavior. This paper is concerned primarily with the identification and chemical behavior of the released fission products with emphasis on antimony, cesium, iodine, and silver. The iodine appeared to b… more
Date: January 1, 1984
Creator: Norwood, K. S.; Collins, J. L.; Osborne, M. F.; Lorenz, R. A. & Wichner, R. P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

ORNL fission product release tests VI-6

Description: The ORNL fission product release tests investigate release and transport of the major fission products from high-burnup fuel under LWR accident conditions. The two most recent tests (VI-4 and VI-5) were conducted in hydrogen. In three previous tests in this series (VI-1, VI-2, and VI-3), which had been conducted in steam, the oxidized Zircaloy cladding remained largely intact and acted as a barrier to steam reaction with the UO{sub 2}. Test VI-6 was designed to insure significant oxidation of t… more
Date: January 1, 1991
Creator: Osborne, M. F.; Lorenz, R. A.; Collins, J. L. & Lee, C. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Data summary report for fission product release test VI-6

Description: Test VI-6 was the sixth test in the VI series conducted in the vertical furnace. The fuel specimen was a 15.2-cm-long section of a fuel rod from the BR3 reactor in Belgium. The fuel had experienced a burnup of {approximately}42 MWd/kg, with inert gas release during irradiation of {approximately}2%. The fuel specimen was heated in an induction furnace at 2300 K for 60 min, initially in hydrogen, then in a steam atmosphere. The released fission products were collected in three sequentially operat… more
Date: March 1, 1994
Creator: Osborne, M. F.; Lorenz, R. A.; Travis, J. R.; Webster, C. S. & Collins, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Data summary report for fission product release Test VI-7

Description: Test VI-7 was the final test in the VI series conducted in the vertical furnace. The fuel specimen was a 15.2-cm-long section of a fuel rod from the Monticello boiling water reactor (BWR). The fuel had experienced a burnup of {approximately}-40 Mwd/kg U. It was heated in an induction furnace for successive 20-min periods at 2000 and 2300 K in a moist air-helium atmosphere. Integral releases were 69% for {sup 85}Kr, 52% for {sup 125}Sb, 71% for both {sup 134}Cs and {sup 137}Cs, and 0.04% for {su… more
Date: May 1, 1995
Creator: Osborne, M. F.; Lorentz, R. A.; Travis, J. R.; Collins, J. L. & Webster, C. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Quarterly Progress Report on Fission Product Behavior in LWRs for the Period October-December 1977

Description: Analysis of release data obtained during High Burnup Fuel Test 10 (HBU-10) has been completed. In this test the fuel rod segment was ruptured by internal pressurization at 900/sup 0/C, at which time the temperature was rapidly increased to 1200/sup 0/C and maintained at this temperature for 10 min. Approximately 0.061% of the total cesium inventory in the rod segment was released; this was accompanied by the release of about 1.69% of the total /sup 85/Kr inventory. Moreover, about 0.022% of the… more
Date: February 1, 1978
Creator: Malinauskas, A. P.; Lorenz, R. A.; Collins, J. L.; Osborne, M. F.; Whatley, S. K. & Towns, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor

Description: Report issued by the Oak Ridge National Laboratory discussing irradiation testing of fast breeder reactors. As stated in the introduction, "it is the purpose of this report to describe the irradiation studies carried out in support of the Core B fuel element development program" (p. 3). This report includes tables, illustrations, and photographs.
Date: November 1964
Creator: Thurber, W. C.; McQuilkin, F. R.; Long, E. L., Jr. & Osborne, M. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Data summary report for fission product release test VI-5

Description: Test VI-5, the fifth in a series of high-temperature fission product release tests in a vertical test apparatus, was conducted in a flowing mixture of hydrogen and helium. The test specimen was a 15.2-cm-long section of a fuel rod from the BR3 reactor in Belgium which had been irradiated to a burnup of {approximately}42 MWd/kg. Using a hot cell-mounted test apparatus, the fuel rod was heated in an induction furnace under simulated LWR accident conditions to two test temperatures, 2000 K for 20 … more
Date: October 1, 1991
Creator: Osborne, M. F.; Lorenz, R. A.; Travis, J. R.; Webster, C. S. & Collins, J. L. (Oak Ridge National Lab., TN (United States))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen