Strontium-90 fluoride data sheet

This report presents a compilation of available data and appropriate literature references on the properties of /sup 90/SrF/sub 2/ and nonradioactive SrF/sub 2/. It represents an updating of one section of the Strontium-90 Data Sheets (ORNL-4358, March 1969) prepared by S. J. Rimshaw and E. E. Ketchen of the Oak Ridge National Laboratory

Quarterly report on the strontium heat source development program, Advanced Nuclear Systems and Projects Division for July-September 1979

Metallographic examination of the metal specimens exposed to /sup 90/SrF/sub 2/ for 20,000 h was completed, as was the examination of the specimens exposed to nonradioactive SrF/sub 2/ for 30,000 hours. Fabrication and welding of the prototype capsules to be used in the qualification testing program was completed

Quarterly report on the strontium heat source development program and the terrestrial radioisotope applications program, Advanced Systems and Materials Production Division for October--December 1977

A separate abstract was prepared for each of the two sections of the report. (TFD

Quarterly report on the strontium heat source development program, Advanced Nuclear Systems and Projects Division for April-June 1980

Oak Ridge National Laboratory completed metallographic examination of the metal specimens from the 30,000-h compatibility tests with /sup 90/SrF/sub 2/. Electron microprobe analysis of the specimens is now under way. Results show that chemical attack of the 30,000-h specimens was not much greater than that observed in the 6000- to 20,000-h tests. Work continues on qualification testing of the as-fabricated prototype outer capsules. As-fabricated Hastelloy S and Hastelloy C-4 outer capsules passed the hydrostatic pressure, percussion, thermal, and thermal-quench tests without difficulty

Design and qualification testing of a strontium-90 fluoride heat source

The Strontium Heat Source Development Program began at the Pacific Northwest Laboratory (PNL) in 1972 and is scheduled to be completed by the end of FY-1981. The program is currently funded by the US Department of Energy (DOE) By-Product Utilization Program. The primary objective of the program has been to develop the data and technology required to permit the licensing of power systems for terrestrial applications that utilize /sup 90/SrF/sub 2/-fueled radioisotope heat sources. A secondary objective of the program has been to design and qualification-test a general purpose /sup 90/SrF/sub 2/-fueled heat source. The effort expended in the design and testing of the heat source is described. Detailed information is included on: heat source design, licensing requirements, and qualification test requirements; the qualification test procedures; and the fabrication and testing of capsules of various materials. The results obtained in the qualification tests show that the outer capsule design proposed for the /sup 90/SrF/sub 2/ heat source is capable of meeting current licensing requirements when Hastelloy S is used as the outer capsule material. The data also indicate that an outer capsule of Hastelloy C-4 would probably also meet licensing requirements, although Hastelloy S is the preferred material. Therefore, based on the results of this study, the general purpose /sup 90/SrF/sub 2/ heat source will consist of a standard WESF Hastelloy C-276 inner capsule filled with /sup 90/SrF/sub 2/ and a Hastelloy S outer capsule having a 2.375-in. inner diameter and 0.500-in. wall thickness. The end closures for this study, the general purpose /sup 90/SrF/sub 2/ heat a Hastelloy S outer capsule having a 2.375-in. inner diameter and 0.500-in. wall thickness. The end closures for the outer capsule will utilize an interlocking joint design requiring a 0.1-in. penetration closure weld. (LCL