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Containment of $sup 90$SrF$sub 2$ at 800 to 1100$sup 0$C preliminary results

Description: A program is currently underway at PNL to develop the data needed to license $sup 90$SrF$sub 2$ for heat source applications. A major portion of the program involves determining the compatibility of $sup 90$SrF$sub 2$ with containment materials at elevated temperatures. The compatibility studies are divided into two phases: an initial series of short-term scouting tests lasting up to 4400 h in which a number of containment materials were evaluated, and a subsequent series of long-term tests in which the three best containment materials identified in the short-term tests will be tested for up to 30,000 h with WESF-produced $sup 90$SrF$sub 2$. The results of the first phase tests are summarized. The short-term tests were carried-out at temperatures of 800, 1000, and 1100$sup 0$C for 1500 and 4400 h using both radioactive and nonradioactive strontium fluoride. Nine potential containment materials were evaluated in the tests: two refractory metals (tungsten and TZM); two cobalt base alloys (Haynes Alloy 25 and Haynes Alloy 188); and five nickel base alloys (Hastelloy C-276, Hastelloy X, Hastelloy N, Inconel 600 and Inconel 625). Test results show that both of the refractory metals are very resistant to fluoride attack, and tungsten and TZM specimens exposed to $sup 90$SrF$sub 2$ exhibited little or no attack. Haynes Alloy 25 was the best of the Ni- and Co-base alloys, but attack up to a depth of 0.004 in. was observed in some Haynes Alloy 25 specimens exposed to $sup 90$SrF$sub 2$. Based on the results of the short-term compatibility tests and several other factors, TZM, Haynes Alloy 25 and Hastelloy C-276, the present WESF capsule material, were selected for long-term testing with $sup 90$SrF$sub 2$. (auth)
Date: November 1, 1975
Creator: Fullam, H.T.
Partner: UNT Libraries Government Documents Department

Ductility in bending of molybdenum alloys irradiated between 425 and 1000/sup 0/C

Description: Molybdenum and the alloys Mo--0.5% Ti and TZM were irradiated at four temperatures between 425 and 1000/sup 0/C, to a displacement level of 11 dpa at a fluence of 2.5 x 10/sup 26/ n m /sup -2/ (> 0.1 MeV). Vacuum bend tests at elevated temperatures showed the ductile-to-brittle transition temperature (DBTT) to be above room temperature for all irradiation temperatures. Irradiation at 585/sup 0/C produced the highest DBTT, 550 to 700/sup 0/C. Differences among the three materials were minor.
Date: January 1, 1979
Creator: Cox, B.L. & Wiffen, F.W.
Partner: UNT Libraries Government Documents Department

Sputtering and surface damage of TFTR protective plate materials (Mo, TZM, graphite) by energetic D/sup +/ ion irradiation. Final report for Princeton Plasma Physics Laboratory

Description: Studies have been conducted in accordance with a service request from the Plasma Physics Laboratory (PPPL) of Princeton University to determine the total sputtering yields and the surface damage of molybdenum (a candidate material for the neutral beam injector protective plate for Princeton's Fusion Test Reactor (TFTR)) caused by the impact of D/sup +/ ions at 120-keV, 60-keV and 40-keV at fluxes and total doses agreed upon between PPPL and ANL. The irradiations have been conducted in a specified pulsed mode as well as in a dc mode. The material TZM (a molybdenum alloy) was included in some tests of surface damage, but not for the full complement of doses planned for molybdenum. According to a request by PPPL the target temperature was not to be controlled (targets were allowed to reach a temperature determined by the beam power deposition and the conductive and radiative heat losses), but the target temperature was to be monitored. The irradiations were conducted at pressures ranging from 4 x 10/sup -9/ torr to 2 x 10/sup -8/ torr.
Date: March 1, 1978
Creator: Kaminsky, M.; Das, S.K. & Dusza, P.
Partner: UNT Libraries Government Documents Department

Surface damage of molybdenum and TZM alloy under D/sup +/ impact

Description: The surface damage of polycrystalline molybdenum and TZM alloy under 40-, 60-, and 120-keV D/sup +/ impact has been investigated for irradiation in both pulsed and continuous mode for total doses varying from 1.7 x 10/sup 17/ to 2.2 x 10/sup 19/ ions/cm/sup 2/ and for target temperatures verying from ambient temperature to 400/sup 0/C. Analysis by scanning electron microscopy of the MO samples held at ambient temperatures during D/sup +/ irradiations in both pulsed and continuous modes revealed surface damage due to blistering for the 40-keV and 60-keV irradiations for doses ranging from 8.7 x 10/sup 17/ to 8.1 x 10/sup 18/ ions/cm/sup 2/, but no detectable damage for the 120-keV D/sup +/ irradiations for doses ranging from 4.3 x 10/sup 18/ to 2.2 x 10/sup 19/ ions/cm/sup 2/. This observed difference in the blistering behavior is attributed to the differences in the ambient target temperature for the 120-keV irradiation and both the 40- and 60-keV irradiations. For irradiations at temperatures above 300/sup 0/C, no blisters could be detected for any of the three energies. For similar irradiation conditions, TZM-alloy showed a reduction in blistering as compared to molybdenum.
Date: January 1, 1977
Creator: Das, S.K.; Kaminsky, M. & Dusza, P.
Partner: UNT Libraries Government Documents Department

Evaluation of molybdenum and its alloys. [Reactor core heat pipes]

Description: The choice of pure molybdenum as the prime candidate material for space reactor core heat pipes is critically examined. Pure molybdenum's high ductile-brittle transition temperature appears to be its major disadvantage. The candidate materials examined in detail for this application include low carbon arc-cast molybdenum, TZM-molybdenum alloy, and molybdenum-rhenium alloys. Published engineering properties are collected and compared, and it appears that Mo-Re alloys with 10 to 15% rhenium offer the best combination. Hardware is presently being made from electron beam melted Mo-13Re to test this conclusion.
Date: January 1, 1981
Creator: Lundberg, L.B.
Partner: UNT Libraries Government Documents Department

Isotopic power materials development progress report for November 1971

Description: Data are given on bend testing of Pt--Rh--W alloys; tensile properties of Pt--Rh--W alloys with and without Hf and Ti additions; tensile properties of recrystallized Ir; effects of contamination by gases (oxygen, degassed impurities, water vapor, CO) on the tensile properties of T-111, TZM, and Mo--46% Re; and fractography and bend testing of T-111 from Pioneer heat source capsules. (DLC)
Date: November 26, 1973
Creator: Donnelly, R.G.
Partner: UNT Libraries Government Documents Department

Quarterly report on the Strontium Heat Source Development Program, Operations and By-Products Utilization Division for April-June 1981

Description: All experimental activities related to the Strontium Heat Source Development Program have been completed. The only remaining activities are preparation and issuance of final reports that summarize program results. This report represents the last of the program quarterly progress reports that will be issued.
Date: September 1, 1981
Creator: Fullam, H.T.
Partner: UNT Libraries Government Documents Department

Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1978--March 31, 1978

Description: The activities associated with the procurement of the materials for the screening test program, information from vendor certification for the materials received, and preliminary information from the materials characterization tests performed by GE are reported. The construction status of the simulated reactor helium supply system, testing equipment, and gas chemistry analysis instrumentation and equipment are discussed. The final recommended impurity levels for the screening phase helium are presented and the rational behind this gas chemistry is discussed. The status of the data management system is presented.
Date: June 26, 1978
Partner: UNT Libraries Government Documents Department