To obtain copies of t h i s docunent, contact: UHC/BCS , Mailstop H6-08. Richland UA 99352. Phone (5 0 9) 372-2420; 1x-46 Date Release Stanp Approved for Public Release A-6400.073 (1 0 / 9 5) GEF321 (3) Revision RECORD OF REVISION I Authorized for Release (5) Cog. Engr. 1 (6) Cog. Ilgr. Oate (4) Description of Change-Replace, Add, and Delete Pages I WHC-SD-WM-ATR-137 1 Page 1 I 0 1 RS (7) Issued on EDT 154935, December 1995 Revision 1 i s a rewrite with changes in text, figures, and appendices. Rev. 1 is issued on ECN 624777.
Recent experiments on developmental fast-flux test facility (FFTF) cladding (20 percent cold-worked Type 316 stainless steel) have extended the data base to a fast neutron fluence of 8.4 × 1022 neutrons (n)/cm2 (E > 0.1 MeV). The specimens were irradiated in the experimental breeder reactor-II (EBR-II) at temperatures ranging from 371 to 816°C, although peak fluence levels were attained on specimens irradiated near 371 and 649°C only. Tension tests were performed at 232°C, near the irradiation temperature, and, in some cases, above the irradiation temperature. Test specimen strain rates ranged from 4 × 10 -5/s to 4 × 10-2/s.
The data generated on cladding irradiated near 371 °C established that the low-temperature strength and ductility are fluence independent beyond about 5 × 1022 n/cm2 (E > 0.1 MeV). The strength behavior of the irradiated cladding at 538, 593, and 649 °C is essentially the same as exhibited by thermally aged developmental cladding at the same temperatures and times out of the reactor. Up to a fluence of ∼5 × 1022 n/cm2 (E > 0.1 MeV), the 538°C ductility values remain relatively fluence independent after an initial decrease. Higher temperature (593 and 649 °C) ductilities decrease continually with increasing fluence.
Tensile parameter correlations were developed for the prediction of irradiation effects on the tensile properties of 20 percent cold-worked Type 316 stainless steel. These correlations are based on unirradiated tensile property correlations developed using Hart's equation-of-state approach. The basic premise is that the condition of plastic deformation of some materials such as 316 stainless steel can be characterized by a structure parameter (σ*) which describes the material's “hardness.” It is found that irradiation effects can be incorporated into this formulation by parameterizing the changes in σ* with irradiation temperature and fluence. The resulting correlations provide a description of strength and ductility over the temperature range of 371 to 871 °C and strain rates of 10-5 to 10 1/s.
This document provides a report of results obtained from testing described in test plan WHC-SD-WM-TP-Ig5. Speed of sound and rheology measurementswere made in a sample of I01-SY tank waste. Also speed of sound measurementswere obtained from a sample of LANL simulant fer the tank waste. Test temperaturesranged from approximately20°C to 50 %.
The maximum Retained Gas Sampler (RGS) interface volume was determined; this volume can trap contamination gases during the sampling process. A new technique (helium backfill) for eliminating contamination gases from the RGS sampler interface volume is described, and verification testing reported. Also demonstrated was that RGS data obtained prior to the introduction of the new helium backfill technique can be compensated for air contamination using the measured oxygen concentration and normal air composition.
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