Densification studies of Synroc D for high-level defense waste
Technical Report
·
OSTI ID:6406364
Small- to medium-scale densification experiments were conducted on Synroc D using graphite dies and metal canisters. Pressures at elevated temperatures were applied both isostatically (HIP) and unidirectionally (HUP). Spray-dried/calcined powders formulated for composite or average sludge compositions exhibited initial packing densities of about 25% theoretical. Final densities were in the range of 95 to 99% theoretical, depending on applied pressure and temperature. In final-stage HUP densification, we have found that porosity varies exponentially with time acording to the well-known expression P + P/sub 0/ exp(-K/sub 0/t). The rate constant (K/sub 0/) has the Arrhenius form K/sub 0/ = Asigma exp(-E/RT) which includes a stress or pressure term. Rate constants are calculated from approximately 20 densification experiments conducted under a wide range of conditions; activation energies in the range of 20 to 35 kcal/mole were calculated for the densification process. HIP densification and leaching results are reported for experiments with a wide range of variables: pressure (3 to 30 ksi), temperature (900 to 1200/sup 0/C), redox calcination method, powder fill density and metal canister material. The results support the conclusion that HUP and HIP densification parameters are very similar and that Synroc-D leaching behavior is essentially independent of density in the range of 90 to 100% theoretical.The densification of Synroc D in a collapsible metal-bellows canister has been simulated by means of modeling calculations. Radial buckling tendencies were also evaluated. Results from large-scale HIP experiments are also reported. Up to 50 kg of Synroc D was densified to greater than 99% theoretical density in a metal-bellows canister 36 cm diameter by 24 cm in height. These data were used as a guide to make recommendations for the full-scale HIP densification of Synroc D using metal-bellows canisters.
- Research Organization:
- Lawrence Livermore National Lab., CA (USA)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 6406364
- Report Number(s):
- UCRL-53392; ON: DE83011564
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
052001* -- Nuclear Fuels-- Waste Processing
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
360201 -- Ceramics
Cermets
& Refractories-- Preparation & Fabrication
CERAMICS
DATA
DENSITY
EXPERIMENTAL DATA
FABRICATION
HIGH-LEVEL RADIOACTIVE WASTES
HOT PRESSING
INFORMATION
MATERIALS
MATERIALS WORKING
NUMERICAL DATA
PHYSICAL PROPERTIES
POROSITY
PRESSING
PRESSURE DEPENDENCE
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
ROCKS
SYNTHETIC MATERIALS
SYNTHETIC ROCKS
TEMPERATURE DEPENDENCE
TIME DEPENDENCE
WASTES
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
360201 -- Ceramics
Cermets
& Refractories-- Preparation & Fabrication
CERAMICS
DATA
DENSITY
EXPERIMENTAL DATA
FABRICATION
HIGH-LEVEL RADIOACTIVE WASTES
HOT PRESSING
INFORMATION
MATERIALS
MATERIALS WORKING
NUMERICAL DATA
PHYSICAL PROPERTIES
POROSITY
PRESSING
PRESSURE DEPENDENCE
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
ROCKS
SYNTHETIC MATERIALS
SYNTHETIC ROCKS
TEMPERATURE DEPENDENCE
TIME DEPENDENCE
WASTES