Heat Transfer Design for Ceramic Waste Forms From Pyro-processing
- 1. Fuel Cycle Programs Division, Idaho National Laboratory, Idaho Falls, Idaho (United States)
Description
Reprocessing spent nuclear fuel to produce fast reactor fuel and fission product waste forms by pyro-processing can expand the Yucca Mountain storage capacity by a factor of five and reduce the time of concern to 300 years. The consolidation (by heating to 900 deg C) and cooling of two different sizes of fission product ceramic waste form (CWF) destined for Yucca Mountain are analyzed. The first size is a 52 cm diameter cylinder from processing EBR-II spent fuel. The second is a 185 cm cylinder from processing spent LWR fuel in a 100 MT/yr reprocessing plant. The objective is to reduce the heating cooling time cycle to increase production. The 52 cm diameter CWF heats up to 900 C in 70 hours. This length of time is due to its low thermal conductivity. Inserting a small diameter stainless steel rod in the middle of the can was investigated to see if this time could be reduced. Rather than reducing the heatup time, it prolongs it because the heat capacitance of the steel is much larger than that of the ceramic. However other materials (aluminum and carbon) yield reduced heatup time. An aluminum rod would have to be encased in a thin walled steel tube since it melts at 660 deg C. After the material has been consolidated at the high temperature, it must be cooled. The consolidated material has a higher thermal diffusivity than the unconsolidated but is encased in an annular furnace. Data indicate that the overall heat transfer coefficient is 1 W/m2K or lower resulting in cooling times of 140 hours. The aluminum center rod also helps with the cooldown. If the CWF were removed from the furnace for cooling, cooling times would be reduced further (20 hours). Thermal stresses are low enough to allow this cooling but operational problems must be overcome to handle the 900 C CWF. The 185 cm diameter (6.1 foot) CWF presents more difficulty. Dimensional analysis allows the small cylinder results to be used to estimate heatup and cooldown times. The time is proportional to the radius squared (a factor of 12.6) resulting in 886 hours for heatup plus 1140 hours for cooldown (∼ 84 days). Operations of the 100 MT/yr reprocessing plant produces this much material every 15 days. A slight increase in furnace temperature and addition of an 18.5 cm radius aluminum center rod plus other remedies can reduce the heatup and cooldown times to approximately 15 days. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-698-5
- Imprint Title
- Proceedings of the 2006 international congress on advances in nuclear power plants - ICAPP'06
- Imprint Pagination
- 2734 p.
- Journal Page Range
- p. 1973-1983
Conference
- Title
- 2006 International congress on advances in nuclear power plants - ICAPP'06
- Dates
- 4-8 Jun 2006
- Place
- Reno - Nevada (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 39038631
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM; CAPACITANCE; CERAMICS; COOLING; COOLING TIME; DESIGN; EBR-2 REACTOR; FISSION PRODUCTS; FUEL REPROCESSING PLANTS; HEAT TRANSFER; PROCESSING; SPENT FUELS; STAINLESS STEELS; TEMPERATURE RANGE 0400-1000 K; THERMAL CONDUCTIVITY; THERMAL DIFFUSIVITY; THERMAL STRESSES; WASTE FORMS
- Descriptors DEC
- ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; ELECTRICAL PROPERTIES; ELEMENTS; ENERGY SOURCES; ENERGY TRANSFER; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; ISOTOPES; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; METALS; NUCLEAR FACILITIES; NUCLEAR FUELS; PHYSICAL PROPERTIES; POWER REACTORS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; STEELS; STRESSES; TEMPERATURE RANGE; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENT ALLOYS; WASTES
Optional Information
- Notes
- 16 refs.