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License Application Design Selection Feature Report: Aging and Blending

Description: The purpose of this document is to evaluate the concepts of Aging and Blending for waste sent to the Monitored Geologic Repository (MGR). These design features are based on pre-emplacement treatment of the waste stream. The envelope of the analysis has been performed under the direction of the License Application Design Selection Team (LADST), which advocated utilizing the Viability Assessment (VA) repository design (DOE 1998c) as the basis. Therefore, this evaluation attempts to modify the VA design only to the extent that Aging and Blending can be accomplished. This modified VA design will be contrasted to the VA Design and the difference in design, costs, and performance will be presented.
Date: April 6, 1999
Creator: Coltoni, B. & Anderson, M.J.
Partner: UNT Libraries Government Documents Department

Light source for use with pneumatic hand tools. Final report

Description: Pnu-Light was formed in 1991 to provide research, design, manufacturing, and wholesale distribution of pneumatically powered lighting systems of the highest quality. These pneumatic lighting systems would replace ordinary flashlights in the individual workplace. When integrated with hand tools, the pneumatic lighting device would provide superior lighting capability, while eliminating battery procurement and battery disposal costs. A portion of the compressed air supplied to the tool would spin a small air motor installed with a miniature generator, producing an electric current. The current would be routed to a lamp that would focus light onto the immediate work area. The company incorporated in March 1993 and was granted US Patent 5,267,129 and International patent {number_sign}PCT21731 on the concept. Pnu-Light was referred to AlliedSignal Federal Manufacturing and Technologies (FM and T) by the Missouri Small Business Development Center at Central Missouri State University located at Warrensburg, Missouri. Pnu-Light approached the FM and T through the Technical Assistance Program with the intent of exploring a potential Cooperative Research and Development Agreement (CRADA). It was determined that a CRADA was in the best interest of both parties at that time. This CRADA effort applied FM and T`s broad base of technical expertise and advanced manufacturing facilities to evaluate, design, and test hardware. This report covers the project background, description, benefits to the Department of Energy, technologies being exercised, and economic impacts.
Date: August 1, 1996
Creator: Chapman, M.G. & Anderson, M.J.
Partner: UNT Libraries Government Documents Department

Verification Of Energy Balance In The Ansys V5.4 Thermal Calculations

Description: The objective of this calculation is to verify the energy balance of the thermal calculations analyzed by ANSYS Version (V) 5.4 solver (see Section 4). The scope of this calculation is limited to calculating the energy balance of a two-dimensional repository thermal representation using the temperatures obtained from ANSYS V5.4. The procedure, AP-3.124, Calculations (Ref. 3), and the Technical Work Plan for: Waste Package Design Description for LA (Ref. 2) are used to develop this calculation. The associated activity is the development of engineering evaluations to support the Licensing Application design activities.
Date: February 8, 2001
Creator: Marr, H. & Anderson, M.J.
Partner: UNT Libraries Government Documents Department

Analysisi Benchmark of the Single Heater Test

Description: The Single Heater Test (SHT) is the first of three in-situ thermal tests included in the site characterization program for the potential nuclear waste monitored geologic repository at Yucca Mountain. The heating phase of the SHT started in August 1996 and was concluded in May 1997 after 9 months of heating. Cooling continued until January 1998, at which time post-test characterization of the test block commenced. Numerous thermal, hydrological, mechanical, and chemical sensors monitored the coupled processes in the unsaturated fractured rock mass around the heater (CRWMS M&O 1999). The objective of this calculation is to benchmark a numerical simulation of the rock mass thermal behavior against the extensive data set that is available from the thermal test. The scope is limited to three-dimensional (3-D) numerical simulations of the computational domain of the Single Heater Test and surrounding rock mass. This calculation supports the waste package thermal design methodology, and is developed by Waste Package Department (WPD) under Office of Civilian Radioactive Waste Management (OCRWM) procedure AP-3.12Q, Revision 0, ICN 3, BSCN 1, Calculations.
Date: July 27, 2006
Creator: Wade, H.M.; Marr, H. & Anderson, M.J.
Partner: UNT Libraries Government Documents Department

Invert Effective Thermal Conductivity Calculation

Description: The objective of this calculation is to evaluate the temperature-dependent effective thermal conductivities of a repository-emplaced invert steel set and surrounding ballast material. The scope of this calculation analyzes a ballast-material thermal conductivity range of 0.10 to 0.70 W/m {center_dot} K, a transverse beam spacing range of 0.75 to 1.50 meters, and beam compositions of A 516 carbon steel and plain carbon steel. Results from this calculation are intended to support calculations that identify waste package and repository thermal characteristics for Site Recommendation (SR). This calculation was developed by Waste Package Department (WPD) under Office of Civilian Radioactive Waste Management (OCRWM) procedure AP-3.12Q, Revision 1, ICN 0, Calculations.
Date: March 17, 2000
Creator: Anderson, M.J.; Wade, H.M. & Mitchell, T.L.
Partner: UNT Libraries Government Documents Department

Thermal Response of the 21-PWR Waste Package to a Fire Accident

Description: The objective of this calculation is to evaluate the thermal response of the 21-PWR WP (pressurized water reactor waste package) to the regulatory fire event. The scope of this calculation is limited to the two-dimensional waste package temperature calculations to support the waste package design. The information provided by the sketches attached to this calculation (Attachment IV) is that of the potential design of the type of waste package considered in this calculation. The procedure AP-3.12Q.Calculations (Reference 1), and the Development Plan (Reference 24) are used to develop this calculation.
Date: October 3, 2000
Creator: Faucher, F.P.; Marr, H. & Anderson, M.J.
Partner: UNT Libraries Government Documents Department

Thermal Response of the 44-BWR Waste Package to a Hypothetical Fire Accident

Description: The purpose of this calculation is to determine the thermal response of the 44-boiling water reactor (BWR) waste package (WP) to the hypothetical regulatory fire accident. The objective is to calculate the temperature response of the waste package materials to the hypothetical short-term fire defined in 10 CFR 7 1, Section 73(c)(4), Reference 1. The scope of the calculation includes evaluation of the accident with the waste package above ground, at the Yucca Mountain surface facility. The scope of this calculation is limited to the two-dimensional waste package temperature calculations to support the waste package design. The information provided by the sketches attached to this calculation is that for the potential design of the type of WP considered in this calculation. In addition to the nominal design configuration thermal load case, the effects of varying the BWR thermal load are determined. The associated activity is the development of engineering evaluations to support the Licensing Application (LA) design activities.
Date: April 5, 2001
Creator: Smotrel, J.R.; Marr, H. & Anderson, M.J.
Partner: UNT Libraries Government Documents Department