PrefaceThis Safety Analysis Report for Packaging (SARP) documents the performance of the Department of Energy (DOE) Model USA/9979/AF-96 shipping package and compliance with the regulatory safety requirements of Title 10 and Title 49 of the Code of Federal Regulations. The SARP is prepared in accordance with U.S. Department of Energy (DOE) Order 460.1D. The Model 9979 Type A Fissile shipping package replaces the Department of Transportation (DOT) UN1A2 Specification Packaging. Formerly, the UN1A2 was authorized under Title 49 of the Code of Federal Regulations, Section 173.417 (2004) for transport of Type A quantities of fissile material over public highways.

The mixing of radioactive waste slurries by Pulse Jet Mixers (PJM) was simulated by using non-Newtonian clay suspensions. A quarter scale mockup of a 6 PJM cluster configuration was tested with different nozzle sizes of 25.4 mm, 31.8 mm, and 38.1 mm I.D., nozzle velocities of 8–18 m/sec, and yield stresses from 11 to 35 Pa. Mixing was measured by dye and ultrasonic velocity probe methods. Under PJM only operation, a well mixed region or cavern is developed which is distinct from the stagnant region. The data of cavern heights to tank diameter ratio are well correlated as a function of the product of the Yield Reynolds number to the square root power and the ratio of nozzle to tank diameter. A fully mixed tank was obtained for a nozzle diameter of 38.1 mm, nozzle velocity of 18 m/sec and yield stress of 21 Pa. An alternate mixing configuration consisting of 25.4 mm nozzles and 5 spargers at 3 scfm each, 18 m/s nozzle velocity and yield stress of 30 Pa was found also to be fully mixed using glass bead tracers which also simulated large solids.

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This paper presents a finite-element technique to simulate the structural responses and to evaluate the cumulative damage of a radioactive material packaging requiring bolt closure-tightening torque and subjected to the scenarios of the Hypothetical Accident Conditions (HAC) defined in the Code of Federal Regulations Title 10 part 71 (10CFR71). Existing finite-element methods for modeling closure stresses from bolt pre-load are not readily adaptable to dynamic analyses. The HAC events are required to occur sequentially per 10CFR71 and thus the evaluation of the cumulative damage is desirable. Generally, each HAC event is analyzed separately and the cumulative damage is partially addressed by superposition. This results in relying on additional physical testing to comply with 10CFR71 requirements for assessment of cumulative damage. The proposed technique utilizes the combination of kinematic constraints, rigid-body motions and structural deformations to overcome some of the difficulties encountered in modeling the effect of cumulative damage. This methodology provides improved numerical solutions in compliance with the 10CFR71 requirements for sequential HAC tests.Analyses were performed for the Bulk Tritium Shipping Package (BTSP) designed by Savannah River National Laboratory to demonstrate the applications of the technique. The methodology proposed simulates the closure bolt torque preload followed by the sequential HAC events, the 30-foot drop and the 30-foot dynamic crush. The analytical results will be compared to the package test data.

The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC) Section III Division 3 (commonly referred to as NUPACK) was issued in 1997 to address the containments of nuclear transportation packagings. Previously, Section III consisted of only 2 divisions that address the construction of nuclear facility components: Division 1 for metal construction and Division 2 for concrete construction. Type B packagings have historically been designed to Division 1 standards. This paper discusses the application of NUPACK to the design of a Type B packaging containment vessel.