Modeling Analysis for Nuclear Material Transport Package

Journal Article · Fri Jul 01 04:00:00 EDT 2016 · Transactions of the American Nuclear Society

OSTI ID:23042869

Lee, Si Y. ^[1]

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1. Savannah River National Laboratory Aiken, SC 29808 (United States)

This paper describes the computational models for the thermal analyses for 9975 nuclear material package under the Normal Conditions of Transport (NCT) and the Hypothetical Accident Conditions (HAC). The package 9975 is a DOE certified package that has been used in the DOE complex for transportation and long term storage of radioactive material. The NCT and HAC thermal analyses for the 9975 package were performed here by taking a computational heat transfer method. The HAC thermal models described here are identical to the models in the current DOE certified 9975 package. Thermal models in this work are for an undamaged package to meet all the regulatory requirements during an HAC thermal event. The model was created using modified shielding where the lead was encapsulated in a 0.036 inches stainless steel casing. The impact of this casing was studied earlier when the modification was proposed and it was found to have minimal impact on the component temperatures. Therefore, the analyses in this paper are good for packages with or without the shielding modifications. Analytical studies show that the realistic value for the solar absorptivity for the stainless steel surface fabricated from the rolling operation is about 0.5. The NCT analyses documented in this report use an absorptivity value of 0.5 to get more realistic component temperature results. Sensitivity studies were also performed to assess the impact of variability in the solar absorptivity for drum surface in the previous work for the NRC certification. The analysis in this paper is based on PuO{sub 2} in a food can. The food can is considered uncredited convenience containers inside the Primary Containment Vessel (PCV) of the 9975 package. PCV is located inside Secondary Containment Vessel (SCV). PuO{sub 2} has a density of 2 g/cc and a heat generation rate of 19 watts. This calculation evaluates the thermal performance for 9975 package with food can configuration during NCT and HAC per NRC regulations in 10 CFR Part 71. The objective of the calculation is to demonstrate that the maximum component temperatures are below their design limits. (authors)

• OSTI ID: 23042869
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 115; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ABSORPTIVITY
COMPUTERIZED SIMULATION
CONTAINERS
DENSITY
HEAT
HEAT TRANSFER
HYPOTHETICAL ACCIDENTS
NEUTRON CAPTURE THERAPY
RADIOACTIVE MATERIALS
ROLLING
SENSITIVITY ANALYSIS
SHIELDING
STAINLESS STEELS
THERMAL ANALYSIS