Session: OAC-04-03 Storage and Transportation of Radioactive and other Hazardous Materials - 3

Paper Number: 106501

106501 - Supplemental Structural Analyses Used in Support of Certification of the Defense Programs Package (DPP)-3 

The Defense Programs Package (DPP)-3 is certified by the National Nuclear Security Administration (NNSA) Packaging and Transportation Division (PTD). Certification was based on successful physical testing of the package, and six certification test units (CTUs) have been subjected to the normal conditions of transport (NCT) and hypothetical accident conditions (HAC) outlined in Title 10 of the Code of Federal Regulations Part 71 (10 CFR 71). During regulatory testing of one of the CTUs, the drum lid closure bolt closest to the impact surface failed during the HAC 30-ft side drop. One of the goals for this CTU was to minimize the thermal pathway from the drum exterior shell to the containment vessel (CV) flange and O-rings, leading to the maximum damage scenario in preparation for thermal testing at 1475 °F. Therefore, the puncture bar impact proceeded as originally planned by striking the side wall of the package exterior closest to the location of the CV flange. This puncture bar impact did not attempt to exploit the region of the failed drum lid closure bolt to potentially cause more damage to the package. After the conclusion of regulatory testing, the DPP-3 package finite element model was used to numerically evaluate the effects of puncture bar impacts to the drum exterior in the vicinity of the failed drum lid closure bolt to further demonstrate the robustness of the DPP-3 design. Three alternate puncture bar impact locations and orientations were evaluated to demonstrate that these puncture bar impacts would not substantially reduce the effectiveness of the DPP-3 packaging. This paper describes the supplemental finite element models performed and structural analysis results that demonstrate the alternate HAC 40-in. puncture bar impact tests would have no deleterious effect on the performance of the DPP-3.

Presenting Author: Peter Sakalaukus Pacific Northwest National Laboratory

Presenting Author Biography: Dr. Sakalaukus does extensive work in the area of ASME BPVC and is an ASME BPV Code Committee Member on Section III, Division 3 Subgroup on Containment Systems for Spent Nuclear Fuel and High-Level Radioactive Material (SG NUPACK) and on the Working Group on Design of Division 3 Containment Systems.

Authors:

Peter J. Sakalaukus Jr. Pacific Northwest National Laboratory
Nathan P. Barrett Pacific Northwest National Laboratory
Brian J. Koeppel Pacific Northwest National Laboratory