NP 700 - ASME Pressure Vessel Code for Nuclear Transport and Storage

(1 unit)

Guidance for ASME Pressure Vessel Code application to nuclear transport and storage. Addresses design, fabrication, examination, and testing of package and cask to meet Code and regulatory requirements. This course is offered primarily Argonne National Laboratory in Illinois, and may occasionally be offered at other authorized locations. Students are responsible for all national laboratory fees and expenses associated with the course location.

Maximum units a student may earn: 1

Prerequisite(s): Graduate standing; basic knowledge of nuclear engineering and regulatory requirements for transportation and storage.

Grading Basis: Graded
Units of Lecture: 1
Offered: Every Fall

Student Learning Outcomes
Upon completion of this course, students will be able to:
1. apply engineering research and theory to advance the art, science, and practice of the discipline.
2. describe the federal regulations that govern packaging and transportation of radioactive material, and dry cask storage systems for spent nuclear fuel.
3. demonstrate understanding of DOE Orders and NRC guidance documents, including standard review plans, regulatory guides, and NUREG reports that are applicable to packagings and storage.
4. explain regulatory and code requirements of structural, thermal, containment, shielding, criticality, and design qualification by test and/or analysis for packages and casks.
5. demonstrate knowledge of the ASME Code requirements of material selection & qualification, design, fabrication, welding, examination, testing, and quality assurance for package/cask.
6. apply their knowledge in material sciences and engineering mechanics to the structural analysis of packages and casks.
7. explain aging effects of materials of storage casks, and time-limited aging analyses and aging management requirements for long-term storage of Spent Nuclear Fuel.

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