Training Course: Application of the ASME Code to Radioactive Material Transportation Packaging

Sponsored by the Office of Site Operations, Packaging Certification Program in DOE EM-70

NOTE:  I have a copy of the 2007 ASME Code that I can sell to.  To buy [click here] for details.

Purpose

The objective of this training course is to provide the participants with guidance for the application of the requirements of the ASME Boiler and Pressure Vessel Code to Type B or fissile material packaging for the transportation of radioactive materials.

Audience

The potential target audiences for this training course are DOE and contract personnel, outside regulatory personnel, and commercial packaging engineering personnel. Those responsible for design, fabrication, or evaluation of Type B or fissile material packaging, as well as preparing or reviewing the associated safety analysis reports, would also benefit.

Format

This is a classroom course consisting of technical presentations, discussions, and examples, with emphasis on understanding the regulatory basis, current design practice, and engineering rationale for applying the ASME Code to packaging for radioactive materials.

Duration

The course can be arranged as a one- or two-day presentation.

Content

Regulatory
Legal and regulatory basis for application of the ASME Code to packaging, including DOE packaging authority, NRC Regulatory Guides, and other guidance.

ASME Code
The history and present structure of the ASME Code, including its nuclear development, as applicable to packaging. The development of the "NuPack" rules, that is ASME Section III, Division 3, for radioactive material transportation packaging containments and the current application of the ASME code to packaging.

Application
Difference between physical and infrastructure requirements. Requirements for design specifications, design reports, and other documentation imposed on packaging owners, designers, and manufacturers.

Section III
The structure of Section III of the ASME code, entitled "Rules for Construction of Nuclear Power Plant Components". Subsections NCA, NB, ND, NF and NG as they apply to packaging. Subsection NB is applied to Category I packaging, ND to Category II, NF to other packaging components, and NG to basket structures. Essential elements of each subsection, and the differences between subsections. Load and stress classification. Code requirements associated with materials, design, fabrication, examination, testing and documentation, with examples used where possible.

ASME NuPack
The recently issued NuPack Division of the code that was written specifically for packaging will be reviewed in relation to Section III of the code. Differences between NuPack and Section III will be highlighted.

Section VIII
Category III packaging components are treated as non-nuclear pressure vessels and are covered by Code Section VIII. This Section will be discussed in relation to the differences between it and Section III of the code.

Prerequisites

All participants should be familiar with general radioactive material packaging concepts and requirements.

Copies of the ASME Code

Copies of the ASME Code itself will be available for reference at the course; however, we cannot provide copies for the participants. You are encouraged to bring your own copies, particularly of Section III Division 3.

Copies can be obtained from The ASME; see the ASME Catalogue, or see the code sections web site, or call 1-800-843-2763 (Fax: 1-973-882-1717) .  

Staff

This training course was prepared and presented for the U.S. Department of Energy by the following Argonne National Laboratory personnel:

Peter Turula, Ph.D., P.E. - Member of the ASME NuPack Subcommittee,
Brent Shelton, P.E. - Member Emeritus of ASME-BNCS (Board of Nuclear Codes and Standards), and
David Raske, Ph.D., P.E.

Contact

e-mail to   .

This course was given on June 30 - July 1, 1998.  There were two full days of presentations.

The number of participants was 28.
See the agenda and the course information web page which Dr. Peter Turula developed for Argonne National Lab.

You can also see the text of the presentation view-graphs which were prepared for this course by P. Turula.

Return to the P. Turula resume page.
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