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Companion Guide to the ASME Boiler & Pressure Vessel Code, Volume 1, Second EditionAvailable to Purchase
Editor
K. R. Rao
K. R. Rao
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ISBN-10:
0791802183
No. of Pages:
700
Publisher:
ASME Press
Publication date:
2006

In Chapter 15, also authored by John D. Stevenson, a commentary is provided about the containment systems used for the transportation and storage packaging of spent fuel and high-level radioactive material waste and spent fuel. In 1997, ASME issued the initial version of Division 3 of Section III. Before the publication of Division 3, Section III, the Section applicable to the construction of nuclear pressure-retaining components and supports had two divisions: Division 1, for metal construction, and Division 2, for concrete construction. Division 3 was added to cover the containment of packaging for nuclear materials; hence its common name “Nupack.” Currently, Division 3 requirements are limited to containment components of transport for only the most hazardous radioactive materials—namely, spent fuel and other highly radioactive materials, such as high-level waste, as contained in the published Subsections WA and WB of the Code. Under active development is Subsection WC, applicable to storage containment of the same type of packaging covered by Subsection WB. Consistent with current Code practice, the primary concern of Division 3 is the integrity of the containment component under the design basis, the operating conditions, and hypothetical accident conditions. In particular, the structural and leak-tight integrity of the containment component, rather than its functionality, is the focus of the ASME B&PV Code rules. Nupack is also concerned with some aspects of vessel-closure functionality because of the potential for seal leakage, which is a key consideration in the containment function. Division 3 covers all construction aspects of the containment component, including administrative requirements, material selection, material qualification, design, fabrication, examination, inspection, testing, quality assurance, and documentation.

15.1 Introduction
15.2 Historical Development
15.3 Code Development
15.4 Scope of Nupack
15.5 General Provisions
15.6 Documentation Requirements
15.7 Specified Loading Categories
15.8 Allowable Stress
15.9 Materials, Fabrication, Installation, Examination, and Testing
15.10 Code Text Organization
15.11 Assessment of the ASME Nupack Design Rules [6]
15.12 Suggested Further Enhancements—Impact Limiters
15.13 Tiedowns∕Transportation Structures
15.14 Gasket∕Seal Design
15.15 Lead Melting
15.16 Example Problems
15.17 Summary of Changes
15.18 References
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