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Chapter 15
Containment Systems for Transportation and Storage Packaging of Spent Fuel and High-Level Radioactive Waste and Spent Fuel

Excerpt

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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