: This chapter reflects the 2015 Edition of Section III, Division 3 of the ASME Boiler and Pressure Vessel (BPV) Code. Division 3 covers all “construction” aspects of the containment of nuclear transportation packagings, including administrative requirements, material selection, material qualification, design, fabrication, examination, inspection, testing, quality assurance, and documentation. The current scope for Division 3 includes the containments for both transportation and storage and the internal support structures for both containments. The chapter first traces the history of the ASME Subgroup NUPACK, and outlines the scope and requirements of Division 3. It then discusses the system of loading classification and the design rules based on these loadings. Division 3 loadings include Design Loadings (Design Pressure, Design Temperature, and Design Mechanical Loadings), Operating Loadings (normal, off-normal, and accident), and Test Loadings (from pressure and leak tests). The chapter also provides a brief review of the ASME stress evaluations and the associated stress acceptance criteria. Code text organization of Division 3 is then considered. The ASME BPV Code Section III, Division 3 is currently divided into three subsections: WA, General Requirements; WB, Class TC Containments; and WC, Class SC Storage Containments. Discussions also include the incorporation of strain-based acceptance criteria, and the current activities in Division 3 such as the development of new subsection WD addressing internal support structures. The chapter concludes with a summary of suggested enhancements for the future in the scope for Division 3.

: This chapter provides commentary on a new division under Section III of the ASME Boiler and Pressure Vessel (BPV) Code. This Division 5 was first published as part of the 2011 Addenda to the 2010 Edition of the BPV Code. The chapter provides information on the scope and need for Division 5, the structure of Division 5, where the rules originated, the basis for the elevated temperature rules specified in Division 5, the various changes made in finalizing Division 5, and the future near-term and long-term expectations for Division 5 development. It reflects the 2015 Edition of Division 5. Division 5 identifies rules for high temperature reactors (HTRs) based on only two classifications, Class A for safety-related components and Class B for non-safety related but with special treatment components. It contains general requirements for both metals and graphite in Subsection HA, Subpart A and Subpart B, respectively. Rules for Class A metallic pressure boundary components, Class B metallic pressure boundary components, and Class A core support structures at both low temperature conditions (under Subpart A) and elevated temperature conditions (under Subpart B) are contained in Subsections HB, HC, and HG, respectively. Rules for Class A and B metallic supports are contained in Subsection NF, Subpart A. Finally, new rules for nonmetallic core support structures (graphite) are contained in Subsection HH, Subpart A. Consistent with current Code practice, the primary concern of Division 5 is the integrity of the components under design, operating conditions (including normal, upset, emergency, and faulted), and test conditions. Division 5 covers all construction aspects of these components, including administrative requirements, material selection and qualification, design, fabrication, examination, inspection, testing, quality assurance, and documentation.

In 1997, the American Society of Mechanical Engineers (ASME) issued the initial version of Division 3 of Section III of the ASME Boiler and Pressure Vessel (BPV) Code. Prior to the publication of Division 3, Section III had only two divisions: Division 1 for metal construction and Division 2 for concrete construction. Division 3 was added to address the containments of nuclear transportation packagings. Hence, the ASME Subgroup responsible for Division 3 has been commonly referred to as “Subgroup NUPACK” even though its official name is the Subgroup on Containment Systems for Spent Fuel and High-Level Waste Transport Packagings. Consistent with current ASME BPV Code practice, the concern of this Division is primarily the integrity of the containment under design, operating, and test conditions. In particular, the structural and leak integrity of the containment is the focus of the Division 3 rules. Subgroup NUPACK is also concerned with aspects of containment closure functionality because the potential for leakage is a key consideration in the containment function of a transport cask or storage containment. Division 3 covers all “construction” aspects of the containment, which is ASME BPV Code terminology that includes administrative requirements, material selection, material qualification, design, fabrication, examination, inspection, testing, quality assurance, and documentation.

This chapter provides commentary on a new division under Section III of the ASME Boiler and Pressure Vessel (BPV) Code. This new Division 5 has an issuance date of November 1, 2011 and is part of the 2010 Edition of the BPV Code. This chapter provides information on the scope and need for Division 5, the structure of Division 5, where the rules originated, the various changes made in finalizing Division 5, and the future near-term and long-term expectations for Division 5 development.

In 1999, an international collaborative initiative for the development of advanced (Generation IV) reactors was started. The idea behind this effort was to bring nuclear energy closer to the needs of sustainability, to increase proliferation resistance, and to support concepts able to produce energy (both electricity and process heat) at competitive costs. Six reactor concepts were chosen for further development: the sodium fast reactor (SFR), the very-high-temperature gas-cooled reactor (VHTR), the lead or lead-bismuth cooled liquid metal reactor, the helium gas-cooled fast reactor, the molten salt reactor (MSR), and the super critical water reactor. In view of sustainability, the Generation IV reactors should not only have superior fuel cycles to minimize nuclear waste, but they should also be able to produce process heat or steam for hydrogen production, synthetic fuels, refinery processes, and other commercial uses. These reactor types were described in the 2002 Generation IV roadmap. Different projects around the world have been started since that time. The most advanced efforts are with reactors where production experience already existed. These reactors include the SFR and the VHTR. The other reactor types are still more in a design concept phase. This chapter briefly describes the six Generation IV concepts and then provides additional details, focusing on the two near-term viable Generation IV concepts. The current status of the applicable international projects is then summarized. These new technologies have also created remarkable demands on materials compared with light water reactors (LWRs). Higher temperatures, higher neutron doses, environments very different from water, and design lives of 60 years present a real engineering challenge. These new demands have led to many exciting research activities and to new Codes and Standards developments, which are summarized in the final sections of this chapter.

In Chapter 15, authored by D. Keith Morton and D. Wayne Lewis, a commentary is provided regarding the containments used for the transportation and storage packaging of spent fuel and high-level radioactive material and waste. John D. Stevenson was the author of this chapter for the earlier two editions of this publication. However, this is a complete rewrite of the Chapter, including a slightly different Chapter title. 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 only two divisions: Division 1, for metal construction, and Division 2, for concrete construction. Division 3 was added to cover the containments of packaging for nuclear materials. Currently, the scope for Division 3 is limited to transportation and storage containments for only the most hazardous radioactive materials—namely, spent fuel and other highly radioactive materials, such as high-level waste. Division 3 contains three published subsections: Subsection WA providing general requirements, Subsection WB addressing rules for transportation containments, and Subsection WC addressing storage containment rules. Under active development is Subsection WD, which will provide the construction rules applicable to internal support structures (baskets) for the transportation and storage containments covered by Subsections WB and WC. Consistent with current Code practice, the primary concern of Division 3 is the integrity of these containments under design, operating conditions (including normal, off-normal, and accident), and test conditions. In particular, the structural and leak-integrity of these containments is the focus of the ASME B&PV Code rules. Division 3 is also concerned with certain aspects of containment-closure functionality because of the potential for leakage, which is a key consideration in the containment function. Division 3 covers all construction aspects of the containment, including administrative requirements, material selection, material qualification, design, fabrication, examination, inspection, testing, quality assurance, and documentation.