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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
Charles R. Brinkman, Vinod K. Sikka, Roy T. King
Nuclear Technology | Volume 33 | Number 1 | April 1977 | Pages 76-95
Technical Paper | Material | doi.org/10.13182/NT77-A31765
Articles are hosted by Taylor and Francis Online.
The available tensile and creep-rupture properties of relevant product forms of Types 316 and 304 stainless steel and associated as-deposited weld metals (i.e., Type 316) have been reviewed. A description of both time-dependent and -independent behavior is emphasized for Type 316 stainless steel, since this material and its weldments in hot-leg piping applications must operate at temperatures within the creep range. Therefore, elevated-temperature fatigue and creep-fatigue interaction of Type 316 stainless steel are discussed over the temperature range from 566 to 593°C for both air and sodium environments. Tensile yields and ultimate strengths as well as creep-rupture strengths of tube/pipe/plate product forms in the as-received or mill-annealed condition were found to be generally above American Society of Mechanical Engineers (ASME) Code minimum trend curves. However, in the case of Type 304 stainless steel, a reannealing treatment lowered some yield strengths to values below the minimum trend curve. Thermal aging of Type 316 stainless steel at temperatures appropriate to piping design for times up to 10 000 h did not result in large changes in the tensile properties. Generally, increases in minimum creep rate, creep ductility, and time-dependent or -independent fatigue cycle life were found following thermal aging of both Types 304 and 316 stainless steel. However, exposure of these materials to creep or creep-fatigue conditions such that considerable creep strain was accumulated prior to tensile testing resulted in reduced tensile properties in some instances. Comparison of the available creep-fatigue data for Type 316 stainless steel with the elastic fatigue design curve found in ASME Code Case 1592 indicated that a considerable margin of safety presently exists. The yield strengths for as-deposited Types 308, 316, and 16-8-2 weld metal, as well as heat-affected zone material, are generally higher than those of the corresponding base materials. While ultimate tensile strengths of these weld metals were generally found to fall within the scatter bands for base materials, instances were found where weld metals had lower tensile strengths than base materials. Annealing of weldments after fabrication can result in reduced yield strengths and increased tensile ductility. Creep rupture strengths of gas tungsten-arc and shielded metal-arc deposited Type 316 and 16-8-2 weld metal are sometimes comparable to base material. However, there are numerous data that indicate that rupture strength values can fall below base material minimum values. Creep-rupture ductilities of these weld metals are generally less than those of base material, with total elongations of only 1 to 2% possible for test times approaching 10 000 h, particularly for Type 316 weld metal.