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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Nuclear Science and Engineering
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Latest News
Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
Ben Frisk, Christopher Hope (NuScale Power)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 290-295
The purpose of this paper is to describe gaps found in programmatic verification activities for safety-critical systems based on field programmable gate array (FPGA) technology; specifically, by comparing the more mature methods used by other regulated industries that commonly use FPGAs and those mandated in the traditional software-based framework of the legacy commercial nuclear power generating industry. This paper also describes the strategies used by NuScale Power, LLC (NuScale) to fill the identified gaps, while maintaining its conformance to IEEE 1012-2004. In addition, the purpose of this paper is to inform and encourage consideration of why the 2004 version of IEEE 1012 is outdated for its application to the commercial nuclear power industry, especially as adoption of non-microprocessor based digital technology becomes widespread. Currently, the regulatory process for ensuring quality and safety for digital plant protection systems specifies independent verification and validation (IV&V) as outlined in IEEE 1012-2004 and endorsed by Regulatory Guide 1.168, Revision 2. Simply put, the reason to move away from the 2004 version and adoption of the 2016 version is due to the holistic systems-based life cycle that is inclusive of hardware, software, and their interfaces, which is now specified in the new version of IEEE 1012 (version 2016). The systems-based strategy is a key factor needed to ensure functional safety and quality throughout the verification and validation process. This is especially true for FPGA-based systems, as there is a tendency to think this technology should be treated only as hardware. This paper will identify critical differences between the versions of IEEE 1012 and explain why the NuScale IV&V program is looking outside of the commercial nuclear industry for methods better suited to FPGA-based I&C systems. In closing, this paper is intended to describe portions of the NuScale IV&V program that meets the requirements specified in IEEE 1012-2004, but also combines innovation with lessons learned from nonnuclear industries used to develop FPGA-based safety I&C systems.
