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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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 new build procurement considerations
It may seem counterintuitive, but the best time to enhance the ability to support operations and maintenance for a new plant is before construction starts. This is one of many lessons learned by the currently operating nuclear fleet. As construction and startup of many nuclear facilities was completed, it quickly became evident that the ability to efficiently support operations and maintenance was limited. Most of the information necessary to establish and manage procurement of spare and replacement items, maintenance, and configuration of the facilities was unavailable and had to be gathered on a case-by-case, “on-demand” basis. Absence of necessary information and the associated challenges resulted in the need for staff augmentation and multiyear-long projects to develop equipment bills of material and maintenance programs and to perform technical evaluations for the huge quantities of spare and replacement items being requested.
Hyun-Sik Park, Hwang Bae, Sung-Uk Ryu, Byong-Guk Jeon, Jin-Hwa Yang, Sung-Jae Yi, Young-Jong Chung
Nuclear Technology | Volume 209 | Number 10 | October 2023 | Pages 1617-1635
Note | doi.org/10.1080/00295450.2023.2217370
Articles are hosted by Taylor and Francis Online.
The thermal-hydraulic research supporting the development of an integral type of reactor named System-integrated Modular Advanced ReacTor (SMART) is discussed. First, the SMART development program is introduced. The Standard Design Approval (SDA) for SMART was certificated in 2012 based on extensive technical validation activities during 2009 to 2012, and a set of passive safety systems (PSSs) was designed and validated for SMART during 2013 to 2015 after the Fukushima Daiichi accident. During 2016 to 2018, the Kingdom of Saudi Arabia and Korea conducted a 3-year project of Pre-Project Engineering (PPE), and now, the Standard Design Approval (SDA) for SMART100 is being processed from 2019. Second, the SMART validation test program and related test facilities are introduced. A set of integral effect tests (IETs) was performed using VISTA-ITL, and several separate effect tests (SETs) using the facilities of SWAT, SCOP, and FTHEL were performed for SMART SDA. Counterpart tests for SMART SDA were performed with the newly constructed SMART-ITL facility, and various validation tests for SMART PSSs were also performed. In addition, dozens of validation tests for SMART PPE were performed to produce IET data for design-basis-accident scenarios and PSSs. Additional SETs for SMART PPE and SMART100 SDA were performed using the facilities of SISTA-1, SISTA-2, and FINCLS. Third, the major test results are discussed for phenomena expected to occur in an integral type of reactor such as the SMART design. They include core cooling behaviors in the reactor coolant system and safety injection behaviors in the passive safety injection system and counterpart test results of a small-break loss-of-coolant accident between VISTA-ITL and SMART-ITL. Fourth, the major analysis results for SMART are discussed. Several sets of code analysis were performed for selected IET cases with the MARS-KS and TASS/SMR-S codes to validate their models and the codes themselves. They include simulation of a SMART safety injection system line break test with the MARS-KS code, validation of the TASS/SMR-S code for natural circulation tests, and validation of the MARS-KS and TASS/SMR-S codes based on a pressurizer safety valve line break test.