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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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June 2024
Nuclear Technology
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Latest News
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
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.
