Assessment of Sensor Technologies for Advanced Reactors

Conference · Mon Aug 01 04:00:00 EDT 2016

OSTI ID:1329318

Korsah, Kofi ^[1]; Kisner, R. A. ^[1]; Britton Jr., C. L. ^[1]; Ramuhalli, Pradeep ^[2]; Wootan, D. W. ^[2]; Anheier Jr., N. C. ^[2]; Diaz, A. A. ^[2]; Hirt, E. H. ^[2]; Vilim, Richard B. ^[3]; Chien, H. T. ^[3]; Bakhtiari, S. ^[3]; Sheen, S. ^[3]; Gopalsami, S. ^[3]; Heifetz, A. ^[3]; Tam, S. W. ^[3]; Park, Y. ^[3]; Upadhyaya, Belle R. ^[4]; Stanford, Austin ^[4]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Electrical and Electronics Systems Research Division
2. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
3. Argonne National Lab. (ANL), Argonne, IL (United States)
4. Univ. of Tennessee, Knoxville, TN (United States)

Sensors and measurement technologies provide information on processes, support operations and provide indications of component health. They are therefore crucial to plant operations and to commercialization of advanced reactors (AdvRx). This report, developed by a three-laboratory team consisting of Argonne National Laboratory (ANL), Oak Ridge National Laboratory (ORNL) and Pacific Northwest National Laboratory (PNNL), provides an assessment of sensor technologies and a determination of measurement needs for AdvRx. It provides the technical basis for identifying and prioritizing research targets within the instrumentation and control (I&C) Technology Area under the Department of Energy’s (DOE’s) Advanced Reactor Technology (ART) program and contributes to the design and implementation of AdvRx concepts. The report is organized under two broad categories: High Temperature Reactors and Fast Reactors. For the purposes of this report, the scope of “High temperature reactors” includes Gen IV reactors whose coolant exit temperatures exceed ~650 °C and are moderated (as opposed to fast reactors). We included in this category gas-cooled reactors that have been built and operated throughout the world to date-including those that use carbon dioxide (CO₂) or Helium (He) as coolant-and the molten salt reactor. However, for the sake of conciseness this report uses the high temperature gas reactor (HTGR) as an example in many cases. With regard to fast reactors, there are several reactor years of experience with several technology variants (including sodium fast reactors and other fast reactors such as the LBFR). In particular, several experimental, prototype and demonstration units have been designed and operated in several countries, including France, India, Japan, USSR/Russia, UK, and the United States. To bound the scope, this report reviewed relevant operating experience from US-operated Sodium Fast Reactor (SFR) and relevant test experience from the Fast Flux Test Facility (FFTF).

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• Contributing Organization: Univ. of Tennessee, Knoxville, TN (United States)
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1329318
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS