Assessment of Nuclear Sensors and Instrumentation Maturity in Advanced Nuclear Reactors

In the last decade, 97% of the worldwide commercial nuclear reactors connected to the grid were Light Water Reactors (LWRs). LWRs are expected to stay the dominant type of nuclear reactors for the next few decades. Reliable and redundant safety systems are required in nuclear reactors to ensure safe operation and shutdown in abnormal conditions. These safety systems are actuated by the signals obtained from several sensors and instrumentation in and out of the reactor core. Research and Development (R&D) in advanced sensors and instrumentation has gained extra attention, particularly following the accident at the Three Mile Island Unit-2 (TMI-2). In LWRs, these sensors and instrumentation have shown a high level of maturity with long operating experience. Ensuring the compatibility of these sensors and instrumentation with advanced nuclear reactors (Generation IV) is necessary, particularly with the expected expansion of the nuclear industry in the next few decades. Nuclear Sensor and instrumentation technologies used in the current generation of LWRs were investigated. The compatibility of these technologies with advanced reactors was assessed by comparing the advanced reactors' environments with those of the currently operating reactors. In addition to that, the needed R&D for such technologies was highlighted. In comparison with the LWRs environment, it was shown that advanced reactor environments are expected to experience elevated temperatures, a fast neutron spectrum, and a harsh corrosion environment. It was demonstrated that R&D is required mainly for fixed in-core nuclear sensors and instrumentation, while it is not a priority for ex-core nuclear sensors and instrumentation.

[1]  J. Shan,et al.  A review of existing SuperCritical Water reactor concepts, safety analysis codes and safety characteristics , 2022, Progress in Nuclear Energy.

[2]  T. Blue,et al.  Parametric Analysis of an Optical Fiber–Based Gamma Thermometer for University Research Reactors Using an Analytic Thermal Model , 2021, Nuclear Technology.

[3]  Thomas E. Blue,et al.  Methodology for inferring reactor core power distribution from an optical fiber based gamma thermometer array , 2020 .

[4]  T. W. Crane,et al.  Neutron Detectors , 2020, Micro-Pattern Gaseous Detectors.

[5]  Y. V. Stogov,et al.  Possibilities of Better Utilization of MOX fuel in VVER type reactors by optimizing neutron spectrum , 2020, Journal of Physics: Conference Series.

[6]  Jiyun Zhao,et al.  Design concepts of supercritical water-cooled reactor (SCWR) and nuclear marine vessel: A review , 2020, Progress in Nuclear Energy.

[7]  L. Vermeeren,et al.  Nuclear Heating Measurements by Gamma and Neutron Thermometers , 2020, IEEE Transactions on Nuclear Science.

[8]  Qingmin Zhang,et al.  Current compensation for material consumption of cobalt self-powered neutron detector , 2020 .

[9]  Jincheng Wang,et al.  Review on neutronic/thermal-hydraulic coupling simulation methods for nuclear reactor analysis , 2020 .

[10]  M. Seidl,et al.  Study of the influence of water gaps between fuel assemblies on the activation of an aeroball measurement system (AMS) , 2020 .

[11]  Yigang Yang,et al.  A Monte-Carlo simulation method for the study of self-powered neutron detectors , 2020 .

[12]  S. Cetiner,et al.  Instrumentation Framework for Molten Salt Reactors , 2018 .

[13]  P. Tsvetkov,et al.  Reactor design strategy to support spectral variability within a sodium-cooled fast spectrum materials testing reactor , 2018 .

[14]  V. Verma,et al.  Self powered neutron detectors as in-core detectors for Sodium-cooled Fast Reactors , 2017 .

[15]  S. W. Tam,et al.  Assessment of Sensor Technologies for Advanced Reactors , 2016 .

[16]  F. Silva,et al.  Determination of the power density distribution in a PWR reactor based on neutron flux measurements at fixed reactor incore detectors , 2016 .

[17]  J. Kloosterman,et al.  The molten salt reactor (MSR) in generation IV: Overview and perspectives , 2014 .

[18]  Ulrich Fischer,et al.  Development of self-powered neutron detectors for neutron flux monitoring in HCLL and HCPB ITER-TBM , 2014 .

[19]  C. Renault,et al.  Supercritical Water-Cooled Reactors , 2014 .

[20]  Giorgio Locatelli,et al.  Generation IV nuclear reactors: Current status and future prospects , 2013 .

[21]  Eric S. Andersen,et al.  Technical Readiness and Gaps Analysis of Commercial Optical Materials and Measurement Systems for Advanced Small Modular Reactors , 2013 .

[22]  S. M. Luker,et al.  Modeling, Calibration, and Verification of a Fission Chamber for ACRR Experimenters , 2013 .

[23]  J. L. Rempe,et al.  TMI-2 - A Case Study for PWR Instrumentation Performance during a Severe Accident , 2013 .

[24]  H. M. Hashemian,et al.  Nuclear Power Plant Instrumentation and Control , 2011 .

[25]  Timothy Abram,et al.  Generation-IV nuclear power: A review of the state of the science , 2008 .

[26]  Douglas S. McGregor,et al.  Micro-pocket fission detectors (MPFD) for in-core neutron flux monitoring , 2005 .

[27]  P. Glasow Aeroball system and energy-dispersive analysis: Important industrial applications of silicon detectors , 1984 .

[28]  Simon Rippon,et al.  History of the PWR and its worldwide development , 1984 .

[29]  J. Beckerley,et al.  Nuclear Power Reactor Instrumentation Systems Handbook , 1975 .

[30]  L. Roseo BOILING WATER REACTORS , 1957 .

[31]  E. S. Bettis,et al.  The Aircraft Reactor Experiment—Design and Construction , 1957 .

[32]  Qingmin Zhang,et al.  Development and verification of a simulation toolkit for Self-Powered Neutron Detector , 2021 .

[33]  M. H. Subki Water Cooled Small Modular Reactors (Integral PWR and BWR) , 2021 .

[34]  S. Cetiner,et al.  Development of a Fast-Spectrum Self-Powered Neutron Detector for Molten Salt Experiments in the Versatile Test Reactor , 2021, EPJ Web of Conferences.

[35]  Branislav Hatala Gas Cooled Fast Reactor System (GFR) , 2020 .

[36]  H. Ray U.S. Options for Licensing a New Commercial Power Plant , 2020 .

[37]  Thuy Mai,et al.  Technology Readiness Level , 2015 .

[38]  K. Theriault Boiling Water Reactors (BWRs) , 2010 .

[39]  T. G. Lewis,et al.  VHTR-Based Systems for Autonomous Co-Generation Applications , 2008 .

[40]  Meininger,et al.  Three Mile Island technical information and examination program instrumentation and electrical summary report , 1985 .

[41]  P. N. Haubenreich,et al.  ZERO-POWER PHYSICS EXPERIMENTS ON THE MOLTEN-SALT REACTOR EXPERIMENT. , 1968 .

[42]  R. Arai,et al.  APPLICATION OF THE GAMMA THERMOMETER AS BWR FIXED IN-CORE CALIBRATION SYSTEM , 2022 .