Monitoring-based HVAC Commissioning of an Existing Office Building for Energy Efficiciency
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NARUC regularly hosts multi-day cybersecurity training events for commissioners and their staff to gain knowledge of IT/OT technologies, understand the spectrum of state and federal approaches to cybersecurity, and explore cybersecurity cost recovery challenges and innovative solutions to address them. About 300 commissioners and staffers typically register for these virtual events.
After a sequence of lab scale and bench scale trials the building of a pyrolysis plant could begin at the Studsvik site in Sweden. The facility is primarily aimed at treatment of uranium contaminated organic waste originating at fuel manufacturing plants and other facilities where the main contamination is uranium. The plant is an extension/addition to the already operating incinerator. In order to further widen the waste acceptance criteria the design of the off-gas treatment system does not have the same design as that of the incinerator. The building of the facility began in April 2011, and the first heating of the facility took place in late December, 2011. The site acceptance tests are planned for January, as are the first inactive trials aimed at optimisation of process control. The facility is planned to be operating with radioactive materials from February 2012. The pyrolysis unit is primarily aimed at treatment of uranium contaminated waste, under conditions that facilitate leaching and recovery of the uranium from the ashes. However, a number of other uses are conceivable. The batch fed pyrolysis unit, with its chosen design of the off-gas treatment system, enables treatment of some waste fractions that are difficult to treat in the incinerator. For instance small campaigns, i.e. smaller quantities of waste (typically <5 tonnes), or waste containing high levels of chlorine and sulphur are possible to treat in the pyrolysis unit. The pyrolysis unit is also expected to perform well in the treatment of other 'difficult' waste fractions, for instance waste containing pyrophoric materials, or other types of waste that benefit from the high level of process control, i.e. control of temperature and atmosphere throughout the process, that can be obtained in the pyrolysis unit compared to the incinerator. Furthermore, treatment in the pyrolysis unit minimises the risk of cross contamination between different waste treatment campaigns. This feature is obtained thanks to the low gas flow rates in the vessel, which means that a higher retention of nuclides in the ashes is obtained, but also through a design that facilitates cleaning of the pyrolysis vessel and the system beyond this, or even exchanging the most critical components, such as the pyrolysis vessel itself, if need be. (authors)
The EndoTOFPET-US collaboration has developed a multi-modal imaging system combining Ultrasound with Time-of-Flight Positron Emission Tomography into an endoscopic imaging device. The objective of the project is to obtain a coincidence time resolution of about 200 ps FWHM and to achieve about 1 mm spatial resolution of the PET system, while integrating all the components in a very compact detector suitable for endoscopic use. This scanner aims to be exploited for diagnostic and surgical oncology, as well as being instrumental in the clinical test of new biomarkers especially targeted for prostate and pancreatic cancer. (authors)
Since a beginning of ChNPP operation, and after a tragedy in 1986, a few thousands m{sup 3} of LRW have been collected in a storage tanks. In 2004 ChNPP started the new project on creation of LRW treatment plant (LRWTP) financed from EBRD fund. But it was stopped in 2008 because of financial and contract problems. In 2010, FSUE RADON jointly with Ukrainian partners has won a tender on completion of LRWTP, in particular I and C system. The purpose of LRTP is to process liquid rad-wastes from SSE 'Chernobyl NPP' site and those liquids stored in the LRWS and SLRWS tanks as well as the would-be wastes after ChNPP Power Units 1, 2 and 3 decommissioning. The LRTP design lifetime - 20 years. (authors)
The Department of Energy's Department of Environmental Management faces the complex task of cleaning up waste from nuclear weapons production. Often, the clean-up requires novel and untested technologies and approaches. In these cases, it is always necessary to provide some measure of assurance that the design engineers will be able to produce a design that will function in the means intended. Too many times we have seen first of a kind nuclear processing technologies put forth as commercially ready, only to be found insufficiently mature once attempted to be readied for operation. As now required by the DOE's Technology Readiness Assessment Process, it is necessary to demonstrate technologies in a similar environment to the current application and tested with a range of bounding simulants, or actual waste materials, if possible. (authors)
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The Neutron Induced Fission Fragment Tracking Experiment (NIFFTE) collaboration is developing a Time Projection Chamber (TPC) to measure neutron-induced fission cross sections with unprecedented accuracy. Modifying TPC technology for nuclear physics applications is a challenging endeavor, and frequent testing and evaluation is required to ensure that all components are behaving as expected. In-beam tests of the NIFFTE TPC at the Los Alamos Neutron Science Center (LANSCE) commenced in 2010. An overview of the NIFFTE TPC experiments performed at LANSCE will be presented, along with preliminary performance results.
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In October and November 2021 the CMS Gas Electron Multiplier (GEM) detectors of station GE1/1 were operated for the first time in presence of a magnetic field in CMS. The phenomena observed in this first period led to performing a test on GE1/1 chambers to study their behaviour in presence of a magnetic field ramp. The magnetic field has been created using the Goliath magnet installed in the CERN North Area. In conclusion, the aim of the test is to determine if a magnetic field ramp causes serious problems to the operation of the GEM chambers and to develop a clear set of procedures, that will permit the safe operations of the GEM chambers during a magnetic field ramp.
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Cross section data for neutron-induced reactions are needed for applications in nuclear astrophysics, stockpile stewardship, and nuclear reactor design but often contain discrepancies and gaps. A neutron source with a high neutron flux, a well-characterized neutron energy distribution, and a wide range of available neutron energies is ideal for studying such reactions in order to improve on existing data and provide new experimental results. For this purpose, the Neutron Irradiation Station (NIS) was developed using the 7 Li(p,n) 7 Be reaction. Neutron energy profiles were obtained using 3 He spectrometers and neutron standards were used to determine the neutron flux using the activation method. The neutron energy profile was found to be quasi-monoenergetic and neutrons were produced at energies from 1 keV to 1 MeV. Finally, the flux at the production target was found to be (1.42 ± 0.20) x 10 8 s −1 cm −2 .
The K-long and muon detector (KLM) constitutes the outer-most volume of the Belle II spectrometer at the interaction region of the SuperKEKB collider in Tsukuba, Japan. The KLM detector was partially upgraded since the Belle experiment by replacing many of its resistive-plate chambers with scintillators containing wavelength-shifting fibers and instrumenting it with silicon photomultipliers. Here, we describe the readout electronics, firmware, and software created to control and acquire data from the scintillators and resistive-plate chambers.
The Correlated Gamma-Neutron Array for sCattering (CoGNAC) is a dual $n$-$γ$ detector array fielded at the Weapons Neutron Research facility at the Los Alamos Neutron Science Center. Here, the detector array utilizes elpasolite detectors and liquid scintillators to perform measurements of neutron elastic and inelastic scattering cross sections and emitted particle angular distributions. This manuscript details the design and experimental setup of CoGNAC as well as some of the preliminary studies performed to select the elpasolite detectors deployed in the array. Examples of the analysis methods available to CoGNAC are given in the context of past CoGNAC measurements of neutron scattering reactions on 28 Si and 56 Fe.