Author: J. A. WalsworthPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Blowdown test matrix for phase i of the BTF nuclear commissioning experiment, BTF-102
Author: J. A. WalsworthBlowdown test matrix for the BTF non-nuclear commissioning experiment, BTF-10006
Author: R. J. ZanattaBTF-102/1.3 preliminary blowdown data set
Author: L. W. DicksonBTF-102/1.1 preliminary blowdown data set
Author: L. W. DicksonAssembly proposal for simulator blowdown tests in preparation for the BTF-105a test (experiment BTF-10030).
Author: L. W. DicksonOperational plan for conducting the BTF-105a test in the blowdown test facility of the NRU reactor
Author: E. P. StockPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
The btf-105 experiment in the blowdown test facility is one of a series of experiments sponsored by the candu owners group (cog) to determine the release, transport and deposition of fission products from nuclear fuel under high-temperature transient conditions. the btf-105 experiment has been broken up into two tests: btf-105a and btf-105b. the btf-105a test is a precursor to the btf-105b test, which will generate fission product release data used to benchmark candu safety analysis codes. the btf-105a test will be used to assess instrumentation and procedures to be used during btf-105b, and to generate correlations between fuel sheath and fuel centreline temperatures. fission product release and transport data will also be obtained from low burnup fuel. the btf-105a test consists of a fuel stringer containing a single unirradiated instrumented zircaloy-clad uo2 fuel element. the assembly will be irradiated at a linear power of 50 kw/m for 10 days to establish an inventory of fission products in the fuel. following the soak irradiation, the stringer will be subjected to a coolant blowdown where the volume average temperature of the uo2 will rise to and be maintained at about 1600-1800 degrees c for about 10 minutes. the fuel element is predicted to fail during the ramp up to this temperature due to complete oxidation of the sheath. fission products released during the transient will be monitored by gamma spectrometers. following the test, the fuel stringer will be removed from the reactor and destructively examined in the crl hot cells. grab samples from inside the test section will also be removed and analyzed for fission products. this report presents an overall plan for the activities to be completed before, during and after the btf-105a blowdown test.
Blowdown test facility (BTF) decontamination system commissioning report
Author: J. B. ArnoldInstrument Engineers' Handbook, Volume 3
Author: Bela G. LiptakPublisher: CRC Press
ISBN: 1439863431
Category : Technology & Engineering
Languages : en
Pages : 1140
Book Description
Instrument Engineers' Handbook – Volume 3: Process Software and Digital Networks, Fourth Edition is the latest addition to an enduring collection that industrial automation (AT) professionals often refer to as the "bible." First published in 1970, the entire handbook is approximately 5,000 pages, designed as standalone volumes that cover the measurement (Volume 1), control (Volume 2), and software (Volume 3) aspects of automation. This fourth edition of the third volume provides an in-depth, state-of-the-art review of control software packages used in plant optimization, control, maintenance, and safety. Each updated volume of this renowned reference requires about ten years to prepare, so revised installments have been issued every decade, taking into account the numerous developments that occur from one publication to the next. Assessing the rapid evolution of automation and optimization in control systems used in all types of industrial plants, this book details the wired/wireless communications and software used. This includes the ever-increasing number of applications for intelligent instruments, enhanced networks, Internet use, virtual private networks, and integration of control systems with the main networks used by management, all of which operate in a linked global environment. Topics covered include: Advances in new displays, which help operators to more quickly assess and respond to plant conditions Software and networks that help monitor, control, and optimize industrial processes, to determine the efficiency, energy consumption, and profitability of operations Strategies to counteract changes in market conditions and energy and raw material costs Techniques to fortify the safety of plant operations and the security of digital communications systems This volume explores why the holistic approach to integrating process and enterprise networks is convenient and efficient, despite associated problems involving cyber and local network security, energy conservation, and other issues. It shows how firewalls must separate the business (IT) and the operation (automation technology, or AT) domains to guarantee the safe function of all industrial plants. This book illustrates how these concerns must be addressed using effective technical solutions and proper management policies and practices. Reinforcing the fact that all industrial control systems are, in general, critically interdependent, this handbook provides a wide range of software application examples from industries including: automotive, mining, renewable energy, steel, dairy, pharmaceutical, mineral processing, oil, gas, electric power, utility, and nuclear power.
Nuclear Fuel Cycle Simulation System (VISTA)
Author: International Atomic Energy AgencyPublisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 112
Book Description
The Nuclear Fuel Cycle Simulation System (VISTA) is a simulation system which estimates long term nuclear fuel cycle material and service requirements as well as the material arising from the operation of nuclear fuel cycle facilities and nuclear power reactors. It is a scenario based simulation tool which can model several nuclear fuel cycle options including existing nuclear power reactor types and future possible reactor types. The past operations of the power reactors and fuel cycle facilities can be modelled in the system, in order to estimate the current amount of spent fuel stored or total Pu in stored spent fuel. It can also accept future projections for nuclear power and other scenario parameters in order to predict future fuel cycle material requirements.The model has been designed to be an optimum mixture of simplicity, speed and accuracy. It does not require too many input parameters if the purpose is just to compare the requirements for selected scenarios. Furthermore, the accuracy of the system can be improved by introducing more detailed and correct sets of input parameters.
Instrument and Automation Engineers' Handbook
Author: Bela G. LiptakPublisher: CRC Press
ISBN: 1000820629
Category : Technology & Engineering
Languages : en
Pages : 3560
Book Description
The Instrument and Automation Engineers’ Handbook (IAEH) is the Number 1 process automation handbook in the world. The two volumes in this greatly expanded Fifth Edition deal with measurement devices and analyzers. Volume one, Measurement and Safety, covers safety sensors and the detectors of physical properties, while volume two, Analysis and Analysis, describes the measurement of such analytical properties as composition. Complete with 245 alphabetized chapters and a thorough index for quick access to specific information, the IAEH, Fifth Edition is a must-have reference for instrument and automation engineers working in the chemical, oil/gas, pharmaceutical, pollution, energy, plastics, paper, wastewater, food, etc. industries.