Investigation of Neutron Reaction Behavior in Water-cooled FBR with MOX Fuel
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چکیده
منابع مشابه
Performance Test of the Electronic Personal Neutron Dosemeter in Neutron Fields Simulating Workplaces of MOX Fuel Fabrication Facilities
Recently, several electronic personal dosemeters (EPDs) capable of measuring neutron dose equivalents were developed and have appeared on the market. The authors initiated the present study to assess performance of neutron EPDs. The EPD selected for this study was NRY21, manufactured by Fuji Electric Systems Co., Ltd. This dosemeter uses two silicon semiconductor detectors (a fast neutron senso...
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ترانسفورماتورهای قدرت از اجزای اصلی شبکه تامین انرژی الکتریکی می باشند که عملکرد قابل اطمینان ترانسفورماتورها یکی از فاکتورهای مهم و تعیین کننده در تامین انرژی الکتریکی محسوب می شود. در نتیجه بررسی و مانیتور عملکرد ترانسفورماتورها در شبکه و همچنین عیب یابی این ترانسفورماتورها غیرقابل اجتناب و ضروری می باشد. به طور کلی عایق های مایع در صنعت فشار قوی کاربردهای متفاوتی دارند که مهمترین وظیفه آنها...
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چکیده ندارد.
15 صفحه اولREACTOR PHYSICS CALCULATIONS ON MOX FUEL IN BOILING WATER REACTORS (BWRs)
The loading of MOX (Mixed Oxide) fuel in BWRs (Boiling Water Reactors) is considered in this paper in a “once-through” strategy. The fuel assemblies are of the General Electric 8×8 type, whereas the reactor is of the General Electric BWR/6 type. Comparisons with traditional UOX (Uranium Oxide) fuel assemblies revealed that the loading of MOX fuel in BWRs is possible, but this type of fuel creat...
متن کاملDynamic behavior of hydration water in calcium-silicate-hydrate gel: a quasielastic neutron scattering spectroscopy investigation.
The translational dynamics of hydration water confined in calcium-silicate-hydrate (C-S-H) gel was studied by quasielastic neutron scattering spectroscopy in the temperature range from 280 to 230 K. The stretch exponent β, the self-diffusion constant D, the average translational relaxation time {τ}, and the temperature dependence of confinement radius α extracted from the elastic fraction of im...
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ژورنال
عنوان ژورنال: Journal of Nuclear Science and Technology
سال: 2005
ISSN: 0022-3131
DOI: 10.3327/jnst.42.153