2 edition of Investigation of some methods of failed-fuel-element detection in water cooled reactors. found in the catalog.
Investigation of some methods of failed-fuel-element detection in water cooled reactors.
Written in English
|Series||Doktorsavhandlingar vid Chalmers tekniska högskola,, nr. 75|
|LC Classifications||TK9180 .S76|
|The Physical Object|
|Pagination||(1), 24 p.|
|Number of Pages||24|
|LC Control Number||76480177|
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Improvements were made to the methods used to calculate the resonance escape probability in heavy water moderated, clustered rod, UO/sub 2/ fueled reactors. A preliminary analog computer investigation of the externally controlled CVTR system was completed.
REACTOR PRIMARY COOLANT SYSTEM RUPTURE STUDY. Quarterly Progress Report No. 18, July--September Failed MTR fuel element detect in a Sipping tests. the average leaking rate R of Cs from the failed fuel element to water was determined by. The book is a complete, clear and up-to. Sipping tests on a failed irradiated MTR fuel element.
the average leaking rate R of Cs from the failed fuel element to water was determined by. The book is a complete, clear and up-to. Container List Series 1: Physical Reports, Add to Shelf This series contains physical reports for which no digital files could be located.
Box-Folder A Wide-Band Square-Law Circuit Element, by A. Soltes, document AFCRC-TR, January, Add to Shelf Box-Folder On the Quantitative Characterization of Low Pressure Centers, by M. McCutchan and R. Bryson, document. Paks Nuclear Power Plant (NPP) plays an important role in energy supply of the country.
The plant has four Pressurised Water Reactors of the Soviet VVER/ type, the first of which was commissioned inwhile the fourth in The rated electric performance of each unit is MW. Some abbreviations or short forms (such as names for code subroutines) are too specialized to be listed in the AML; other short forms may be too well known to need to be included here.
Even though an aronym may be included in this list (for example, an office or a program name), CIC-1 cannot guarantee that it is still accurate or in use. For some reactors (e.g. critical In the event of the detection of fuel failure, an investigation shall be conducted to identify the failed fuel element.
Authorized limits shall not be exceeded In the design of water cooled reactors particular attention shall be paid to preventing the uncovering of the core. IAEA-TECDOC Fuel failure in normal operation of water reactors: experience, mechanisms and management Proceedings of a Technical Committee Meeting held in Dimitrovgrad, Russian Federation, May INTERNATIONAL ATOMIC ENERGY AGENCY.
June The IAEA does not normally maintain stocks of reports in this series. However, microfiche copies of these reports can be. Fast breeder reactor protection system. DOEpatents.
van Erp, J.B. Reactor protection is provided for a liquid-metal-fast breeder reactor core by measuring the coolant outflow temperature from each of the subassemblies of the core. The outputs of the temperature sensors from a subassembly region of the core containing a plurality of subassemblies are combined in a logic circuit.
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