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Musick, C.R.
Combustion Engineering, Inc., New York (USA)1977
Combustion Engineering, Inc., New York (USA)1977
AbstractAbstract
[en] The invention is a method and apparatus for calculating and predicting the impending violation of a design limit if no corrective action is taken. Various mathematical indices can be devised, such as the departure from nucleate boiling ratio (DNBR), which indicate the proximity of the limiting conditions for the design limit in question, i.e., the occurrence of departure from nucleate boiling (DNB) and fuel clad overheating. A critical value of the index can be defined to be that value at which design limit violation occurs
Primary Subject
Source
11 Oct 1977; 92 p; CA PATENT DOCUMENT 1019078/A/; Available from Commissioner of Patents, Ottawa-Hull, Canada K1A 0E1
Record Type
Patent
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Tolubinskij, V.I.; Domashev, E.D.; Litoshenko, A.K.; Matorin, A.S.
Abstracts of papers and communications submitted to the 5. all-union heat and mass transfer conference1976
Abstracts of papers and communications submitted to the 5. all-union heat and mass transfer conference1976
AbstractAbstract
No abstract available
Original Title
Krizis teplootdachi pri kipenii v kontsentricheskikh i ehkstsentricheskikh kol'tsevykh shchelyakh
Primary Subject
Source
AN Belorusskoj SSR, Minsk. Inst. Teplo- i Massoobmena; p. 103; 1976; 5. all-union conference on heat and mass transfer; Minsk, Byelorussian SSR; 1975; Published in summary form only.
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Report
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AbstractAbstract
[en] Instability of the process of nucleus formation in metastable medium and model of essentially non-linear relaxation autooscillations arisinq in steep dependence of the rate of nucleus formation on temperature are investigated. Equation of heat balance with account of medium heating by an external source and heat absorption by growing nuclei as well as a kinetic equation for nucleus distribution function by dimensions with account of their continuous generation and removal from the system are used to describe the process of nucleus homogeneous generation. These equations are reduced to the single integrodifferential equation for relative superheating of medium having the only stationary solution. The mentioned solution is instable at certain values of parameters, and autooscillating regime is establnshed in the system. Characteristics of this regime are studied for the case when the dependence of the formation rate on superheating temperature is very steep and autooscillations have breaking character. Similar autooscillations can be stated undeK liquid cooling in metastable phase, i. e. under homogeneous crystallization
Original Title
K teorii udarnogo kipeniya
Primary Subject
Source
For English translation see the journal Journal of Engineering Physics (USA).
Record Type
Journal Article
Journal
Inzhenerno-Fizicheskij Zhurnal; ISSN 0021-0285;
; v. 47(6); p. 919-926

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Zhang, Rui; Cong, Tenglong; Tian, Wenxi; Qiu, Suizheng; Su, Guanghui, E-mail: ghsu@mail.xjtu.edu.cn2015
AbstractAbstract
[en] Highlights: •Improved RPI wall boiling model was used to study DNB phenomena. •DNB phenomena and CHF value were obtained by CFD method. •Maximum deviation between predicted and experimental CHF was less than 15.0%. •Mean absolute relative error of predicted CHF was 7.1%. -- Abstract: Two-fluid model coupled with improved RPI wall boiling model (CHF model) was employed to investigate the departure from nuclear boiling (DNB) phenomena in vertical pipes under extremely high heat flux by using FLUENT 14.5 code. The distributions of temperature before and after DNB and the critical heat fluxes (CHF) at corresponding DNB points were obtained. The maximum deviation of predicted CHFs with experimental data was less than 15.0%. The results proved that two-fluid model coupled with CHF model was qualified to predict CHF accurately. This work can be referred when one predicts CHF in complicated geometry by CFD methodology.
Original Title
Critical heat flux (CHF);Departure from nucleate boiling (DNB);Subcooled boiling;Critical heat flux model
Primary Subject
Source
S0149197014002650; Available from http://dx.doi.org/10.1016/j.pnucene.2014.10.001; Copyright © 2014 Elsevier Ltd. All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
Record Type
Journal Article
Journal
Progress in Nuclear Energy; ISSN 0149-1970;
; v. 78; p. 196-200

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AbstractAbstract
[en] The feasibility of implementing a post-DNB fuel design limit (FDL) for Condition II (moderate frequency) events is investigated. The FDL is defined, a comprehensive separate effects investigation is performed, and limits are specified for post-DNB operation. Limiting transients are evaluated using the FDL, and power benefits are determined. A research program required for implementation of the new FDL is formulated. Finally, recommendations are made regarding implementation of the post-DNB FDL in plant licensing
Primary Subject
Source
Aug 1981; 163 p; Available from NTIS., PC A08/MF A01
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Report
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AbstractAbstract
[en] In smooth heat transfer tubes, spirals are inserted in contact with the inner tube surface. The inserted spirals have a different pitch and cross section which is either circular, elliptic or polygonal. This equipment caused additional turbulence of the flowing steam-water mixture in the region of departure nucleate boiling and shifts the point of departure nucleate boiling towards the region of higher steam dryness where temperature pulsations on the tube wall are no longer dangerous. (J.P.)
Original Title
Zarizeni k intenzifikaci prestupu tepla v horizontalnich popripade naklonenych trubkach clankovych parnich generatoru
Primary Subject
Source
15 Jan 1979; 3 p; CS PATENT DOCUMENT 176513/B/
Record Type
Patent
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Groeneveld, D.C.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.1975
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.1975
AbstractAbstract
No abstract available
Primary Subject
Source
Mar 1975; 22 p
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Report
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Lykov, E.V.
Abstracts of papers and communications submitted to the 5. all-union heat and mass transfer conference1976
Abstracts of papers and communications submitted to the 5. all-union heat and mass transfer conference1976
AbstractAbstract
No abstract available
Original Title
Akusticheskie spektry v oblasti krizisa kipeniya zhidkostej
Primary Subject
Source
AN Belorusskoj SSR, Minsk. Inst. Teplo- i Massoobmena; p. 88; 1976; 5. all-union conference on heat and mass transfer; Minsk, Byelorussian SSR; 1975; Published in summary form only.
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Report
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Conference
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AbstractAbstract
No abstract available
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Source
Paper No. 74-WA/HT-41; 1974; 16 p; American Society of Mechanical Engineers; New York; Winter annual meeting of the American Society of Mechanical Engineers; New York, NY; 17 Nov 1974
Record Type
Book
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Conference
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Kamal, S.A.; Pai, D.H.; Chern, J.M.
Structural mechanics in reactor technology. Transactions. Vol. E1979
Structural mechanics in reactor technology. Transactions. Vol. E1979
AbstractAbstract
[en] In the DNB (Departure from Nucleate Boiling) region of steam generator evaporator, the heat transfer tubes are subjected to oscillating thermal condition with high frequency and the resulting high cycle fatigue damage in these tubes is usually evaluated on the basis of the alternating stress intensity and the mean stress intensity during the thermal cycle. Due to the three-dimensional nature of the thermal loading, a three-dimensional stress analysis is required to rigorously determine the stress intensity. However, in practical design, simplified stress analyses with proven validity are preferred because of the analytical complexity involved in the three-dimensional analysis. This paper presents a systematic numerical comparison of the simplified and three-dimensional analyses and recommends an appropriate simplified model for practical applications. (orig.)
Primary Subject
Secondary Subject
Source
Jaeger, T.A.; Boley, B.A. (eds.); Commission of the European Communities, Brussels (Belgium); Bundesanstalt fuer Materialpruefung, Berlin (Germany, F.R.); International Association for Structural Mechanics in Reactor Technology; p. E3/7 (1-8); ISBN 0444 85361 8;
; 1979; p. E3/7 (1-8); North-Holland Publishing Co; Amsterdam, Netherlands; 5. international conference on structural mechanics in reactor technology (SMIRT-5). 9. international seminar and 2. international seminar on structural reliability of mechanical components and subassemblies of nuclear power plants and 2. international seminar on containment of fast breeder reactors (CONFABRE-2); Berlin, Germany, F.R; 9 - 21 Aug 1979; INKA-CONF--79-321-162

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Book
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