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Borkowski, J.
Keuring van Electrotechnische Materialen NV, Arnhem (Netherlands)1991
Keuring van Electrotechnische Materialen NV, Arnhem (Netherlands)1991
AbstractAbstract
[en] The subcooling in the downcomer of the reactor calculated by code TRAC-BF1 was not in agreement with the data measured in the reactor vessel at steady state conditions. The most important phenomenon, which influences the subcooling is steam-water separation by gravity above the chimney. The steady-state input model has been changed in several ways in order to investigate the effect on the subcooling. Some alterations have been definitively implemented in the model, not because they strongly influence the subcooling, but because they are physical more correct. The level tracking option was left off. The implementation in the input of a perfect steam separator model, located above the chimney, resulted in calculations with stable water height and subcooling data more consistent with the measured data. It is recommended to conduct additional test in the GKN reactor. The purpose will be comparing calculated results with measured data, such as downcomer subcooling and flow rate in order to improve the validity of the model. (author). 3 refs.; 3 figs.; 3 tabs
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28 Aug 1991; 19 p; PROJECT NR. 98010; Photocopies available from Library KEMA; P.O.Box 9035, 6800 ET Arnhem, The Netherlands; Prepared within the KEMA Collective Contract 'Generation'.
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Report
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AbstractAbstract
No abstract available
Original Title
Vorgehen bei der Konstruktion, Dimensionierung und Berechnung der Komponenten und Bauteile des Primaerkreises am Beispiel der Reaktoreinbauten fuer Hochtemperaturreaktoren
Primary Subject
Source
Kerntechnische Gesellschaft im Deutschen Atomforum e.V., Bonn (Germany, F.R.); p. 701-704; 1978; p. 701-704; ZAED; Eggenstein-Leopoldshafen, Germany, F.R; Reactor congress; Hannover, Germany, F.R; 4 - 7 Apr 1978; AED-CONF--78-006-172; 7 figs. Short communication only.
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Book
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Conference
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AbstractAbstract
[en] A method developed for the prediction of critical flow of subcooled and saturated water is compared to the Marviken full scale experiments and some other relevant data. It is shown that this method gives better agreement with the data than other methods. Besides that, the method is relatively simple to use since its equations give the flow in an explicit form. (author)
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Source
International Atomic Energy Agency, Vienna (Austria). Technical Committee on Thermal Reactor Safety Research; 320 p; Jul 1984; p. 207-215; Specialists' meeting on experimental and modelling aspects of small-break LOCA; Budapest (Hungary); 3-7 Oct 1983
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Report
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Conference
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Mori, Tsugio.
Toshiba Corp., Kawasaki, Kanagawa (Japan)1982
Toshiba Corp., Kawasaki, Kanagawa (Japan)1982
AbstractAbstract
[en] Purpose: To prevent cooling water in a pressure vessel from leaking upon dismantling or assembling work of a water-submerged motor for driving a pump. Constitution: Refrigeration pipes are disposed to a flow passage to a pump section and a water-submerged motor passing through the bottom wall of a reactor container and refrigerant is introduced through the refrigeration pipes to refrigerate the cooling water in the flow passage to thereby obtain water sealing effects. That is, a refrigerator is operated upon maintenance work and the refrigerant is cyclically supplied to the refrigeration pipes by opening valves. Then, the cooling water present around the refrigeration pipes is refrigerated to block the flow passage. Then, inspection or like other operation can be carried out by opening the motor case. (Aizawa, K.)
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Source
30 Apr 1982; 3 p; JP PATENT DOCUMENT 57-70496/A/; Available from JAPATIC. Also available from INPADOC
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Patent
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AbstractAbstract
[en] We present an efficient method for subrecoil cooling of neutral atoms by applying Raman cooling in two dimensions to a four-level tripod system. The atoms can be cooled simultaneously in two directions using only three laser beams. We describe the cooling process with a simple model showing that the momentum distribution can be rapidly narrowed to velocity spread down to 0.1vrec, corresponding to effective temperature equal to 0.01Trec. This method opens new possibilities for cooling of neutral atoms.
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(c) 2011 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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AbstractAbstract
[en] Tests were carried out at Westinghouse Canada Inc., Hamilton, Ontario, to measure impact forces and axial depressurization of initially subcooled water jets discharging into the atmosphere. The purpose of the tests was to provide data for model studies investigating the consequences of a hypothetical nuclear reactor primary coolant circuit rupture. Break openings of 25 mm, 76 mm and 102 mm were tested using simple convergent nozzles. Two targets were used: A 1 m diameter flat circular plate and a section of 57 mm diameter pipe with axis on the jet centreline and perpendicular to it. Further tests were conducted with a slender instrumented probe supported on the jet centreline to measure the depressurization of the 'free' jet. Test conditions included initial reservoir pressures up to 7 MPa and liquid subcooling to 60 K. The impingement plate test results with the 25 mm nozzle indicate that a thrust coefficient of from 1.3 to 1.4 is appropriate, except where surrounding structures restrict free expansion. For the latter case, thrust coefficients up to 4 were measured. Also there are indications that a subcooled core exists within the jet extending to an L/D of at least 1. (orig.)
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Source
3. international topical meeting on reactor thermal hydraulics; Newport, RI (USA); 15-18 Oct 1985; CONTRACT 19-30840-11
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Journal Article
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Brachet, Alain.
Electricite de France, 75 - Paris1981
Electricite de France, 75 - Paris1981
AbstractAbstract
[en] This invention concerns improvements to secondary coolant-systems for sodium cooled nuclear reactors. It further concerns a protective device for a free level mechanical pump which prevents any gas bubbles due to leaks of the working gas of the pump from entering the secondary system of the nuclear reactor
[fr]
Cette invention a pour objet des perfectionnements aux circuits caloporteurs secondaires pour reacteurs nucleaires refroidis par du sodium liquide. Elle concerne egalement un dispositif de protection d'une pompe mecanique a niveau libre qui permet d'eviter d'eventuelles remontees de bulles de gaz dues aux fuites de gaz fonctionelles de la pompe dans le circuit secondaire du reacteur nucleaireOriginal Title
Perfectionnements aux circuits caloporteurs secondaires pour un reacteur nucleaire du type refroidi par un metal liquide
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Source
31 Jul 1981; 8 p; FR PATENT DOCUMENT 2474744/A/; Available from Institut National de la Propriete Industrielle, Paris (France)
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Patent
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Werkema, Steve
Fermi National Accelerator Lab., Batavia, IL (United States). Funding organisation: US Department of Energy (United States)2002
Fermi National Accelerator Lab., Batavia, IL (United States). Funding organisation: US Department of Energy (United States)2002
AbstractAbstract
[en] Control of the RF frequency: (1) 'RF Freq Check' on P85 (E835 Baby Sitter) should be turned OFF. (2) The RF frequency should be adjusted so that it is in the notch of the 4-8 GHz momentum cooling pickup response. The RF frequency device to be controlled depends on which RF system is on. If ARF2 is on, the RF frequency device is A:RLLFS1. If ARF3 is on, the RF frequency device is A:RLLFS0. IMPORTANT NOTE: A:RLLFS0 and A:RLLFS1 have very different data base scaling (A:RLLFS0 is 4 bytes and A:RLLFS1 is 2 bytes). A:RLLFS0 can be safely knobbed with a mult factor of 1.0 (i.e. no multiplier is required). A:RLLFS1 requires a mult factor of 0.02 or smaller. The monitoring and adjustment of the RF frequency is accomplished by the following steps: (3) Set up SA1 so that it is connected to CP48-SCH (4-8 GHz momentum cooling pickup). Set the SA center frequency to a harmonic of the RF frequency. This is most easily accomplished by doing one of the following: (a) If ARF3 is on, send P41 file 22 to SA1. (b) If ARF2 is on, set A:RLLFS0 to the set value of A:RLLFS1 then send P41 file 22 to SA1. (4) SA1 can be viewed on CATV channel pbar 20. If the notch in the momentum cooling pickup response is not at the center frequecy of SA1 adjust the RF. (On the low energy ramp, 1 division on the SA1 display at 5.5 GHz corresponds to 2.3 Hz in revolution frequency). Once you've made an adjustment to the RF frequency you should reset the SA1 display according to step 3 above.
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Source
1 Jan 2002; 2 p; AC02-76CH03000; Available from http://lss.fnal.gov/cgi-bin/find_paper.pl?pbar-637.pdf; PURL: https://www.osti.gov/servlets/purl/984597-XlWpAs/; doi 10.2172/984597
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Report
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External URLExternal URL
Paiva, I.P.V.
Semi-annual report of Nuclear Technology and Development Center (CDTN) - July to December 19881989
Semi-annual report of Nuclear Technology and Development Center (CDTN) - July to December 19881989
AbstractAbstract
[en] The main activities developed during the year of 1988 are described. (E.G.)
[pt]
Descrevem-se as atividades desenvolvidas no periodo de 01.01.88 a 31.12.88 no programa de testes de componentes do CDTN. (E.G.)Original Title
Relatorio anual do programa testes de componentes - 1988
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Source
Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), Belo Horizonte, MG (Brazil); 353 p; 1989; p. 133-148; DETR--277-88
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Report
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Progress Report
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AbstractAbstract
[en] The design parameters for the ORNL proposed Heavy Ion Storage Ring for Atomic Physics (HISTRAP) are reviewed in a series of viewgraphs. Topics considered include beam cooling, space charge, ion sources, beam injection, beam extraction and vacuum systems. Beam optics are described and the present status of the HISTRAP proposal is summarized
Primary Subject
Source
Oak Ridge National Lab., TN (USA); p. E.1-E.51; Apr 1986; p. E.1-E.51; Workshop on atomic physics with stored cooled heavy ion beams; Oak Ridge, TN (USA); 13-15 Jan 1986; Available from NTIS, PC A19/MF A01; 1 as DE86010009
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Report
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