Filters
Results 1 - 10 of 3262
Results 1 - 10 of 3262.
Search took: 0.028 seconds
Sort by: date | relevance |
Presser, W.; Charzewski, C. von.
Hochtemperatur-Reaktorbau G.m.b.H., Dortmund (Germany, F.R.)1985
Hochtemperatur-Reaktorbau G.m.b.H., Dortmund (Germany, F.R.)1985
AbstractAbstract
[en] The service life of the absorber rods is extended by 1) exchanging the absorber rods used for controlling the output for absorber rods in the end position, depending on the irradiation dose absorbed, 2) by driving the absorber rods used for controlling the output to the same depth in the fuel element pebble bed, for temporary fast shutdown of the reactor, 3) by inserting all absorber rods into the fuel element pebble bed for long term shutdown. (orig./HP)
[de]
Die Standzeit der Absorberstaebe wird dadurch verlaengert, dass 1) je nach der aufgenommenen Bestrahlungsdosis die fuer das Regeln der Leistung eingesetzten Absorberstaebe gegen gleichgestaltete, in der Endstellung befindliche Absorberstaebe ausgetauscht werden, 2) dass fuer das voruebergehende Schnellabschalten die fuer das Regeln der Leistung eingesetzten Absorberstaebe auf gleiche vorgegebene Tiefe in die Brennelementschuettung eingefahren werden und 3) dass zum Langzeitabschalten saemtliche Absorberstaebe in die Brennelementschuettung eingebracht werden. (orig./HP)Original Title
Verfahren zum Regeln und Abschalten eines gasgekuehlten Hochtemperaturreaktors mit einer Schuettung kugelfoermiger Brennelemente
Primary Subject
Secondary Subject
Source
10 Jan 1985; 19 Dec 1980; 6 p; DE PATENT DOCUMENT 3047961/C/; ?: 19 Dec 1980
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Minnick, L.E.
Electric Power Research Inst., Palo Alto, CA (USA); Deutsches Patentamt, Muenchen (Germany, F.R.)1978
Electric Power Research Inst., Palo Alto, CA (USA); Deutsches Patentamt, Muenchen (Germany, F.R.)1978
AbstractAbstract
[en] The fast shutdown effect is based on an intervention into the operative connection between control rod and control rod drive mechanism. During operation of the LMFBR the coolant sodium is developing sufficient differential pressure on the separating plate and on the seal of the control rod to press the rod against the separating plate and to keep it above the neutron high-flux region of the core. If the flow rate of the coolant is reduced (accident, leak or rupture in the primary loop, earthquake) or the control rod is moved laterally the differential pressure on the separating plate decrases. The control rod drops because of gravity. A scramwill follow. (DG)
[de]
Die Schnellstoppwirkung beruht auf einem Eingriff auf die Wirkungsverbindung zwischen Steuerstab und Steuerstabsantriebsvorrichtung. Im Betrieb des LMFBR entwickelt das Na-Kuehlmittel eine hinreichende Druckdifferenz an der Trennplatte und an der Dichtung des Steuerstabes, um diesen gegen die Trennplatte zu druecken und oberhalb des Neutronen-Hochfluss-Bereiches des Kerns zu halten. Wenn der Durchfluss des Kuehlmittels vermindert (Stoerfall, Leck oder Bruch in der Primaerleitung, Erdbeben) oder der Steuerstab seitlich bewegt wird, nimmt die Druckdifferenz an der Trennplatte ab. Der Steuerstab faellt aufgrund der Schwerkraft. Es erfolgt der Schnellstopp. (DG)Original Title
Schnellstoppeinrichtung fuer einen Nuklear-Reaktor
Primary Subject
Secondary Subject
Source
3 Aug 1978; 27 p; DE PATENT DOCUMENT 2801005/A/
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Zacharias, T.; Leyer, S.; Herbst, V.; Uhrig, S.; Wagner, T.; Pasler, D.; Wich, M.
Proceedings of ICAPP 20112011
Proceedings of ICAPP 20112011
AbstractAbstract
[en] KERENA is a medium capacity boiling water reactor. The SCRAM system of KERENA is based on the concept of German BWR power plants where the energy for the fast hydraulic control rod insertion is provided via pressure vessels. In contrast to the existing SCRAM systems, where nitrogen is used to provide the pressure as driving force, for KERENA electrically heated water/steam tanks will be used. The advantage of this design is, that in case of a scram, non-condensable gases are prevented from entering the RPV. Therefore negative impact on the heat transfer capacity of the Emergency Condenser (passive safety system for residual heat removal from the RPV) is avoided. Another difference compared to existing systems is that the two ring manifolds (ring lines) are not connected. Each ring line is supported by three scram vessels and each vessel can insert 50 % of the control rods at the required time. To avoid thermal loads in the piping system and the control rod drives hot water should not reach the piping system. So, the steady state temperature profile and the amount of cold water which is available is of special interest. In order to stop the leakage mass flow into the RPV as soon as possible after a scram a pressure suppression system is installed in the KERENA scram vessels. To study the temperature profile in the scram vessel as well as the pressure reduction 1:1 scaling tests were carried out. Beyond that, the operating behavior, e.g. how long does it take to reach steady state conditions, how long does it take to bring the vessel back into operational conditions can be analyzed as well. (authors)
Primary Subject
Source
Societe Francaise d'Energie Nucleaire - SFEN, 5 rue des Morillons, 75015 Paris (France); 2851 p; 2011; p. 1816-1821; ICAPP 2011 - Performance and Flexibility: The Power of Innovation; Nice (France); 2-5 May 2011; 1 ref.; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Minimization of safety rod actuator operating time is studied. The rods are held out of the core by electromagnets and springs are used to insert them in. An optimal relationship is derived between start-up time of the holding electromagnets and motion time of safety rods. Two basic variants of safety rod motion are considered: in a gaseous and liquid medium. Minimum operating time of the actuator is found to occur if the start-up time of the electromagnets equals half the motion time of the safety rods
Original Title
Optimal'noe sootnoshenie mezhdu sostavlyayushchimi vremeni srabatyvaniya privoda avarijnoj zashchity
Primary Subject
Source
For English translation see the journal Sov. At. Energy.
Record Type
Journal Article
Journal
Atomnaya Ehnergiya; v. 42(4); p. 259-262
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Therond, J.-P.
CEA, 75 - Paris (France)1974
CEA, 75 - Paris (France)1974
AbstractAbstract
[en] The control process described is for a protection system, particularly of a nuclear reactor, according to which, as from N measurements of one or several physical values measurements are processed by N adaptation members and/or calculations. The median value is selected of the N signals corresponding to N determinations, and the median value is compared with a reference value so that this comparison initiates the triggering off of the desired protective action. This process can be used to carry out the emergency shutdown of a nuclear reactor by dropping safety absorbers into the core
[fr]
On presente un procede de comande d'un systeme de protection, en particulier d'un reacteur nucleaire, selon lequel, a partir de N mesures d'une meme ou de plusieurs grandeurs physiques on traite des mesures par N organes d'adaptation et/ou de calcul. On selectionne la valeur mediane des N signaux correspondant aux N mesures, et on compare la valeur de la mediane a une valeur de reference afin que cette comparaison initie le declenchement de l'action de protection recherchee. Ce procede peut etre utilise pour assurer l'arret d'urgence d'un reacteur nucleaire par la chute d'adsorbants de securite dans le coeurOriginal Title
Procede et dispositif electronique de commande a securite positive
Primary Subject
Source
11 Dec 1974; 20 p; FR PATENT DOCUMENT 2294473/A/; Available from Institut National de la Propriete Industrielle, Paris (France)
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Bevilacqua, F.
Combustion Engineering, Inc., New York (USA)1978
Combustion Engineering, Inc., New York (USA)1978
AbstractAbstract
[en] The method of operating the linear drive devices to increase reliability to scram involves first raising and holding the control elements using the drive means and first holding means for each of the linear drive devices. Then, for a first portion of the linear drive devices, the control elements associated therewith are further raised, the second holding means actuated, and the first holding means de-actuated to place the control elements in engagement with the second holding means of the portion of linear drive devices. De-actuation and disengagement of the first holding means of the first portion of linear drive devices is then detected to ensure that the first holding means will not interfere with the release of the control elements by the second holding means to scram the control elements into the nuclear core. The linear drive devices of the present invention comprise a magnetic jack type drive having a second type of holding means which is operative to engage and hold the control element drive extension in a fully withdrawn position with respect to the nuclear core
Primary Subject
Source
11 Apr 1978; 25 p; CA PATENT DOCUMENT 1029478/A/; Available from Commissioner of Patents, Ottawa-Hull, Canada K1A 0E1
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
American Nuclear Society annual meeting; Las Vegas, NV, USA; 8 - 13 Jun 1980; CONF-800607--; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; ISSN 0003-018X;
; v. 34 p. 324-325

Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Wilson, J.N.; Besant, R.W.; Barclay, F.W.; Frey, J.R.
Atomic Energy of Canada Ltd., Ottawa, Ontario1974
Atomic Energy of Canada Ltd., Ottawa, Ontario1974
AbstractAbstract
No abstract available
Primary Subject
Source
1 Oct 1974; 20 p; CA PATENT DOCUMENT 955694; Available from Commissioner of Patents, Ottawa; Filed 10 Oct 1972. 12 claims, 6 figs. Available from Commissioner of Patents, Ottawa.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A vertical control rod includes an absorber formed of flexible members and suspended by a traction device below the reactor core during operation of the reactor and a tensional spring for drawing the absorber into the reactor core to shut off the reactor. The control rod is operable independently of gravity and avoids jamming of the absorber in the guide
Original Title
Patent
Primary Subject
Source
13 Jan 1976; 6 p; US PATENT DOCUMENT 3,932,215
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Secondary Subject
Source
Transactions of the American Nuclear Society 1976 international meeting; Washington, DC, USA; 14 Nov 1976; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 24 p. 339-340
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |