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Neef, H.J.
Kernforschungsanlage Juelich G.m.b.H. (F.R. Germany)1976
Kernforschungsanlage Juelich G.m.b.H. (F.R. Germany)1976
AbstractAbstract
[en] The patent claims apply to the reflector wall of a pebble-bed reactor. The graphite of the reflector wall is doped with neutron-absorbing materials except in that part of the wall through which the absorber rods are led and which encloses the absorber rods. These materials are doped over the thickness of the reflector wall in such a way that esup(- Σaxd) <= 10-3, where Σa is the mean macroscopic cross section. (UA)
[de]
Gegenstand des Patentanspruchs ist die Reflektorwandung eines Kugelhaufenreaktors. Der Graphit der Reflektorwandung ist mit Ausnahme des Teils der Wandung, den die Absorberstaebe druchdringen und der die Absorberstaebe umgreift, mit neutronenabsorbierenden Stoffen dotiert. Diese Stoffe sind so ueber die Dicke d der Wandung des Reflektors dotiert, dass esup(- Σaxd) <= 10-3 ist, wobei Σa der gemittelte makroskopische Wirkungsquerschnitt ist. (UA)Original Title
Kernreaktor
Primary Subject
Source
29 Jul 1976; 4 p; DE PATENT DOCUMENT 2365531/B/; 1 fig.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Neef, H.J.
Kernforschungsanlage Juelich G.m.b.H. (F.R. Germany)1975
Kernforschungsanlage Juelich G.m.b.H. (F.R. Germany)1975
AbstractAbstract
[en] The insertion depth of the absorber rods of a pebble-bed reactor with graphite reflector shielding is reduced without increasing the number of absorber rods. For this, the parts of the reflectors not in contact with the absorber rods are doped with neutron poison in order to achieve the reduction of reactivity desired for control and shutdown. The doping, e.g. of the bottom reflector and parts of the side reflector with absorber rods inserted from above, is done with boron. It follows the relation esup(-Σad) <= 10-3, where d is the thickness of the reflector walls and Σa, the averaged macroscopic cross-section for neutron absorption. This arrangement also enables a reduction of the neutron flux in reactor parts inaccessible to the absorber rods. (RW/AK)
[de]
Die Endringtiefe der Absorberstaebe eines Kugelhaufenreactors mit Reflektorabschirmung aus Graphit wird verringert, ohne deren Anzahl zu erhoehen. Hierzu werden zur Verminderung der Reaktivitaet, die zur Regelung und Abschaltung notwendig ist, die Teile des Reflektors mit Neutronengiften dotiert, welche von den Absorberstaeben nicht ueberstrichen werden. Die Dotierung, z.B. des Bodenreflektors und Teilen des Seitenreflektors bei von oben eingefahrenen Absorberstaeben, erfolgt mit Bor. Sie gehorcht jedoch der Beziehung esup(-Σad) <= 10-3, wobei d die Dicke der Wandung des Reflektors und Σa der gemittselte makrokopische Wirkungsquerschnitt der Neutronenabsorption ist. Hiermit kann auch der Neutronenfluss in Teilen des Reaktors abgesenkt werden, die nicht von den Absorberstaeben erreichbar sind. (RW)Original Title
Kernreaktor
Primary Subject
Source
31 Jul 1975; 9 p; DE PATENT DOCUMENT 2365531/A/; 1 fig.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Neef, H.J.
Kernforschungsanlage Juelich G.m.b.H. (F.R. Germany). Inst. fuer Reaktorentwicklung; Technische Hochschule Aachen (F.R. Germany)1973
Kernforschungsanlage Juelich G.m.b.H. (F.R. Germany). Inst. fuer Reaktorentwicklung; Technische Hochschule Aachen (F.R. Germany)1973
AbstractAbstract
No abstract available
Original Title
Berechnung der Wirksamkeit von Absorberstaeben in Hochtemperaturreaktoren unter Verwendung transporttheoretisch bestimmter Randbedingungen mit einem dreidimensionalen Diffusionsprogramm
Primary Subject
Source
Jul 1973; 94 p; With figs.; tabs.; 30 refs. With abstract in German and English.; Diss.
Record Type
Report
Literature Type
Thesis/Dissertation
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Neef, H.J.
Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.)1977
Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.)1977
AbstractAbstract
[en] If a graphite reflector of a pebble bed reactor is equipped with insertable absorber rods power control is achieved by less insertion depth of these rods than would be required for conventional designs for the same type of reactor. Therefore the difficulties growing with insertion depth and the danger of damaging fuel elements are reduced. With less stroke, the drives of the control rods are simplified, too. A means for this is doping the graphitic reflector bottom and the lower part of the reflector with neutron-absorbing material. A partial flow of neutrons forced downwards on insertion of the control rods into the upper zone of the reflector will be absorbed in this lower region. A formula is given for this doping. (HP)
[de]
Die Ausruestung des Graphitreflektors eines Kugelhaufenreaktors erfordert bei der Leistungssteuerung mittels einzufahrender Absorberstaebe geringere Eintauchtiefen dieser Staebe als herkoemmliche Konstruktionen fuer den gleichen Reaktortyp. Damit werden die, mit der Eintauchtiefe wachsenden Schwierigkeiten und die Gefahr der Beschaedigung von Brennelementen verringert. Auch die Antriebe werden bei geringerem Hub der Steuerstaebe vereinfacht. Mittel hierzu ist die Dotierung des graphitischen Reflektorbodens und des unteren Teils des Reflektors mit neutronenabsorbierenden Stoffen. Ein Teilfluss von Neutronen, der beim Einfahren der Steuerstaebe im oberen Reflektorbereich nach unten abgedraengt wird, dann in diesem unteren Bereich absorbiert. Fuer diese Dotierung ist ein Formelwert genannt. (HP)Original Title
Kernreaktor
Primary Subject
Source
17 Mar 1977; 3 p; DE PATENT DOCUMENT 2365531/C/; Also available from Dt. Patentamt, Muenchen (FRG); 1 fig.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Scherer, W.; Neef, H.J.
Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.). Inst. fuer Reaktorentwicklung1976
Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.). Inst. fuer Reaktorentwicklung1976
AbstractAbstract
[en] The representation of control rod regions in reactor calculations requires a combination of transport and diffusion theory calculations. A method is described which produces equivalent cross sections for a rodded region. These cross sections used in a diffusion theory calcualtion yield the same rod efficiency and reaction rate distribution as the transport theory calculation for the explicit heterogeneous control rod. The description of the method is complemented by sample problems. (orig.)
[de]
Die Darstellung von Absorberstabgebieten in Reaktorberechnungen erfordert eine Kombination von Diffusions- und Transporttheorie. Es wird eine Methode beschrieben, mit der aequivalente Wirkungsquerschnitte fuer ein Stabgebiet bestimmt werden koennen. Mit diesen Querschnitten erhaelt man dieselbe Stabwirksamkeit und dieselben Reaktionsratenverteilungen sowohl in der Diffusionsrechnung als auch in der Transportrechnung fuer den heterogenen Kontrollstab. Die Beschreibung der Methode wird durch Beispiele vervollstaendigt. (orig.)Primary Subject
Source
Jul 1976; 24 p; 7 figs.; 2 tabs.; 10 refs.
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Wagemann, R.; Wahl, D.; Neef, H.J.
Arbeitsgemeinschaft Versuchs-Reaktor AVR GmbH (Germany)1971
Arbeitsgemeinschaft Versuchs-Reaktor AVR GmbH (Germany)1971
AbstractAbstract
[en] Automatic translation: The task of the present study is to show in a detailed manner taking into account more precise data and methods - under the present conditions (that is: maintaining the core and Reflector geometry, as well as the current shutdown rod system) to find the optimal low-enriched core and through a Analysis of the associated reactivity balance and the feasibility of the above operating condition for a virgin examine low-enriched core.
[de]
Aufgabe der vorliegenden Studie ist es, in detaillierter Weise unter Berücksichtigung genauerer Daten und Methoden ein - unter den vorliegenden Bedingungen (das ist: Beibehaltung der Core und Reflektorgeometrie, sowie des derzeitigen Abschaltstabsystems) optimales niedrig angereichertes Core zu finden und durch eine Analyse der zugehbrigen Reaktivitatsbilanz die Realisierbarkeit des oben angeführten Betriebszustandes für ein jungfräuliches niedrig angereichertes Core zu untersuchen.Original Title
Nukleare Versuchsanlage - AVR: Erstcore mit niedrig angereichertem Uran
Primary Subject
Source
1971; 64 p; Country of input: International Atomic Energy Agency (IAEA); Document from Juelich Preservation Project; 29 refs., 13 figs., 23 tabs.
Record Type
Report
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Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Hansen, U.; Neef, H.J.; Waterson, R.H.
Central Electricity Generating Board, Berkeley (UK). Berkeley Nuclear Labs.1976
Central Electricity Generating Board, Berkeley (UK). Berkeley Nuclear Labs.1976
AbstractAbstract
[en] An analysis of the HITREX 1 reactor experiment has been jointly performed by the DRAGON project/KFA and the CEGB, Berkeley, applying methods and codes currently in use within these organisations. The different methods are described and the results of the analyses are compared with each other and with experiment. Although in general the various methods give comparable results, there are two areas of significant discrepancy. First, the thermalisation data in the DRAGON codes is shown to be inadequate, so that the Pu/U fission ratio is over-estimated by some 3%, and secondly, there are differences of about 2 or 3% in the 238U absorption rates. From existing analyses, it is not possible to conclude which method gives the best overall representation of the resonance events. Concerning thermal reaction rate distribution, it is concluded that for an accuracy of about +- 1% it is necessary to perform a reactor spectrum calculation in many groups before condensation. The 32-group WIMS model achieves this, but the XSDRN/CITATION 10-group model does not. The DRAGON/KFA power reactor method predicts reaction rates in the core to within a few per cent. All methods grossly under-estimate the gradient of fast neutron flux at the core/reflector interface. (author)
Primary Subject
Secondary Subject
Source
Jun 1976; 82p
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Report
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INIS IssueINIS Issue
AbstractAbstract
[en] It is by now fairly widely known that the high temperature reactor (HTR) is a unique nuclear energy source which can supply heat at temperatures up to 10000C for application in chemical processes, for which previously exclusively conbustion heat sources have been used. With the HTR, it is possible to apply nuclear energy not only for electrical power production but also for the synthesis of liquid or gaseous energy carrier. Nuclear coal gasification appears most promising as the first step for the demonstration and industrial application of nuclear process heat technology in the Federal Republic of Germany. Reactor manufacturers and coal mining companies in co-operation with the Nuclear Research Center established a joint project in 1975 for the development of an HTR with a coolant outlet temperature of 950C, for the development and testing of nuclear coal gasification, for the detailed engineering of a prototype plant consisting of an HTR and gasification plant and finally for the construction and operation of this prototype plant for nuclear process heat (PNP). The authors describe the status of the PNP-project and the scope for future development. (Auth.)
Primary Subject
Secondary Subject
Record Type
Journal Article
Journal
Nuclear Engineering and Design; ISSN 0029-5493;
; v. 54(2); p. 157-174

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AbstractAbstract
No abstract available
Primary Subject
Source
European nuclear conference; Paris, France; 21 Apr 1975; Published in summary form only.
Record Type
Journal Article
Literature Type
Conference
Journal
Transactions of the American Nuclear Society; v. 20 p. 416-418
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Regelstabwirksamkeit in Hochtemperaturreaktoren
Primary Subject
Secondary Subject
Source
1973; 7 p; Experts meeting on the present state and requirements of the prediction of physical parameters for thermal and fast power reactors; Juelich, F.R. Germany; 23 Jan 1973; 4 figs.; 3 refs.
Record Type
Report
Literature Type
Conference
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