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Smith, R.D.; Regazzoni, Pierre.
Electricite de France, 75 - Paris1981
Electricite de France, 75 - Paris1981
AbstractAbstract
[en] This invention concerns a gamma ray thermometer for nuclear reactors, fitted with a thermal bridge for use as a centring device. In accordance with the invention, an elastic device fills all the annular space between the gamma thermometer and the orifice through which the thermometer is introduced. This elastic device has the two-fold role of providing a thermal bridge at the gamma thermometer location suitable as a heat well, and of acting as a device for centring the thermometer in the orifice into which it has been introduced
[fr]
La presente invention a pour objet un thermometre a rayons gamma pour reacteurs nucleaires, muni d'un pont thermique servant d'element de centrage. Conformement a l'invention, un moyen elastique occupe tout l'espace annulaire compris entre le thermometre gamma et l'alesage dans lequel on a introduit ce thermometre. Ce moyen elastique a le double role d'assurer un pont thermique a l'endroit du thermometre gamma qui convient comme puits de chaleur, et de constituer un element de centrage du thermometre dans l'alesage ou on l'a introduitOriginal Title
Installation thermometrique a rayons gamma pour reacteurs nucleaires
Source
2 Jan 1981; 16 p; FR PATENT DOCUMENT 2458877/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 13 Jun 1979, US.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Smith, R.D.
Electricite de France, 75 - Paris1981
Electricite de France, 75 - Paris1981
AbstractAbstract
[en] This invention concerns the measurement of the level of the linear release of heat given off in a unit length of a nuclear reactor fuel rod. This linear release heat level varies with the point under consideration along the fuel rod, since the fission depends in part on the proximity of other radioactive sources. It is calculated as from the data provided by a series of gamma thermometers located in the reactor core
[fr]
La presente invention se rapporte a la mesure du taux de degagement lineaire de chaleur degagee dans une longueur unite d'une aiguille combustible de reacteur nucleaire. Ce taux de degagement lineaire de chaleur varie suivant le point considere le long de l'aiguille combustible, etant donne que la fission est en partie fonction de la proximite d'autres sources radioactives. Il est calcule a partir des donnees fournies par une serie de thermometres gamma disposee dans le coeur du reacteurOriginal Title
Dispositif de mesure de la chaleur degagee par une portion de longueur donnee d'aiguille combustible de reacteur nucleaire
Source
2 Jan 1981; 27 p; FR PATENT DOCUMENT 2458878/A/; Available from Institut National de la Propriete Industrielle, Paris (France); Priority claim: 13 Jun 1979, US.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Dayal, Yogeshwar; Culbertson, R.J.
General Electric Co., New York (USA)1974
General Electric Co., New York (USA)1974
AbstractAbstract
No abstract available
Source
17 Dec 1974; 15 p; CA PATENT DOCUMENT 959581; Available from Commissioner of Patents, Ottawa; Filed 4 Apr 1972. Priority USA 15 Apr 1971 (134,339). 5 claims, 9 figs. Available from Commissioner of Patents, Ottawa.
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Bierney, T.K.
Operation of instruments in adverse environments, 1976. Invited and contributed papers from the conference on the operation of instruments in adverse environments, held in London on 4 and 5 October 19761977
Operation of instruments in adverse environments, 1976. Invited and contributed papers from the conference on the operation of instruments in adverse environments, held in London on 4 and 5 October 19761977
AbstractAbstract
[en] The measurement of vibration and pressure (including acoustic levels) in hostile environments such as those found in generation of nuclear power presents many special problems. Transducers may be required to operate in environments composed of a combination of high temperature, high pressure, high acoustic levels, high radiation exposure and a corrosive atmosphere. These hostile environments can present a challenge to the transducer designer in terms of materials to be used and the mounting of the transducers. The challenge extends further as the transduced signal must be transmitted to monitoring equipment outside the hostile environment. The signal conditioning of transducers used at high temperature also requires careful design to obtain useful data. For example, conventional charge amplifiers may be unusable with transducers at high temperature due to the sensing element of the transducer undergoing severe changes in its characteristics. This paper will discuss the types of vibration transducer for a nuclear reactor environment, the design of suitable piezoelectric transducers and the signal transmission and conditioning. (author)
Primary Subject
Source
Knight, J. (ed.); Institute of Physics, London (UK); Institute of Physics Conference Series; no. 34; p. 103-116; ISBN 0 85498 125 X; 
; 1977; p. 103-116; Institute of Physics; Bristol; Conference on the operation of instruments in adverse environments; London, UK; 4 - 5 Oct 1976
; 1977; p. 103-116; Institute of Physics; Bristol; Conference on the operation of instruments in adverse environments; London, UK; 4 - 5 Oct 1976
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Breuze, G.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Services d'Electronique1979
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Services d'Electronique1979
AbstractAbstract
[en] The description is given of a system of transmission by optical fibre opto-electronic links capable of carrying out many point by point transmissions of logical signals: between acquisition and protection processing units, between acquisition and protection processing units and the control room, between acquisition and protection processing units and logical safety units, and between logical safety units and control room. A short description is also given of an optical fibre signal transmission system constituting a new instrumentation for stabilising spectra coming from NaI (Tl) scintillation detectors. In addition to the remote control of the detectors such an instrumentation is capable of improving the stability performance of gamma ray cameras (a beam of monofibres is then necessary) as well as that of any detector placed in an inaccessible or hostile environment (fuel reprocessing plant, for example)
[fr]
On presente un systeme de transmission par liaisons optoelectroniques a fibres optiques capable d'assurer de nombreuses transmissions point a point de signaux logiques: entre unites d'acquisition et de traitement de protection (UATP), entre UATP et salle de controle, entre UATP et ULS (unites logiques de sauvegarde) et entre ULS et salle de controle. On presente, aussi rapidement, un dispositif de transmission de signaux par fibre optique constituant une nouvelle instrumentation destinee a la stabilisation de spectres issus de detecteurs a scintillation NaI (Tl). Outre le controle a distance des detecteurs une belle instrumentation est susceptible d'ameliorer les performances de stabilite des cameras a scintillation (un faisceau de monofibres est alors necessaire) ainsi que celles de tout detecteur place en milieu inaccessible ou hostile (usines de retraitement de combustibles, par exemple)Original Title
Applications des liaisons optiques a l'instrumentation de protection des centrales nucleaires et a la stabilisation des detecteurs a scintillation
Source
1979; 6 p; Electronic information meeting; Saclay, France; 15 - 17 May 1979
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Marmonier, Pierre; Moreau, Jean; Nervi, J.-C.
CEA, 75 - Paris (France)1976
CEA, 75 - Paris (France)1976
AbstractAbstract
[en] This invention concerns a neutron flux measuring device for liquid coolant reactors and particularly applies to fast power reactors, cooled by liquid sodium. It is essential to have facilities for permanently measuring the flux of neutrons emanating from the core, not only when the reactor starts up but also when working at full power. An improvement to the solutions already considered allows for a more accurate and more sensitive measurement of the neutron flux, even when the reactor is working at very low rates. To this effect, the device considered, comprising at least one neutron detection chamber placed under and outside the vessel and as close as possible to it, is characterised in that it includes at least a neutron guide, composed of two separate superposed components. The first, top component includes a case open at the top, having an external profile identical to that of all the core assemblies and resting through its lower part on a bearing surface of a supporting prop on the diagrid in which penetrates a foot centrally extending the case. The second, bottom component, in which the foot of the first engages coaxially, is fixed inside the supporting prop and includes a closed tube filled with an inert gas, extending past the diagrid to near the internal surface of the bottom of the vessel. The first component contains a neutron emitting medium extending at least over its major part above the mid plane of the core
[fr]
La presente invention est relative a un dispositif de mesure du flux neutronique pour reacteur nucleaire a refrigerant liquide et s'applique plus particulierement dans le cas des reacteurs de puissance a neutrons rapides, refroidis par circulation de sodium fondu. Il est indispensable de disposer de moyens permettant de mesurer en permanence le flux des neutrons issus du coeur, aussi bien lors du demarrage du reacteur que lors d'un fonctionnement en puissance. Un perfectionnement aux solutions deja envisagees permet une mesure plus precise et plus sensible du flux de neutrons, meme pour des regimes de fonctionnement tres reduits du reacteur. A cet effet, le dispositif considere, comprenant au moins une chambre de detection des neutrons placee sous la cuve a l'exterieur et au plus pres de celle-ci, se caracterise en ce qu'il comporte au moins un guide de neutrons, constitue de deux elements separables superposes. Le premier element, superieur, comporte un boitier ouvert en partie haute, presentant un profil externe identique a celui de tous les assemblages du coeur et reposant en partie basse sur une portee d'appui d'une chandelle de support portee par le sommier dans laquelle penetre un pied prolongeant axialement le boitier. Le second element inferieur, dans lequel s'engage coaxialement le pied du premier, est fixe a l'interieur de la chandelle de support et comporte un tube ferme rempli d'un gaz inerte, se prolongeant au-dela du sommier jusqu'au voisinage de la surface interne du fond de la cuve. Le premier element contient un milieu emissif de neutrons s'etendant au moins sur sa majeure partie au-dessus du plan median du coeurOriginal Title
Dispositif de mesure de flux neutronique pour reacteur nucleaire; liquid sodium cooled reactors
Primary Subject
Source
21 Sep 1976; vp; FR PATENT DOCUMENT 2365186/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
AbstractAbstract
[en] Nuclear instrumentation equipment was purchased for the reactor control room and reactor facility
Primary Subject
Source
10 Sep 1990; 1 p; FG02-90ER12976; Available from Paper copy available at OSTI: phone, 865-576-8401, or email, reports@adonis.osti.gov
Record Type
Miscellaneous
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Equipment for measuring especially pressure temperature and power in nuclear fuels by means of a mechanical vibrating system. Stimulation and detection of oscillation is included, the resonance frequency of the system depends on the value of the above described physical dimensions. (J.K.)
Original Title
Messvorrichtung in Kernreaktoren
Primary Subject
Source
15 Jul 1980; 8 p; AT PATENT DOCUMENT 361093/B/; Available from the Oesterreichisches Patentamt, Kohlmarkt 8-10, A-1010 Vienna, Austria
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Primary Subject
Source
14 Aug 1973; 12 p; US PATENT DOCUMENT 3,752,735
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Patent
Primary Subject
Source
16 Oct 1973; 4 p; US PATENT DOCUMENT 3,766,005
Record Type
Patent
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
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