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AbstractAbstract
[en] In order to assess the primary to secondary leakage, radioactive isotopes, formed in the primary coolant as a result of fission or neutron capture, are usually monitored in the pressurized water reactor (PWR) secondary coolant. Some years ago, it appeared necessary to improve both leak rate assessments and the steam generator tube rupture (SGTR) detection. Studies and tests were started with the following goals in mind: (1) to set up a highly sensitive, convenient, and reliable measuring channel to assess the leak rates continuously and accurately; (2) to enable an early detection of an SGTR from the hot shutdown state to full power; and (3) to check the steam volumetric activity. In a first step, French efforts focused on the monitoring of 16N activity within the secondary coolant, allowing the high-energy gamma rays to be detected through the steam pipe wall and predictability of the rate of 16N production. The total gamma dose rate due to 16N at the touch of the steam pipe is rather low. For this reason, EdF has developed and tested a spectrometric method. In a second step, it was decided to analyze the low-energy gamma spectrum with the same apparatus in order to meet the second and third requirements. These gamma rays are emitted by noble gas fission products, which are assumed to be still present in the primary coolant while the reactor is in a hot shutdown state
Primary Subject
Source
American Nuclear Society winter meeting; Los Angeles, CA (USA); 15-19 Nov 1987; CONF-8711195--
Record Type
Journal Article
Literature Type
Conference
Journal
Country of publication
ARGON ISOTOPES, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, BOILERS, COOLING SYSTEMS, DAYS LIVING RADIOISOTOPES, ENRICHED URANIUM REACTORS, EVEN-ODD NUCLEI, FAILURES, HOURS LIVING RADIOISOTOPES, HYDROGEN ISOTOPES, INTERMEDIATE MASS NUCLEI, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, LIGHT NUCLEI, MATERIALS, MEASURING INSTRUMENTS, MONITORING, NUCLEI, ODD-EVEN NUCLEI, POWER REACTORS, RADIATION DETECTORS, RADIOACTIVE MATERIALS, RADIOISOTOPES, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, SCINTILLATION COUNTERS, SHUTDOWN, SOLID SCINTILLATION DETECTORS, THERMAL REACTORS, VAPOR GENERATORS, WATER COOLED REACTORS, WATER MODERATED REACTORS, XENON ISOTOPES, YEARS LIVING RADIOISOTOPES
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AbstractAbstract
[en] The method of transit time measurements by cross-correlation of random signals, produced by a physical phenomenon transported by the fluid is described and analysed. Application to primary coolant flow rate of PWR reactors by cross correlation of gamma emission of nitrogen 16 is given, the accuracy is 2 per cent
[fr]
On decrit et on analyse: la methode de mesure du temps de transit par intercorrelation de signaux aleatoiresOriginal Title
Debitmetrie en conduite fermee par la mesure du temps de transit du fluide. 2. Partie: methode par intercorrelation
Primary Subject
Record Type
Journal Article
Journal
Bulletin d'Information du Bureau National de Metrologie; ISSN 0373-3815; ; (no.48); p. 35-47
Country of publication
Reference NumberReference Number
Related RecordRelated Record
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Dubail, A.; Champion, G.; Pailhes, A.
Electricite de France (EDF), 75 - Paris (France)1994
Electricite de France (EDF), 75 - Paris (France)1994
AbstractAbstract
[en] Two probes are placed inside the reactor containment to measure the concentration of nitrogen 13 in gas which is sampled respectively from the inside space under the casing on the reactor closure head and from free space inside the containment. Each probe consists of a measurement chamber isolated from the ambient radiation by shielding. A signal processing system, outside the containment, indicates the presence of leak and its flow rate. 5 figs
Original Title
Dispositif indicateur du debit d'une fuite d'un circuit primaire de reacteur nucleaire
Primary Subject
Source
14 Jan 1994; 10 Jul 1992; 21 p; FR PATENT DOCUMENT 2693551/A/; FR PATENT APPLICATION 9208596; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 10 Jul 1992
Record Type
Patent
Country of publication
BETA DECAY RADIOISOTOPES, BETA-PLUS DECAY RADIOISOTOPES, BUILDINGS, CONTAINMENT, COOLING SYSTEMS, ELECTRON CAPTURE RADIOISOTOPES, ENRICHED URANIUM REACTORS, ISOTOPES, LIGHT NUCLEI, MINUTES LIVING RADIOISOTOPES, NITROGEN ISOTOPES, NUCLEI, ODD-EVEN NUCLEI, POWER REACTORS, RADIOISOTOPES, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
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INIS IssueINIS Issue
AbstractAbstract
[en] In order to assess the primary to secondary leakage, radioactive isotopes, formed in the primary coolant as a result of fission or neutron capture, are usually monitored in the pressurized water reactor (PWR) secondary coolant. Conventional methods mainly based on the detection of 133Xe, tritium, and 41Ar are widely used on French Electricite de France (EdF) PWRs. Some years ago, it appeared necessary to improve both leak rate assessments and steam generator tube rupture (SGTR) detection. A volumetric activity measuring channel inside steam (VAMCIS) has been developed for this purpose. The SGTR that occurred at the North Anna PWR has focused the attention of safety authorities on this new measuring channel. It is planned to implement VAMCIS at North Anna in order to check the leak rate variations more accurately
Primary Subject
Secondary Subject
Source
Topical meeting on engineering for nuclear plant operation and maintenance; Myrtle Beach, SC (USA); 17-20 Apr 1988; CONF-880422--
Record Type
Journal Article
Literature Type
Conference
Journal
Country of publication
BOILERS, COOLING SYSTEMS, ENRICHED URANIUM REACTORS, FAILURES, MEASURING INSTRUMENTS, POWER REACTORS, RADIATION DETECTORS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, SCINTILLATION COUNTERS, SOLID SCINTILLATION DETECTORS, THERMAL REACTORS, VAPOR GENERATORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] This ionizing radiation particle counter used for measuring the leak rate between primary and secondary circuits of a steam generator has a detector delivering detection pulses, a reference source generating radiation of different energy, an amplitude discriminator counting the number of pulses and a controller adjusting the amplitude ranges and the amplitude of pulses generated by the reference source
[fr]
L'invention concerne un dispositif de comptage de particules d'un rayonnement ionisant. Le dispositif comprend des moyens de detection et une source de reference en amont des moyens de detection et delivrant un rayonnement de reference, dont le spectre est situe a l'exterieur du spectre du rayonnement ionisant a detecter. Des moyens de discrimination en amplitude et en energie du rayonnement ionisant recu et des moyens permettent le reglage de la position relative de niveaux d'amplitude Ci de l'echelle d'amplitude et de l'amplitude des impulsions engendrees par le rayonnement de reference. Application a la surveillance du debit de fuite entre circuits primaire et secondaire d'un generateur de vapeur de centrale nucleaireOriginal Title
Dispositif de comptage de particules d'un rayonnement ionisant et son utilisation pour la mise en oeuvre d'un procede de mesure de debit de fuite entre les circuits primaire et secondaire d'un generateur de vapeur
Primary Subject
Source
24 Jun 1988; 10 Jul 1986; 35 p; FR PATENT DOCUMENT 2608778/A/; FR PATENT APPLICATION 8610088; Available from Institut National de la Propriete Industrielle, Paris (France); Application date: 10 Jul 1986
Record Type
Patent
Country of publication
ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, AMERICIUM ISOTOPES, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, BOILERS, ELECTRONIC CIRCUITS, ENRICHED URANIUM REACTORS, EQUIPMENT, HEAVY NUCLEI, ISOTOPES, LIGHT NUCLEI, MEASURING INSTRUMENTS, MICROELECTRONIC CIRCUITS, NITROGEN ISOTOPES, NUCLEI, ODD-EVEN NUCLEI, ODD-ODD NUCLEI, POWER REACTORS, RADIOISOTOPES, REACTORS, SECONDS LIVING RADIOISOTOPES, THERMAL REACTORS, VAPOR GENERATORS, WATER COOLED REACTORS, WATER MODERATED REACTORS, YEARS LIVING RADIOISOTOPES
Reference NumberReference Number
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INIS IssueINIS Issue
AbstractAbstract
[en] Classical methods of flowrate measuring in closed pipes generally make use of indirect principles (for example: the measurements of the pressure loss through an orifice plate). Absolute or fundamental methods of the measurements of volume and time allow the ''in situ'' calibration and control of flowmeters in their nominal conditions of use. The method of transit-time measurements by fast injection of a radioactive tracer is described and analyzed
[fr]
Les methodes de mesure classiques du debit en conduite fermee font, en general, appel a des principes indirects (par exemple mesure de la perte de charge d'un organe deprimogene). Les methodes absolues ou fondamentales passant par la mesure du volume et du temps permettent l'etalonnage et le controle ''in situ'' de debitmetres dans leurs conditions nominales d'emploi. On decrit et on analyse: la methode de mesure du temps de transit par injection rapide d'un tracteur radioactifOriginal Title
Debitmetrie en conduite fermee par la mesure du temps de transit du fluide. Pt.1 Methode du temps de transit d'un traceur radioactif
Primary Subject
Record Type
Journal Article
Journal
Bulletin d'Information du Bureau National de Metrologie; ISSN 0373-3815; ; (no.47); p. 5-14
Country of publication
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AbstractAbstract
[en] The circuit which enables the turbine in an electrical power plant to function contains several types of heat exchanges. It is important to detect and trace leaks which may appear since they can have immediate negative effects for the correct operation of the power plant and because the corresponding defects can get worse and lead to ever more important incidents. The most performant methods used to detect leaks are based on the utilization of gaseous (helium) or radioactive (nitrogen 16) tracers, chemical tracers (cesium) and acoustic emission testing
[fr]
Le circuit qui permet de faire fonctionner la turbine des centrales electriques comporte plusieurs types d'echangeurs de chaleur. Il est important de detecter et de localiser les fuites qui peuvent y apparaitre, parce qu'elles ont des effets directement nefastes au bon fonctionnement de la centrale et parce que les defauts correspondants peuvent s'aggraver et donner lieu a des incidents plus graves. Les methodes de detection les plus performantes sont basees sur l'emploi de traceurs gazeux (helium), radioactifs (azote 16), chimiques (cesium) et de l'emission acoustiqueOriginal Title
Detection et localisation des fuites dans les echangeurs des centrales nucleaires
Primary Subject
Record Type
Journal Article
Journal
Epure; CODEN EPURE; (no.11); p. 29-43
Country of publication
ACOUSTIC TESTING, ALKALI METALS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, BOILERS, ELEMENTS, ENRICHED URANIUM REACTORS, EQUIPMENT, ISOTOPES, LIGHT NUCLEI, MATERIALS TESTING, METALS, NITROGEN ISOTOPES, NONDESTRUCTIVE TESTING, NONMETALS, NUCLEAR FACILITIES, NUCLEI, ODD-ODD NUCLEI, POWER PLANTS, POWER REACTORS, RADIOISOTOPES, RARE GASES, REACTORS, SECONDS LIVING RADIOISOTOPES, SEPARATION EQUIPMENT, TESTING, THERMAL POWER PLANTS, THERMAL REACTORS, VAPOR CONDENSERS, VAPOR GENERATORS, VAPOR SEPARATORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
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AbstractAbstract
[en] VAMCIS, an on-line steam generator monitoring system which enables very low leak rates (0.1 litre/h) to be continuously recorded is described. It has now been installed at a number of PWRs in France and around the world. (author)
Original Title
Steam generator monitoring in pressurized water reactors
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Record Type
Journal Article
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Champion, G.; Dubail, A.; Marsigne, C.; Le Dieu de Ville, A.; Vergnaud, T.
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1984
CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)1984
AbstractAbstract
[en] This paper describes a new method of measuring the gamma radiation energy spectrum and the associated dose equivalent rate under the vessel of a 900 MW PWR. The method is based on the use of thermoluminescent detectors (TLDs) placed under iron and neutron-absorbing material screens, overcoming the influence of neutrons. The spectral radiation breakdown is obtained by measuring the response of the TLDs for iron screens of different thicknesses. The thicknesses and types of neutron-absorbing materials have been determined on the bases of transport computations and preliminary tests. The problems posed by the practical implementation of this measurement system under the vessel and inside the pit of the vessel are also described. The measurement results that have become available demonstrate that gamma radiation under the vessel has a high energy level, resulting essentially from phenomena related to the diffusion or capture of neutrons
Primary Subject
Source
1984; 12 p; ANS topical meeting on reactor physics and shielding; Chicago, IL (USA); 17-19 Sep 1984
Record Type
Report
Literature Type
Conference
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AbstractAbstract
[en] The VAMCIS system has been jointly developed by Electricite de France (EdF) and the French manufacturer Merlin-Gerin Provence (MGP) for 4 yr. The continuous monitoring of the 16N activity within steam enables proper assessment of leak rates inside pressurized water reactor (PWR) steam generators (SGs). The VAMCIS system includes three main components: (1) sodium iodine sensor, coupled with its photomultiplier, (2) electrical cabinet, which provides the output signal spectral analysis, and (3) digital rate meters with software to transform the gross count rates into leak rate physical units. The paper discusses the implementation 1E-K3, and operational feedback. VAMCIS is now available in a large number of PWRs all over the world
Primary Subject
Secondary Subject
Source
Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit; San Francisco, CA (USA); 26-30 Nov 1989; CONF-891103--
Record Type
Journal Article
Literature Type
Conference
Journal
Country of publication
AGING, ALARM SYSTEMS, COMPUTER CODES, CONTROL ROOMS, FISSION PRODUCT RELEASE, IMPLEMENTATION, LEAKS, NAI DETECTORS, NITROGEN 16, ON-LINE MEASUREMENT SYSTEMS, PHOTOMULTIPLIERS, PWR TYPE REACTORS, REACTOR MONITORING SYSTEMS, REACTOR OPERATION, REACTOR SAFETY, RELIABILITY, RETROFITTING, RUPTURES, SEISMIC EFFECTS, STANDARDIZATION, STEAM, STEAM GENERATORS, TUBES
BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, BOILERS, ENRICHED URANIUM REACTORS, FAILURES, ISOTOPES, LIGHT NUCLEI, MEASURING INSTRUMENTS, NITROGEN ISOTOPES, NUCLEI, ODD-ODD NUCLEI, ON-LINE SYSTEMS, OPERATION, PHOTOTUBES, POWER REACTORS, RADIATION DETECTORS, RADIOISOTOPES, REACTORS, SAFETY, SCINTILLATION COUNTERS, SECONDS LIVING RADIOISOTOPES, SOLID SCINTILLATION DETECTORS, THERMAL REACTORS, VAPOR GENERATORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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