Reactor Dosimetry

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Volume 1 Volume 2 Dosimetry Methods for Fuels, Cladding and Structural Materials Proceedings of the Fifth ASTM-Euratom Symposium on Reactor Dosimetry, GKSS Research Centre, Geesthacht, F.R.G., September 24-28,1984, 2 Bde

ISBN: 940108873X
ISBN 13: 9789401088732
Herausgeber: J P Genthon/Heinz Röttger
Verlag: Springer Verlag GmbH
Umfang: xxi, 1043 S.
Erscheinungsdatum: 22.07.2014
Auflage: 1/2014
Produktform: Kartoniert
Einband: Kartoniert

InhaltsangabeList of Contents.- I: LWR-PV Surveillance.- Amelioration de la Surveillance de la Cuve D’un Reacteur a eau Pressurisee de la S.E.N.A.- Pressure Vessel Dosimetry at U.S. PWR Plants.- Improvement of LWR Pressure Vessel Steel Embrittlement Surveillance: 1982-1983 Progress Report on Belgian Activities in Cooperation with the USNRC and Other R&D Programs.- Utility Perspectives Related to Pressure Vessel and Support Structure Surveillance.- Uncertainty Considerations in Development and Application of Charpy Trend Curve Formulas.- Babcock & Wilcox Reactor Vessel Surveillance Service Activities.- Notch Ductility and Tensile Strength Determinations for Reference Steels in PSF Simulated Surveillance and Through-Wall Irradiation Capsules.- Transport Calculation of Neutron Flux and Spectrum in Surveillance Capsules and Pressure Vessel of a PWR.- Calculated Spectral Fluences and Dosimeter Activities for the Metallurgical Blind Test Irradiations at the ORR-PSF.- Battelle’s Columbus Laboratories Reactor Vessel Surveillance Service Activities.- Trend Curve Exposure Parameter Data Development and Testing.- Effect of Thermal Power Averaging Method on the Determination of Neutron Fluence for LWR-PV Surveillance.- Dosimetry Measurements and Calculation of Fast Neutron Flux in the Reactor Cavity of a 3-Loop Pressurized Water Reactor.- Standardized Physics-Dosimetry for US Pressure Vessel Cavity Surveillance Programs.- Re-Evaluation of the Physics-Dosimetry from PWR and BWR Reactor Pressure Vessel Surveillance Programs.- ORNL Evaluation of the ORR-PSF Metallurgical Experiment and „Blind Test“.- Status of Regulatory Issues and Research in Light Water Reactor Surveillance Dosimetry in the U.S.- II: Fast Reactors.- Super Phenix. Surveillance des Structures Soumises a Irradiation Programme de Mesures et Calculs Neutroniques.- Fluence, Dosimetry, and Steel-DPA Rates in EBR-II.- Tritium Production From the 10B(n,t)2? Reaction in FFTF.- Recent Japanese Activities in the Fast Breeder Reactor Program and Reactor Dosimetry Works.- III: Fusion and Spallation.- Nickel Sample Irradiation in the BR2 Reactor at MOL in the Framework of the Optimization Study of the Time-Dependent Helium Production/Damage Ratio for In-Pile Fusion Materials Testing.- Reference Spectrum of d(13)-Be at the INPE Cyclotron.- Recent Developments in Neutron Dosimetry and Damage Calculations for Fusion Materials Irradiations.- Materials Irradiation Testing in Support of the European Fusion Programme.- Investigation of the Neutron Energy Transfer by Nuclear Cascade Reactions for Improving Neutron Damage Data Up to 40 MeV.- Removal Cross-Section Technique for Kerma Estimation of 14 MeV Neutrons Passed Through Shielding Layers.- The Importance of Anisotropic Scattering in High Energy Neutron Transport Problems.- Fusion Materials Research and Neutron Activation.- Delayed Neutron Counting System for Jet Plasma Neutron Yields Diagnostics.- IV: Techniques.- Use of Niobium for Accurate Relative Fast Neutron Fluence Measurements at the Pressure Vessel in a VVER-440 NPP.- Niobium Neutron Fluence Dosimeter Measurements.- Calculation of the Thermal Neutron Flux Perturbation Factor for Foil Detectors in Various Media Using the Code Perturb.D.- Nondestructive Determination of Reactor Pressure Vessel Neutron Exposure by Continuous Gamma-Ray Spectrometry.- Advances in Continuous Gamma-Ray Spectrometry and Applications.- The Use of Beryllium Oxide Thermoluminescence Dosemeters for Measuring Gamma Exposure Rates.- Fast Neutron Dosimetry by Means of the Scraping Sampling Method.- Mesure des Debits de Dose Dtrradiation Ionisante en Atmosphere Surchauffee.- Special Considerations for LWR Neutron Dosimetry Experiments.- Characterization of the Imperial College Reference Gamma Ray Field.- Improved Microcalorimetry for Radiation Absorbed Dose Measurements.- Application of the Multi-Component Wire Activation Detector System for In-Core Neutron Spectrometry at a NPS.- Data Acquisition and Control System for the K

Artikelnummer: 7053030 Kategorie:

Beschreibung

Ouverts a I'ensemble de la communaute internationale, les symposia ASTM-EURATOM sur la dosimetrie des rayonnements de reilcteur traitent de tous les sujets de dosimetrie dans tous les systemes a neutron: dosimetrie des experiences en reacteur, codes d'ajustement, precision, etalons et intercomparaison, donnees nucleaires, techniques de mesure, correlation de dommages radio-induits, echauffement nucleaire, etc. appliques principalement aujourd'hui aux problemes des reacteurs a eau legere, des reacteurs a neutrons rapides et aux systemes a fusion. Les travaux en dosimetrie, tout comme I'ensemble du domaine de I'energie atomique, sont moins caracterises aujourd'hui par des idees scientifiques franchement nouvelles que par la necessite d'echange, de cooperation, de collaboration, appliques a la satisfaction de besoins de type industriel ou quasi-industriel. L'organisation de nos symposia a suivi cette evolution.Nombre de ceux qui y ont participe ont un souvenir emu du ler symposium a Petten en 1975, qui fut une reussite complete.L'organisation et Ie devouement du CCR de Petten y avait beaucoup contribue. Et puis, aussi, c'etait un commencement, c'etait Ie premier de nos symposia. Les symposia suivants, alternativement aux USA et en EUROPE, a rythme sensiblement bi-annuel, ont du faire face progressivement a un besoin plus grand d'echange et de discussion par petits groupes, ainsi qu'a afflux croissant de propositions de communications de valeur. L'organisation a du s'adapter en consequence. Ce 5eme sy~posium ASTM­ EURATOM represente, de part sa belle reussite, une etape importante de cette evolution et un garant de la maturation correspondante.

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