Reactor Dosimetry

List 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 K1C -HSST Experiments at the ORR.- Use of Stainless Steel Flux Monitors in Pressure Vessel Surveillance.- Simultaneous Application of Activation and Damage Detectors.- The S32(n,p)P32 Threshold Detector and its Application for Fast Neutron Dosimetry (Fast Reactors and Fusion Reactors).- Puissance deposee dans un dispositif complexe par les gammas de reacteur d’essais. Experiences et calculs realises a siloe.- Solid-State Track Recorder Neutron Dosimetry in Light Water Reactor Pressure Vessel Surveillance Mockups.- A European Community Source of Reference Materials for Neutron Metrology Requirements.- Niobium-Aluminium Foils as Monitors for Routine Measurement of Fast Neutrons.- Recent Developments in Very High-Count-Rate Gamma Spectroscopy.- International Comparison of Interpolation Procedures for the Efficiency of Germanium Gamma-Ray Spectrometers (Interim Report on the GAM-83 Exercise).- V: Damage Models, Physics, Dosimetry and Materials.- Embrittlement Profile in the Fracture Plane of Irradiated CT100 Specimens.- The Effect of Damage Rates and Different Kinds of Irradiation on the Ductility of Amorphous Fe40 Ni40 B2O.- Defect Microstructure and Irradiation Strengthening in Fe/Cu Alloys and Cu Bearing Pressure Vessel Steels.- The Use of Silicon Transistors as Damage Monitors in Reactor Neutron Metrology.- VI: Neutron and Gamma Spectrum Determination.- Calculation of the 252Cf Neutron Slowing Down Spectrum and Reaction Rate Ratios in Moderating Media.- Experimental Validation of Neutron Spectra Calculated Via Transport Codes.- Neutron and Gamma Ray Flux Calculations for the Venus PWR Engineering Mockup.- Characterization of Fuel Distribution in the Three Mile Island Unit 2 (TMI-2) Reactor System By Neutron and Gamma-Ray Dosimetry.- A Study of the Embrittlement of Reactor Vessel Steel Supports.- Evaluation of Neutron Exposure Conditions for the Buffalo Reactor.- Recent Progress and Developments in LWR-PV Calculational Methodolgy.- A New Adjustment Code Based on the Bayes’ Theory Combined with the Monte-Carlo Technique.- Evaluation of Uncertainties of 235U Fission Spectrum.- Evaluation of Gamma-Heating Rates in the JMTR Core (Benchmark Calculation).- LSL-M1 and LSL-M2: Two Extensions of the LSL Adjustment Procedure for Including Multiple Spectrum Locations.- Systematic Study on Spectral Effects in the Adjustment Calculations Using the NEUPAC-83 Code.- Neutron Energy Spectrum Calculations in Three PWR.- On the Conversion of Coarse Group Spectra to Fine Group Spectra (Using a Continuity Principle).- Calculation of the Neutron Source Distribution in the Venus PWR Mockup Experiment.- New Aspects in Least Squares Adjustment Methods.- Plans for a Real-84 Exercise.- VII: Benchmarks, Reference and Standard Spectra.- A Comparative Analysis of the Oak Ridge PCA and NESDIP PCA ‘Replica’ Experiments Using the London Adjustment Technique.- The Nessus Reference Field in the Nestor Reactor at Winfrith.- Comparisons of Theoretical and Experimental Neutron Spectra, 115In(n,n’) and Fission Rates, in the Centre of Three Spherical Natural Uranium and Iron Shell Configurations, Located at BR1.- Venus PWR Engineering Mock-Up: Core Qualification, Neutron and Gamma Field Characterization.- Evaluation of Neutron Flux in the Pool Critical Assembly.- The U.S. U-235 Fission Spectrum Standard Neutron Field Revisited.- Recent Experiments on Cf-252 Spectrum-Averaged Neutron Cross Sections.- Spectrum-Averaged Neutron Cross Sections Measured in the U-235 Fission-Neutron Field in MOL.- Unfolded Ano-1 Fluxes Using the Lepricon Methodology.- VIII: Nuclear Data.- Consistency Check of Iron and Sodium Cross- Sections with Integral Benchmark Experiments Using a Large Amount of Experimental Information.- Benchmark Experiment for Neutron Transport in Nickel.- Consistency of Cross-Section Data in Integral Experiments.- Cross Section Measurements in the 235U Fission Spectrum Neutron Field.- Spectrum-Integrated Helium Generation Cross Sections for 6Li and 10B in the Intermediate-Energy Standard Neutron Field.- IX: General Interest.- Boucle 4 Crayons Combustibles eau Legere Irradiee en Peripherie du Reacteur Osiris. Techniques de Dosimetrie Mises en Oeuvre.- Qualification Dans Melusine de Devolution Neutronique de Combustibles de la Filiere a eau Legere.- Comparison of Measured and Calculated Reaction Rates From D2o-Moderated 252cf Neutrons.- Dosimetry Work and Calculations in Connection with the Irradiation of Large Devices in the High Flux Materials Testing Reactor BR2: Fuel Burn-Up Aspects in Correlation with the Other Dosimetry Data.- Use of Threshold Activation Detectors to Obtain Neutron Kerma for Biological Irradiations.- Status of Recovery — Three Mile Island Unit 2: Reactor Head Removal.- On the Utilization of ?? — ITN Benchmark Field.- Neutron and Gamma Ray Dose Studies in CAGR Instrumentation and Fuel Components.- Developments in Health Physics Dosimetry.- Radiation Field Associated with Hiroshima and Nagasaki.- The Activity of the Czechoslovak Working Group on Reactor Dosimetry in the Period from 1980 to 1983.- Neutronic Modelling of the Harwell Mtr’s: Some Recent Problems.- A Comprehensive Approach to the Problems of Uncertainty Analysis in the Assessment of Irradiated Materials Performance.- X: Chairmen’s Reports on Workshops and Highlights of the Symposium.- Workshop: LWR-PV Physics, Dosimetry, Damage Correlation and Materials Problem.- Atelier: Physique, Dosimetrie et Problemes des Materiaux en Reacteurs Rapides.- Workshop: Low Threshold Reactions.- Workshop: Dosimetry for High-Energy Neutrons.- Workshop: Modelling of Small Reactor Cores.- Workshop: Interlaboratory Intercomparison.- Workshop: Adjustment Problems.- Annex 1: Report on the Meeting of the ASTM E.10.05.01 Task Group on “Uncertainty Analysis and Calculational Procedures”.- Annex 2: Report on the IAEA Consultants’ Meeting on the REAL-84 exercise.- Workshop: Gamma Dosimetry and Calorimetry.- Workshop: Damage Monitors.- Highlights of the Symposium.- Conference Programme Summary.- List of Chairmen.- List of Participants.- Authors’ Index.