Reactor dosimetry : radiation metrology and assessment /
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| Imprint: | W. Conshohocken, PA : ASTM, 2001. |
|---|---|
| Description: | xxxvii, 858 p. : ill. ; 24 cm. |
| Language: | English |
| Subject: | |
| Format: | Print Book |
| URL for this record: | http://pi.lib.uchicago.edu/1001/cat/bib/4753427 |
Table of Contents:
- In Memoriam
- Overview
- History
- Workshop Summaries
- Summary of Workshop Meetings
- Keynote Addresses
- Why Do We Need Dosimetry?
- ASTM Standards for Reactor Dosimetry and Pressure Vessel Surveillance
- Developments in Reactor Dosimetry in Japan
- Dosimetry for Power Reactor Surveillance
- French PWR Vessel Surveillance Program Dosimetry: Experience Feedback from More than a Hundred Capsules
- Reactor Pressure Vessel Neutron Dosimetry Assessments for UK PWR Plant
- Assessment of Neutron Fluence Uncertainty and its Impact on Safety Issues
- Review of Problems and Requirements in VVER Reactor-Type Pressure Vessel Dosimetry
- Overview of the Surveillance Dosimetry Activities in Ukraine
- Improved Evaluation of the Atucha-I Ex-Vessel Dosimetry
- Reactor Dosimetry in the Surveillance Program of Kozloduy NPP Reactor Pressure Vessels
- Evaluation of the Reactor Dosimetry Results Obtained During the First Ten Years of the RPV Surveillance Program at the NPP Paks
- Neutron Dosimetry for VVER Reactor Pressure Vessels in the Czech Republic
- Analysis of Pressure Vessel Surveillance Dosimetry Inserted into Korean PWR
- Integrity Assessment for Aging Reactor Vessel of Japan's First Generation PWR Plants
- Measurement of Neutron Flux Distribution for Decommissioning in Tokai Power Station
- Impact of the ENDF/B-VI Cross Sections on the RPV Fluence Determination
- Factors Affecting Predicted Neutron Dose Rates to Steel Pressure Vessels of Magnox Plant
- The Attenuation of Neutron Dose Rates through the Steel Pressure Vessels of Magnox Power Plants
- Assessment of Activation of Concrete Wall for Decommissioning of Nuclear Power Plants
- Use of SSTRs and a Multi-Component Shield Assembly to Measure Radiation Penetrating the Reactor Biological Shield in the Presence of Radiation Streaming from Other Sources
- Dosimetry for Test Reactors and Accelerator Sources
- Spectral Unfolding of Mixed Proton/Neutron Fluences in the LANSCE Irradiation Environment
- Neutron Beam Characterization at the Finnish BNCT Facility--Measurements and Calculations
- Establishment of Fe-Filtered Neutron Beam Facility and Measurement of the Filtered Neutrons
- Design and Characterization of a Facility for Fast Neutron Irradiation of Semiconductors at Penn State
- Comprehensive Nuclear Fuel Dosimetry Program in the OSIRIS Reactor
- Dosimetry of a GeV Proton-Driven Spallation Neutron Field by the Activation Method
- The Irradiation Characteristics of the KUR Heavy Water Facility--Neutron Energy Spectra for Several Irradiation Modes
- Radiation Dosimetry at the BNL High Flux Beam Reactor and Medical Research Reactor
- Measurement of Neutron Spectrum at HANARO
- Combining Measurements and 3D Neutron Transport Calculations--A Powerful Tool in Detailed Neutron Dosimetry and Damage Analysis
- Characterization of Neutron Field for Stainless Steel Irradiation Experiments in JMTR
- Assessment of the Fission Power Level in Fuel Rods Irradiated in the High Flux Materials Testing Reactor BR2 with the Aid of Fluence Dosimetry and Comparison with Other Methods
- Local Changes of a Neutron Spectrum in the Fast Reactor BOR-60 for Extension of Research Tasks
- Improvement of Reactor Dosimetry for Irradiation Tests in the Experimental Fast Reactor JOYO
- Estimation of Low Level Neutron Doses Based on Neutron Spectra in the Vicinity of a Nuclear Reactor
- Conceptual Neutronics Design of "Neutron Factory" as a Future Plan on Neutron Source in Kyoto University Research Reactor Institute (KURRI)
- Benchmarks and Intercomparisons
- Results from the NIST Round Robin Test of Fissionable Dosimeters in a Reactor Leakage Spectrum
- New NEA Benchmarks for Calculating Fast Neutron Fluence in the Rector Pressure Vessel
- Database for WWER-1000 Reactor Pressure Vessel IAEA Regional Project RER 4/017
- Balakovo-3 Ex-vessel Exercise: Intercomparison of Results
- Re-analysis of the Experimental Leakage Neutron Spectrum from a Silicon Spherical Shell with Incident 14 MeV Neutrons using Different and Modified Neutron Cross Section Libraries
- Monte Carlo Calculations of Neutron Fluence Spectra, Activation Measurements, Uncertainty Analysis and Spectrum Adjustment for the KORPUS Dosimetry Benchmark
- Actual and Potential Measurements of Fission-Rate Ratios in the NIST Iron Sphere
- Adjustment of the [superscript 235]U Fission Spectrum
- Analysis of the ORNL PCA Benchmark Using TORT and BUGLE-96
- Development of Calibration Fields of Intermediate Neutrons by Using Several Sources
- A Study on 14 MeV Neutron Beam Characteristics and its Applications
- Cross Sections and Nuclear Data
- Integral Assessment of the Revised JENDL Dosimetry File
- High Energy Neutron Activation Cross Sections
- SPALLDOS: New Neutron Metrology Cross-Section Library for Use at Spallation Neutron Sources
- Integral Testing of Spallation Cross Sections for Neutron Dosimetry at 113 and 256 MeV
- Production of a Dosimetry Cross Section Set Up to 50 MeV
- Neutron and Non-neutron Nuclear Data for Radiation Dosimetry
- New Measurements of the H(n,n)H Angular Distribution
- Fission Cross Section Measurements of Th-229 and Pa-231 Using Linac-Driven Lead Slowing-Down Spectrometer
- Measurement of Differential Neutron-Induced Charged-Particle Emission Cross Sections for 5-75 MeV Neutrons
- Fast Neutron Yields Generated from Deuteron Break-up in Low Energy Reactions of Light Nuclei
- Measurement of the Neutron Capture Cross-sections for Dy and Hf between 0.001 eV and 50 keV Using Total Energy Absorption Detector
- Calculations and Adjustment Methods
- Modeling of BWR for Neutron and Gamma Fields Using PENTRAN
- Activity Determination with High Precision for Component Disposal
- PV-Surveillance Dosimetry and Adjustment: Review of Several Significant Oral Laws
- Physically Constrained Adjustment of Calculated Neutron Spectra for Dosimetry and Vessel Locations
- Algorithm and Computer Code of Group Neutron Spectra Transformation
- Improved Covariance Analysis and Spectrum Adjustment for VVER-1000 Pressure Vessel Fluences
- A Parametrized Approach for Unfolding the Neutron Flux Spectrum
- Accuracy and Parallel Performance of PENTRAN Using the VENUS-3 Benchmark Experiment
- Three Dimensional Neutron Analysis in the Baffle-Former Area of PWR Plant
- MCBEND-A Fluence Modeling Tool
- Performance of A[superscript 3]MCNP for Calculation of 3-D Neutron Flux Distribution in a BWR Core Shroud
- Development of 3D MCNP-Based BWR Fluence Computational Software Package: MF3D
- BWR Neutron Fluence Computations using MF3D
- Development of Induced Activity Estimation Method for PWR Containment
- Damage Correlations and Damage Dosimetry
- Comparative Analysis of DPA Processed from Current Evaluated Nuclear Data Libraries
- JENDL PKA/KERMA File for IFMIF Project
- A Study of Displacement Cross Section in Medium-Energy Region
- Radiation Hardening in BWR Core Shrouds: Relative Roles of Neutron and Gamma Irradiation
- Correlating Radiation Exposure with Embrittlement: Comparative Studies of Electron- and Neutron-Irradiated Pressure Vessel Alloys
- The PKA Energy Spectrum Analysis of Defect Structures in Neutron Irradiated Metals
- A Comparison of the NRT Displacement Model and Primary Damage Formation Observed in Molecular Dynamics Cascade Simulations
- Fusion Neutron Irradiation Effects on Some Electronic Devices
- Projects AMES Dosimetry and MADAM. Results and Future Activities
- U.S. NRC Embrittlement Data Base (EDB)[superscript 2]
- Experimental Techniques
- Measurement of Eigenvalue Separation in Coupled-Core Systems Using Optical Fiber with Scintillator
- Selective and Prompt Self-Powered Neutron Detectors for Characterization of Mixed Radiation Fields in Reactors
- Neutron and Gamma Ray Dosimetry in Spent-Fuel Radiation Environments Using Silicon Carbide Semiconductor Radiation Detectors
- Retrospective Fast Neutron Dosimetry of Nuclear Power Plants by Means of Scraping Samples Using the [superscript 93]Nb(n,n')[superscript 93m]Nb Reaction
- A Novel Neutron Spectrometer with Response of Wide Energy Range
- Characterization and Representation of the HPGE Detector Efficiency
- Accreditation and Certification in Radioactivity Measurement: Experience of the CEA/Reactor Dosimetry Laboratory
- A Laser Compton-Scattered Photon Source for Potential Calibration of Gamma-Ray Detectors in the Energy Range from 2 to 22 MeV
- Stilbene Neutron Spectrometer with Spreading of a One Parameter Pulse Shape Discrimination Dynamic Range
- Use of Reaction [superscript 93]Nb(n,n')[superscript 93m]Nb to Determine Neutron Spectra at Outer PV Surface of WWER-1000 Reactor
- Experimental Method of Neutron Spectra Determination with Activation Foils
- Qualifying C8/F9 Spectrum Index Measurements by Using Standard Neutron Fields
- Metal Discs as Very Low Thermal Neutron Flux Monitors in Reactor Environment
- Development of a Neutron and Gamma-Ray Flux Distribution Measurement System with Scintillator and Optical Fiber Combination
- Real-Time Dosimetry Method Using an Imaging Plate
- Application of Accumulative Type ESR-Sensors for Determination of Intensity, Spectral Characteristics and Volume Distribution of Intense Gamma and Neutron Fields
- Neutron Dosimetry Using Diallyl Phthalate Resin
- Development of In-Core Monitoring System using Optical Fiber for Advanced Fission Reactor
- Development and Modeling of Neutron Detectors for In-Core Measurement Requirements in Nuclear Reactors
- Reduction of Inter-Event Dead Time in Data Acquisition System Simultaneous Measurement of Neutron Pulse Series in Time and Space
- A System Design for Measuring Boron Concentration in PLWR Cooling Water
- Appendixes
- Appendix I. Symposium Organization
- Appendix II. Attendees of Tenth International Symposium on Reactor Dosimetry
- Author Index
- Subject Index
