Reactor Dosimetry

The Table of Contents for the full book PDF is as follows:

• Foreword
• Organisation of the 9th International Symposium on Reactor Dosimetry
• REACTOR PRESSURE VESSEL SURVEILLANCE AND PLANT LIFE MANAGEMENT
  • Significance of Reactor Dosimetry for Reactor Safety
  • Evaluation of RPV Steel Surveillance Program in Japanese PWR: Radiation Embrittlement, Prediction
  • Verification of Neutron Fluence on VVER-440/230 Vessel of Unit 1 at Kozloduy NPP
  • Neutron Dosimetry in Extended Surveillance Program on the 4th Unit of NPP Dukovany
  • SIEMENS-KWU Experience in Evaluating Fluence Detectors Inside and Outside the RPV in German Light Water Reactor Plants
  • Atucha I Ex-Vessel Dosimetry
  • Reactor Dosimetry Aspects of the RPV Service Life Management at the PAKS NPP
  • Determination of Pressure Vessel Neutron Fluence Spectra for a Low Leakage Rovno-3 Reactor Core Using Three Dimensional Monte Carlo Neutron Transport Calculations and Ex-vessel Neutron Activation Data
• TECHNIQUES
  • Thermal and Intermediate Neutron Spectrum Determination by Cd-Ratio Measurements with Activation Foils
  • Measurement of Low Energy Neutron Spectrum below 10 keV Inside Various Bulk Media with the Slowing Down Time Method
  • Measurements of Neutron Spectra at KUCA by Multiple Foil Activation
  • MoLLY-G Environment Behind CdO-Polyethylene Shielding
  • Gamma-Ray Spectrometry in Mixed Radiation Fields Using Stilbene Scintillator
  • The Experimental and Calculational Investigation of Radiation Fields in the SM High Flux Research Reactor
  • Establishment of New Irradiation Facilities at the Portuguese Research Reactor
  • The Materials Dosimetry Reference Facility Round Robin Tests of ²³⁷Np and ₂₃₈U Fissionable Dosimeters
  • Factors Affecting Use of Fission Foils as Dosimetry Sensors
  • A New Method for Fast Neutron Dosimetry with a Circulating Liquid
  • Helium Gas Measurements for Neutron Dosimetry
  • Measurement of In-Core Gamma-Ray Flux Distributions by Using Optical Fiber with Scintillator
  • Simple, Quick and Precise Measurement of In-Core Neutron Flux Distributions by Using Optical Fiber with Scintillator
  • New Optical Methods of Reactor Dosimetry
  • Doppler Effect Measurement up to 2000°C in the Fast Critical Facility FCA
  • Design and Applications of Dual-Range Solid State Track Recorders for Reactor Neutron Dosimetry
  • Measurements and Analyses of ²³⁸U Capture to ²³⁹Pu Fission Rate Ratio and ²³⁸U Capture ²³⁵U Fission Rate Ratio at Fast Critical Facility FCA
  • The Measurement of Photofission Contribution to Fission Detector Results in the MDRF
  • A Method for Neutron Dosimetry in Ultrahigh Flux Environments
  • Development of Prompt Self-Powered Neutron Detectors for Characterization of Mixed Radiation Fields in Reactors and for Instantaneous Determination of the Power in a Fuel During Fast Transients
  • Development of a Method for the Determination of Manganese-54 in Long-Cooled Active Steel Samples
  • Measurement of Mass Attenuation Coefficient of ^92mNb and _93mNb X-Radiation in Metallic Niobium
  • Application of Neural Network to Neutron Dosimetry Using Activation Foils
  • A New Approach for Unfolding PHA Problems Based only on the Bayes’ Theorem
  • Simultaneous Neutron and Gamma Spectrum Adjustment
  • Simultaneous Adjustment of Cross Sections by Critical-Mass Measurements and Pulsed-Sphere Experiments
  • Improved Validation of Neutron Spectrum Shapes at Nuclear Fission Reactors
  • Development of an Adjustment Library for the Kernel-Based Preview Program
  • Experiences with the Module STAYNL of the Neutron Metrology File NMF-90
  • Influence of Input Neutron Spectrum Covariances on Results of Pressure Vessel Neutron Spectrum Adjustments
  • Current Status and Upgrading Activity of Reactor Material Dosimetry in the Experimental Fast Reactor “JOYO”
  • Radioactive Air Effluent Emission Measurements at Two Research Reactors
  • Supplementary Investigation of the Calculated and Measured Gas Formation in Beryllium Samples Irradiated in the High Flux Materials Testing Reactor BR2
  • Investigation of LVR-15 Neutron Spectral Characterisation; Measurements and Calculations Comparison
  • Reactor Dosimetry for Irradiation Experiments Performed at the LVR-15 Research Reactor
  • International Neutron Metrology in the LVR-15 Research Reactor
  • ORPHEE Research Reactor Surveillance Dosimetry
  • Damage Energy Cross Sections of Charged Particles from Light Nuclides Irradiated with High Energy Neutrons
  • Analysis of Integral Experiment on Beryllium Slab with LANL and ENDF/B-VI Evaluations
  • Nuclear Heating Experiments for the Validation of the Fusion Reactor Shielding Performance
  • Calculation of Transmutations with Complex Error Monitoring on the Basis of Block-Triangular Matrix Presentation of Differential Equation System
  • Investigation of Neutron and Gamma-Ray Spectra in a Blanket Mock-up of the International Thermonuclear Experimental Reactor (ITER)
• BENCHMARKS
  • Comparison of Calculated and Experimental Dosimetry Activities for Bechmark Neutron Fields
  • Sensitivity Analysis of Leakage Spectra from Iron Spheres
  • Experimental and Theoretical Studies on VVER-1000 Reactor Dosimetry
  • Experimental and Calculation Characterization of the Irradiation Facility KORPUS (Preliminary Results)
  • Interlaboratory VVER-1000 Ex-Vessel Experiment at Balakovo-3 NPP
  • WINES: Water Inelastic Neutron Scattering Experimental Study
• NUCLEAR DATA
  • Status of PKA, KERMA and DPA Files of JENDL
  • Revision of JENDL Dosimetry File
  • Measurements of Activation Cross Sections for the Neutron Dosimetry at an Energy Range from 17.5 to 30 MeV by Using the ⁷Li(p,n) Quasi-mono-Energetic Neutron Source
  • Influence of the Iron Multigroup Neutron Cross Section Libraries on the VVER Vessel Neutron Flux Evaluation
  • Status of Russian Dosimetry File
• DAMAGE CORRELATION AND EXPOSURE PARAMETERS
  • Consistent Vessel Fluence and PTS Embrittlement Uncertainties
  • Oak Ridge National Laboratory Embrittlement Data Base (EDB) and Dosimetry Evaluation (DE) Program
  • The Role of Gamma Rays and Freely-Migrating Defects in Reactor Pressure Vessel Embrittlement
  • Experimental Evaluation of the DPA Cross Section of Silicon by Making Use of Four Neutron Fields with Different Energy Spectra
  • Neutron Spectrum Effect and Damage Analysis of Pressure Vessel Steels Irradiations
  • Review of the Status of Reactor Vessel Embrittlement Prediction
  • Dosimetry in Support of the European Network AMES
• CHARACTERISATION OF ENVIRONMENTS (EXPERIMENTS AND CALCULATIONS)
  • Comparison of Three-Dimensional Neutron Flux Calculations for Maine Yankee
  • A Challenge to the International Reactor Dosimetry Community: Quantify Gamma-Ray Spectra
  • Gamma-Ray Leakage from a Critical Assembly
  • Benchmark of the Nuclear Heat Deposition in the NIST Liquid Hydrogen Cold Source
  • Validation of Neutron and Gamma-Ray Propagation Calculations Using DORT and a Coupled Transport Cross-Section Library on the NESDIP Experiment and PWR Cavity Benchmark Dosimetry
  • The Prediction of Fast and Thermal Neutron Dose Rates for the Pressure Vessels of Magnox Power Plants
• SURVEILLANCE, BENCHMARKS AND NUCLEAR DATA (APPLICATIONS)
  • Uncertainty of Silicon 1-MeV Damage Function
  • Calculations of Energy Partition for Neutron Induced Radiation Damage
  • Atomic Displacement Processes and Threshold Energies in Irradiated Alloys
  • Status of the NEANSC Subgroup Working on Improving the ¹⁰B(n,α) Standard Cross Sections
  • Fission Cross Section Measurements of Am-241 and Am-243 Between 0.1 eV and 10 keV with Lead Slowing-Down Spectrometer
  • Standardization of Neutron Energies at 2.413 MeV and 14.00 MeV
  • Systematic Evaluation of Fission Neutron Spectra for Heavy Nuclides
  • JENDL-3.1 and ENDF/B-VI Iron Validation on the (H₂O/Fe) PCA-Replica Shielding Benchmark
  • Generation of a Coupled n-γ Multi-Group Library from JEF2.2 and Application to Shielding Problems
  • Evaluation of the ²³⁷Np Fission Cross-Section in the Energy Range 100 keV – 20 MeV
  • Helium Production Neutron Cross Section Data Library
  • Study of the ⁹³Nb(n,n′)^93mNb Reaction in Fast Reactor Neutron Spectra
  • Benchmarking of YAEC Pressure Vessel Fluence Calculations on Maine Yankee
  • ²⁵²Cf Fission Neutron Transport Through an Iron Sphere
  • The Benchmark for the MCNP Gamma and Neutron Spectra Calculation in VVER Geometry
  • Neutron Streaming Environment at the White Sands Missile Range MoLLY-G Reactor Facility
  • High Speed Monte Carlo Codes for Neutron and Photon Transport Problems
  • New Directional Theta-Weighted (DTW) Differencing Scheme and Reduction of Estimated Pressure Vessel Fluence Uncertainty
  • Acceleration of Monte Carlo Reactor Cavity Dosimetry Calculations with the Discrete Ordinates Adjoint Function
  • Characterization of the Radiation Environment at the Army Pulse Radiation Facility with Monte Carlo
  • ASYNT – An Adjoint Synthesis Method for Neutron Irradiation Estimation on the Vessels of VVER/PWR Reactors
  • Calculations of a VVER-1000 Mockup with MCBEND
  • A Nondestructive Measuring Method for Assessment of Material Degradation in Aged Reactor Pressure Vessels
  • Evaluation of Surveillance Program in Tokyo Electric Power Co.’s BWRs
  • Systematic Evaluation of Surveillance Capsule Data
  • Surveillance Test and Integrity Evaluation of PWR Reactor Pressure Vessel in Japan Against Brittle Fracture
  • Overview of Results from Nuclear Power Plant Radiation and Temperature Monitoring with Equipment Lifetime™ Monitors and Contact Integrating Thermal Monitors
  • Intercomparison of LEPRICON (S_N) and TRIPOLI (MC) Calculated and Measured Neutron Reaction Rates in the Ex-Vessel Cavity of SLB1
  • Ex-Vessel Fast Neutron Fluence Monitoring at NPP Dukovany
  • Study of Core Loading Patterns to Reduce Neutron Irradiation Dose for PWR Reactor Vessels
  • Three-Dimensional Correlations of Fast Neutron Fluence and DPA Within the Reactor Pressure Vessel and the Material Surveillance Capsules
• DOSIMETRY FOR RFSEARCH REACTORS AND IRRADIATION EXPERIMENTS
  • Neutron Dosimetry for Material Irradiation Tests in JMTR
  • The Reaction Rate Distribution Measurements by the Foil Activation Method in the Prototype FBR MONJU
  • Use of the ⁹³Nb(n,n′)^93mNb Reaction for Dosimetry in the FFTF, EBRII, and HFIR Reactors
  • Fusion Dosimetry Based on Nuclear Heating Measurement with Microcalorimeters
  • Neutron Dosimetry of the BR2 Aluminium Vessel
• Summaries of Workshop Meetings
• Participants of the 9th International Symposium on Reactor Dosimetry
• Author Index