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