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    Reactor Dosimetry: Radiation Metrology and Assessment

    Williams JG, Vehar DW, Ruddy FH, Gilliam DM
    Published: 2001

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    One hundred papers provide an extensive overview of latest advances in reactor dosimetry. An additional nine summaries provide the status of technical workshops held at the Tenth International Symposium on Reactor Dosimetry and three keynote papers address: why we need dosimetry; the role of ASTM Committee E10 on Nuclear Technology, and reactor dosimetry activities in Japan. The 100 papers span seven areas including:

    Power Reactor Surveillance includes 17 papers on reactor vessel surveillance for pressurized water reactors (PWRs) in France, United Kingdom, Korea, Japan and the United States; for VVERs in Russia, Czech Republic, Ukraine, Bulgaria and Hungry; for heavy water reactor in Argentina; and for MAGNOX reactors in the United Kingdom. Three papers also address concrete structures outside reactor vessels

    Test Reactors and Accelerator Sources addresses facilities for such applications as boron neutron capture therapy (BNCT), semiconductor testing, structural steel testing, and nuclear fuel testing in a variety of types of reactor and accelerator neutron sources.

    Benchmarks and Intercomparisons contains 11 papers on experiments and analysis used to test and improve techniques and data by means of standards and calibrations and specially designed reference fields.

    Cross Sections and Nuclear Data provides 11 papers on cross section measurements and evaluations; and compilation and testing of cross section libraries.

    Calculations and Adjustment Methods includes 14 articles, half on neutron transport codes for modeling LWR vessels and internal structures. Remaining papers address computational methods for estimation of induced activity in ex-vessel components and neutron spectrum adjustment methods.

    Damage Correlations and Damage Dosimetry discusses calculation of displacements-per-atom, kerma, and atomic-recoil energy spectra, and data libraries derived for these.

    Experimental Techniques are discussed in 21 papers. Half address active detector techniques, including spectrometers and instruments for in-core monitoring and the remaining discuss passive irradiation monitoring, including activation monitoring methods.

    Table of Contents

    Why Do We Need Dosimetry?

    ASTM Standards for Reactor Dosimetry and Pressure Vessel Surveillance

    Developments in Reactor Dosimetry in Japan

    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

    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 Change 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)

    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 Reactor 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 235U 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

    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

    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 A3MCNP™ 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

    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)

    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 93Nb(n,n')93mNb 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 93Nb(n, n')93mNb 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 for Simultaneous Measurement of Neutron Pulse Series in Time and Space

    A System Design for Measuring Boron Concentration in Pressurized Light Water Reactor Cooling Water


    Author Index

    Subject Index

    Committee: E10

    DOI: 10.1520/STP1398-EB

    ISBN-EB: 978-0-8031-5450-6

    ISBN-13: 978-0-8031-2884-2