You are being redirected because this document is part of your ASTM Compass® subscription.
    This document is part of your ASTM Compass® subscription.

    STP1550

    Reactor Dosimetry: 14th International Symposium

    Vehar David, Selby Douglas, Sparks Mary
    Published: 2012


      Format Pages Price  
    PDF (53M) $174   ADD TO CART
    Hardcopy (shipping and handling) $174   ADD TO CART
    Hardcopy + PDF Bundle - Save 25%
    (shipping and handling)
    $261.00   ADD TO CART


    Fifty-seven peer-reviewed papers provide an extensive examination of timely topics in the field of Reactor Dosimetry. Also, two keynote papers address: the energy future and structural materials for innovative nuclear systems.

    Topics cover:
    • Reactor surveillance and plant life
    • Nuclear data, uncertainties, and sensitivity studies
    • Reactor surveillance and retrospective dosimetry
    • Benchmarks and intercomparisons
    • Research/test reactor and accelerator dosimetry
    • Neutron and gamma-ray transport calculations and modelling
    • Experimental techniques, new developments, and optical methods


    Table of Contents

    Reactor Dosimetry and RPV Life Management

    Korean Standard Nuclear Plant Ex-Vessel Neutron Dosimetry Program Ulchin 4

    Dosimetry Assessments for the Reactor Pressure Vessel and Core Barrel in UK Pressurized Water Reactor (PWR) Plant

    Comparison of Attenuation Coefficients for VVER-440 and VVER-1000 Pressure Vessels

    Ringhals Unit 3 and 4—Fluence Determination in a Historic and Future Perspective

    Dosimetry Analyses of the Ringhals 3 and 4 Reactor Pressure Vessels

    Modernization of Existing VVER-1000 Surveillance Programs

    Exposure Conditions of Reactor Internals of Rovno VVER-440 Nuclear Power Plant Units 1 and 2

    2010 Review of Neutron and Non-Neutron Nuclear Data

    Path Forward for Dosimetry Cross Sections

    A New Technique for Dosimetry Reaction Cross-Section Evaluation

    New Work on Updating and Extending the Nuclear Data Standards

    Uncertainties of Responses Calculated with a “Tuned” Library: Geometrical and Algebraic Insights

    A New Formulation of the Unified Monte Carlo Approach (UMC-B) and Cross-Section Evaluation for the Dosimetry Reaction 55Mn(n,γ)56Mn

    Updating and Extending the IRDF-2002 Dosimetry Library

    Uncertainty-Accounted Calculational–Experimental Approach for Improved Conservative Evaluations of VVER RPV Radiation Loading Parameters

    Sensitivity of Adjustment to Parameter Correlations and to Response-Parameter Correlations

    Application of Different Nuclides in Retrospective Dosimetry

    Retrospective Dosimetry Analyses of Reactor Vessel Cladding Samples

    Neutron Flux Reduction Programs for Reactor Pressure Vessel of Korea Nuclear Unit 1

    A Three-Dimensional Methodology for the Assessment of Neutron Damage and Nuclear Energy Deposition in Graphite Components of Advanced Gas-Cooled Reactors

    Dosimetry of the Decommissioned High-Flux Beam Reactor at Brookhaven Lab

    The Current Status of the Shielding Integral Benchmark Archive and Database (SINBAD)

    VENUS-F: A First Fast Lead Critical Core for Benchmarking

    Benchmarking of Neutron Production of Heavy-Ion Transport Codes

    Neutron and Gamma Field Investigations in the VVER-1000 Mock-Up Concrete Shielding on the Reactor LR-0

    New Measurements and the Associated Unfolding Methodologies to Characterize the Caliban Pulsed Reactor Cavity Neutron Spectrum by the Foil Activation Method

    Los Alamos National Laboratory Fission Basis

    Sensitivity Studies Associated with Dosimetry Experiment Interpretation

    Comparison of Regulatory Guide 1.99 Fluence Attenuation Methods

    The Power Distribution and Neutron Fluence Measurements and Calculations in the VVER-1000 Mock-Up on the LR-0 Research Reactor

    VVER-440 and VVER-1000 Reactor Dosimetry Benchmark—BUGLE-96 Versus ALPAN VII.0

    Development and Experimental Validatio of a Calculation Scheme for Nuclear Heating Evaluation in the Core of the OSIRIS Material Testing Reactor

    Analysis of Gamma-Ray Dosimetry Experiments in the Zero Power MINERVE Facility

    Jules Horowitz Reactor, a New Irradiation Facility: Improving Dosimetry for the Future of Nuclear Experimentation

    Measurements of Actinide-Fission Product Yields in Caliban and Prospero Metallic Core Reactor Fission-Neutron Fields

    Reactor Pulse-Repeatability Studies at the Annular Core Research Reactor

    A Feasibility Study to Determine Cooling Time and Burnup of Advanced Test Reactor Fuel Using a Nondestructive Technique and Three Types of Gamma-ray Detectors

    The Neutron Standard Fields at the BR1 Reactor at SCK•CEN

    Photon Spectrum behind Biological Shielding of the LVR-15 Research Reactor

    Ex-Vessel Neutron Dosimetry Analysis for Westinghouse 4-Loop XL Pressurized Water Reactor Plant Using 3D Parallel Discrete Ordinates Code RAPTOR-M3G

    A Broad-Group Cross-Section Library Based on ENDF/B-VII.0 for Fast Neutron Dosimetry Using the CPXSD Methodology

    Development and Testing of the VITAMIN-B7/BUGLE-B7 Coupled Neutron-Gamma Multigroup Cross-Section Libraries

    Application of Ex-Vessel Neutron Dosimetry Combined with In-core Measurements for Correction of Neutron Source Used for Reactor Pressure Vessel Fluence Calculations

    Neutron Flux Measurements in the Side-Core Region of Hunterston B Advanced Gas-Cooled Reactor

    Analysis of Dosimetry from the H. B. Robinson Unit 2 Pressure Vessel Benchmark Using -3 and ALPAN

    The Fast Neutron Fluence and the Activation Detector Activity Calculations Using the Effective Source Method and the Adjoint Function

    A Database-Informed Approach to New Plant Shielding Design

    EPR/PTFE Dosimetry for Test Reactor Environments

    CALMOS: Innovative Device for the Measurement of Nuclear Heating in Material Testing Reactors

    Fitting Method for Spectrum Deduction in High-Energy Neutron Field Induced by GeV-Protons Using Experimental Reaction-Rate Data

    Development of for Inspection of Spent Fuel Pool

    Design and Testing of a Boron Carbide Capsule for Spectral Tailoring in Mixed-Spectrum Reactors

    An Alternative Calibration Method for Counting P-32 Reactor Monitors

    New Experimental Proposal for 235U PFNS Measurement to Answer a Fifty Year Old Question

    Development of Neutron Measurement in Intense Gamma Field Using New Type of Nuclear Emulsion

    Development of an Active Detector for the Characterization of the Late-Time Radiation Environment from a Reactor Pulse

    Participants, Author and Subject Index

    Author Index

    Subject Index


    Committee: E10

    DOI: 10.1520/STP1550-EB

    ISBN-EB: 978-0-8031-7553-2

    ISBN-13: 978-0-8031-7536-5

    ASTM International is a member of CrossRef.


    978-0-8031-7536-5
    STP1550-EB