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

This document is part of your ASTM Compass® subscription.

Vehar David, Gilliam David, Adams James

**Published:** 2007

Format |
Pages |
Price |
||

PDF (20M) | $126 | ADD TO CART | ||

Hardcopy (shipping and handling) |
$126 | ADD TO CART | ||

Hardcopy + PDF Bundle - Save 25% ( shipping and handling) |
$189.00 | ADD TO CART |

The latest edition of this popular ASTM series provides an extensive overview of the latest advances in reactor dosimetry.

As operating nuclear power reactors have aged and continue to operate on extended operating licenses, new pressure vessel surveillance techniques have been required. Eastern European pressurized water reactors, especially those of the VVER-440 type, continue to have greater concerns about steel embrittlement, because of higher neutron radiation exposures than most Western European and US reactors. Accordingly, broader dosimetry studies are being made on the VVER reactors through retrospective dosimetry, ex-vessel dosimetry, and careful re-analysis of previously reported data.

60 peer-reviewed papers cover:

• Power Reactor Surveillance

• Test Reactors, Accelerators, and Advanced Systems

• Benchmarks and Intercomparisons

• Cross Sections, Nuclear Data; Damage Correlations

• Transport Calculations

• Adjustment Methods

• Experimental Techniques

Validation of the Neutron Fluence Calculation on the VVER-440 RPV support structure

Reactor Dosimetry Study of the Rhode Island Nuclear Science Center

Characterizing the Time- and Energy-Dependent Reactor *n*/γ Environment

Determination of Adjusted Neutron Spectra in Different MUSE Configurations by Unfolding Techniques

Characterization of Neutron Fields Using MCNP in the Experimental Fast Reactor JOYO

Benchmark on the 3-D VENUS-2 MOX-Fueled Reactor Dosimetry Calculations by DANTSYS Code System

Benchmark Experiments/Calculations of Neutron Environments in the Annular Core Research Reactor

Verification of MultiTrans Calculations by the VENUS-3 Benchmark Experiment

Radiation Dosimetry in the BNCT Patient Treatment Room at the Brookhaven Medical Research Reactor

TRIM Modeling of Displacement Damage in SiC for Monoenergetic Neutrons

Neutron and Photon Dosimetry at the LR-0 Reactor Using Paired Detectors

Survey of the Latest Evaluated Nuclear Data

Gas Production in Reactor Materials

Dosimetry Requirements for Pressure Vessel Steels Toughness Curve in the Ductile to Brittle Range

Mesh Tally Radiation Damage Calculations and Application to the SNS Target System

Attenuation of Radiation Damage and Neutron Field in Reactor Pressure Vessel Wall

An International Evaluation of the Neutron Cross Section Standards

Spallation Radiation Damage Calculations and Database: Cross-Section Discrepancies between the Codes

Proton Induced Activation in Mercury: Comparison of Measurements and Calculations

Advances in Calculation of Fluence to Reactor Structures

Coarse-Mesh Adjoint Biasing of a Monte Carlo Dose Calculation

Influence of the Multigroup Approximation on VVER-1000 RPV Neutron/Gamma Flux Calculation

A New Derivation of the Perturbation Operator Used in MCNP

Calculation of Neutron Fluxes for Radioactive Inventory Assessment of Magnox Power Plant

Extensive Revision of the Kernel-Based PREVIEW Program and Its Input Data

Investigation of Radiation Transport Modeling Trends in the WSMR Fast Burst Reactor Environments

Coupled Neutron-Gamma Calculations for the LR-0 Experimental Benchmark

Sensitivity Analysis and Neutron Fluence Adjustment for VVER-440 RPV

Generalized Linear Least-Squares Adjustment, Revisited

Comparison of Predicted and Measured Helium Production in U.S. BWR Reactors

Shielding Calculations for the Upgrade of the HFIR HB 2 Beam Line

Development of a Silicon Calorimeter for Dosimetry Applications in a Water-Moderated Reactor

Fast Neutron Dosimetry and Spectrometry Using Silicon Carbide Semiconductor Detectors

Spent Fuel Monitoring with Silicon Carbide Semiconductor Neutron/Gamma Detectors

Application of a Silicon Calorimeter in Fast Burst Reactor Environments

The Validity of the Use of Equivalent DIDO Nickel Dose for Graphite Dosimetry

Neutron Damage in SiC Semiconductor Radiation Detectors in the GT-MHR

A New Methodology for Adjustment of Iron Scattering Cross Sections Using Time-of-Flight Spectroscopy

**Committee:** E10

**DOI:** 10.1520/STP1490-EB

**ISBN-EB:** 978-0-8031-6242-6

**ISBN-13:** 978-0-8031-3412-6

978-0-8031-3412-6

STP1490-EB