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Fuels and Materials Fast-Reactor Dosimetry Data Development and Testing

Data up to Jan 2025

Published1975
Citations23
References25

Total Citations Per Year

Abstract

References (25)

Measurement of Absolute Fission Rates

1975 • 79 citations

Fission Yields of Over 40 Stable and Long-Lived Fission Products for Thermal Neutron Fissioned 233U, 235U, 239Pu, and 241Pu and Fast Reactor Fissioned 235U and 239Pu

1970 • 41 citations

A Study of Fission-Neutron Spectra with High-Energy Activation Detectors. Part II: Fission Spectra

1968 • 38 citations

Calculation of Differential Fast-Neutron Spectra from Threshold-Foil Activation Data by Least-Squares Series Expansion Methods

1965 • 34 citations

The Spectral Distribution of Neutrons and Neutron Reaction Cross Sections in an Unreflected Uranium-235 Critical Assembly and the Fission Neutron Spectrum

1972 • 33 citations

Measurement of Neutron Flux Spectra by a Multiple Foil Activation Iterative Method and Comparison with Reactor Physics Calculations and Spectrometer Measurements

1969 • 29 citations

Evaluated Decay Scheme Data

1975 • 28 citations

Helium Production Cross Section of Boron for Fast-Reactor Neutron Spectra

1975 • 27 citations

Nonfission Reaction Rate Measurements

1975 • 25 citations

The Secondary Intermediate-Energy Standard Neutron Field at the MOL-ΣΣ Facility

1975 • 23 citations

CFRMF Neutron Field Flux Spectral Characterization

1975 • 18 citations

Implications of Recent Fission-Averaged Cross-Section Measurements

1969 • 16 citations

Fission-Product-Rate Measurements and Yields

1975 • 12 citations

Preparation and Characterization of Neutron Dosimeter Materials

1975 • 11 citations

National neutron cross-section center

1977 • 11 citations

The Central Neutron Spectrum of the Fast Critical Assembly BIG-TEN

1975 • 10 citations

Analysis of Burnups in EBR-II Driver-Fuel Elements

1975 • 9 citations

Neutron Dosimetry for Fast Reactor Applications

1970 • 9 citations

ENDF/B File for Dosimetry Applications

1975 • 7 citations

The Yield of Short-Lived Gamma-Ray Emitting Nuclides from Fast- and Thermal-Neutron Fission

1974 • 7 citations

Measurement of Fission Product Yields and the Energy Integral Fission Cross Section of Thorium-232 in a Californium-252 Fission-Neutron Spectrum

1975 • 5 citations

High Flux Level Reaction Rate Measurements

1975 • 4 citations

A Method of Nondestructive Measurement of the Absolute Cumulative Barium-140 Yield of Uranium Irradiated in Thermal and Fast Neutron Spectra

1971 • 4 citations

Analysis of Dosimetry Measurements in EBR-II

1975 • 4 citations

Chemical Nuclear Data Measurements and Applications

1971 • 3 citations

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