Neutron Intensity Measurements of BWR Spent Fuels

Journal of Nuclear Science and Technology - United Kingdom
doi 10.1080/00223131.2000.10874957
Full Text
Abstract

Available in full text

Date
Authors
Publisher

Informa UK Limited

Related search

Evaluation of Thermal Margin During BWR Neutron Flux Oscillation.

Journal of Nuclear Science and Technology
High Energy PhysicsNuclearEngineeringNuclear Energy
1992English

Neutron Generators for Spent Fuel Assay

2010English

Neutron-Coupled Thermal Hydraulic Calculation of BWR Under Seismic Acceleration

Progress in Nuclear Science and Technology
2011English

Application of Advanced Neutron Absorbing Materials to Structural Material of Inner Basket of Storage Casks for High Burnup and MOX Spent Fuels.

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
1997English

Voloxidation: Removal of Volatile Fission Products From Spent LMFBR Fuels.

1973English

Neutron Spectra Measurements

Nuclear Science and Engineering
EngineeringNuclear Energy
1959English

Measurement and Analysis of Neutron Emission Rate for Irradiated BWR Fuel

Journal of Nuclear Science and Technology
High Energy PhysicsNuclearEngineeringNuclear Energy
1981English

Effects of Temperature Cycling and Heating Rate on Fission Gas Release of BWR Fuels

Journal of Nuclear Science and Technology
High Energy PhysicsNuclearEngineeringNuclear Energy
1991English

Spallation Neutron Production Measurements

Nuclear Science and Engineering
EngineeringNuclear Energy
1998English

Amanote Research

Note-taking for researchers

Follow Amanote

© 2024 Amaplex Software S.P.R.L. All rights reserved.

Privacy PolicyRefund Policy