As part of the Department of Energy`s spent nuclear fuel acceptance criteria, the mass of uranium and transuranic elements in spent research reactor fuel must be specified. These data are, however, not always known or readily determined. It is the purpose of this report to provide estimates of these data for some of the more common research reactor fuel assembly types. The specific types considered here are MTR, TRIGA and DIDO fuel assemblies. The degree of physical protection given to spent fuel assemblies is largely dependent upon the photon dose rate of the spent fuel material. These data also, are not always known or readily determined. Because of a self-protecting dose rate level of radiation (dose rate greater than 100 ren-x/h at I m ...
The radionuclide inventory of materials irradiated in a reactor depends on the initial material comp...
A fuel-element assembly from the first loading of the OMRE was examined in detail after experiencing...
Past studies have identified and evaluated important radionuclide contributors to dose from reproces...
This document has been prepared to assist research reactor operators possessing spent fuel containin...
Photon dose rates as a function of fission product decay times have been calculated for spent fuel a...
Parametric burnup calculations are performed to estimate radionuclide isotopic mass and activity con...
The challenge of estimating the radiation dose received by a worker is a complex task. This study w...
The paper discusses the stages of calculating the radiation safety of spent nuclear fuel (SNF) trans...
With the reactor operation conditions - 4.3 wt% $^{235}U$ initial enrichment, burn-up 55,000 MWd/MTU...
Spent fuel containing material (SFCM) can arise during severe nuclear reactor accident by melting of...
Gross gamma-ray dose rates from six spent TRIGA fuel elements were measured and compared to calculat...
This report presents a preliminary survey and analysis of the five primary types of commercial nucle...
A computational study has been performed for various options of the thorium reactor core loading. Ne...
Operation of nuclear reactors leads to the production of spent nuclear fuel (SNF). There are two bas...
This report is a review of the status of nondestructive assay (NDA) methods used to determine burnup...
The radionuclide inventory of materials irradiated in a reactor depends on the initial material comp...
A fuel-element assembly from the first loading of the OMRE was examined in detail after experiencing...
Past studies have identified and evaluated important radionuclide contributors to dose from reproces...
This document has been prepared to assist research reactor operators possessing spent fuel containin...
Photon dose rates as a function of fission product decay times have been calculated for spent fuel a...
Parametric burnup calculations are performed to estimate radionuclide isotopic mass and activity con...
The challenge of estimating the radiation dose received by a worker is a complex task. This study w...
The paper discusses the stages of calculating the radiation safety of spent nuclear fuel (SNF) trans...
With the reactor operation conditions - 4.3 wt% $^{235}U$ initial enrichment, burn-up 55,000 MWd/MTU...
Spent fuel containing material (SFCM) can arise during severe nuclear reactor accident by melting of...
Gross gamma-ray dose rates from six spent TRIGA fuel elements were measured and compared to calculat...
This report presents a preliminary survey and analysis of the five primary types of commercial nucle...
A computational study has been performed for various options of the thorium reactor core loading. Ne...
Operation of nuclear reactors leads to the production of spent nuclear fuel (SNF). There are two bas...
This report is a review of the status of nondestructive assay (NDA) methods used to determine burnup...
The radionuclide inventory of materials irradiated in a reactor depends on the initial material comp...
A fuel-element assembly from the first loading of the OMRE was examined in detail after experiencing...
Past studies have identified and evaluated important radionuclide contributors to dose from reproces...