skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: NAC-1 cask dose rate calculations for LWR spent fuel

Abstract

A Nuclear Assurance Corporation nuclear fuel transport cask, NAC-1, is being considered as a transport and storage option for spent nuclear fuel located in the B-Cell of the 324 Building. The loaded casks will be shipped to the 200 East Area Interim Storage Area for dry interim storage. Several calculations were performed to assess the photon and neutron dose rates. This report describes the analytical methods, models, and results of this investigation.

Authors:
Publication Date:
Research Org.:
HNF Hanford Site (US)
Sponsoring Org.:
US DOE Office of Environmental Management (US)
OSTI Identifier:
781543
Report Number(s):
HNF-3016-REV0; EW7040000
EW7040000; TRN: US0111165
DOE Contract Number:
AC06-96RL13200
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 24 Feb 1999
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; SPENT FUEL CASKS; DOSE RATES; NEUTRONS; PHOTONS; SPENT FUELS; DRY STORAGE; TRANSPORT; CALCULATION METHODS; MATHEMATICAL MODELS

Citation Formats

CARLSON, A.B. NAC-1 cask dose rate calculations for LWR spent fuel. United States: N. p., 1999. Web. doi:10.2172/781543.
CARLSON, A.B. NAC-1 cask dose rate calculations for LWR spent fuel. United States. doi:10.2172/781543.
CARLSON, A.B. 1999. "NAC-1 cask dose rate calculations for LWR spent fuel". United States. doi:10.2172/781543. https://www.osti.gov/servlets/purl/781543.
@article{osti_781543,
title = {NAC-1 cask dose rate calculations for LWR spent fuel},
author = {CARLSON, A.B.},
abstractNote = {A Nuclear Assurance Corporation nuclear fuel transport cask, NAC-1, is being considered as a transport and storage option for spent nuclear fuel located in the B-Cell of the 324 Building. The loaded casks will be shipped to the 200 East Area Interim Storage Area for dry interim storage. Several calculations were performed to assess the photon and neutron dose rates. This report describes the analytical methods, models, and results of this investigation.},
doi = {10.2172/781543},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1999,
month = 2
}

Technical Report:

Save / Share:
  • The air cooling annulus of the Ventilated Storage Cask (VSC)-17 spent fuel storage cask was inspected using a Toshiba 7 mm (1/4”) CCD video camera. The dose rates observed in the annular space were measured to provide a reference for the activity to which the camera(s) being tested were being exposed. No gross degradation, pitting, or general corrosion was observed.
  • This report contains the results of a time/motion analysis and a radiation dose assessment made during the receipt from barge transport and the loading of CAst iron cask for Storage and Transport Of Radioactive material (CASTOR) V/21 storage casks with spent nuclear fuel at the Surry Power Station in Virginia during 1987. The study was a cooperative effort between Pacific Northwest Laboratory (PNL) and Virginia Electric and Power Company (Virginia Power), and was funded by the US Department of Energy (DOE) Transportation Program Office. In this study, cask handling activities were tracked at the Surry Power Station, tracing the transfermore » of the empty spent fuel storage cask from an ocean-going vessel to a barge for river transport through the activities required to place the loaded storage cask at an at-reactor storage location.« less
  • This report contains the results of a time/motion analysis and a radiation dose assessment made during the receipt from barge transport and the loading of CAst iron cask for Storage and Transport Of Radioactive material (CASTOR) V/21 storage casks with spent nuclear fuel at the Surry Power Station in Virginia during 1987. The study was a cooperative effort between Pacific Northwest Laboratory (PNL) and Virginia Electric and Power Company (Virginia Power), and was funded by the US Department of Energy (DOE) Transportation Program Office. In this study, cask handling activities were tracked at the Surry Power Station, tracing the transfermore » of the empty spent fuel storage cask from an ocean-going vessel to a barge for river transport through the activities required to place the loaded storage cask at an at-reactor storage location.« less
  • The literature has been reviewed to determine the possible influences of strain rate and temperature on the yield and fracture toughness behavior of selected steels suggested for use in an LMFBR Spent Fuel Shipping Cask. Based on this information, recommendations have been made for further work which is intended to alleviate potential problems prior to their having a major impact on the shipping cask program.
  • Calculations of the skyshine gamma-ray dose rates from three spent fuel storage pools under worst case accident conditions have been made using the discrete ordinates code DOT-IV and the Monte Carlo code MORSE and have been compared to those of two previous methods. The DNA 37N-21G group cross-section library was utilized in the calculations, together with the Claiborne-Trubey gamma-ray dose factors taken from the same library. Plots of all results are presented. It was found that the dose was a strong function of the iron thickness over the fuel assemblies, the initial angular distribution of the emitted radiation, and themore » photon source near the top of the assemblies. 16 refs., 11 figs., 7 tabs.« less