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Guidelines for beamline and front-end radiation shielding design at the Advanced Photon Source.

Description: Shielding for the APS will be such that the individual radiation worker dose will be as low as reasonably achievable (ALARA). The ALARA goals for the APS are to keep the total of the work-related radiation exposure (exposure coming from other than natural or medical sources) as far below 500 person-mrem per year, collective total effective dose equivalent, as reasonably achievable. For an individual APS radiation worker, the goal is to keep the maximum occupational total effective dose equivale… more
Date: September 11, 2008
Creator: Fernandez, P. & Division, X-Ray Science
Partner: UNT Libraries Government Documents Department
open access

Safeguards Approaches for Very Long-Term Storage of Spent Fuel

Description: No Description Available.
Date: October 11, 2013
Creator: Kollar, L.; Mendez-Torres, A.; Diaz Marcano, H.; Therios, I. (Nuclear Engineering Division) Nuclear Engineering Division & Laboratory), (Savannah River National
Partner: UNT Libraries Government Documents Department
open access

Status report on high fidelity reactor simulation.

Description: This report presents the effort under way at Argonne National Laboratory toward a comprehensive, integrated computational tool intended mainly for the high-fidelity simulation of sodium-cooled fast reactors. The main activities carried out involved neutronics, thermal hydraulics, coupling strategies, software architecture, and high-performance computing. A new neutronics code, UNIC, is being developed. The first phase involves the application of a spherical harmonics method to a general, unstru… more
Date: December 11, 2006
Creator: Palmiotti, G.; Smith, M.; Rabiti, C.; Lewis, E.; Yang, W.; Leclere,M. et al.
Partner: UNT Libraries Government Documents Department
open access

Review of environmental effects on fatigue crack growth of austenitic stainless steels.

Description: Fatigue and environmentally assisted cracking of piping, pressure vessel cladding, and core components in light water reactors are potential concerns to the nuclear industry and regulatory agencies. The degradation processes include intergranular stress corrosion cracking of austenitic stainless steel (SS) piping in boiling water reactors (BWRs), and propagation of fatigue or stress corrosion cracks (which initiate in sensitized SS cladding) into low-alloy ferritic steels in BWR pressure vessel… more
Date: July 11, 1994
Creator: Shack, W. J.; Kassner, T. F. & Technology, Energy
Partner: UNT Libraries Government Documents Department
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