Nuclear Technology Programs Semiannual Progress Report: April-September 1990 (open access)

Nuclear Technology Programs Semiannual Progress Report: April-September 1990

Progress report of the Argonne National Laboratory's Nuclear Technology Programs, including R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management.
Date: June 1992
Creator: Steindler, M. J.; Battles, J. E. & Harmon, J. E.
System: The UNT Digital Library
Operational Health Physics Training (open access)

Operational Health Physics Training

This revised publication updates a previous report (ANL-7291) initially published in 1965, entitled Radiation Safety Technician Training Course which was intended to complement on-the-job monitoring training for Health Physics Technicians. Sections include basic information concerning atomic structure and other useful physical quantities, natural radioactivity, the properties of alpha, beta, gamma, x rays and neutrons, and the concepts and units of radiation dosimetry (including SI units).
Date: June 1992
Creator: Moe, H. J. & Vallario, Edward J.
System: The UNT Digital Library
State-of-the-Art for Assessing Earthquake Hazards in the United States, Report 28: Recommended Accelerograms for Earthquake Ground Motions (open access)

State-of-the-Art for Assessing Earthquake Hazards in the United States, Report 28: Recommended Accelerograms for Earthquake Ground Motions

Abstract: "A catalog of recommended accelerograms and response spectra is provided to accompany all representative values for Richter magnitudes at distance determined peak horizontal accelerations-velocities-durations, hard and soft sites, shallow and deep earthquakes. Accelerograms are also recommended for corresponding Modified Mercalli intensities. The accelerograms are related to the Krinitzsky-Chang-Nuttli curves for magnitude and distance, and the Krinitzsky-Chang curves for MM intensity."
Date: June 1992
Creator: Leeds, David J.
System: The UNT Digital Library
Stress Corrosion Cracking of Candidate Waste Container Materials: Final Report (open access)

Stress Corrosion Cracking of Candidate Waste Container Materials: Final Report

Six alloys have been selected as candidate container materials for the storage of high-level nuclear waste at the proposed Yucca mountain site in Nevada. These materials are Type 304L stainless steel (SS). Type 316L SS, Incoloy 825, phosphorus-deoxidized Cu, Cu-30%Ni, and Cu-7%Al. The present program has been initiated to determine whether any of these materials can survive for 300 years in the site environment without developing through-wall stress corrosion cracks. and to assess the relative resistance of these materials to stress corrosion cracking (SCC)- A series of slow-strain-rate tests (SSRTs) and fracture-mechanics crack-growth-rate (CGR) tests was performed at 93(degree)C and 1 atm of pressure in simulated J-13 well water. This water is representative, prior to the widespread availability of unsaturated-zone water, of the groundwater present at the Yucca Mountain site.
Date: June 1992
Creator: Park, J. Y.; Malya, P. S.; Soppet, W. K.; Diercks, D. R.; Shack, W. J. & Kassner, T. F.
System: The UNT Digital Library