Savannah River Technology Center monthly report, March 1993
DOE
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Description
This report outlines progress and accomplishments in the following categories: Reactor; Tritium; Separations; Environmental; Waste Management; and General. Reactor topics are a summary of the Applied Physics Group`s work for the K-15.1 cycle; FLOWTRAN-TF code test certification, documentation, and reactor support; analysis of Mark 16B material from the L-Reactor Dissassembly Basin; the Reactor Tank inspection program T-Weld project; and Consistency Matrix support. Tritium topics are Leak Test Systems for the Container Management Facility; Replacement Tritium Facility technical issues tracking; transmission electron microscopy specimen preparation; the tritium aging effect on LaNi4.95A10.05 compressor material; and the life storage program. Separations topics are the F-Canyon Safety Analysis Report Addendum; an H-Canyon dissolver model; non-reactor assistance to the Nuclear Regulatory Commission; and onsite packaging criteria draft documentation. Environmental topics are Pond C studies with an underwater HPGe detector; the PREDICT run for the 1992 Annual Environmental Report; an integrated demonstration for cleanup of organic soils and groundwater at non-arid sites; and radio frequency soil heating -- fiberoptic temperature measurement probes. Waste Management topics are adding sodium titanate to in-tank precipitation simulants; lab-scale stripper column defoaming tests; the development of an extended sludge processing batch one model; and a canister temperature study. General topics are video image capture system -- drum inspection; old solvent tank characterization; plutonium storage containers; a glove box docking port; the development of SRS engineering and scientific software catalog; Nuclear Incident Monitor and criticality analysis for separations equipment development; and Nuclear Regulatory Commission assistance. Publications and other items of interest are cited at the end of this report.. Authors: Ferrell, J M. DOE Contract: AC09-89SR18035. Subjects: 052000; 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 22 GENERAL STUDIES OF NUCLEAR REACTORS; 220000; 220600; ENVIRONMENTAL EFFECTS; L REACTOR; Nuclear Criticality Safety Program (NCSP); NUCLEAR ENGINEERING; NUCLEAR REACTOR TECHNOLOGY; PROGRAMMING; PROGRESS REPORT; RADIOACTIVE WASTE MANAGEMENT; REACTOR TECHNOLOGY; RESEARCH PROGRAMS; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS; SAFETY ANALYSIS; SAVANNAH RIVER PLANT; SEPARATION P
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