LWR Fuel Recycle Program. Quarterly progress report, April--June 1976. [Head end processes, off-gas treatment, Purex Process]

Technical Report · Thu Jul 01 00:00:00 EDT 1976

DOI:https://doi.org/10.2172/7348252· OSTI ID:7348252

Irish, E R ^[1]; Simmons, J L ^[2]

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1. comp.
2. ed.

Work was begun on the initial task of estimating U/sub 3/O/sub 8/ supply 1 prices. In the spent fuel receipt and storage project, review of existing and planned process equipment and concepts was initiated through discussions with both laboratory and industry personnel and through plant visits. Effort was also initiated to catalog existing fuel designs. Available information was reviewed on the voloxidation process and on various pyrochemical and pyrometallurgical steps for fuel reprocessing application. Further development work was done in the off-gas treatment project using charcoal filters to capture low concentrations of TBP vapor and x-ray fluorescence to analyze for phosphorus. A series of standards was prepared and is being analyzed. Several inorganic sorbent materials have been received and will be used in initial screening tests to determine TBP removal efficiency. Commercially available macroreticular polymeric adsorbents and anion exchange resins for the removal of iodine from dilute nitric acid streams (simulating concentrator overheads condensate) are being tested with encouraging results being obtained. The major portion of the literature search on solvent extraction equipment alternatives was completed, and a bibliographic listing of approximately 1000 items was generated. In the removal and re-entrainment of plutonium and other radionuclides project, a literature search was conducted to provide parameterizations for the draft Environmental Impact Statement for the LWR--Model Fuel Recycle Facilities. Recommended procedures are to ignore deposition and resuspension when calculating direct and inhalation doses; use Gaussian plume models only out to distances where sigma/sub z/ = h/2, then use the mixing height h out to 24-hr travel time, and thereafter use a constant mixing ratio; for calculating the indirect dose use a total (wet plus dry) deposition velocity of 3 cm/sec for reactive gases and all particles, regardless of size. (LK)

• Research Organization: Battelle Pacific Northwest Labs., Richland, WA (United States)
• DOE Contract Number: E(45-1)-1830
• OSTI ID: 7348252
• Report Number(s): BNWL-2080-1
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
IODINE
ADSORPTION
ION EXCHANGE
SPENT FUELS
REPROCESSING
RESEARCH PROGRAMS
AIR FILTERS
BWR TYPE REACTORS
CHARCOAL
ENVIRONMENTAL EFFECTS
EQUIPMENT
FUEL REPROCESSING PLANTS
HEAD END PROCESSES
NITRIC ACID
OFF-GAS SYSTEMS
PUREX PROCESS
PWR TYPE REACTORS
SOLVENT EXTRACTION
SPENT FUEL STORAGE
TBP
ADSORBENTS
BUTYL PHOSPHATES
ELEMENTS
ENERGY SOURCES
ESTERS
EXTRACTION
FILTERS
FUELS
HALOGENS
HYDROGEN COMPOUNDS
INORGANIC ACIDS
NONMETALS
NUCLEAR FACILITIES
NUCLEAR FUELS
ORGANIC COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
PHOSPHORIC ACID ESTERS
POLLUTION CONTROL EQUIPMENT
REACTOR MATERIALS
REACTORS
SEPARATION PROCESSES
SORPTION
WATER COOLED REACTORS
WATER MODERATED REACTORS
050800* - Nuclear Fuels- Spent Fuels Reprocessing
210802 - Nuclear Power Plants- Economics- Fuel Cycle
052001 - Nuclear Fuels- Waste Processing