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Title: LWR fuel recycle program. Quarterly progress report, July--September 1976

Abstract

This is the third quarterly progress report. The LWR Fuel Recycle Program is designed to assist in the commercialization of the LWR fuel cycle. Included in this program are both activities in support of specific design studies and other activities of more general applicability to fuel recycle technology. The following are reported in this document: economic and environmental documentation, spent fuel receipt and storage, head end processes, off-gas treatment, Purex process, finishing processes, environmental effects, and general support. (DLC)

Authors:
 [1]
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  1. (comp.)
Publication Date:
Research Org.:
Battelle Pacific Northwest Labs., Richland, Wash. (USA)
OSTI Identifier:
7129720
Report Number(s):
BNWL-2080-2
DOE Contract Number:
E(45-1)-1830
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; FUEL CYCLE; RESEARCH PROGRAMS; POWER REACTORS; WATER COOLED REACTORS; ENVIRONMENTAL EFFECTS; HEAD END PROCESSES; IODINE; PUREX PROCESS; SPENT FUEL STORAGE; ELEMENTS; HALOGENS; NONMETALS; REACTORS; REPROCESSING; SEPARATION PROCESSES; 050800* - Nuclear Fuels- Spent Fuels Reprocessing

Citation Formats

Jarrett, J.H. LWR fuel recycle program. Quarterly progress report, July--September 1976. United States: N. p., 1976. Web. doi:10.2172/7129720.
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Jarrett, J.H. LWR fuel recycle program. Quarterly progress report, July--September 1976. United States. doi:10.2172/7129720.
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Jarrett, J.H. Fri . "LWR fuel recycle program. Quarterly progress report, July--September 1976". United States. doi:10.2172/7129720. https://www.osti.gov/servlets/purl/7129720.
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@article{osti_7129720,
title = {LWR fuel recycle program. Quarterly progress report, July--September 1976},
author = {Jarrett, J.H.},
abstractNote = {This is the third quarterly progress report. The LWR Fuel Recycle Program is designed to assist in the commercialization of the LWR fuel cycle. Included in this program are both activities in support of specific design studies and other activities of more general applicability to fuel recycle technology. The following are reported in this document: economic and environmental documentation, spent fuel receipt and storage, head end processes, off-gas treatment, Purex process, finishing processes, environmental effects, and general support. (DLC)},
doi = {10.2172/7129720},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Oct 01 00:00:00 EDT 1976},
month = {Fri Oct 01 00:00:00 EDT 1976}
}
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Technical Report:
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DOI:  10.2172/7129720
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  • Two additional dissolutions were made using irradiated fuel for the H.B. Robinson II reactor; the solids are being characterized. An extension of time was given for bid proposals for a model /sup 1///sub 2/-ton/day voloxidizer. Preliminary heat transfer tests of a rotary kiln voloxidizer were completed. Residence times were measured in a 6-in. dia. tube; results were in agreement with those obtained in a previous test with a commercial kiln. The remaining fluorocarbon adsorption process pilot-plant tests scheduled under campaign 3 were completed; more than 99.99% of the carbon dioxide and xenon impurities were removed. Studies of stainless steel corrosionmore » by R-12 solutions in presence of iodine and water are continuing. Methyl iodide was found to be miscible in R-12. An ORNL/SRL survey study was made of commercial and potential spent LWR fuel reprocessors to identify unresolved shearing and related head-end problems. Areas of difficulty were categorized as: (A) mechanical technology, (B) safety technology, (C) waste disposal, and (D) a pressing need for an LWR fuel Reference Information Center. A new hot-cell domestic shearing system must be developed, and remote operability and maintenance must be demonstrated at high throughputs. 22 tables, 10 fig. (DLC)« less

  • ; ; ; ...
    LWR Off-Gas Treatment: A reference facility has been described in a draft report. A survey of technical literature for immobilization of /sup 14/CO/sub 2/ was completed. Waste Management: Laboratory evaporations were continued using simulated HLLW solutions representing three fuel cycle processes. Total solids content at various degrees of evaporation are presented together with boiling point rises and slurry densities. Substitution of less costly materials for Rh, Pd, and Tc did not affect the physical properties of the slurries or the quantity of solids formed. The effect of adding nuclear poisons (gadolinium, boron, or cadmium) on physical properties of HLLW andmore » on solids formation is reported. Solids formed in all HLLW solutions contained major amounts of Zr and Mo. The design of the small-scale thermosyphon evaporator and the reboiler tube test specimen are presented. Evaporated HLLW slurries stored for two months at 35/sup 0/C have not produced significantly more solids. Laboratory corrosion data showed excessive corrosion occurred in HLLW containing high iron concentrations and 7 M HNO/sub 3/, apparently due to Cr formed by stainless steel corrosion. Iodine-129 Adsorbent and Storage Development: Silver-exchanged zeolite (AgX) and mordenite (AgZ) were loaded with and stripped of elemental iodine for evaluation for recycle behavior. After five cycles, the AgZ showed no decrease in loading (approximately 440 mg/g); the AgX loading dropped about 50 percent from its initial value of 320 mg/g. (DLC)« less

  • Progress in the following studies is reported: head-end processes, off-gas treatment, and finishing processes. Preliminary tabulations have been made of various treatment concepts, both U.S. and foreign, as alternatives to voloxidation. Laboratory work was initiated in the development of a sensitive method to quantitatively analyze low concentrations of TBP vapor by capturing TBP on charcoal filters and analyzing for phosphorus using x-ray fluorescence. Collecting of applicable literature needed for planned evaluations in the mixed oxide studies was initiated. (LK)

  • ;
    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 formore » 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)« less