[en] The TMI-2 EPICOR-II Resin/Liner Low-Level Waste Data Base Development Program funded by the US Nuclear Regulatory Commission (USNRC) is obtaining information on performance of radioactive waste in a disposal environment. Waste forms fabricated using ion exchange resins from EPICOR-II prefilters employed in the cleanup of the Three Mile Island Nuclear Power Station are being tested to: (a) develop a low-level waste data base, and (b) obtain information on survivability of waste forms in a disposal environment. This paper updates field testing of those waste forms during FY-1988, presents results of waste form leach testing, and compares those results to the releases of radionuclides from these lysimeter waste forms. 16 refs., 12 figs., 3 tabs

[en] The TMI-2 EPICOR-II Resin/Liner Low-Level Waste Data Base Development Program is obtaining information on the performance of radioactive waste in a disposal environment. Waste forms fabricated using ion-exchange resins from EPICOR-II prefilters employed in the cleanup of the Three Mile Island (TMI) Nuclear Power Station are being tested to: develop a low-level waste data base, and obtain information on survivability of waste forms in a disposal environment. This paper gives field testing results of those waste forms through FY-1989. The results from the lysimeter experiments are presented and the use of lysimeter data to determine input parameters used in performance assessment is discussed. 7 refs., 11 figs., 2 tabs

[en] ASTM biodegradation tests were conducted on waste forms containing high specific activity ion exchange resins from EPICOR-II prefilters. Those tests were part of a program to test waste forms in accordance with the NRC Branch Technical Position on Waste Form. Small waste forms were manufactured using two different solidification agents, Portland Type I-II cement and vinyl ester-styrene (VES). Ion exchange material was taken from two EPICOR-II prefilters; PF-7, which contained all organic material, and PF-20, which contained organic resins and a layer of inorganic zeolites. Test results showed that the VES waste forms supported microbial growth, while cement waste forms did not support that growth. Growth was also observed adjacent to some VES waste forms. Radiation levels found in the ion exchange resins used in this study were not found to inhibit microbial growth. The extent of degradation of the waste forms could not be determined using the ASTM tests specified by the NRC Branch Technical Position on Waste Form. As a result of this work, a different testing methodology is recommended, which would provide direct verification of waste form capabilities. That methodology would evaluate solidification materials without using the ASTM procedures or subsequent compression testing. The proposed tests would provide exposure to a wide range of microbial species, use appropriately sized specimens, provide for possible use of alternate carbon sources, and extend the test length. Degradation would be determined directly by measuring metabolic activity or specimen weight loss. 16 refs., 15 figs., 3 tabs

[en] The Low-Level Waste Data Base Development - EPICOR-II Resin/Liner Investigation Program funded by the US Nuclear Regulatory Commission is obtaining information on performance of radioactive waste in a disposal environment. Waste forms manufactured from ion exchange resins used to clean up water from the accident at Three Mile Island Nuclear Power Station are being examined in field tests. This paper presents a description of the field testing and results from the first year of operation. 8 refs., 8 figs., 4 tabs

[en] The TMI-2 [Three Mile Island Unit 2] EPICOR-II Resin/Liner Low-Level Waste Data Base Development Program, funded by the U.S. Nuclear Regulatory Commission (NRC), is obtaining information on the performance of radioactive waste in a disposal environment. Waste forms fabricated using ion-exchange resins from EPICOR-II prefilters employed in the cleanup of the Three Mile Island Nuclear Power Station are being tested to: (a) develop a low-level waste data base, and (b) obtain information on survivability of waste forms in a disposal environment. This paper updates field testing of those waste forms during FY-1989. The results of the lysimeters is presented and the use of lysimeter data in performance assessment is discussed. 16 refs., 10 figs., 5 tabs

[en] The purpose of the field testing task, using lysimeter arrays, is to expose samples of solidified resin waste to the actual physical, chemical, and microbiological conditions of disposal enviroment. Wastes used in the experiment include a mixture of synthetic organic ion exchange resins and a mixture of organic exchange resins and an inorganic zeolite. Solidification agents used to produce the 4.8-by 7.6-cm cylindrical waste forms used in the study were Portland Type I-II cement and Dow vinyl ester-styrene. Seven of these waste forms were stacked end-to-end and inserted into each lysimeter to provide a 1-L volume. There are 10 lysimeters, 5 at ORNL and 5 at ANL-E. Lysimeters used in this study were designed to be self-contained units which will be disposed at the termination of the 20-year study. Each is a 0.91-by 3.12-m right-circular cylinder divided into an upper compartment, which contains fill material, waste forms, and instrumentation, and an empty lower compartment, which collects leachate. Four lysimeters at each site are filled with soil, while a fifth (used as a control) is filled with inert silica oxide sand. Instrumentation within each lysimeter includes porous cup soil-water samplers and soil moisture/temperature probes. The probes are connected to an on-site data acquisition and storage system (DAS) which also collects data from a field meteorological station located at each site. 9 refs

[en] This paper reviews the components, causative agents, corrosion sites, and potential failure modes of stainless steel components susceptible to microbially influenced corrosion (MIC). The stainless steel components susceptible to MIC are located in the reactor coolant, emergency, and reactor auxiliary systems, and in many plants, in the feedwater train and condenser. The authors assessed the areas of most high occurrence of corrosion and found the sites most susceptible to MIC to the heat-affected zones in the weldments of sensitized stainless steel. Pitting is the predominant MIC corrosion mechanisms, caused by sulfur reducing bacteria (SRB). Also discussed is the current status of the diagnostic, preventive, and mitigation techniques, including use of improved water chemistry, alternate materials, and improved thermomechanical treatments. 37 refs., 3 figs

[en] We are investigating the use of macrocyclic and acyclic chelating systems in the selective removal and recovery of f-elements from solution. Since actinides are often carried in acidic waste streams, we have been studying the reactions which occur when complexing ligands are added to acidic solutions of U(IV) and uranyl salts. In the case of simple crown ethers, often hydronium, ammonium, or sodium ion complexes of the ether are isolated with large uranyl counterions. We have structurally characterized several of these

[en] Several recent national and international reports have predicted that the demand for radionuclides used in medicine will increase significantly over the next 20 years. Separation science is an integral part of the production and development of new radionuclides for diagnostic and therapeutic applications and will play a major role in process improvements to existing radiopharmaceuticals to meet increasing demands. The role of separation science in the production of radionuclides for medical applications is briefly discussed, followed by an overview of the manuscripts from the American Chemical Society symposium 'Nuclear Separations for Radiopharmacy'. A listing of the most widely used radionuclides in clinical application and medical research serves as a foundation for the discussion of future research opportunities in separation science

[en] Use of selected microorganisms for the degradation and/or detoxification of hazardous organic compounds is gaining wide acceptance as an alternative waste treatment technology. The INEL Biotechnology Unit is developing the technology for the in-plant treatment of waste industrial solvents. The work centers around the use of microorganisms specially selected for their ability to degrade common industrial solvents such as benzene, toluene, xylene, etc. Because these waste solvents are often contaminated with other materials (heavy metals, water, detergents, etc.) they are difficult and expensive to dispose and many times are not economical to recover through recycling. Even if the disposal option is used, the generator is still faced with continued liability in the event of mishandling or improper disposal of the waste. Biological treatments offers the option of reducing these solvents into harmless by-products provided that both the requisite microorganisms and the proper processing technology are successfully brought together. Work on the optimization of a bioreactor process for the degradation of xylene will be discussed. 15 figs., 7 refs