[en] Silver iodide based glasses, 60Agl-20Ag sub 2 O-20B sub 2O sub 3, 6 Agl-20Ag sub 2 O-20 MoO sub 3 and 60Agl-20Ag sub 2O-20WO sub 3, all in the mol % ratio, were prepared by rapidly quenching the melts of the chemicals in a stainless steel container; kept in a liquid nitrogen bath. The glassy nature of the as-quenched materials was confirmed by X-ray diffraction (XRD). The electrical conductivity of the glasses was measured at various temperatures ranging from 30 to 70 degree C using an impedance bridge operating in the frequency range between 40 Hz to 100 kHz. The plot of In σT versus 1000/T for each glassy material obeys Arrhenius law and the activation energy obtained is between 0.2 to 0.3 eV. Thermopower measurement was also carried out in the same temperature range as the conductivity measurement to obtain the heat of transport

[en] The aim of this study is to investigate the efficiency treatment in removing Zn-65, Mo-99 and I-1 25 from an aqueous radioactive effluent. The wastes are currently being produced from hospitals, research institutes, clinics and universities. Effluent was spiked separately with each type of the radioisotope and was treated by the coagulation-flocculation process. By varying the chemical dosages (i.e., alum, soda ash, ferric chloride and coagulant aid) in the treatment, different decontamination factor values were obtained. Optimum dosages and types of chemical used to remove a particular radioisotope was determined. Results indicated that optimum pH value for removing Zn-65 in an effluent was pH 8. The highest decontamination factor value was 61. In removal of 1-125 radioisotope, ferric chloride was suitable as a coagulant that gives the highest decontamination factor value of 5.0. Treatment to remove Mo-99 radioisotopes was conducted in the laboratory and treatment plant scale. For Mo-99 radioisotope treatment by laboratory and Plant scale, the highest decontamination factor obtained was between pH values of 4.0 to 4.5. By extrapolation of both scales, the plant scale treatment does not vary significantly from laboratory scale. This indicated treatment dosages of chemicals for the Low Level Treatment Plant scale be deduced from the laboratory scale

[en] The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1997. The department's research and development activities were organized in four research programmes: Reactor Safety, Radiation protection, Radioecology, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the educational reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

[en] Solid Waste Storage Area (SWSA) 6, located at the US Department of Energy (DOE) Oak Ridge National Laboratory (ORNL) facility, is a shallow land burial site for low-level radioactive waste (LLW) and other waste types. Wastes were disposed of in unlined trenches and auger holes from 1969 until May 1986, when it was determined that Resource Conservation and Recovery Act (RCRA) regulated wastes were being disposed of there. DOE closed SWSA 6 until changes in operating procedures prevented the disposal of RCRA wastes at SWSA 6. The site, which reopened for waste disposal activities in July 1986, is the only currently operated disposal area for low-level radioactive waste at ORNL. This report provides the results of the 1998 RCRA groundwater assessment monitoring. The monitoring was performed in accordance with the proposed routine monitoring plan recommended in the 1996 EMP. Section 2 provides pertinent background on SWSA 6. Section 3 presents the 1998 monitoring results and discusses the results in terms of any significant changes from previous monitoring efforts. Section 4 provides recommendations for changes in monitoring based on the 1998 results. References are provided in Section 5. Appendix A provides the 1998 RCRA Sampling Data and Appendix B provides a summary of 1998 Quality Assurance results

[en] SrCu₂O₃ and Sr₂Cu₃O₅ containing two-leg and three-leg S=1/2 ladders made of antiferromagnetic Cu-O-Cu linear bonds, respectively, were synthesized at high pressure, and their crystallographic and magnetic properties were investigated. Both susceptibility and T₁ data of NMR revealed the existence of a large spin gap only for SrCu₂O₃. Superconductivity, which had been predicted theoretically for carrier-doped SrCu₂O₃ could not be realized although partial substitution of La³⁺ for Sr²⁺ seemed to be carried out successfully. Electron carriers injected seems to remain localized

[en] A prototype of the Josephson-effect spectrum analyzer developed for the millimeter-wave band is described. The measurement results for spectra obtained in the frequency band from 50 to 250 GHz are presented

[en] DOE proposes to construct and operate a Tritium Extraction Facility (TEF) at H Area on the Savannah River Site (SRS) to provide the capability to extract tritium from commercial light water reactor (CLWR) targets and from targets of similar design. The proposed action is also DOE's preferred alternative. An action alternative is to construct and operate TEF at the Allied General Nuclear Services facility, which is adjacent to the eastern side of the SRS. Under the no-action alternative DOE could incorporate tritium extraction capabilities in the accelerator for production of tritium. This EIS is linked to the Final Programmatic Environmental Impact Statement for Tritium Supply and Recycling, from which DOE determined that it would produce tritium either in an accelerator or in a commercial light water reactor. The purpose of the proposed action and alternatives evaluated in this EIS is to provide tritium extraction capability to support either tritium production technology. The EIS assesses the environmental impacts from the proposed action and the alternatives, including the no action alternative

[en] During FY97, the University of Wisconsin Fusion Technology Institute personnel have participated in the ARIES-RS and the ARIES-ST projects. The main areas of effort are: (1) neutronics analysis; (2) shielding of components and personnel; (3) neutron wall loading distribution; (4) radiation damage to in-vessel components; (5) components lifetimes; (6) embrittled materials designs issues; (7) stress and structural analysis; (8) activation, LOCA, and safety analysis; (9) support and fabrication of components; (10) vacuum system; and (11) maintenance. Progress made in these areas are summarized

[en] This presentation focuses on illustrating by case histories the range of applications and limitations of time domain electromagnetic (TDEM) systems for buried metal detection. Advantages claimed for TDEM metal detectors are: independent of instrument response (Geonics EM61) to surrounding soil and rock type; simple anomaly shape; mitigation of interference by ambient electromagnetic noise; and responsive to both ferrous and non-ferrous metallic targets. The data in all case histories to be presented were acquired with the Geonics EM61 TDEM system. Case histories are a test bed site on Molokai, Hawaii; Fort Monroe, Virginia; and USDOE, Rocky Flats Plant. The present limitations of this technology are: discrimination capabilities in terms of type of ordnance, and depth of burial is limited, and ability of resolving targets with small metallic ambient needs to be improved

[en] In fiscal year (FY) 1998 two new fusion technology programs were initiated in the US, with the goal of making marked progress in the scientific understanding of technologies and materials required to withstand high plasma heat flux and neutron wall loads. APEX is exploring new and revolutionary concepts that can provide the capability to extract heat efficiently from a system with high neutron and surface heat loads while satisfying all the fusion power technology requirements and achieving maximum reliability, maintainability, safety, and environmental acceptability. ALPS program is evaluating advanced concepts including liquid surface limiters and divertors on the basis of such factors as their compatibility with fusion plasma, high power density handling capabilities, engineering feasibility, lifetime, safety and R and D requirements. The APEX and ALPS are three-year programs to specify requirements and evaluate criteria for revolutionary approaches in first wall, blanket and high heat flux component applications. Conceptual design and analysis of candidate concepts are being performed with the goal of selecting the most promising first wall, blanket and high heat flux component designs that will provide the technical basis for the initiation of a significant R and D effort beginning in FY2001. These programs are also considering opportunities for international collaborations