[en] The development of the program for the production of transplutonium elements, ²⁴¹Am, ²⁴³Am and ²⁴⁴Cm, in France, required a major effort from the technological and chemical standpoints. Pre-existing hot cells were reconditioned and others specially built for these production operations. From the chemical standpoint, the development of extractive chromatography on the preparative scale has allowed the definition of simple processes. This type of process, initially developed for the treatment of Pu/Al targets, is ideal for the treatment of industrial wastes for their decontamination and for the production of ²⁴¹Am

[en] By means of the adapter a connection may be created between a sup(99m)Tc-generator in a lead container, a tank filled with, e.g. NaCl for elutriation and an evacuated eluate tank. The connecting channels e.g. needles, a non-pyrogenic oxygen filter, and a sterilizing filter are fully integrated into the lead adapter, i.e. encapsulated together with it. The adapter is mechanically connected with the lead container for the generator and forms a unit ready to be shipped. (DG)

[en] By using the spectrophotometric method the kinetics and mechanism of berkelium (4) self-reduction in perchloric and nitric acid solutions have been investigated. It has been found that berkelium (4) self-reduction occurs only at the expense of Bk (4) interaction with the solution radiolysis products. The rate constants for Bk (4) self-reduction and the radiation-chemical yields for Bk (3) in the above media have been estimated

[en] A process for the photochemical separation of carbon 13 and oxygen 18 uses 123.54 nm resonance radiation from a gaseous discharge containing Kr and an inert gas to excite selectively ₁₃C₁₆O, ₁₂C₁₈O, or both with no significant excitation of ₁₂C₁₆O. The excited molecules react with ground state CO to yield CO² and C³O². The isotopically-enriched products are removed from the reactants by condensation

[en] Operations during this report period are summarized, and the amounts of materials obtained and shipped are listed. Proposed processing schedules and anticipated yields of various products in the near future are outlined. The original and current contents (²⁵²Cf and ²⁴⁸Cm) of existing neutron sources made at TRU, as well as the individuals to whom these sources are currently loaned, are tabulated. Also, a variety of special projects that required use of the facilities available at TRU are described

No abstract available

[en] On December 1, 1992, the Indiana Regional Cancer Center reported to the US Nuclear Regulatory Commission's (NRC) Region I that they believed a 1.37 E + 11 becquerel (3.7-curie) iridium-192 source from their Omnitron 2000 high dose rate remote brachytherapy afterloader had been found at a biohazard waste transfer station in Carnegie, Pennsylvania. After notifying the NRC, this cancer center, one of several operated by the licensee, Oncology Services Corporation, retrieved the source, and Region I dispatched an inspector and a supervisor to investigate the event. The source was first detected when it triggered radiation alarms at a waste incinerator facility in. Warren, Ohio. The licensee informed the NRC that the source wire had apparently broken during treatment of a patient on November 16, 1992, leaving the source in the patient. On the basis of the seriousness of the incident, the NRC elevated its response to an Incident Investigation. The Incident Investigation Team initiated its investigation on December 3, 1992. The investigation team concluded that the patient received a serious misadministration and died on November 21, 1992, and that over 90 individuals were exposed to radiation from November 16 to December 1, 1992. In a press release dated January 26, 1993, the Indiana County Coroner stated that the cause of death listed in the official autopsy report was ''Acute Radiational Exposure and Consequences Thereof'' An almost identical source wire failure occurred with an afterloader in Pittsburgh, Pennsylvania, on December 7, 1992, but with minimal radiological consequences. This incident was included in the investigation. This report discusses the Omnitron 2000 high dose rate afterloader source-wire failure, the reasons why the failure was not detected by Indiana Regional Cancer Center, the potential consequences to the patient, the estimated radiological doses to workers and the public, and regulatory aspects associated with this incident

[en] A pulsed Copper Vapour Laser (CVL), with a nominal 6 kHz repetition rate, was designed, build, and commissioned at Chalk River laboratories. The laser was required for Resonant Ionization Mass Spectroscopy (RIMS) experiments and for projects associated with Atomic Vapour laser Isotope Separation (AVLIS) studies. For the laser to operate, copper coupons position along the length of a ceramic tube must be heated sufficiently to create an appropriate vapour pressure. The AECL CVL uses an external heater element with a unique design to raise the temperature of the tube. The Cylindrical graphite heating element is shaped to compensate for the large radiation end losses of the laser tube. The use of an external heater saves the expensive high-current-voltage switching device from heating the laser tube, as in most commercial lasers. This feature is especially important given the intermittent usage typical of experimental research. As well, the heater enables better parametric control of the laser output when studying the lasing of copper (or other) vapour. This report outlines the lasing process in copper vapour, describes in detail all three major laser sub-systems: the laser body; the laser tube heater; the high voltage pulsed discharge; and, reports parametric measurements of the individual sub-systems and the laser system as a whole. Also included are normal operating procedures to heat up, run and shut down the laser

[en] This Report provides information on the state agencies assigned to radioactive materials transportation incidents in 16 Southern States Energy Board member states. For each, the report lists the agencies with primary authority for preparedness and response, their responsibilities and personnel within the agencies who can offer additional information on their radioactive materials transportation programs. The report also lists each state's emergency team members and its laboratory and analytical capabilities. Finally, the governor's designee for receiving advance notification of high-level radioactive materials and spent fuel shipments under 10 CFR Parts 71 and 73 of the US Nuclear Regulatory Commission's regulations is listed for each state. Part 71 requires prenotification for large quantity radioactive waste shipments. Part 73 addresses prenotification for spent nuclear reactor fuel shipments

No abstract available