[en] This volume of the LLE Review, covering January-March 2005, features the new 'Saturn' target design concept for use in polar direct drive on National Ignition Facility (NIF) while the facility is in its initial, indirect-drive configuration

[en] This volume of the LLE Review, covering October to December 2004, highlights the significance of shaped adiabats to inertial confinement fusion. Theory suggests that inertial confinement fusion (ICF) capsules compressed by shaped adiabats will exhibit improved hydrodynamic stability

[en] The hydrogen is separated by a two layer diaphragm. The primary side layer has lower solubility for hydrogen and a lower release constant than the secondary side at working temperatures. Due to the drop in solubility and release of the diaphragm, the hydrogen permeation supported by dissociation is increased. As transport back through the diaphragm is a disadvantage, a section with a series of two layer diaphragms and dissociation devices in the intermediate chambers can be used for separation of isotopes. (orig./PW)

[en] An upgraded version of a metal hydride based clean-up system for tritium gloveboxes has been recently designed. An earlier version of a prototypical, recirculating system has been under evaluation in tritium service at OHT for nearly 2 years. A metal getter alloy, Zr₂Fe, is used to remove tritium and trace impurities from inert and nitrogen glovebox cover gas. The second generation SEC system features several notable improvements over its predecessor in areas of gas conductance, process instrumentation for tritium and moisture detection, and operator interface. A second bed has been added to enhance the removal of tritium and impurities. The system is controlled by computer programmed to automatically maintain the glovebox pressure, temperature and the impurity level of the glovebox cover gas, and to respond effectively to upset conditions by corrective action and to alarm the off-normal condition. The lifetime of the metal alloy getter is affected by the presence of impurities, notably moisture, which dictates the need to ensure system leak tightness. For example, the tritium concentration at the bed outlet will rise by approximately one order of magnitude as a result of introducing a continuous moisture load of 5 ppmv for 6 months while maintaining a flow rate of 2 L/s. The second generation system will be commissioned with tritium during 1995. 9 refs., 3 figs

[en] This paper reviews the development of tritium handling systems which have been designed to process torus effluent from fusion reactors. Several subsystems: Torus evacuation, impurity stripping and processing, and tritium storage are reaching a level of maturity which permit realistic extrapolation to reactor scale. Long term tests using tritium are required to shakedown these processes. Their status are reviewed and areas which require additional research are discussed. (orig.)

[en] Tritiated stainless steel surfaces are shown to evolve tritiated species other than HTO and HT. These species are identified as being organic in nature and highly condensable on system walls. The source of the organics is viewed as being the hydrocarbon layer on the stainless steel surface. X-ray photoelectron spectroscopy of cleaned stainless steel surfaces indicate that a majority of the surface is covered by carbon. The carbon is bound predominantly in hydrocarbon groups. Engineering materials are expected to be sources of hydrocarbons awaiting tritiation. These volatile tritiated organics could have an impact on dosimetric calculations and on surface contamination of metals

No abstract available

[en] A 1500 curie tritium laboratory is being constructed at Ontario Hydro Research Division. A special feature of this laboratory is the tritium storage and delivery system (TSDS). This system can dispense up to 125 curies of pure tritium gas per batch to experimenter's facilities within the laboratory. The system consists of two uranium storage beds, a circulation pump, an assay volume, a vacuum system and an analysis station. All components which routinely see high levels of activity are metallic. This paper describes the TSDS, outlines typical operating scenarios and discusses anticipated abnormal events and the recovery procedures

[en] Short communication

[en] Tritiated waste and glovebox cleanup systems contain significant levels of trititated methane impurities which require reducing and processing to recover the tritium. A viable approach to the recovery of tritium is the conversion of tritiated methane into elemental tritium and carbon by thermal cracking on a heated metal matrix. Through the conversion reaction of HTO/H₂O with hot Al₄C₃ powder, tritiated methane concentrations in the 0.4 to 0.9 mCi/m³ range are achievable. The HTO/H₂O ratio is approx.10^-7. Conversion efficiencies for the decomposition of methane are measured for Zr-Fe-Mn alloy, iron oxide and supported nickel catalyst. HT and HTO are created by decomposing methane. Zr-Fe-Mn alloy achieved a maximum conversion efficiency of approx.70% at 700 degree C. Iron oxide thermally cracked methane at 36% at a temperature of 700 degree C. Supported nickel operating at 450 degree C achieved conversion efficiencies ranging from 65 to 100%. 5 refs., 6 figs., 1 tab