Isotope separation system experiments at the TSTA

The recent results of the Isotope Separation System (ISS) operations at the Tritium Systems Test Assembly (TSTA) with 100 g of tritium indicate that the system generally satisfies design goals, while system stability problems remain to be solved. We configured the ISS system for the three column mode to eliminate such instability and operated it for six days. Fluctuations in flows and liquid levels were improved. Column separation characteristics obtained were satisfactory and agreed with the numerical analysis. The amount of discharged tritium was an acceptable effluent level. This means that the existing ISS system can be used as a three column system and possibly be applied to numerous fuel concepts. Presently, a new laser Raman spectroscopic gas analyzer has been installed at the ISS. This on-line system enables studies of the ISS dynamic behavior for further stability and performance data. 12 refs., 10 figs., 2 tabs

Untersuchungen zum Abbindeverhalten von Zementsuspensionen

SIGLEDEGerman

Oxidation of Zircaloy-4 under limited steam supply at 1000 and 1300 C

SIGLECopy held by FIZ Karlsruhe; available from UB/TIB Hannover / FIZ - Fachinformationszzentrum Karlsruhe / TIB - Technische InformationsbibliothekDEGerman

The influence of thermomechanical treatment on the creep behaviour of DIN 1.4970 austenitic stainless steel at 973 K

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K"+ production in relativistic nuclear collisions

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Molecular Sieve Regeneration System for assaying HTO from detritiation systems

A Molecular Sieve Regeneration System (MSRS) is being added to the existing Tritium Waste Treatment system (TWT) within the Tritium Systems Test Assembly (TSTA) at the Los Alamos National Laboratory. This system is an upgrade to the TWT to provide accurate measurements of the liquid waste generated from this system. Within the TWT, hydrogen isotopes are removed from the effluent gas stream by the catalytic conversion to water and the subsequent removal of water by molecular sieve trapping prior to the release to the environment. Within the TWT and similar systems, molecular sieve regeneration is required to rejuvenate the beds. The major difference of the MSRS and other regeneration systems is the capability of direct assay of long-term storage waste containers. This is accomplished with loop-flow regeneration, water collection, and tritiated water assay by scintillation and calorimetric techniques. This paper describes the MSRS in detail and how it is interfaced with the Tritium Waste Treatment system

Study on temperature coefficients of actinide burning HTGRs

HTGRs have the potential to achieve a high transmutation ratio, burning transuranium isotopes. The main reason is the large burnup, which is achieved by the fuel in the form of coated particles. In view of inherent safety features temperature coefficients have been studied for HTGR-fuel containing Pu and Minor Actinides in various fuel specifications in each case aiming at a high Pu burning ratio. The performed cell burnup calculations indicate, that HTGRs have the potential to achieve a high transmutation potential. In view of the temperature coefficients U"2"3"8 as breed material has an advantage compared to Th"2"3"2, maintaining a negative temperature coefficient even at a very high fuel burnup. In order to maximize the yearly depletion rate of Pu, small amounts should be loaded to the fuel elements without U. For utilizing Pu effectively, i.e. to achieve a long burnup cycle and a high burnup of the Pu loaded to the fuel elements, a high heavy metal loading including U as breed material is adequate. (orig.)Available from TIB Hannover: RA 831(3449) / FIZ - Fachinformationszzentrum Karlsruhe / TIB - Technische InformationsbibliothekSIGLEDEGerman

A prior-form distorted wave Born approximation analysis of the elastic break-up of 156 MeV 6Li projectiles

SIGLECopy held by FIZ Karlsruhe; available from UB/TIB Hannover / FIZ - Fachinformationszzentrum Karlsruhe / TIB - Technische InformationsbibliothekDEGerman

Joint programme on the technical development and further improvement of IAEA safeguards between the Government of the Federal Republic of Germany and the International Atomic Energy Agency. Task C.17 Operations manual for the KfK hubrid K-edge/K-XRF densitometer

SIGLECopy held by FIZ Karlsruhe; available from UB/TIB Hannover / FIZ - Fachinformationszzentrum Karlsruhe / TIB - Technische InformationsbibliothekDEGerman