scholarly journals Characterization of LWR spent fuel MCC-approved testing material-ATM-101

1984 ◽  
Author(s):  
J.O. Barner
Keyword(s):  
Testing Material ◽  
Spent Fuel

scholarly journals Characterization of spent fuel approved testing material---ATM-105

1991 ◽  
Author(s):  
R.J. Guenther ◽  
D.E. Blahnik ◽  
T.K. Campbell ◽  
U.P. Jenquin ◽  
J.E. Mendel ◽  
...  
Keyword(s):  
Testing Material ◽  
Spent Fuel

scholarly journals Characterization of spent fuel approved testing material--ATM-104

1991 ◽  
Author(s):  
R.J. Guenther ◽  
D.E. Blahnik ◽  
U.P. Jenquin ◽  
J.E. Mendel ◽  
L.E. Thomas ◽  
...  
Keyword(s):  
Testing Material ◽  
Spent Fuel

scholarly journals Characterization of spent fuel approved testing material: ATM-106

1988 ◽  
Author(s):  
R.J. Guenther ◽  
D.E. Blahnik ◽  
T.K. Campbell ◽  
U.P. Jenquin ◽  
J.E. Mendel ◽  
...  
Keyword(s):  
Testing Material ◽  
Spent Fuel

scholarly journals Characterization of spent fuel approved testing material: ATM-103

1988 ◽  
Author(s):  
R.J. Guenther ◽  
D.E. Blahnik ◽  
T.K. Campbell ◽  
U.P. Jenquin ◽  
J.E. Mendel ◽  
...  
Keyword(s):  
Testing Material ◽  
Spent Fuel

scholarly journals SiLiF Neutron Counters to Monitor Nuclear Materials in the MICADO Project

Sensors ◽  
2021 ◽  
Vol 21 (8) ◽  
pp. 2630
Author(s):  
Luigi Cosentino ◽  
Quentin Ducasse ◽  
Martina Giuffrida ◽  
Sergio Lo Meo ◽  
Fabio Longhitano ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Detector Response ◽  
Nuclear Materials ◽  
Spent Fuel ◽  
Neutron Detectors ◽  
Intermediate Level Radioactive Waste ◽  
Eu Project ◽  
Interim Storage ◽  
Waste Drums

In the framework of the MICADO (Measurement and Instrumentation for Cleaning And Decommissioning Operations) European Union (EU) project, aimed at the full digitization of low- and intermediate-level radioactive waste management, a set of 32 solid state thermal neutron detectors named SiLiF has been built and characterized. MICADO encompasses a complete active and passive characterization of the radwaste drums with neutrons and gamma rays, followed by a longer-term monitoring phase. The SiLiF detectors are suitable for the monitoring of nuclear materials and can be used around radioactive waste drums possibly containing small quantities of actinides, as well as around spent fuel casks in interim storage or during transportation. Suitable polyethylene moderators can be exploited to better shape the detector response to the expected neutron spectrum, according to Monte Carlo simulations that were performed. These detectors were extensively tested with an AmBe neutron source, and the results show a quite uniform and reproducible behavior.

scholarly journals Preparation and characterization of "Libby Amphibole" toxicological testing material

2012 ◽  
pp. i-20
Author(s):  
Heather Lowers ◽  
Stephen A. Wilson ◽  
Todd M. Hoefen ◽  
William M. Benzel ◽  
Gregory P. Meeker
Keyword(s):  
Testing Material ◽  
Libby Amphibole ◽  
Toxicological Testing

Spent Fuel: Characterization Studies and Dissolution Behaviourunder Disposal Conditions

1987 ◽  
Vol 112 ◽  
Author(s):  
L. H. Johnson ◽  
D. W. Shoesmith ◽  
S. Stroes-Gascoyne
Keyword(s):  
Release Kinetics ◽  
Fission Products ◽  
Solution Chemistry ◽  
Future Research ◽  
Spent Fuel ◽  
Research Areas ◽  
Dissolution Model ◽  
Underground Disposal ◽  
Radionuclide Release

AbstractThe concept of disposal of unreprocessed spent fuel has now been under study internationally for over ten years. Considerable progress has been made in understanding the factors that will control radionuclide release from spent fuel in an underground disposal vault. This progress is reviewed and the research areas of significance in providing further data for source term models are discussed. Key areas for future research are identified; these include improved characterization of spent fuel to determine the inventories of fission products at grain boundaries, together with their release kinetics; and a better understanding of the effects of solution chemistry on spent fuel dissolution, in particular the effects of salinity, redox chemistry, and radiolysis of groundwater. Approaches to modelling the dissolution of spent fuel are discussed, and a possible approach for developing an oxidative dissolution model is outlined.

Neodymium Incorporation in Zirconolite-Based Glass-Ceramics

2000 ◽  
Vol 663 ◽  
Author(s):  
P. Loiseau ◽  
D. Caurant ◽  
N. Baffier ◽  
C. Fillet
Keyword(s):  
Heat Treatment ◽  
Glass Ceramics ◽  
Fission Products ◽  
Treatment Temperature ◽  
Spent Fuel ◽  
X Ray Diffraction ◽  
Parent Glass ◽  
X Ray ◽  
Spin Resonance

ABSTRACTThe investigations on enhanced reprocessing of nuclear spent fuel, and notably on separating the long-lived minor actinides, such as Am and Cm, from the other fission products have led to the development of highly durable specific matrices such as glass-ceramics for their immobilization. This study deals with the characterization of zirconolite (CaZrTi2O7) based glass-ceramics synthesized by devitrification of an aluminosilicate parent glass. Trivalent actinide ions were simulated by neodymium, which is a paramagnetic local probe. Glass-ceramics with Nd2O3 contents ranging from 0 to 10 weight % were prepared by heat treatment of a parent glass at two different growth temperatures: 1050° and 1200°C. X-ray diffraction (XRD), energy dispersive X-ray analysis (EDX) and electron spin resonance (ESR) measurements clearly indicate that Nd3+ ions are partly incorporated in zirconolite crystals formed in the bulk of the glass-ceramic samples. The amount of neodymium in the crystalline phase was estimated using ESR results and was found to decrease with increasing either heat treatment temperature or total Nd2O3 content.

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