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United Kingdom Support Programme to IAEA Safeguards
Type:Annual Meeting Proceedings
Author(s):Jim Tushingham, Bill McCarthy
Abstract:
The United Kingdom Support Programme (UKSP) to IAEA Safeguards was initiated in 1981. This paper briefly describes some of the highlights…
Update on Establishing the Feasibility of Lead Slowing Down Spectroscopy for Direct Measurement of Plutonium in Used Fuel
Type:Annual Meeting Proceedings
Author(s):Kevin K. Anderson, Avigdor Gavron, Jon Kulisek, Andy Casella, Yaron Danon, Glen A. Warren
Abstract:
Developing a method for the accurate, direct, and independent assay of the fissile isotopes in bulk materials (such as used fuel) of next-…
Update on the Next Generation Safeguards Initiative’s Spent Fuel Nondestructive Assay Project
Type:Annual Meeting Proceedings
Author(s):Young S. Ham, John S. Hendricks, H.O. Menlove, B. L. Broadhead, A.P. Belian, Ian C. Gauld, T.L. Burr, B.A. Ludewigt, D. Henzlova, A. Favalli, W. S. Charlton, Jon Kulisek, J. Hu, J. Galloway, A. LaFleur, H. Trellue, S.J. Tobin, Julia Eigenbrodt, C. Romano, Jeremy J. Gerhart, Peter Jansson, Henrik Liljenfeldt, H. D. Kim, S. H. Park, Marc Humphrey, A. C. Kaplan, S. Grape, L.W. Campbell, T.J. Ulrich, V. Mozin, V Henzel
Abstract:
The Next Generation Safeguards Initiative (NGSI) Spent Fuel Nondestructive Assay Project was started in March of 2009. The primary focus of…
Uranium Enrichment Determination with Commercial CZT Detectors and a Non-proprietary Analysis Algorithm
Type:Annual Meeting Proceedings
Author(s):Thomas M. Weber, Nathanael Brown, Julia Cantrell, Manuel M. Trujillo
Abstract:
Sandia National Laboratories, in partnership with the Y-12 National Security Complex and Lawrence Livermore National Laboratory, has worked…
US-Russian Experience in Maintaining the Effectiveness of Upgrades for Nuclear Material Control and Accounting Equipment and Methods
Type:Annual Meeting Proceedings
Author(s):Taisia A. Piskureva, Alexander M. Chlenov, Brent R. McGinnis
Abstract:
The FSUE Research Institute of Scientific Instruments (RISI) has a well-established nuclear material control and accountability (MC&A)…
Use of EPRI Depletion Benchmarks for Transport Criticality Burnup Credit
Type:PATRAM Proceedings
Author(s):Dale B. Lancaster, Charles T. Rombough, Albert J. Machiels, Kord S. Smith
Abstract:
EPRI sponsored the generation of depletion reactivity benchmarks that can be used to validate burnup credit for spent fuel casks. These…
USED FUEL ASSEMBLY TRANSPORTCASK TN®G3 FAMILY
Type:PATRAM Proceedings
Author(s):NULL NULL
Abstract:
TN International has extensive experience in domestic (in France) and international transport of used fuel assemblies (in France about 2,…
USED FUEL SECURITY – PRIORITIZED ISSUES, R&D NEEDS, BEST PRACTICES, AND SECURITY RISK ANALYSIS FOR EXTENDED STORAGE
Type:PATRAM Proceedings
Author(s):Felicia A. Durán, Gregory D. Wyss, Scott DeMuth, James A. Blink
Abstract:
In light of the report, The Blue Ribbon Commission on America’s Nuclear Future, lessons learned from the accident at Fukushima, and a…
Used Nuclear Materials at Savannah River Site: Asset or Waste?
Type:Annual Meeting Proceedings
Author(s):Virginia E. Magoulas
Abstract:
The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum…
Used TRIGA Fuel Burns Again
Type:PATRAM Proceedings
Author(s):Jamie Adam
Abstract:
Used TRIGA Fuel Elements were mined out of dry storage at Idaho National Laboratory, INTEC facility and transported to Atominstitut Vienna…
Using a Containment Vessel Lifting Apparatus for Remote Operations of Shipping Packages
Type:PATRAM Proceedings
Author(s):Bradley Loftin, Richard Koenig
Abstract:
The 9977 and the 9975 shipping packages are used in various nuclear facilities within the Department of Energy. These shipping packages are…
Using a Lanthanum Bromide detector to monitor Pu content in MOX fuel rod
Type:Annual Meeting Proceedings
Author(s):Anthony D. Lavietes, Nicholas Mascarenhas
Abstract:
Several mixed oxide (MOX) fuel facilities are now under development including J-MOX in Japan and the Mixed Oxide Fuel Fabrication Facility…
Using Fallout Gamma Spectra to Identify Nuclear Device Characteristics at Short Times after the Event
Type:Annual Meeting Proceedings
Author(s):John Mattingly, Anthony Nettleton
Abstract:
Identification of device characteristics from nuclear fallout shortly after a low-yield nuclear detonation can provide important clues to…
Utilization of Process Monitoring Data in the Tokai Reprocessing Plant for Future Nuclear Security
Type:Annual Meeting Proceedings
Author(s):Hironobu Nakamura, Yasuyuki Shimizu
Abstract:
Japanese regulation of reprocessing safety and security was revised in March 2012, and almost all requirements except for nuclear material…
UV-VISIBLE SPECTROSCOPIC PROCESS MONITOR FOR HOT CELL MIXERSETTLER SEPARATIONS AT ORNL’S RADIOCHEMICAL ENGINEERING UV-VISIBLE SPECTROSCOPIC PROCESS MONITOR FOR HOT CELL MIXERSETTLER SEPARATIONS AT ORNL’S RADIOCHEMICAL ENGINEERING UV-VISIBLE SPECTROSC
Type:Annual Meeting Proceedings
Author(s):Dennis E. Benker, Robert M. Wham, Brad Patton, Jamie L. Warburton, Clarice Phelps
Abstract:
This work builds upon previous related studies of UV-Visible spectroscopic online monitoring that were applied for safeguards and…
VALIDATION OF CRITICAL PARAMETER CALCULATIONS FOR SODIUM DIURANATE USING SENSITIVITY AND UNCERTAINTY ANALYSIS
Type:PATRAM Proceedings
Author(s):P. H. Sewell, P. J. Vescovi
Abstract:
Periodically, UF6 cylinders are cleaned and recertified for continued use. A new process being developed to reconvert the uranium recovered…
Validation of Total Combustion Methods to Determine Low Level C/S/N/O in Limited Size Samples
Type:Annual Meeting Proceedings
Author(s):Lisa Colletti, Frank Dickson
Abstract:
Los Alamos National Laboratory’s Actinide Analytical Chemistry group recently replaced its custom built conventional manomeric system for…
Variations of Point Model Analysis in Neutron Multiplicity Counting and Ongoing Theoretical Developments
Type:Annual Meeting Proceedings
Author(s):Danielle K. Hauck, Peter A. Santi, Andrea Favalli, Stephen Croft
Abstract:
Fissioning material emits neutrons in temporally correlated bursts corresponding to the length of the fission chains. Measuring the degree…
VERIFICATION AND VALIDATION OF FINITE ELEMENT MODELS FOR TRANSPORTATION PACKAGINGS
Type:PATRAM Proceedings
Author(s):Z. H. Han, V. N. Shah, Y.Y. Liu
Abstract:
Design, performance assessment, and certification of transportation packagings for high-level radioactive materials are based on testing…
VERIFICATION OF DESIGN LEAKAGE RATES FOR ACTIVITY RELEASE CALCULATION
Type:PATRAM Proceedings
Author(s):Annette Rolle, Hans- Peter Winkler, Viktor Ballheimer, Tino Neumeyer
Abstract:
The mechanical and thermal loadings associated with the routine, normal and accident conditions of transport can have a significant effect…