Nuclear Nonproliferation Research at Los Alamos National Laboratory

Dan_Holden
SPEAKER:
DAN HOLDEN
DATE/TIME:
THU, 03/31/2011 - 4:00PM TO 5:00PM
LOCATION:
3105 ETCHEVERRY HALL
Spring 2011 Colloquium Series
Abstract:

The topic of nuclear nonproliferation (both cooperative and non-cooperative) is broad, drawing upon interdisciplinary scientific, political and social sciences. At Los Alamos National Lab, as well as across the entire National Nuclear Security Administration complex, virtually all aspects of this urgent problem are being addressed. Research is ongoing in the safeguarding special nuclear materials (SNM), remote and in situ sensing of nuclear facilities, producing proliferation-resistant nuclear fuels and medical targets, technical forensics and in policy. Tracking and accounting for SNM involves not only the direct physics measurements of neutron and gamma emissions, but also the attendant accounting methodologies, much like tracking banking transactions. State-of-the-art micro-calorimeter and X-ray fluorescence techniques are improving our ability to assay plutonium. Remotely inferring reactor core burn up rates might be possible via an anti-neutrino technique that uses the containment structure itself as the sensor. New polymer ligand films are being developed that will selectively pre-concentrate plutonium into thin film geometry to increase selectivity and sensitivity for assaying actinides and their isotopes. Remote sensing can range from space-borne sensors looking at gamma, X-ray, optical and radio frequency signals to spectroscopic returns from laser induced breakdown spectroscopy inside a building. Powering reactors and manufacturing medical targets using low enriched uranium (LEU) and designing efficient fuels with taggants to identify their source all lower the proliferation risk. Social and political science play equally important roles in understanding both the problems and the solution.

About the Speaker:

Dan Holden currently serves as the program manager for nuclear nonproliferation verification science and technology at Los Alamos National Lab, a broad research portfolio that funds approximately one hundred staff members. His research interests are in radio frequency remote sensing of both natural and manmade phenomena. After earning his Bachelors’ Degree at UC Berkeley in Astronomy, he switched to physics where he earned graduate degrees at the New Mexico Institute of Mining and Technology and Clemson University specializing in lightning and thunderstorm research. He enjoys whale watching along the coast of Northern California from a sailboat that he keeps on San Francisco Bay.

Video:

Chemical separation processes for advanced nuclear fuel cycles: Challenges and possibilities

Mikael_Nilsson
SPEAKER:
MIKAEL NILSSON
DATE/TIME:
MON, 03/14/2011 - 4:00PM TO 5:00PM
LOCATION:
3105 ETCHEVERRY HALL
Spring 2011 Colloquium Series
Abstract:

In the world today, nuclear energy comprises ~15% of the total electricity mix. This power source produces no CO2 during the operation of the plants and can provide bulk power to industry and households 24/7. Concerns about CO2 emissions from burning fossil fuels (coal, oil and natural gas) have caused the world demand of nuclear power to rise. With increasing interest in nuclear energy, we are facing a problem of sharing the readily available uranium resources. To increase the energy utilization and decrease the radiotoxicity of the waste advanced concepts for fuel reprocessing are being investigated on a global scale. This is a multi disciplinary research field spanning from organic synthesis to particle physics, and no single research group can hope to cover all aspects. Collaboration is crucial to the success of these projects. For a successful advanced nuclear fuel cycle, one or several chemical separations steps are required to fractionate the different elements in spent fuel. These separations processes are of varying complexity and use a range of different chemicals making it challenging to implement them on industrial scale. Furthermore, some of the processes under development are still in the experimental stage and require supporting fundamental studies to succeed. In this presentation, similarities and differences between the different separation schemes are discussed, emphasizing the challenges that will be faced before an advanced nuclear fuel cycle can be implemented in industry. Current projects carried out by the UC Irvine nuclear group that address some of these challenges will be presented and discussed.

About the Speaker:

Mikael (Micke) Nilsson joined the department of Chemical Engineering and Materials Science at University of California – Irvine in January 2009. His expertise is in the field of nuclear energy and nuclear waste treatment, and encompasses both the fundamental and applied aspects of the field. Dr. Nilsson is a specialist in separations technology as it applies to the reprocessing of spent fuel from nuclear reactors. He also studies the effects of radioactive decay on solvents and chemicals used for nuclear waste management. Dr. Nilsson received an M.S. degree in chemical engineering in 2000 and a Ph.D. in nuclear chemistry in 2005 from Chalmers University of Technology, Sweden. Between 2006 and 2008 he was a post-doc in the chemistry department at Washington State University. At UC Irvine, Dr. Nilsson teaches courses in chemical engineering thermodynamics and unit operations, nuclear chemistry, and the nuclear fuel cycle. Dr. Nilsson recently (October 2010) passed the Nuclear Regulatory Commission exam and became a qualified senior reactor operator on the UC Irvine TRIGA reactor. The research group of Dr. Nilsson currently comprises 5 graduate student researchers and 4 undergraduate students.

Video:

Trivalent Actinide and Lanthanide Interactions with Phosphate Materials

Kiel_Holliday
SPEAKER:
KIEL HOLLIDAY
DATE/TIME:
WED, 03/09/2011 - 4:00PM TO 5:00PM
LOCATION:
3105 ETCHEVERRY HALL
Spring 2011 Colloquium Series
Abstract:

The incorporation of Eu and Cm into the LaPO4 monazite structure is presented as a model phosphate system, relevant as a nuclear waste form. Site selective time resolved laser fluorescence spectroscopy of Eu and Cm was used as a structural probe. This revealed “satellite” species previously seen in LuPO4 [1]. These species are now clearly resolved and their origin is discussed. Apatite is considered to be a barrier to radionuclide migration due to its ability to incorporate a wide range of elements and the low solubility of actinides in phosphate media. Little is known about the incorporation mechanism of trivalent actinides and lanthanides in apatite at temperatures and conditions relevant to the environment. Previous work identifies Eu3+ incorporated into apatite at room temperature by TRLFS and describes the species as incorporated into the Ca(I) site with C3 symmetry. All published TRLFS emission spectra show a splitting of the F1 transition that is greater than expected for C3 symmetry and is attributed to impurities from natural apatite [2] or multiple site excitations [3]. The presented study eliminates these possibilities and produces similar spectra. The explanation proposed is that Eu3+ incorporates into amorphous grain boundaries producing a range of related species with low symmetry. Possibilities for charge compensation before and after heat treatment are also discussed [4, 5]. The mechanistic understanding of uptake in apatite is expanded to studies on biologically produced apatite. In this case, the mechanism proposed by the current study explains observed trends of uptake in apatite produced by Serratia bacteria. By tailoring the microstructure of the apatite produced one can design a material suited for various applications, such as filter material for decontaminating ground water or as a coating for surgical implants. These studies illustrate the value in attaining an atomic scale mechanistic understanding of the sorption and incorporation mechanisms that dictate actinide behavior. References [1] Murdoch, K.M., Edelstein, N.M., Boatner, L.A., Abraham, M.M.: Excited state absorption and fluorescence line narrowing studies of Cm3+ in LuPO4. J. Chem. Phys. 105, 2539 (1996). [2] M Gaft, R Reisfeld, G Panczer, G Boulon, S Shoval, B Champagnon, Optical Materials, 1997, 8, 149-156. [3] M Karbowiak, S Hubert, Journal of Alloys and Compounds, 2000, 302, 87-93. [4] R. Ternane, M. Trabelsi-Ayedi, N. Kbir-Ariguib, B. Pirou, Journal of Luminescence, 1999, 81, 165-170. [5] R. Sahoo, S.K. Bhattacharya, R. Debnath, Journal of solid state chemistry, 2003, 175, 218-225.

About the Speaker:

Kiel Holliday is a post doctoral scholar in the group of Thorsten Stumpf at the Institut für Nukleare Entsorgung at the Karlsruhe Institut für Technologie were he specializes in time resolved laser fluorescence spectroscopy and radionuclide migration. He received his Ph.D. in Radiochemistry from the University of Nevada, Las Vegas under Ken Czerwinski studying the synthesis, characterization and dissolution behavior of advanced nuclear fuel. Kiel Holliday has also performed investigations on materials for various applications such as waste forms, target materials, and exotic phase compositions for radiation damage studies.

Video:

Delayed Gamma Assay for Nuclear Safeguards

Vladimir_Mozin
SPEAKER:
VLADIMIR MOZIN
DATE/TIME:
MON, 03/07/2011 - 4:00PM TO 5:00PM
LOCATION:
3105 ETCHEVERRY HALL
Spring 2011 Colloquium Series
Abstract:

The UC Berkeley Nuclear Engineering Department in collaboration with Los Alamos National Laboratory and Lawrence Berkeley National Laboratory participates in the US DOE Next Generation Safeguards Initiative with a focus on developing advanced instruments and methods in nuclear material control and accountancy. Within this context, a delayed gamma non-destructive assay (NDA) technique is being investigated as a means to directly quantify both the fissile and fertile content of spent nuclear fuel, and as a general safeguards tool that can be easily integrated with other active interrogation instruments. In support of this research, a newly developed modeling technique was introduced, offering a versatile capability for time- and spatially-dependent, prompt and delayed discrete gamma source term and detector response calculations. The new modeling approach was validated in a series of experiments involving accelerator-driven neutron sources and samples of fissile and fertile materials and their combinations with varying parameters for interrogation setups.

About the Speaker:

Vladimir Mozin graduated from the Moscow Engineering Physical Institute in 2002 with an M.S. in Radiochemistry. He spent several years working as an engineer at a nuclear fuel reprocessing facility. Currently, he is a Ph.D. candidate participating in a collaborative research effort between the UC Berkeley Nuclear Engineering Department, Los Alamos National Laboratory, and Lawrence Berkeley National Laboratory.

Video:

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