Resources

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Advancing Networking And Mentoring Opportunities For Women In Nuclear Security
Type:Annual Meeting Proceedings
Author(s):Olga Martin, Margarita Kalinina-Pohl
Abstract:
The proposed paper will provide a summary of current activities and planned next steps under DOE NNSA Office of International Nuclear…
Advancing The On-Line Enrichment Monitor (OLEM) Capability
Type:Annual Meeting Proceedings
Author(s):James Ely, Rodrigo Guerrero, Benjamin S McDonald, Mital Zalavadia
Abstract:
The International Atomic Energy Agency (IAEA) has deployed the On-Line Enrichment Monitor (OLEM) to monitor the enrichment levels of UF6…
Advancing Transportation Security During The Covid-19 Pandemic
Type:Annual Meeting Proceedings
Author(s):Karen Y Kaldenbach, Bouchra Boustani, AssiaLasfar AssiaLasfar, Allison Parnell
Abstract:
Advancing Transportation Security during the COVID-19 PandemicKaren Kaldenbach: Oak Ridge National LaboratoryBouchra Boustani: Agence…
Agile, Team-based Response In Casting Furnace Placement And Technology Realization
Type:Annual Meeting Proceedings
Author(s):Raynella M. Connatser, Ryan L. Stillwell, Pamela M. Moor, Jessica N. Farrell, Thomas Greg Schaaff
Abstract:
In 2018, a joint leadership team comprised of personnel from the U.S. National Nuclear Security Association (NNSA/NA-195), Lawrence…
An Approach To Comparative Evaluation Of Nuclear Energy System Options Based On Multi-attribute Value Theory
Type:Annual Meeting Proceedings
Author(s):Vladimir V Kuznetsov, Galina Fesenko, Andrei Andrianov
Abstract:
The International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) was established in 2000 with the goal of ensuring a…
An Estimation Of Fissile Material Production From The 5 Mwe Yong-byon Graphite-moderated Reactor By MCNP6 And SCALE6 Calculation
Type:Annual Meeting Proceedings
Author(s):Wonsik Jung, Gyehong Kim, Geehyun Kim
Abstract:
The estimation of the fissile material production from 5 MWe Yong-byon graphite-moderated reactor is important to evaluate North Korea’s…
An Indigenous Isotopic Analysis Code Developed at Radiochemistry Division-Bhabha Atomic Research Centre-Inter-Comparison with FRAM and MGA
Type:JNMM
Volume:49
Issue:3
Author(s):Ramkumar Venkataraman, Pradeep Kumar Pujari, Rahul Tripathi, Andrea Favalli, Duc Vo, Metodi Iliev, Laura Limback
Abstract:
Under the auspices of joint Indo-US collaboration agreement between the Department of Atomic Energy, India and the United States Department…
An Integrated And Collaborative International Framework For Building Public Support And Acceptance For The Safe And Secure Long-term Management Of Spent Fuel
Type:Annual Meeting Proceedings
Author(s):Ben Belfadhel
Abstract:
The development of Deep Geological Repositories (DGRs) for spent fuel is a necessary step in the nuclear fuel cycle. We have the knowledge…
An Overview Of Recent And Planned Advances In The Evaluation Of Environmental Sample And Nuclear Material Characterization Analysis Results
Type:Annual Meeting Proceedings
Author(s):Mika Nikkinen, Ben Dabbs, Todd Mock, Kenneth Vilece
Abstract:
The competent and timely evaluation of environmental sample and nuclear material characterization analysis results within the Department of…
Analysis Of In-line Plutonium Mass Measurements, In A Dynamic Background Environment, For Nuclear Material Control And Accounting In Nuclear Fuel Cycle Facilities
Type:Annual Meeting Proceedings
Author(s):Sarah Sarnoski, Thomas Stockman, Emily Casleton, Vlad Henzl, Metodi Iliev, Paul M Mendoza, Matthew Newell, Carlos Rael, Misha Skurikhin, Jacob Stinnett, Duc Vo, Brian Weaver, Robert K. Weinmann-Smith, Andrea Favalli, Rollin E Lakis
Abstract:
In nuclear material production environments Non-Destructive Assay (NDA) is an important part of Nuclear Material Control and Accounting (…
ANALYSIS OF PNAR SPENT FUEL SAFEGUARDS MEASUREMENTS USING THE ORIGEN DATA ANALYSIS MODULE
Type:Annual Meeting Proceedings
Author(s):Jianwei Hu, Germina Ilas, Ian C Gauld, Jenny Tobin, Topi Tupasela, Tapani P Honkamaa, Marita Mosconi
Abstract:
This paper summarizes the analysis of the Passive Neutron Albedo Reactivity (PNAR) measurements using the ORIGEN data analysis module for…
Analysis Of Pnar Spent Fuel Safeguards Measurements Using The Origen Data Analysis Module
Type:Annual Meeting Proceedings
Author(s):Jianwei Hu, Germina Ilas, Ian C Gauld, Stephen J Tobin, Topi Tupasela, Tapani P Honkamaa, Marita Mosconi
Abstract:
This paper summarizes the analysis of the Passive Neutron Albedo Reactivity (PNAR) measurements for 23 boiling water reactor spent fuel…
Analysis On Essential Factors For Successful Denuclearization
Type:Annual Meeting Proceedings
Author(s):Makiko Tazaki, Hiroshi Tamai, Ryo Shimizu, Takashi Kimura, Takayoshi Nakatani, Kazunori Suda
Abstract:
In order to maintain nuclear nonproliferation regime based on the Treaty on the Non-Proliferation of Nuclear Weapons, it is indispensable…
Analyzing Elemental Composition Using Nrta With An Isotopic Neutron Source
Type:Annual Meeting Proceedings
Author(s):Farheen Naqvi
Abstract:
Neutron resonance transmission analysis technique (NRTA) uses the resonance phenomenon to identify the isotopic composition of unknown…
Analyzing Information On Nuclear-Related Trade, Industrial Capabilities And Technical Assistance In The Context Of Safeguards Implementation And State Evaluation
Type:Annual Meeting Proceedings
Author(s):Malin Ardhammar, Rabih Ayache, Menekse Basturk Tatlisu, Stephen Francis, Marcy R. Fowler, Nicholas Gillard, Jacqueline Idinger, Elena Marinova, Nancy Olea, Catherine Pasterczyk
Abstract:
The analysis of information on a State’s nuclear-related trade, industrial capabilities and received technical assistance contributes to…
Applicability Of The JCPOA Experience To The Korean Peninsula Crisis Resolution
Type:Annual Meeting Proceedings
Author(s):Jaewoo Shin, Veronika Bedenko, Laura Rockwood
Abstract:
The paper explores what lessons can be drawn from the process and framework of negotiations on the Joint Comprehensive Plan of Action (…
Application Of Approximate Bayesian Computation In Neutron Multiplicity Measurements: Providing Uncertainty Distributions And Correlations In All The Assay-item Parameters
Type:Annual Meeting Proceedings
Author(s):Tom L. Burr, Andrea Favalli, Andrea Favalli, Brian Weaver, Daniela Henzlova
Abstract:
Uncertainty quantification (UQ) for safeguards applications can be approached from physical first principles (“bottom-up”) or approached…
Application Of Virtual Tour For Online Training Safeguards Exercises
Type:Annual Meeting Proceedings
Author(s):Megumi Sekine, Hidetoshi Sukegawa, Yasuhiro Ishikuro, Koji Ohyama, Takashi Obata, Kazuhiko Hayashi, Naoko Inoue
Abstract:
The Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of the Japan Atomic Energy Agency (JAEA) developed…
Application Of γ-γ Coincidence Technique With CLLBC Detectors To Enhance 134Cs Gamma Signal In A Mixed Gamma Field
Type:Annual Meeting Proceedings
Author(s):Jay P Joshi, William Charlton
Abstract:
Measurement and quantification of fission products such as 134Cs, 137Cs, and 154Eu can be used to determine burnup of used nuclear fuel by…
Arcana: The National Nuclear Materials And Signatures Database
Type:Annual Meeting Proceedings
Author(s):Naomi Marks, Martin Robel
Abstract:
The National Nuclear Material Archive (NNMA) collects, characterizes, and preserves nuclear material samples of US origin. The NNMA…