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At least 847 records · Page 47

Brief Overview of the DOE/NNSA Nuclear Criticality Safety Program [Slides]

The mission of the DOE/NNSA Nuclear Criticality Safety Program is to provide sustainable expert leadership, direction and the technical infrastructure necessary to develop, maintain, and disseminate the essential technical tools, training, and data required to support safe, efficient fissionable material operations within DOE. The vision of the program is to create a continually improving, adaptable, and transparent program that communicates and collaborates globally to incorporate technology, practices, and programs to be responsive to the essential technical needs of those responsible for developing, implementing, and maintaining nuclear criticality safety.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗

GNDS v2.0 release and future developments [Slides]

This presentation begins by discussing the major changes in v2.0 of GNDS and that the GNDS-2.0 formatted libraries are now available. It also examines how code support for GNDS is growing with processing codes, APIs and transport codes, and evaluation/testing codes. The presentation states that while migrating to GNDS can be a major effort it worthwhile, especially for anyone who is just getting started as nuclear data creator or user. Additionally, this presentation outlines the established milestones that the EG-GNDS (the group in charge of GNDS specs) has for the next GNDS release and elaborates on the first goal, which is to migrate GNDS specifications to the new JSON schema language.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Verification and validation testing and tools: comparison between MCNP code versions and nuclear data libraries [Slides]

This presentation discusses the primary goal of software testing which is to test the code for correctness. It also discusses the results for individual suites and the role of validation and verification also referred to in the presentation as V&V. In summation, the V&V framework enables easy comparison between calculations performed with different code versions and/or nuclear data libraries. This entire framework will be distributed with the upcoming MCNP6.3 release. V&V test suites shown and several that were not (Criticality, LAQGSM, Lockwood) will be distributed in the new framework.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Results and Responses for the 2022 User Forum Survey [Slides]

This presentation discusses the results of a MCNP user survey. Example of questions asked include: "Which MCNP particle types do you typically use?," "What sort of simulations do you run most often?," "Do you build the code?," "Which variance reduction methods do you use?," "Opinions on HDF5," with frequent discussions regarding each question.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗

MCNP6.3: A Year in Review [Slides]

This presentation discusses the past year and the many accomplishments of the MCNP6.3 team. It states that the MCNP6.3 release is imminent and that the approved, final documents have been making their way to the website. The code executables and source are already packaged up for distribution and the new installer is being finalized and tested now, for all platforms. The package will be sent to RSICC before the end of October 2022. Additionally, the presentation discusses some things to think about as MCNP6.3 is requested and/or used. For example, many of the recent efforts have been focused on making development, updates, and distribution of the code and documents more robust and streamlined. They will be revising/updating documents more frequently than ever before and they will be exploring avenues to distribute official patches to MCNP6.3. As they explain, this allows them to be more responsive to bugs and issues that are identified. In conclusion, the application of a patch to MCNP6.3 will require having the source code.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗

Index of Classified Reports Collection now available Vital resource for Weapons researchers, today’s mission work

The collection is made up of classified technical reports containing weapons data dating back to the start of the nuclear security enterprise. The information is compiled into reports, slides, handbooks and literature. It originated from Los Alamos, Lawrence Livermore, and Sandia Labs, as well as from the Department of Defense and likely every other organization involved in nuclear testing, including contractors and those that are now defunct.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗

Theoretical and calculable dependent variables and their covariance in nuclear data libraries [Slides]

This presentation begins by defining observables, including theoretical observable, calculable observable, and measured observable. It also provides definitions and examples of experimental effects. Additionally, uncertainty in evaluated libraries and a metric to probe evaluated uncertainty is presented. In conclusion, being related to theoretical quantities such as resonance parameters, the uncertainty in ENDF libraries (e.g., ENDF/B-VIII.0) can be overestimated because it is usually evaluated under the guidance of experimental uncertainty: lim Δσexp.corr.→0 Δσ = Δσ theoretical model . The presentation states that a clear distinction of the uncertainty between nuclear theoretical models and experimental corrections should be revisited and this is important since (e.g., transport) simulations need theoretical quantities convoluted with specific operational parameters and material configurations. It also states that strong coupling between uncertainty quantification methodologies and optimization procedures exists, and it is necessary to develop methodologies to obtain uncertainty on theoretical models from physical and mathematical constraints.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

Subcritical Assembly at ORNL [Slides]

This presentation discusses the US Department of Energy (DOE) Nuclear Criticality Safety Program (NCSP), specifically regarding the training and education courses. Also discussed is the AGN-201M reactor and fuel disk. Additionally, the ORSA conceptual design and design changes are presented. In conclusion, the ORSA design has moved from conceptual to implementable. ORSA hands-on experiments will remain subcritical under normal and credible abnormal conditions. The ORSA location will have minimal security and safety basis impact and is feasible for a diversity of students. The implementation of ORSA will improve upon NCSP T&E’s vision to remain adaptable and responsive.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

An Analysis of the Johnson-Lindenstrauss Lemma with the Bivariate Gamma Distribution

Probabilistic proofs of the Johnson-Lindenstrauss lemma imply that random projection can reduce the dimension of a data set and approximately preserve pairwise distances. If a distance being approximately preserved is called a success, and the complement of this event is called a failure, then such a random projection likely results in no failures. Assuming a Gaussian random projection, the lemma is proved by showing that the no-failure probability is positive using a combination of Bonferroni's inequality and Markov's inequality. This paper modifies this proof in two ways to obtain a greater lower bound on the no-failure probability. First, Bonferroni's inequality is applied to pairs of failures instead of individual failures. Second, since a pair of projection errors has a bivariate gamma distribution, this probability of a pair of successes is bounded using an inequality from [Jensen, 1969]. If n is the number of points to be embedded and μ is the probability of success, then this leads to an increase in the lower bound on the no-failure probability of $\frac{1}{2}$ ($\genfrac{}{}{0pt}{}{n}{2}$) (1- μ ) 2 is ($\genfrac{}{}{0pt}{}{n}{2}$) is even and $\frac{1}{2}$ (($\genfrac{}{}{0pt}{}{n}{2}$)-1) (1- μ ) 2 if ($\genfrac{}{}{0pt}{}{n}{2}$) is odd. For example, if n =10 5 points are to be embedded in k =10 4 dimensions with a tolerance of ϵ=0.1, then the improvement in the lower bound is on the order of 10 -14 . We also show that further improvement is possible if the inequality in [Jensen, 1969] extends to three successes, though we do not have a proof of this result.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗

Improved Chemical Kinetics and Algorithms for More Accurate, Faster Simulations

Internal combustion engine design is increasingly driven by computational models used to predict change in performance due to change of design. The design process previously depended on limited intuition and expensive and time-consuming physical testing. Improved model capabilities shorten design cycles and enable the production of cleaner and more efficient engines. This project focuses on advancing the state of the art in internal combustion engine simulations. The overarching goal is to enable predictive models and reduced time to solution for simulations that impact combustion engine design.

02 PETROLEUM↗

Big Data Analysis of Synchrophasor Data: Outcomes of Research Activities Supported by DOE FOA 1861

This report describes the key outcomes of research activities sponsored by the Department of Energy’s Funding Opportunity Announcement (FOA) number 1861 that was aimed at advancing the state-of-the-art in big data analytics applied to transmission-level synchrophasor measurements. The FOA resulted in eight research grants where the awardees developed machine learning and artificial intelligence tools and approaches. The commonalities in tools and approaches used by the awardees are explored, and insights gained from how the project outcomes might be operationalized are discussed. This report does not seek to comprehensively summarize all research supported by the FOA, rather it focuses on enabling the fast dissemination of major findings to the broader power systems community.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗

LANL Accident Analysis and Atmospheric Dispersion Modeling [Slides]

After completion of this course, the analyst will: 1) Understand the differences between an unmitigated analysis and a mitigated analysis; 2) Know the key receptors that a radiological and hazardous chemical accident analysis must consider; 3) Understand how to calculate a radiological release source term and a toxic chemical release source term for various phenomenology; 4) Understand how to calculate a radiological and toxic chemical health insult to key receptors and compare to consequence thresholds; 5) understand the role of atmospheric dispersion in radiological and toxic consequence calculations; 6) understand atmospheric dispersion modeling and the inputs to and outputs from the MACCS/POSTMAX codes.

54 ENVIRONMENTAL SCIENCES↗

TA-18-1 Slotin Building Restoration – Summary of Work to be Performed

The National Historic Preservation Act (NHPA) requires LANL to identify, evaluate, record, and protect eligible historic properties like TA-18-1 Slotin Building. The Environmental Protection and Compliance-Environmental Stewardship (EPC-ES) Cultural Resources program consults with the New Mexico State Historic Preservation Office (SHPO) on undertakings that may affect these properties. TA-18-1 Slotin Building is an exceptionally significant Manhattan Project Property that has been determined eligible for the National Register of Historic Places and is included within the boundary of the Manhattan Project National Historical Park. The building was constructed in 1946 and served as laboratory space for criticality testing. It is the location of the May 1946 criticality accident that resulted in the death of Louis Slotin. As a result of the accident, new procedures and designs for criticality experiments were implemented to prevent further accidents.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗

Triage Exam, August 2006 (V.2.2)

The following questions test knowledge relevant to the DOE Radiological Triage and DHS Secondary Reachback programs. There is no time limit, and you may use any reference materials you like. Each question has only one best answer. There are 20 questions, and a score of 80% is required to pass.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

RCT Unit 1 Exam Review [Slides]

The terminal objective is stated as: Given the need to perform duties as an RCT, recognize fundamental concepts of radiation protection, in accordance with DOE-HDBK-1122, Radiation Control Technician Training .

61 RADIATION PROTECTION AND DOSIMETRY↗

TA-55 building entrusted with more plutonium capability: What does it mean for the mission?

The first floor of the Radiological Laboratory/Utility/Office Building at TA-55, known as RLUOB (roo-lob) or Plutonium Facility-400 (PF-400), will soon become a bustling and dynamic space as employees and programs increase their work scope thanks to the new hazard category 3 designation. On Feb. 7, NNSA gave the final stamp of approval designating RLUOB as a hazard category 3 (HC-3) nuclear facility. RLUOB has been designated as a radiological facility (less than HC-3) since 2013, when the first phase of RLUOB Equipment Installation was completed. HC-3 is a level up in facility hazard category, a major effort to support the national security mission.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗

Release of ENDF/B-VIII.1β1-Based ACE Data Files

On March 1 st , 2023, the National Nuclear Data Center (NNDC) released the ENDF/B-VIII.1β1 nuclear data library, which contained neutron, spontaneous and neutron-induced fission yield, and alpha sublibraries. The library was released in the standard Evaluated Nuclear Data File (ENDF) format. The files can be accessed on Brookhaven National Laboratory’s GitLab. The thermal scattering law (TSL) sublibrary will be released at a later date. The files provided in the neutron sublibrary were processed into A Compact ENDF (ACE)-formatted files, verified, and validated by the XCP-5 Nuclear Data Team. The resulting collection of ACE files will be referred to as the “e81b1” library. This report details the processing of these files and the quality assurance approach taken. This is not intended to be a full validation effort; rather, this library is intended to simply reproduce the released files for further validation testing by the community. The e81b1 ACE library will be released to the NNDC for access through GitLab and hosted locally on LANL computing resources. This library is only intended for analysis to support the future ENDF/B-VIII.1 release and should not be used for production results.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗