Engineering Papers⌕ Search

SEARCH · Engineering Papers

Results for “Plutonium”

Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.

Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.

At least 559 records · Page 31

NNSS Soils Monitoring: Plutonium Valley (CAU366) FY2012

The U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), Nevada Site Office (NSO), Environmental Restoration Soils Activity has authorized the Desert Research Institute (DRI) to conduct field assessments of potential sediment transport of contaminated soil from Corrective Action Unit (CAU) 366, Area 11 Plutonium Valley Dispersion Sites Contamination Area (CA) during precipitation runoff events.

54 ENVIRONMENTAL SCIENCES↗

Corrective Action Plan for Corrective Action Unit 366: Area 11 Plutonium Valley Dispersion Sites, Nevada National Security Site, Nevada

This Corrective Action Plan has been prepared for Corrective Action Unit (CAU) 366, Area 11 Plutonium Valley Dispersion Sites, in accordance with the Federal Facility Agreement and Consent Order (FFACO, 1996 as amended). CAU 366 consists of the following six Corrective Action Sites (CASs) located in Area 11 of the Nevada National Security Site.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Factors Controlling Redox Speciation of Plutonium and Neptunium in Extraction Separation Processes

The objective of the project was to examine the factors controlling redox speciation of plutonium and neptunium in UREX+ extraction in terms of redox potentials, redox mechanism, kinetics and thermodynamics. Researchers employed redox-speciation extractions schemes in parallel to the spectroscopic experiments. The resulting distribution of redox species w studied using spectroscopic, electrochemical, and spectro-electrochemical methods. This work resulted in collection of data on redox stability and distribution of redox couples in the nitric acid/nitrate electrolyte and the development of redox buffers to stabilize the desired oxidation state of separated radionuclides. The effects of temperature and concentrations on the redox behavior of neptunium were evaluated.

Paulenova, Alena↗

Closure Report for Corrective Action Unit 366: Area 11 Plutonium Valley Dispersion Sites, Nevada National Security Site, Nevada

This Closure Report (CR) presents information supporting closure of Corrective Action Unit (CAU) 366, Area 11 Plutonium Valley Dispersion Sites, and provides documentation supporting the completed corrective actions and confirmation that closure objectives for CAU 366 were met. This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; the U.S. Department of Energy (DOE), Environmental Management; the U.S. Department of Defense; and DOE, Legacy Management (FFACO, 1996 as amended).

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

A Lapping Technique for Metallic, Alpha-Phase, Plutonium: Achieving and Measuring Nano-Meter Roughness and Sub-Micron Flatness

There are various processes and techniques by which one can achieve well polished (highly reflective) and smooth, flat (low roughness) surfaces on a wide variety of materials. Historically, precision lapping processes were first applied to optical materials for the production of lenses for telescopes and microscopes. These processes have been developed by a multitude of technicians over the centuries and reported in countless publications. These same grinding, lapping and polishing processes have been of great importance in the fabrication and structural characterization of countless optical materials and engineering structures, e.g. optics, Si wafers, precision machined surfaces, engineered devices, low-friction surfaces, mechanical systems, metallographic examination of microstructures, to name but a few. The development of lapping and polishing processes and techniques as applied to extremely hazardous and highly (chemically) reactive materials, such as metallic plutonium (Pu), has been limited. This is due in part due to the sensitive nature of the work as applied to nuclear applications, and limited access and need to work with these materials. For the limited information regarding polishing and lapping of Pu materials that has been documented, there has been virtually no quantitative assessment of qualities such as surface roughness and flatness on the nanometer scale. In this report we use the word “lapping” to refer to the traversing of a specimen surface across an abrasive surface in a controlled manner in order to achieve smooth/flat surfaces. We differentiate lapping from polishing, in that we define polishing as traversing of a sample surface across a non-abrasive surface that contains loose abrasive particles, e.g. diamond paste on nylon nap, in order to achieve a highly reflective surface. In this report, we will detail a simple and repeatable lapping process as applied to alpha-phase metallic Pu. We will provide quantitative measurements of the surface roughness and flatness. We will demonstrate the ability to achieve sub-10 nm surface roughness and to lap millimeter-size areas to a flatness of approximately 1.0 µm. Additionally, we will assess the current limitations and discuss any artifacts that arise as a result of our polishing processes applied to metallic Pu materials.

36 MATERIALS SCIENCE↗

A Calibration to Predict the Concentrations of Impurities in Plutonium Oxide by Prompt Gamma Analysis Revision 2

This report documents the new PG calibration regression equation. These calibration equations incorporate new data that have become available since revision 1 of “A Calibration to Predict the Concentrations of Impurities in Plutonium Oxide by Prompt Gamma Analysis” was issued [3] The calibration equations are based on a weighted least squares (WLS) approach for the regression. The WLS method gives each data point its proper amount of influence over the parameter estimates. This gives two big advantages, more precise parameter estimates and better and more defensible estimates of uncertainties. The WLS approach makes sense both statistically and experimentally because the variances increase with concentration, and there are physical reasons that the higher measurements are less reliable and should be less influential. The new magnesium calibration includes a correction for sodium and separate calibration equation for items with and without chlorine. These additional calibration equations allow for better predictions and smaller uncertainties for sodium in materials with and without chlorine. Chlorine and sodium have separate equations for RICH materials. Again, these equations give better predictions and smaller uncertainties chlorine and sodium for RICH materials.

Instrumentation Related to Nuclear Science & Techn↗

Preparation and Characterization of a Master Blend of Plutonium Oxide for the 3013 Large Scale Shelf-Life Surveillance Project

A mixture of chlorine-containing, impure plutonium oxides has been produced and has been given the name Master Blend. This large quantity of well-characterized chlorinecontaining material is available for use in the Integrated Surveillance and Monitoring Program for shelf-life experiments. It is intended to be representative of materials packaged to meet DOE-STD-3013.1 The Master Blend contains a mixture of items produced in Los Alamos National Laboratory’s (LANL) electro-refining pyrochemical process in the late 1990s. Twenty items were crushed and sieved, calcined to 800ºC for four hours, and blended multiple times. This process resulted in four batches of Master Blend. Calorimetry and density data on material from the four batches indicate homogeneity.

3013 electro-refining storagage radioactive↗

Gamma-ray imaging assay of cells 3-5 of the east cell line in the 235-F plutonium fuel form facility

In August and September, 2016, scientists from the Savannah River National Laboratory (SRNL) took a series of gamma-ray imaging measurements through the cell windows in front of Cells 3-5 on the east line of the Plutonium Fuel Form (PuFF) Facility using an electrically cooled, high-purity germanium detector. A Germanium Gamma Ray Imager (GeGI) was utilized since it allowed for the location from which the radiation was being emitted to be identified by incoming gamma-ray energy. This measurement technique provided a tool which allowed for the relative concentration of Pu-238 to be mapped throughout each cell. The mapping and new assay data were then used to update the model used in an assay discussed in a 2014 report (SRNL-STI-2014-00629) and to calculate a more accurate value for the holdup in each of the cells [1]. Note that the mapping and new assay data did not replace the previous assay data in the model. Rather, the mapping and new assay data provided additional details on source distribution, which supplemented the previous assay data.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Using MCNP6 to Estimate Fission Neutron Properties of a Reflected Plutonium Sphere

The purpose of this project was to determine the fission multiplicity distribution, p(v), for the Beryllium Reflected Plutonium (BeRP) ball and to determine whether or not it changed appreciably for various High Density Polyethylene (HDPE) reflected configurations. The motivation for this project was to determine whether or not the average number of neutrons emitted per fission, v, changed significantly enough to reduce the discrepancy between MCNP6 and Robba, Dowdy, Atwater (RDA) point kinetic model estimates of multiplication. The energy spectrum of neutrons that induced fissions in the BeRP ball, NIF (E), was also computed in order to determine the average energy of neutrons inducing fissions, NIF . p(v) was computed using the FMULT card, NIF (E) and NIF were computed using an F4 tally with an FM tally modifier (F4/FM) card, and the multiplication factor, k eff , was computed using the KCODE card. Although NIF (E) changed significantly between bare and HDPE reflected configurations of the BeRP ball, the change in p(v), and thus the change in v, was insignificant. This is likely due to a difference between the way that NIF is computed using the FMULT and F4/FM cards. The F4/FM card indicated that NIF (E) was essentially Watt-fission distributed for a bare configuration and highly thermalized for all HDPE reflected configurations, while the FMULT card returned an average energy between 1 and 2 MeV for all configurations, which would indicate that the spectrum is Watt-fission distributed, regardless of the amount of HDPE reflector. The spectrum computed with the F4/FM cards is more physically meaningful and so the discrepancy between it and the FMULT card result is being investigated. It is hoped that resolving the discrepancy between the FMULT and F4/FM card estimates of NIF(E) will provide better v estimates that will lead to RDA multiplication estimates that are in better agreement with MCNP6 simulations.

72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗

Status Summary of Chemical Processing Development in Plutonium-238 Supply Program

This document summarizes the status of development of chemical processing in the Plutonium-238 Supply Program (PSP) near the end of Demonstration 1. The objective of the PSP is “to develop, demonstrate, and document a production process that meets program objectives and to prepare for its operation” (Frazier et al. 2016).

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Closure Report for Corrective Action Unit 415: Project 57 No. 1 Plutonium Dispersion (NTTR) Nevada Test and Training Range, Nevada, Revision 0 with ROTC-1

This Closure Report (CR) presents information supporting the closure of Corrective Action Unit (CAU) 415: Project 57 No. 1 Plutonium Dispersion, which is located on Range 4808A of the Nevada Test and Training Range (NTTR). This CR complies with the requirements of the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management. CAU 415 comprises one corrective action site (CAS): NAFR-23-02, Pu Contaminated Soil. The purpose of this CR is to provide justification and documentation supporting the recommendation that no further corrective action is needed for CAU 415 based on the implementation of the corrective action of Closure in Place.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Modernizing the nation’s stockpile: Plutonium Surface Science Lab

Los Alamos National Laboratory is the Department of Energy’s premier nuclear weapons lab and the nation’s Plutonium R&D Center of Excellence. The Lab combines decades of expertise with one-of-a-kind tools to ensure the safety and stability of the nation’s nuclear stockpile.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗

Parametric Studies for Plutonium Metal-Water Mixtures in Arrays of 6-Inch Columns

A parametric study for arrays of 6-inch diameter tank columns was performed in order to assist in the practical development of limits for plutonium solution operations. This technical document utilizes approaches taken in NCS-TECH-10-009 [Reference 1]. While this technical document expands on areas where the authors feel appropriate, it does not attempt to recreate all parts of the existing technical document. This technical document is intended to be used in conjunction with the previous technical document. The results reported in this technical document may be used to support facility-specific program documents or individual Criticality Safety Evaluation Documents (CSEDs). This technical document does not derive any specific requirements. Caution should be taken when applying these results; it is the criticality safety analyst's responsibility, if he/she chooses to utilize this technical document, to properly assess the applicability of the results presented herein for his/her application.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Evaluation of the Need to Consider Colloid-Facilitated Plutonium Transport in Contaminant Boundary Calculations for Pahute Mesa at the Nevada Nuclear Security Site

The testing of nuclear weapons at the Nevada National Security Site (NNSS), formerly the Nevada Test Site, has led to the deposition of substantial quantities of plutonium (Pu) into the environment. While tritium ( 3 H) is the most abundant anthropogenic radionuclide deposited in the NNSS subsurface from an activity standpoint (4.7×10 6 TBq decay corrected to September 23, 1992), Pu is the most abundant anthropogenic element by mass. Between 1951 and 1992, 828 underground nuclear tests were performed and approximately 2.8 metric tons (3.1×10 4 TBq) of Pu remains in the NNSS subsurface (Smith et al., 2003). The vast majority of this Pu is sequestered in nuclear melt glass that pools at the bottom of cavities formed by nuclear explosions.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Assessment of the current status of cross-section evaluations of plutonium minor isotopes

Much attention have been given to nuclear data and reaction evaluations relative to the major actinides, as they constitute the main component in many nuclear applications. For this reason, the currency of evaluated files for minor actinides has not been maintained with the same level of accuracy. Motivated by future applications that will be sensitive to minor isotopes of plutonium, this report aims to review and assess the current status of the reaction evaluations in the ENDF/B library for 238;240;241;242 Pu, as well as to compile available experimental data that have not yet been incorporated into evaluated files.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗