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At least 631 records · Page 35

Final Radiological Assessment of External Exposure for CLEAR-Line Americium Recovery Operations

Los Alamos National Laboratory is currently planning to implement an americium recovery program. The americium, ordinarily isotopically pure 241Am, would be extracted from existing Pu materials, converted to an oxide and shipped to support fabrication of americium oxide-beryllium neutron sources. These operations would occur in the currently proposed Chloride Extraction and Actinide Recovery (CLEAR) line of glove boxes. This glove box line would be collocated with the currently-operational Experimental Chloride Extraction Line (EXCEL). The focus of this document is to provide an in-depth assessment of the currently planned radiation protection measures and to determine whether or not further design work is required to satisfy design-goal and ALARA requirements. Further, this document presents a history of americium recovery operations in the Department of Energy and high-level descriptions of the CLEAR line operations to provide a basis of comparison. Under the working assumptions adopted by this study, it was found that the evaluated design appears to mitigate doses to a level that satisfies the ALARA-in-design requirements of 10 CFR 835 as implemented by the Los Alamos National Laboratory procedure P121. The analyses indicate that extremity doses would also meet design requirements. Dose-rate calculations were performed using the radiation transport code MCNP5 and doses were estimated using a time-motion study developed in consort with the subject matter expert. A copy of this report and all supporting documentation are located on the Radiological Engineering server at Y:\Rad Engineering\2013 PROJECTS\TA-55 Clear Line.

61 RADIATION PROTECTION AND DOSIMETRY↗

Sandia National Laboratories Ten-Year Site Plan (Fiscal Year 2016)

During the next 10 years, Sandia’s most critical investments are as follows: 1) Complete the Sandia Silicon Fabrication Revitalization (SSiFR) initiative to replace outdated microelectronics production tools, capital equipment, and processes at the Microsystems and Engineering Sciences Applications (MESA) Complex. 2) Plan, design, and construct the Rad Hard Foundry to sustain the microelectronics-trusted foundry capability in support of critical microsystems science and technology (S&T) for NNSA and SPP. 3) Plan, design, and construct the Weapons Engineering Facility (WEF) to recapitalize core NW capabilities in R&D facilities and excess major buildings that are at the end of their designed service lives. 4) Plan, design, and construct the Emergency Operations and Response Center (EORC) to provide emergency incident management from a modern facility that serves and supports both local and national response teams. 5) Continue to facilitate the deactivation and eventual renovation or demolition of Building 892, a 60-year old facility that is rapidly approaching functional obsolescence.

96 KNOWLEDGE MANAGEMENT AND PRESERVATION↗

Prompt Radiation-Induced Conductivity in Polyurethane Foam and Glass Microballoons

We performed measurements and analyses of the prompt radiation-induced conductivity (RIC) in thin samples of polyurethane foam and glass microballoon foam at the Little Mountain Medusa LINAC facility in Ogden, UT. The RIC coefficient was non-linear with dose rate for polyurethane foam; however, typical values at 1E11 rad(si)/s dose rate was measured as 0.8E-11 mho/m/rad/s for 5 lb./cu ft. foam and 0.3E-11 mho/m/rad/s for 10 lb./cu ft. density polyurethane foam. For encapsulated glass microballoons (GMB) the RIC coefficient was approximately 1E-15 mho/m/rad/s and was not a strong function of dose rate.

36 MATERIALS SCIENCE↗

Inline CBET Model Including SRS Backscatter

Cross-beam energy transfer (CBET) has been used as a tool on the National Ignition Facility (NIF) since the first energetics experiments in 2009 to control the energy deposition in ignition hohlraums and tune the implosion symmetry. As large amounts of power are transferred between laser beams at the entrance holes of NIF hohlraums, the presence of many overlapping beat waves can lead to stochastic ion heating in the regions where laser beams overlap [P. Michel et al., Phys. Rev. Lett. 109, 195004 (2012)]. Using the CBET gains derived in this paper, we show how to implement these equations in a ray-based laser source for a rad-hydro code.

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗

Measurement of the ambient gamma dose equivalent and kerma from the small 252 Cf source at 1 meter and the small 60 Co source at 2 meters

NASA Langley Research Center requested a measurement and determination of the ambient gamma dose equivalent rate and kerma at 100 cm from the 252 Cf source and determination of the ambient gamma dose equivalent rate and kerma at 200 cm from the 60 Co source for the Radiation Budget Instrument Experiment (Rad-X). An Exradin A6 ion chamber with Shonka air-equivalent plastic walls in combination with a Supermax electrometer were used to measure the exposure rate and free-in-air kerma rate of the two sources at the requested distances. The measured gamma exposure, kerma, and dose equivalent rates are tabulated.

07 ISOTOPE AND RADIATION SOURCES↗

Measurement of the neutron spectrum and ambient neutron dose rate equivalent from the small 252 Cf source at 1 meter

NASA Langley Research Center requested a measurement of the neutron spectral distribution and fluence from the 252 Cf source (model NS-120, LLNL serial # 7001677, referred as the SMALL Cf source) and determination of the ambient neutron dose rate equivalent and kerma at 100 cm for the Radiation Budget Instrument Experiment (Rad-X). The dosimetric quantities should be based on the neutron spectrum and the current neutron-to-dose conversion coefficients.

07 ISOTOPE AND RADIATION SOURCES↗

The search for a 100MA RancheroS magnetic flux compression generator

The Eulerian AMR rad-hydro-MHD code Roxane was used to investigate modifications to existing designs of the new RancheroS class of Magnetic Flux Compression Generators (FCGs) which might allow some members of this FCG family to exceed 100 MA driving a 10 nH static load. This report details the results of that study and proposes a specific generator modification which seems to satisfy both the peak current and desired risetime for the current pulse into the load. The details of the study and necessary modifications are presented. For details of the LA43S RancheroS FCG design and predictions for the first use of the generator refer to the relevant publications.

42 ENGINEERING↗

A simple model of the effect of ocean ventilation on ocean heat uptake

Presentation includes slides on Earth System Models vs. Simple Climate Models; A Popular SCM: Energy Balance Model of Anomalies; On calibrating against one ESM experiment, the SCM correctly captures that ESM's surface warming response with other forcings; Multi-Model Analysis: Multiple ESMs, Single SCM; Posterior Distributions of ECS; However In Excess of 90% of TOA Energy Imbalance is Sequestered in the World Oceans; Heat Storage in the Two Layer Model; Heat Storage in the Two Layer Model; Including TOA Rad. Imbalance and Ocean Heat in Calibration Improves Repr., but Significant Errors Persist; Improved Vertical Resolution Does Not Fix Problem; A Series of Expts. Confirms That Anomaly-Diffusing Models Cannot Properly Represent Ocean Heat Uptake; Physics of the Thermocline; Outcropping Isopycnals and Horizontally-Averaged Layers; Local interactions between outcropping isopycnals leads to non-local interactions between horizontally-averaged layers; Both Surface Warming and Ocean Heat are Well Represented With Just 4 Layers; A Series of Expts. Confirms That When Non-Local Interactions are Allowed, the SCMs Can Represent Both Surface Warming and Ocean Heat Uptake; and Summary and Conclusions.

58 GEOSCIENCES↗

Cygnus Performance on Vega

The Cygnus Dual Beam Radiographic Facility consists of two identical radiographic sources, Cygnus 1 and Cygnus 2, each with the following specifications: 4-Rad dose at 1 m, 1-mm spot size, 50-ns pulse length, and 2.25-MeV endpoint energy. Cygnus 1 and 2 have been used for radiography of subcritical experiments at the Nevada National Security Site (NNSS) since 2004. The Cygnus Facility is located in an underground tunnel complex named U1a. The Cygnus sources were developed as a primary diagnostic for these experiments. The first subcritical experiment to utilize Cygnus, Armando, was executed on May 25, 2004. Since Armando, several other subcritical experiments have been executed in front of Cygnus, as well as physics experiments and plutonium calibration tests.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Multiple Ion Temperatures

We consider the implementation of multiple ion temperatures in an existing rad-hydro code. Particular issues which arise including splitting of the energy deposition terms including those involved in modeling shocks in the hydro; the calculation of thermonuclear burn rates in the presence of different ion temperatures; thermal diffusion with multiple temperatures including the difficulty associate with contact discontinuities; and the thermal coupling between different ions and between the individual ions and the electrons. A few simulations are performed to demonstrate the resulting improved modeling capability.

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗

Analysis of Uranium Ion Exchange Resin from the 200 West Pump-and-Treat Facility

The 200 West Area Pump-and-Treat (P&T) Facility at the Hanford Site is a multifunctional groundwater treatment facility consisting of unit processes to remove radionuclides such as uranium (U) and technetium (Tc-99) as well as other inorganic (nitrate and hexavalent chromium), and organic (carbon tetrachloride and trichloroethene) contaminants. The RAD building of the P&T Facility removes U and Tc-99 using ion exchange chromatography. In 2016, the Purolite A530E resin used for the Tc-99 removal was replaced and the spent resin was analyzed. In addition to Tc-99, the Purolite A530E resin also retained I-129 and Co-60; however, the resin loading was dominated by common groundwater constituents such as calcium, iron, silicon, and sulfate.

54 ENVIRONMENTAL SCIENCES↗

Self-powered Wireless Dual-mode Langasite Sensor for Pressure/Temperature Monitoring of Nuclear Reactors

Safety issues in nuclear power plants are of extreme importance. Numerous sensors are used within nuclear power plants for sensing and monitoring of its critical operation parameters. As currently implemented, during massive losses of power across the plant in accidents, the backup batteries for the monitoring sensors will ultimately be drained and can cease to operate. The overall objective of this NEUP project is to develop a novel self-powered wireless hybrid sensor which can accurately monitor both pressure and temperature using a single device, even in the extreme harsh environments of severe nuclear accidents, without the requirement of external electricity. At Virginia Tech side, a heat pipe assisted thermoelectric generator (TEG) energy harvester and associated power management and data transmission circuits were developed. The energy harvester can produce electrical power continuously, even in loss of plant and external power situations, providing power for important data transmission for accident diagnosis. The self-powered sensing system could be integrated directly onto key nuclear components including pipes, pump housings, heat exchangers, reactor vessels, and shielding structures inside and outside of the reactor core. Two TEG based energy harvesters which can work in relatively low (50-250 ºC) and high temperature ranges (250-350 ºC) were established and tested. In the prototypes, heat pipes were introduced to reduce the heat resistances of the device at the hot and cold ends. The power output of the heat pipe assisted TEG module is 2.22 W, which is 6 times more than one using an aluminum rod. In-lab tests showed that these devices canmeet the requirement to power the sensors and circuit during normal and off-normal conditions.Amodel was then built to analyze the thermal network in the energy harvester, and was used to optimize its performance and reduce its geometry size. The design and testing of the vibrational energy harvester were completed. The harvester, has shown to effectively increase the vibrational potential of the main coolant pump, though it has been shown that thermal energy has a much higher potential for the powering of sensors. In this project, a self-start charger circuit for the energy harvester was designed to regulate and manage the power. An energy storage element was incorporated into the energy harvesting module for sensors and wireless transceivers in an off-normal situation. The signal conditioning and wireless communication electronic circuits were developed and tested in the lab. An important consideration for an energy harvester within a nuclear power plant is the level of radiation it will encounter during operation. The two main sources of radiation in a nuclear power plant are gamma and neutron radiation. Aradiation experiment was conducted in the Westinghouse Electric Company during which the prototypes were placed in a 106 rad radiation environment to test their ability to operate in the extreme environment. The results showed that this level of radiation had little effect on the performance of the TEGmaterial and heat pipe heat exchanging system. Its influence on the circuit was still under research, however the need for more development on radiation hardened electronics is needed. Pressure measurement based on piezoelectric crystal resonators has advantages over the commercially available methods like capacitive, electromagnetic, optical, potentiometric, and piezo resistive strain gauges. Since the output of piezoelectric based sensors are digital in format, it has a very high resolution, high accuracy, and long-term stability. Quartz is one of the commonly used piezoelectric material in digital pressure sensors design. This material is elastic in nature, providing high stability, high repeatability, high elasticity, repeatable mechanical behavior for many cycles of operation, and is free of hysteresis. The quartz resonator has a high Q, which means that very high vibration can be driven with the very low electric power. Langasite (LGS) is a new promising piezoelectric material that combines the advantageous properties of quartz with a better performance at high temperatures. LGS will not undergo any phase transitions up to its melting temperature of 1473 C, and hence, the application of Langasite in measuring pressure at high temperatures is promising. In this project, the design and fabrication of the piezo oscillator crystal for temperature and pressure measurement has been completed. The entire sensor has been fabricated and tested to see its sensitivity to temperature and pressure changes. The design and optimization of the radiation shielding systems that can effective protect the duel-mode Langasite sensor inside reactor core were demonstrated. To maximize the radiation shielding effectiveness, different types of materials are investigated based upon recent developments of radiation shielding systems including aluminum + Boron carbide and bismuth borosilicate glass B2O3 in addition to tungsten/B4C. New materials based upon metatheses is included as potential shielding to mitigate neutron fluencies. The radiation shielding effectiveness of selected composites are evaluated within a broader neutron spectrum from thermal, epithermal, fast (1 MeV) and 15 MeV neutrons. Performance analysis was also conducted to evaluate the effects of selected composite systems.Aconceptual design was also proposed for the packaging and integration of the radiation shielding system with the sensor, and its applicability within the reactor core was discussed. At end of the project, all components necessary for a complete sensing and monitoring system, including a langasite sensor, electrodes, the TEG harvester, an energy storage device, and power management and transmission electronics were integrated to demonstrate feasibility in powering the sensor. Finally, integration of each component into a full package, and a full demonstration were done.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Radiation Limits for CBETA Halbach Magnets (CBETA machine note #036)

The radiation damage calculation proceeds via several stages to get from energy lost by the beam to the field degradation from radiation damage: • Beam energy lost → Specific radiation dose. This just divides the absorbed energy by the mass it was deposited in to convert from J to Gy=J/kg, or rad=0.01Gy. • Specific radiation dose → Magnetisation loss. This depends on the permanent magnet material grade as well as the magnetisation geometry (the “H” field). Magnetisation loss rates have been studied in the literature and this note will follow the formula. • Magnetisation loss → Field change in beam aperture. For uniform magnetisation loss, this is simply proportional (1% less magnetisation = 1% less field). For nonuniform demagnetisation, nonlinear fields errors are also introduced. As the magnetic material has mu_r ~= 1, in this note the H and M fields will be scaled by mu_0 to put them in units of Tesla, which allows easy comparison with B fields and the residual field Br.

43 PARTICLE ACCELERATORS↗

Analysis of Technetium Ion Exchange Resin from the 200 West Pump-and-Treat Facility

The 200 West Area Pump-and-Treat (P&T) facility at the Hanford Site is a combined treatment train consisting of unit processes to remove radionuclides such as uranium (U) and technetium (Tc-99), other inorganic (nitrate and hexavalent chromium), and organic (carbon tetrachloride and trichloroethene) contaminants. The RAD building of the P&T facility removes Tc-99 and U using ion exchange chromatography, while the other inorganic and organic contaminants are removed in the facility’s BioPlant portion. The original design of the ion exchange resin for Tc-99 allowed for a 3-month Tc-99 breakthrough and subsequent resin canister change out. However, no Tc-99 breakthrough was noted for 3 years. The objective of the work was to analyze spent resin to determine if there are other compounds that may interfere with Tc-99 adsorption, and to determine whether the resin was removing any I-129.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Annual LDRD Report (FY2019)

The performance of Nuclear Deterrence (ND) systems could be improved by adopting advanced commercial CMOS technologies. However, the radiation hardness of these ND systems must be assured. This project quantified dose rate upset thresholds, allowing us to evaluate whether advanced commercial technologies can be used in rad hard applications. This project also evaluated the susceptibility of advanced commercial technologies to neutron displacement damage and single event effects, and developed hardness assurance methods. As a result of this work, Sandia is now collaborating more closely with DoD agencies and their contractors to understand and improve the radiation hardness of advanced commercial technologies. Sandia Capabilities (SPHINX, lon Beam Lab, FPGA test capabilities) were developed and are being utilized by other programs. Staff were trained to do radiation survivability testing and developed proposals that were funded. Internal and external collaborations and partnerships were developed, including with Georgia Tech. This project received the Best Paper award at the 2019 Hardened Electronics And Radiation Technology (HEART) Conference.

36 MATERIALS SCIENCE↗

Selective hydrothermal extraction of lanthanides: Mimicking natural ore-forming processes [Slides]

Rare Earth Elements (REE) consumption in the US was 20,000 metric ton in 2018. China controls 97% of the global REE market. The aims for new technology are to 1. Avoid investing in extraction of cheap LREE, extract M/HREE only → increase the value of the intermediate/final product, 2. Exclude extraction and concentration of U and Th → avoid investment in rad remediation, and 3. Maximize environmental friendliness of the technology. Hints from nature can aid in achieving these amis.

01 COAL, LIGNITE, AND PEAT↗

Encryption of Signal Pulses to Replace Tamper-indicating Conduit

In order to verify signal integrity and point of origin for TTL pulse data used in IAEA systems, and to avoid the need for expensive tamper-indicating conduit or electronic techniques, we propose the development of a signal pulse signing and encryption in-line device. In measurement applications in which the data acquisition electronics is separate from the enclosed, sealed detector, tamper-indicating techniques are required to protect raw TTL pulse streams between the detector and the data acquisition module, i.e UMSR. The goal of this proposed project is to design a rad-tolerant transmitter that would mount inside the sealed detector system and a receiver in the sealed electronics cabinet with the data acquisition instrument. This transmitter/receiver pair would digitally sign and encrypt the pulse stream data at the detector then transmit the data to the sealed cabinet where the receiver would decrypt the data and reproduce the original pulse stream. Existing tamper indicating techniques, such as LiveWire’s spread spectrum time domain reflectometry rely on detecting physical changes to the wiring system and can be blind to fast coupling of micro-second wide pulses. Digital signing and encryption techniques such as the Sandia Laboratories Enhanced Data Authentication System (EDAS) are capable of encrypting communications data, i.e. RS-232, but are not capable reproducing a critical time correlated data streams. Recent NA-241 Safeguards Technology supported developments have reduced the need for special conduit to transmit data via Ethernet by incorporating the IAEA RAINSTORM data encryption and authentication protocol, a tamper indicator is still required to protect raw pulse data from detectors to the acquisition electronics. Encrypting pulse data is especially complicated for radiation detection instruments due to the time correlation data analysis that is performed on this data stream. Any corruption in the timing information will produce errors in measurement values.

97 MATHEMATICS AND COMPUTING↗

Resistive memory for radiation resistant non-volatile memory (NSTRF Final Report)

As space programs increase in number and scope, there is an increasing need for radiation-hardened electronic devices and circuits. In particular, missions to high-radiation environments, such as Europa, would greatly benefit from improved radiation hardness in electronic devices. In pursuit of this goal, resistive memory (RRAM) devices were fabricated at SUNY Polytechnic Institute and evaluated for radiation hardness. Our objectives were to produce RRAM devices resistant to high levels of radiation damage and to demonstrate that these devices would improve mission lifetime in high-radiation environments. Furthermore, the underlying mechanisms of radiation were investigated to provide recommendations for radiation-hardening RRAM devices, which could be applied to any candidate RRAM devices being considered for space applications. Devices were fabricated using several fabrication approaches, including patterning by shadow mask, photolithography-based etching, and photolithography-based liftoff. In each of these cases, total ionizing dose (TID) effects and displacement damage dose (DDD) effects were measured. TID effects from exposure to a 60Co gamma source were not observed to cause changes in device resistance or switching parameters in any experiments, with each device tested to at least 20 Mrad(Si). DDD was measured as radiation-generated oxygen vacancies per cm 3 since oxygen vacancies are generally considered to be the active species involved in switching these devices. The lowest DDD level that caused a device to change resistance state was 10 21 vacancies per cm 3 , and most devices failed at 1022 vacancies per cm 3 . This is an extremely high DDD level, even for RRAM devices, which have been reported to fail in the range of 10 17 -10 20 vacancies per cm 3 . For comparison, an example flash memory device failed at 10 15 vacancies per cm 3 . Vendor-fabricated devices with a similar composition to our own were also tested against TID and DDD. The vendor-fabricated devices did not exhibit changes due to TID, up to the tested level of 30 Mrad(Si). Meanwhile, vendor devices exhibited resistance state changes at 10 21 vacancies per cm 3 , similar to our own devices. These results indicate that Ta0x-based RRAM devices may be particularly resilient to both TID and DDD effects. The very high tolerance to radiation effects is most likely due to the high intrinsic concentration of oxygen vacancies within our devices. Based on X-ray photoelectron spectroscopy (XPS) measurements, there are approximately 10 22 oxygen vacancies per cm 3 in our devices as deposited. Most devices failed when the radiation-induced vacancies reached this level, indicating suggesting that a high intrinsic vacancy concentration protects against lower levels of displacement damage. High vacancy concentration likely also protects against TID by facilitating leakage of trapped charge out of the oxide. The use of a thin switching oxide (25 nm Ta0 x , for our devices) is also expected to improve radiation hardness, as there is less room for charge trapping. Therefore, those wishing to produce very radiation-tolerant RRAM devices can probably achieve this by using a thin oxide that contains a high intrinsic concentration of oxygen vacancies. Our devices appear to be very tolerant of radiation effects, and would greatly increase the expected lifetime of a mission to Europa or another high-radiation target compared to flash memory devices. The similar radiation performance of vendor-fabricated devices is promising for adoption of RRAM devices as radiation-hardened memory devices for use in space. With continued commercial development of these devices, RRAM devices are strong candidates for next-generation memories that are inherently rad-hard.

36 MATERIALS SCIENCE↗