Engineering Papers⌕ Search

SEARCH · Engineering Papers

Results for “Safeguards”

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 271 records · Page 15

Acoustic Monitoring of Pyroprocessing for Safeguards

As pyroprocessing continues to be an attractive option for the reprocessing of spent nuclear fuel worldwide, safeguards technologies are needed to address the monitoring capabilities that can help state level authorities, or the International Atomic Energy Agency (IAEA) maintain continuity of knowledge of the plant operations. Idaho National Laboratory (INL) is studying the possibility of using acoustic monitoring as a means to monitor a pyroprocessing facility for safeguards purposes. This paper discusses the experimental design and some preliminary results of tests conducted at the Fuel Conditioning Facility, a pyrochemical capable facility, at INL.

98 - NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL↗

Investigating the non-ideal behavior of the Amptek A111 charge sensitive preamplifier & discriminator board— 3 He proportional counter combination used in common safeguards neutron coincidence counters

Neutron coincidence counting is a well-established technique used for the nondestructive quantification of specialnuclear material during international safeguards inspections. The neutron counters are commonly designedwith an annular body, centered about an inner well or cavity into which a measurement item is placed,and the moderating annulus is populated with 3 He tubes connected to a varying number of preamplifiers.The Canberra Industries JAB-01 preamplifier/amplifier/discriminator board is employed within the company’sneutron coincidence counters, built for use by the International Atomic Energy Agency. Non-ideal behavior ofthese boards was identified during a detector characterization, using list mode data acquisition, of a CanberraIndustries JCC-71 Neutron Coincidence Collar implementing four JAB-01 boards. List mode data acquisition andanalysis reveals features that have commonly been overlooked by historic timing gate selection while using shiftregister data acquisition methods, which are routinely adopted in international safeguards. It has been shownthat double pulsing effects are not fully captured within the predelay setting; therefore, they may influencethe response of the system within the standard operating regime. We set out to identify and correct for doublepulsing in our post analysis of neutron pulse trains, while isolating this behavior to the relevant system. Tounderstand and potentially address these concerns, the responses of two different JAB-01 board systems – theJCC-71 Neutron Coincidence Collar and a modified JCC-51 Active Well Neutron Coincidence Counter – arecompared with the responses of an AnTech Inc. N2071 Neutron Coincidence Collar that also uses an amplifierbuilt on the Amptek A111 Charge Sensitive Preamplifier & Discriminator chip, and a JCC-71 that employs custompreamplifiers designed at Oak Ridge National Laboratory

42 ENGINEERING↗

The Importance of Safeguards Culture

This is a paper we plan to submit to the Nonproliferation Review for publication. The paper provides an analysis of the concept of safeguards culture and gauges its value to the safeguards community. Accompanying the paper are three additional documents that contain the figures and tables cited in the paper. NPR guidelines state these figures and tables are to be submitted in separate documents.

Mladineo, Stephen V.↗

Development of coherent germanium neutrino technology (CoGeNT) for reactor safeguards

Antineutrinos are extremely penetrating elementary particles that have unique features of interest for safeguards at nuclear reactors. Current antineutrino detectors systems have large size and often use hazardous materials, presenting concerns to the safeguards agencies. We propose a new antineutrino detector, based on HPGe detector technology, which is much smaller and safer and therefore more likely to find widespread acceptance as a monitoring tool. The proposed system should be sensitive to a universally predicted but as-yet undetected antineutrino signature, the coherent neutrino-nucleus scattering, for which an unprecedentedly low noise threshold is required. Based on the noise analysis of an existing HPGe detector and the results of noise tests, a new system was designed and fabricated in collaboration with LBNL, though a full noise optimization has not been possible. Shielding design has been analyzed in the context of other deployment results, and an anticoincidence veto with high neutron efficiency has been tested.

Cabrera-Palmer, Belkis↗

Enhancing Safeguards Analysts’ Geospatial Usage

This report is the final summation of Sandia‘s Laboratory Directed Research and Development (LDRD) project #151316, "Open Source Information Verification" (OSIV) which ran from FY11 through FY12. The aim of OSIV was to research, develop, and evaluate relevant geospatial analysis capabilities that address open-source information needs for international safeguards. OSIV generated a number of technical, programmatic, and cultural advances, detailed in this report. There were new methodological insights and research that resulted in ten publications and presentations; this report concludes with an abstract-annotated listing of all materials. OSIV generated a substantial prototype, GeoSafeguards, that not only achieved its intended goal of testing our hypothesis, but which also served as a vehicle for customer education and program development. OSIV, as intended, has catalyzed future work in this domain; by the end of two years, it has already brought considerable attention to this work both domestically and with our international partners. Finally, the OSIV project knit together previously disparate research staff and user expertise in a fashion that not only addressed our immediate research goals, which has created cross- understanding, in service of Sandia‘s national security responsibilities in safeguards and nonproliferation.

97 MATHEMATICS AND COMPUTING↗

Trial Application of the Facility Safeguardability Assessment Process to the NuScale SMR Design

FSA is a screening process intended to focus a facility designer’s attention on the aspects of their facility or process design that would most benefit from application of SBD principles and practices. The process is meant to identify the most relevant guidance within the SBD tools for enhancing the safeguardability of the design. In fiscal year (FY) 2012, NNSA sponsored PNNL to evaluate the practical application of FSA by applying it to the NuScale small modular nuclear power plant. This report documents the application of the FSA process, presenting conclusions regarding its efficiency and robustness. It describes the NuScale safeguards design concept and presents functional "infrastructure" guidelines that were developed using the FSA process.

Coles, Garill A.↗

Laboratory demonstration of a multi-sensor unattended cylinder verification station for uranium enrichment plant safeguards

The objective of safeguards is the timely detection of the diversion of a significant quantity of nuclear materials, and safeguarding uranium enrichment plants is especially important in preventing the spread of nuclear weapons. The IAEA’s proposed Unattended Cylinder Verification Station (UCVS) for UF 6 cylinder verification would combine the operator’s accountancy scale with a nondestructive assay system such as the Passive Neutron Enrichment Meter (PNEM) and cylinder identification and surveillance systems. In this project, we built a laboratory-scale UCVS and demonstrated its capabilities using mock UF 6 cylinders. We developed a signal processing algorithm to automate the data collection and processing from four continuous, unattended sensors. The laboratory demonstration of the system showed that the software could successfully identify cylinders, snip sensor data at the appropriate points in time, determine the relevant characteristics of the cylinder contents, check for consistency among sensors, and output the cylinder data to a file. This paper describes the equipment, algorithm and software development, laboratory demonstration, and recommendations for a full-scale UCVS.

42 ENGINEERING↗

Next Generation Safeguards Initiative Efforts at Los Alamos National Laboratory: Developing Our Human Capital FY2015

This report documents the accomplishments of the Safeguards HCD Fiscal Year 2015 (FY15) Project Work Plan, highlighting LANL’s work as well as the accomplishments of our NGSI-sponsored students, graduate and postdoctoral fellows, and mid-career professionals during this past year. While fiscal year 2015 has been a year of transition in the Human Capital Development area for LANL, we are working to revitalize our efforts to promote and develop Human Capital in Safeguards and Non-proliferation and are looking forward to implementing new initiatives in the coming fiscal year and continuing to transition the knowledge of staff who have been on assignment at IAEA and Headquarters to improve our support to HCD.

Human Capital Development University Engagement↗

FY16 Safeguards Technology Cart-Portable Mass Spectrometer Project Final Report

The Oak Ridge National Laboratory project for the Next Generation Safeguards Initiative Safeguards Technology Development Subprogram has been involved in the development of a cart portable mass spectrometer based on a Thermo ITQ ion trap mass spectrometer (referred to simply as the ITQ) for the field analysis of 235U/238U ratios in UF6. A recent discovery of the project was that combining CO2 with UF6 and introducing the mixture to the mass spectrometer (MS) appeared to increase the ionization efficiency and, thus, reduce the amount of UF6 needed for an analysis while also reducing the corrosive effects of the sample. However, initial experimentation indicated that mixing parameters should be closely controlled to ensure reproducible results. To this end, a sample manifold (SM) that would ensure the precise mixing of UF6 and CO2 was designed and constructed. A number of experiments were outlined and conducted to determine optimum MS and SM conditions which would provide the most stable isotope ratio analysis. The principal objective of the project was to provide a retrofit ITQ mass spectrometer operating with a SM capable of achieving a variation in precision of less than 1% over 1 hour of sampling. This goal was achieved by project end with a variation in precision of 0.5 to 0.8% over 1 hour of sampling.

47 OTHER INSTRUMENTATION↗

Developing reliable safeguards seals for application verification and removal by State operators

Once a geological repository has begun operations, the encapsulation and disposal of spent fuel will be performed as a continuous, industrial-scale series of processes, during which time safeguards seals will be applied to transportation casks before shipment from an encapsulation plant, and then verified and removed following receipt at the repository. These operations will occur approximately daily during several decades of Sweden's repository operation; however, requiring safeguards inspectors to perform the application, verification, and removal of every seal would be an onerous burden on International Atomic Energy Agency's (IAEA's) resources. Current IAEA practice includes allowing operators to either apply seals or remove them, but not both, so the daily task of either applying or verifying and removing would still require continuous presence of IAEA inspectors at one site at least. Of special importance is the inability to re-verify cask or canisters from which seals have been removed and the canisters emplaced underground. Successfully designing seals that can be applied, verified and removed by an operator with IAEA approval could impact more than repository shipments, but other applications as well, potentially reducing inspector burdens for a wide range of such duties.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Industrial Internet-of-Things & Data Analytics for Nuclear Power & Safeguards

Data analytics applied to nuclear power operations and nuclear safeguards is in a nascent state, yet some significant initial efforts are being undertaken by industry and academia. This report highlights our findings as to the current state-of-the-art of such efforts, in particular considering the Industrial Internet-of-Things aspect of this work, as well as an investigation into the utility of machine learning tools being developed for other industries. Blockchain applications were also studied. A consideration was undertaken into how to apply data analytics and machine learning to nuclear power and safeguards within the realm of Probabilistic Risk Assessments (PRAs), predictive maintenance & edge analytics, and proprietary data sharing.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Development of a Pyroprocessing Flowsheet Model for Safeguards Analysis

Pyroprocessing flowsheets have been designed that have efficient actinide recovery, meet nonproliferation objectives, minimize waste, and are commercially viable. The analysis of safeguards of pyrochemical recycle systems for the treatment of used fast reactor metal fuel can be greatly enhanced with the employment of robust dynamic models. Electrochemical process modeling also contributes to broader objectives of the MPACT program by supporting MC&A, options screening, and safeguards analysis and can inform development of sensor systems for a used fuel recycle facility. Modeling can also provide a method for defining metrics and requirements on advanced analysis techniques.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Nondestructive Assay for Nuclear Safeguards [Slides]

The objective of safeguards is the timely detection of diversion of significant quantities of nuclear material from peaceful nuclear activities to the manufacture of nuclear weapons. Currently, the IAEA is working to achieve universal acceptance of the AP, safeguards-by-design, unattended monitoring & data integration, and state-level concept/approach. We are trying to verify special nuclear material (SNM) is where it should be, and in the proper amount.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Non-invasive Pipe Pressure Monitoring for Safeguards

Our project explores a new solution to complement current safeguards toolbox by independently, and noninvasively, determining the pressure inside uranium hexafluoride (UF 6 )-carrying Gas Centrifuge Enrichment Plant (GCEP) pipes. Proof-of-principle, non-invasive pipe pressure monitoring tests were conducted through measurements of hoop and axial strain using an optical-interference dilatometry technique based on fiber Bragg gratings (FBGs) inscribed in the core of telecommunication-type 125 µm diameter optical fibers. The fibers were affixed to commercial stainless steel and aluminum tubes and pipes of the type expected to be found at GCEP’s, each measuring four inches in diameter. When the internal air pressure in the pipes changes their external diameter and length follow, and the pitch in the FBG shrinks and/or expands accordingly. In turn, these changes result in a shift of the light wavelength reflected by the FBGs. Several FBGs physically attached to the pipe, as well as control FBGs not attached, were interrogated during the process using state-of-the-art commercial interrogators that operate on swept-wavelength laser technology. Strains measured were contrasted against calculations based on the known elastic and mechanical properties of the pipes. Good agreement is found, and strategies are proposed for further improvement of the experimental resolution as well as future implementation of this novel approach for GCEP safeguards.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Assessment of Self-interrogation Safeguards Signatures for Pebble Bed Reactor Fuel

New reactor designs, such as pebble-bed reactors, present challenges for the safeguarding of fissile material. Due to the multi-pass fuel circulation design and the non-uniform path a pebble may traverse through a pebble-bed reactor, there will be variations in the irradiation history of spent fuel pebbles. The standard approach of estimating actinide quantities based on fission gamma spectra or neutron emission paired with depletion modeling may yield uncertainties too large for safeguards and material accountancy. This project investigated, through modeling and experimentation, the potential of neutron self-interrogation of spent fuel pebbles as an innovative method to implement materials accountability. As an example, our feasibility studies indicate that the mass of U-235, U-238, Pu-239 and Pu-241 can be predicted to 4.1, 0.86, 13 and 13 % accuracy, respectively, when measuring 100 closely packed end-of-life spent fuel pebbles over approximately 12 days using a 4π counting geometry.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

An Assessment of the Safeguards Implications of Particle and Alloy Formation in MSRs

Molten salt reactors (MSRs) present unique challenges for applying safeguards measures and differ significantly from traditional nuclear reactors. Although the special fissionable materials within MSRs principally exist as dissolved species within the fuel salt, key actinides of interest may also be converted to solid phases including alloys and precipitated oxides via chemical and electrochemical reactions. These solid-phase components will complicate the nuclear material accounting and control (NMAC) approaches that have, so far, primarily targeted measurements of the liquid salt itself. For example, most of the proposed monitoring and characterization methods for MSRs are reliant on homogeneity of the salt and the ability to maintain accountable materials in solution. Solid deposits and particulates could invalidate the assumption of homogeneity and necessitate the use of new models and measurement tools to permit a full accounting of all nuclear material in an MSR. To address this, the likelihood of solids formation in MSRs, estimated the rate at which these solids could form, and assessed the monitoring tools that are available to account for the presence of these materials were examined. Specifically, three solid forming mechanisms were investigated, including (1) the accumulation of actinides within the MSR’s structural materials due to alloying, (2) the accumulation of actinides within noble metal fission product particulates, and (3) the generation of actinide oxides from interactions with salt impurities. These modeling-informed studies were completed with considerations to both fluoride- and chloride-containing salts. It was determined that, although measurable amounts of special fissionable material were expected to alloy with the structural elements and fission products, the predicted amounts were below levels considered as significant quantities (SQ) by the International Atomic Energy Agency (IAEA). However, it was determined that sufficiently large oxygen concentrations could potentially lead to significant quantities of special fissionable material being converted to solid oxide phases. As such, a comparative study of technologies that are commercially available to assist in monitoring and accountancy of this material was presented. Policy implications, design recommendations, and suggestions for follow-on experimental work were also presented to further assist reactor vendors in designing and controlling the fuel salt chemistry to address potential safeguards considerations.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

Plutonium Signatures in Molten-Salt Reactor Off-Gas Tank and Safeguards Considerations

Fluid-fueled molten-salt reactors (MSRs) are actively being developed by several companies, with plans to deploy them internationally. The current IAEA inspection tools are largely incompatible with the unique design features of liquid fuel MSRs (e.g., the complex fuel chemistry, circulating fuel inventory, bulk accountancy, and high radiation environment). For these reasons, safeguards for MSRs are seen as challenging and require the development of new techniques. This paper proposes one such technique through the observation of the reactor’s off-gas. Any reactor design using low-enriched uranium will build up plutonium as the fuel undergoes burnup. Plutonium has different fission product yields than uranium. Therefore, a shift in fission product production is expected with fuel evolution. The passive removal of certain gaseous fission products to the off-gas tank of an MSR provides a valuable opportunity for analysis without significant modifications to the design of the system. Uniquely, due to the gaseous nature of the isotopes, beta particle emissions are available for observation. The ratios of these fission product isotopes can, thus, be traced back to the relative amount and types of fissile isotopes in the core. This proposed technique represents an effective safeguards tool for bulk accountancy which, while avoiding being onerous, could be used in concert with other techniques to meet the IAEA’s timeliness goals for the detection of a diversion.

Dunkle, Nicholas (ORCID:000000027323011X)↗

NASA guidelines for assuring the adequacy and appropriateness of security safeguards in sensitive applications

The Office of Management and Budget (OMB) Circular A-71, transmittal Memorandum No. 1, requires that each agency establish a management control process to assure that appropriate administrative, physical and technical safeguards are incorporated into all new computer applications. In addition to security specifications, the management control process should assure that the safeguards are adequate for the application. The security activities that should be integral to the system development process are examined. The software quality assurance process to assure that adequate and appropriate controls are incorporated into sensitive applications is also examined. Security for software packages is also discussed.

Tompkins, F. G.↗