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At least 217 records · Page 12

Information Filters for Safeguards Applications: A Scoping Study

A core concern of the Department of Energy is protecting sensitive information in the face of verification agreements that may make use of increasingly sophisticated and intrusive sensors. The conflict between intrusiveness and information protection is evident in existing treaties, such as the Chemical Weapons Convention (CWC) and the Additional Protocol (AP), where Congress has seen a need to step in and enact implementing legislation to protect, for example, sensitive information such as certain unique chemical signatures, but in so doing has introduced complexities into U.S. treaty compliance policy. Information barriers or filters (IFs) – broadly defined as physical and/or encryption mechanisms that preclude acquisition of sensitive, quantitative information while allowing the acquisition of treaty-relevant qualitative information by an inspectorate – could play a useful role in avoiding this type of conflict. In order to stimulate new thinking on ways to meet existing and future safeguard challenges, this scoping study investigates how IFs – a technique borrowed from the realm of arms control verification - might contribute to international safeguards activities. Information filters (IFs) have long been recognized as an important tool for the protection of sensitive signals and other data in the verification of bilateral and multilateral arms control treaties. The implementation of NPT safeguards, while differing somewhat in context from arms control verification, involves similar sensitivity concerns. This report examines whether or not IFs can be useful in the world of international safeguards, and provides a survey of methods of barring or filtering information that could be applied. The study finds that while many safeguards activities involve non sensitive data, there are also a number of areas where IFs are already in use and others where IFs could make a useful contribution. Examples include verification of enrichment plants, complementary access inspections, and the Additional Protocol (AP) to Comprehensive Safeguards Agreements (CSAs) under the Nuclear Non-proliferation Treaty (NPT).

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗

Safeguards Approaches for Black Box Processes or Facilities

The objective of this study is to determine whether a safeguards approach can be developed for “black box” processes or facilities. These are facilities where a State or operator may limit IAEA access to specific processes or portions of a facility; in other cases, the IAEA may be prohibited access to the entire facility. The determination of whether a black box process or facility is safeguardable is dependent upon the details of the process type, design, and layout; the specific limitations on inspector access; and the restrictions placed upon the design information that can be provided to the IAEA. This analysis identified the necessary conditions for safeguardability of black box processes and facilities.

black box↗

A Zero Knowledge Protocol For Nuclear Warhead Verification

The verification of nuclear warheads for arms control faces a paradox: International inspectors must gain high confidence in the authenticity of submitted items while learning nothing about them. Conventional inspection systems featuring ''information barriers'', designed to hide measurments stored in electronic systems, are at risk of tampering and snooping. Here we show the viability of fundamentally new approach to nuclear warhead verification that incorporates a zero-knowledge protocol, designed such that sensitive information is never measured so does not need to be hidden. We interrogate submitted items with energetic neutrons, making in effect, differential measurements of neutron transmission and emission. Calculations of diversion scenarios show that a high degree of discrimination can be achieved while revealing zero information. Timely demonstration of the viability of such an approach could be critical for the nexxt round of arms-control negotiations, which will likely require verification of individual warheads, rather than whole delivery systems.

70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗

Electronic Safety Resource Tools -- Supporting Hydrogen and Fuel Cell Commercialization

The Pacific Northwest National Laboratory (PNNL) Hydrogen Safety Program conducted a planning session in Los Angeles, CA on April 1, 2014 to consider what electronic safety tools would benefit the next phase of hydrogen and fuel cell commercialization. A diverse, 20-person team led by an experienced facilitator considered the question as it applied to the eight most relevant user groups. The results and subsequent evaluation activities revealed several possible resource tools that could greatly benefit users. The tool identified as having the greatest potential for impact is a hydrogen safety portal, which can be the central location for integrating and disseminating safety information (including most of the tools identified in this report). Such a tool can provide credible and reliable information from a trustworthy source. Other impactful tools identified include a codes and standards wizard to guide users through a series of questions relating to application and specific features of the requirements; a scenario-based virtual reality training for first responders; peer networking tools to bring users from focused groups together to discuss and collaborate on hydrogen safety issues; and a focused tool for training inspectors. Table ES.1 provides results of the planning session, including proposed new tools and changes to existing tools.

08 HYDROGEN↗

Feasibility Study of Implementing a Mobile Collaborative Information Platform for International Safeguards Inspections

In response to the growing pervasiveness of mobile technologies such as tablets and smartphones, the International Atomic Energy Agency and the U.S. Department of Energy National Laboratories have been exploring the potential use of these platforms for international safeguards activities. Specifically of interest are information systems (software, and accompanying servers and architecture) deployed on mobile devices to increase the situational awareness and productivity of an IAEA safeguards inspector in the field, while simultaneously reducing paperwork and pack weight of safeguards equipment. Exploratory development in this area has been met with skepticism regarding the ability to overcome technology deployment challenges for IAEA safeguards equipment. This report documents research conducted to identify potential challenges for the deployment of a mobile collaborative information system to the IAEA, and proposes strategies to mitigate those challenges.

97 MATHEMATICS AND COMPUTING↗

Radiological Toolbox User’s Guide

The Radiological Toolbox software developed by Oak Ridge National Laboratory (ORNL) for U. S. Nuclear Regulatory Commission (NRC) is designed to provide electronic access to the vast and varied data that underlies the field of radiation protection. These data represent physical, chemical, anatomical, physiological, and mathematical parameters detailed in various handbooks which a health physicist might consult while in his office. The initial motivation for the software was to serve the needs of the health physicist away from his office and without access to his handbooks; e.g., NRC inspectors. The earlier releases of the software were widely used and accepted around the world by not only practicing health physicist but also those within educational programs. This release updates the software to accommodate changes in Windows operating systems and, in some aspects, radiation protection. This release has been tested on Windows 7 and 8 and on 32- and 64-bit machines. The nuclear decay data has been updated and thermal neutron capture cross sections and cancer risk coefficients have been included. This document and the software’s user’s guide provide further details and documentation of the information captured within the Radiological Toolbox.

59 BASIC BIOLOGICAL SCIENCES↗

Measurement of Plutonium Isotopic Composition - MGA

In this module, we will use the Canberra InSpector-2000 Multichannel Analyzer with a high-purity germanium detector (HPGe) and the MGA isotopic anlysis software to assay a variety of plutonium samples. The module provides an understanding of the MGA method, its attributes and limitations. You will assess the system performance by measuring a range of materials similar to those you may assay in your work. During the final verification exercise, the results from MGA will be combined with the 240Pueff results from neutron coincidence or multiplicity counters so that measurements of the plutonium mass can be compared with the operator-declared (certified) values.

07 ISOTOPE AND RADIATION SOURCES↗

Idaho National Laboratory Human Capitol Development Program Summary

The Next Generation Safeguards Initiative HCD Subprogram has successfully employed unique nuclear capabilities and employee expertise through INL to achieve multiple initiatives in FY14. These opportunities range from internship programs to university and training courses. One of the central facets of this work has been the international safeguards pre inspector training course. Another significant milestone is the INL led university engagement effort which resulted in courses being offered at ISU and University of Utah.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗

Evaluation of Boulder, CO, SmartRegs Ordinance and Better Buildings Program

Under the SmartRegs ordinance in the city of Boulder, Colorado, all rental properties in the city must achieve an energy efficiency level comparable to a HERS Index of approximately 120 points or lower by the year 2019. The City of Boulder received a $12 million grant from the DOE’s Better Buildings initiative to create and incentivize their EnergySmart Program. In this report, the Consortium for Advanced Residential Buildings (CARB) describes its work with the program, including energy audits of rental properties, developing training programs for insulators and inspectors, and conducting interviews with property owners.

32 ENERGY CONSERVATION, CONSUMPTION, AND UTILIZATI↗

Current Status of Helium-3 Alternative Technologies for Nuclear Safeguards

International safeguards inspectorates (e.g., International Atomic Energy Agency {IAEA}, or Euratom) rely heavily on neutron assay techniques, and in particular, on coincidence counters for the verification of declared nuclear materials under safeguards and for monitoring purposes. While 3 He was readily available, the reliability, safety, ease of use, gamma-ray insensitivity, and high intrinsic thermal neutron detection efficiency of 3 He-based detectors obviated the need for alternative detector technologies. However, the recent decline of the 3 He gas supply has triggered international efforts to develop and field neutron detectors that make use of alternative materials. In response to this global effort, the U.S. Department of Energy’s (DOE) National Nuclear Security Administration (NNSA) and Euratom launched a joint effort aimed at bringing together international experts, technology users and developers in the field of nuclear safeguards to discuss and evaluate the proposed 3 He alternative materials and technologies. The effort involved a series of two workshops focused on detailed overviews and viability assessments of various 3 He alternative technologies for use in nuclear safeguards applications. The key objective was to provide a platform for collaborative discussions and technical presentations organized in a compact, workshop-like format to stimulate interactions among the participants. The meetings culminated in a benchmark exercise providing a unique opportunity for the first inter-comparison of several available alternative technologies. This report provides an overview of the alternative technology efforts presented during the two workshops along with a summary of the benchmarking activities and results. The workshop recommendations and key consensus observations are discussed in the report, and used to outline a proposed path forward and future needs foreseeable in the area of 3 He-alternative technologies.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

On-Site Inspection RadioIsotopic Spectroscopy (Osiris) System Development

We have designed and tested hardware and software for the acquisition and analysis of high-resolution gamma-ray spectra during on-site inspections under the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The On-Site Inspection RadioIsotopic Spectroscopy—Osiris—software filters the spectral data to display only radioisotopic information relevant to CTBT on-site inspections, e.g.,132I. A set of over 100 fission-product spectra was employed for Osiris testing. These spectra were measured, where possible, or generated by modeling. The synthetic test spectral compositions include non-nuclear-explosion scenarios, e.g., a severe nuclear reactor accident, and nuclear-explosion scenarios such as a vented underground nuclear test. Comparing its computer-based analyses to expert visual analyses of the test spectra, Osiris correctly identifies CTBT-relevant fission product isotopes at the 95% level or better.The Osiris gamma-ray spectrometer is a mechanically-cooled, battery-powered ORTEC Transpec-100, chosen to avoid the need for liquid nitrogen during on-site inspections. The spectrometer was used successfully during the recent 2014 CTBT Integrated Field Exercise in Jordan. The spectrometer is controlled and the spectral data analyzed by a Panasonic Toughbook notebook computer. To date, software development has been the main focus of the Osiris project. In FY2016-17, we plan to modify the Osiris hardware, integrate the Osiris software and hardware, and conduct rigorous field tests to ensure that the Osiris system will function correctly during CTBT on-site inspections. The planned development will raise Osiris to technology readiness level TRL-8; transfer the Osiris technology to a commercial manufacturer, and demonstrate Osiris to potential CTBT on-site inspectors.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Safeguards by Design Challenge

The International Atomic Energy Agency (IAEA) defines Safeguards as a system of inspection and verification of the peaceful uses of nuclear materials as part of the Nuclear Nonproliferation Treaty. IAEA oversees safeguards worldwide. Safeguards by Design (SBD) involves incorporation of safeguards technologies, techniques, and instrumentation during the design phase of a facility, rather that after the fact. Design challenge goals are the following: Design a system of safeguards technologies, techniques, and instrumentation for inspection and verification of the peaceful uses of nuclear materials. Cost should be minimized to work with the IAEA’s limited budget. Dose to workers should always be as low are reasonably achievable (ALARA). Time is of the essence in operating facilities and flow of material should not be interrupted significantly. Proprietary process information in facilities may need to be protected, thus the amount of information obtained by inspectors should be the minimum required to achieve the measurement goal. Then three different design challenges are detailed: Plutonium Waste Item Measurement System, Marine-based Modular Reactor, and Floating Nuclear Power Plant (FNPP).

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗

Nondestructive Assay Data Integration with the SKB-50 Assemblies - FY16 Update

A project to research the application of non-destructive assay (NDA) techniques for spent fuel assemblies is underway at the Central Interim Storage Facility for Spent Nuclear Fuel (for which the Swedish acronym is Clab) in Oskarshamn, Sweden. The research goals of this project contain both safeguards and non-safeguards interests. These nondestructive assay (NDA) technologies are designed to strengthen the technical toolkit of safeguard inspectors and others to determine the following technical goals more accurately; Verify initial enrichment, burnup, and cooling time of facility declaration for spent fuel assemblies; Detect replaced or missing pins from a given spent fuel assembly to confirm its integrity; and Estimate plutonium mass and related plutonium and uranium fissile mass parameters in spent fuel assemblies. Estimate heat content, and measure reactivity (multiplication).

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Assess How Changes in Fuel Cycle Operation Impact Safeguards

Since the beginning of commercial nuclear power generation in the 1960s, the ability of researchers to understand and control the isotopic content of spent fuel has improved. It is therefore not surprising that both fuel assembly design and fuel assembly irradiation optimization have improved over the past 50+ years. It is anticipated that the burnup and isotopics of the spent fuel should exhibit less variation over the decades as reactor operators irradiate each assembly to the optimum amount. In contrast, older spent fuel is anticipated to vary more in burnup and resulting isotopics for a given initial enrichment. Modern fuel therefore should be more uniform in composition, and thus, measured safeguards results should be easier to interpret than results from older spent fuel. With spent fuel ponds filling up, interim and long-­term storage of spent fuel will need to be addressed. Additionally after long periods of storage, spent fuel is no longer self-­protecting and, as such, the IAEA will categorize it as more attractive; in approximately 20 years many of the assemblies from early commercial cores will no longer be considered self-­protecting. This study will assess how more recent changes in the reactor operation could impact the interpretation of safeguards measurements. The status quo for spent fuel assay in the safeguards context is that the overwhelming majority of spent fuel assemblies are not measured in a quantitative way except for those assemblies about to be loaded into a difficult or impossible to access location (dry storage or, in the future, a repository). In other words, when the assembly is still accessible to a state actor, or an insider, when it is cooling in a pool, the inspectorate does not have a measurement database that could assist them in re-­verifying the integrity of that assembly. The spent fuel safeguards regime would be strengthened if spent fuel assemblies were measured from discharge to loading into a difficult or impossible to access location. The primary driver for suggesting this shift in approach is the change in robotic technology and information technology in general. It should be possible, with minimal impact to the facility, to measure each assembly every time that it is moved in the pool, with the first measurements being made at discharge. The following conclusions were reached: The total neutron count rate can be accurately predicted at any future moment in time based upon the measured count rate at discharge, provided the initial enrichment and burnup of the assembly is known at discharge. It is expected that the total neutron count rate measured at discharge will be indicative of the initial enrichment and burnup of that assembly. If the automated robot were to focus on measuring the assemblies in the rack without moving them, the time available would increase immensely.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Possible Nuclear Safeguards Applications: Workshop on Next-Generation Laser Compton Gamma Source

These are a set of slides for the development of a next-generation photon source white paper. The following topics are covered in these slides: Nuclear Safeguards; The Nuclear Fuel Cycle; Precise isotopic determination via NRF; UF 6 Enrichment Assay; and Non-Destructive Assay of Spent Nuclear Fuel. In summary: A way to non-destructively measure precise isotopics of ~kg and larger samples has multiple uses in nuclear safeguards; Ideally this is a compact, fieldable device that can be used by international inspectors. Must be rugged and reliable; A next-generation source can be used as a testing ground for these techniques as technology develops.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗

Upgrading FLIR NanoRaider with the next Generation of CdZnTe Detectors. Goal - Integrate VFG detectors into FLIR R200. Advanced Virtual Grid ASIC (AVG-ASIC).

This document presents motivations, goals and the current status of this project; development (fabrication, performance) of position-sensitive virtual Frisch-grid detectors proposed for nanoRaider, an instrument commonly used by nuclear inspectors; ASIC developments for CZT detectors; and the electronics development for the detector prototype..

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗