Nuclear Safeguards and Non-Destructive Assay

Safeguards

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Nuclear Safeguards are measures to verify that States comply with their international obligations not to use nuclear materials (plutonium, uranium and thorium) for nuclear explosives purposes. Global recognition of the need for such verification is reflected in the requirements of the Treaty on the Non-Proliferation of Nuclear Weapons (NPT) for the application of safeguards by the International Atomic Energy Agency (IAEA). Also, the Treaty Establishing the European Atomic Energy Community (the Euratom Treaty) includes requirements for the application of safeguards by the European Commission. Organizations such as the IAEA and EURATOM and others are tasked with ensuring declared amounts of material are indeed present in the facilities in which they are stored and that such material is not being diverted to other uses.

Sometimes referred to as MPC&A (Materials protection, control and accountancy) and more generally as Nuclear Materials Security, safeguards has become more recently the subject of renewed interest as representing the first line of defense against nuclear materials diversion.

New applications are emerging such as the field of Nuclear Forensics.

ORTEC has supplied such equipment in the form of specialized components and system for many years.

Non-Destructive Assay (NDA) Techniques

NDA techniques are applied to a broader range of applications than nuclear safeguards alone, which historically have meant the accountancy of declared quantities of nuclear materials by safeguards inspection organizations. The techniques of non-destructive assay measurement are applied across a broader range of measurment problems to establish the quantities of nuclear materials present in samples of various types. The broad ORTEC product lines for safeguards and non-destructive assay derive from ORTEC own developed product, product licensed from leading national laboratories and centres of excellence, and from commercial partners whose products ORTEC distributes and supports.

Safeguards and Non-Destructive Assay Instruments and Systems

Gamma-Ray Systems

	Micro-trans-SPEC Portable UF6 Cylinder Verification System (MICRO-UF6-PKG-1) UF6 cylinder verification system implemented on the ORTEC Micro-trans-SPEC HPGe Portable Spectrometer. All-in-one light weight instrument with software designed to follow the current procedures for UF6 cylinder inspection by safeguards inspectors. High precision, rapid results through combining tried-and-tested methodology with the latest advances in HPGe spectrometry. Solves spectral interference problems encountered with NaI based systems. Micro-trans-SPEC hardware can be used for other related applications. Download the MICRO-UF6 data sheet.

	Holdup Measurement System 4 (HMS4) For: Determination of changes in holdup inventories in process plants. A portable, easy to use solution to SNM Holdup. Complete solution for uranium and plutonium hold-up tracking. Highly automated, measurement points are identified using bar codes. Incorporates the Los Alamos (LANL) Generalized Geometry Holdup (GGH) methodology. Download the HMS4 data sheet.

	Hybrid K-Edge Densitometer For: (a) Analysis of input solutions in fuel reprocessing plants. (b) Analysis of output product in fuel reprocessing plants. (c) Measurement of actinide-bearing samples in the analytical laboratory setting. The HKED instrument offered by ORTEC employs the latest technology developed by the NIS-5 group at LANL. This new technology results from consequent and continuous development over several years. The superior analysis routine resulting provides a substantial improvement in performance over traditional HKED units. It also extends the scope of applications to include analytical laboratory applications. Download the HKED data sheet.

Neutron Systems

ANTECH Model 2442 Active Well Coincidence Counter (AWCC)

For: Uranium determination (active mode) and Pu determination (passive mode).

Reproduces the physics and measurement characteristics of the original LANL AWCC design.
High detection efficiency of 31% in large sample configuration.
Serves as both active neutron detector for measuring uranium and passive neutron multiplicity detector for measuring plutonium.
Advanced electronics with de-randomising mixer buffer circuitry to reduce count losses.
Provides complete passive and active assay system when used with the ANTECH/ORTEC AMSR 150 Neutron Coincidence/Multiplicity Counter.

Download the ANTECH 2442 data sheet.

Waste Assay Systems

	ISO-CART Mobile Assay System For: In-situ assay of large containers, pipes, surfaces, etc. Cart-mounted mobile system for in-situ measurement of surfaces and objects Incorporates the latest version of ORTEC ISOPLUS analysis software: Handles a wide variety of container sizes and densities: Boxes, Drums, Pipes, Surfaces (Collimated Detector), Wide Area Assay of Soils and Surfaces (Uncollimated Detector: M-1 Methodology) Simple point-source calibration Models geometry and matrix corrections "Fine-tune" interative graphic plot validates configuration assumptions Download the ISO-CART brochure.

	QED Low Level Waste Assay and Segregation System Detection limits easily meet free release levels resulting in cost savings Supports 208 liter (55 gal.) containers and smaller boxes Container weighing up to 725 kg (1600 lbs) via load cell Automatic drum handling conveyor options High sensitivity LN2-free HPGe detectors with advanced digital signal processing electronics Flexible reporting Download the QED data sheet.

	ANTECH Model 2200 Passive Neutron/Gamma Multiplicity Drum Monitor For: measurement of Plutonium bearing intermediate and low level waste in 220 litre (55 gallon) drums Comprehensive neutron Coincidence and Multiplicity counting data analysis software incorporating analytical dead-time correction Individual totals count and statistical analysis for each of 16 counting chains, (each chain has a separate head amplifier) Detector efficiency of 20% with 64 He-3 detector tubes close coupled to the drum forming a decagon Internal Cadmium liner may be removed for higher efficiency totals counting Download the ANTECH 2200 data sheet.

	ANTECH Series 3800 Tomographic Gamma Scanner (TGS) For: Assay of drummed waste, potentially containing inhomogeneous matrices (e.g. scrap, decommissioning waste). The Model 3800 Combined Tomographic Gamma Scanner for up to 400 liter drums combines the functions of a TGS, SGS, and Pu Isotopic System (using the PC/FRAM code) in one skid mounted instrument. TGS technique meets both safeguards and WIPP measurement and QA requirements Provides tomographic maps of absorbers and sources in heterogeneous matrices Measures samples with Am-241 content which cannot be measured with neutron techniques Automatic gamma-ray energy calibration using the Se-75 transmission source Accuracy is typically better than 10% for measurement of cans and 20% for matrices with average density 2g/cm3. Download the ANTECH 3800 data sheet.

Calorimeters

ANTECH Model 200 High Sensitivity Large Sample Calorimeter

For: The measurement of plutonium and tritium

True Isothermal ‘Air Bath’ Absolute Calorimetry Measurements
Automatic software algorithms for equilibrium sample power prediction and measurement end point determination
Automatic Plutonium and Americium decay correction
Custom designs are available for different size and dimensions of sample containers and measurement sensitivities
Software selectable redundant measurement sensors and operation modes to optimize accuracy of measurement time

ANTECH 200 data sheet.

High Performance Germanium (HPGe) Detectors

Specifically designed to meet the demanding requirements of isotopic ratio software codes used in Safeguards and NDA.
Excellent resolution is maintained over a wide range of count rates, enhancing measurement flexibility
Available in a full range of crystal diameters
Extensive range of cryostats with multi-orientation dewar options for applications requiring portability
Compatible with all existing Safeguards multichannel analyzers

The precise measurement of isotopic ratios required in Safeguards and non-destructive assay (NDA) applications places a severe demand on the techniques of gamma-ray and x-ray spectroscopy. Figure 14 demonstrates the complexity of the 90–130 keV region of a typical Pu spectrum. (The choice of energy region(s) for analysis depends specifically on the sample type and origin and the material matrix.

National laboratory software codes1 written to obtain highly accurate isotopic ratios, must deal with these spectra to analyze low-energy and/or high-energy regions in which groups of peaks are located close together. Each code requires exceptional system resolution and stability in order to achieve accurate unfolding of these regions.

Recent safeguards development trends have led to a growing requirement of isotopic ratio determinations involving higher energy gamma-rays. Such needs spring from the need to measure attenuated samples, such as those found in waste assay and in certain homeland security applications. Software codes such as PC/FRAM and MGAHI2 can now determine Pu isotopic ratios from the higher energy regions of the spectrum. As a consequence, it is desirable to produce HPGe detectors that offer improved higher energy performance, while maintaining the excellent resolution characteristics required in such applications.

The ORTEC Safeguards series include both coaxial and planar geometry detectors, specifically designed to meet the demands of the applications software used for isotopic ratio determination, have been developed to strike an optimum balance between low-energy resolution and high-energy efficiency.

Download the Safeguards GEM Detector Configuration Guide

Download the Safeguards Planar Detector Configuration Guide

Safeguards and Non-Destructive Assay Applications Software

ISOTOPIC-32 Advanced Software Solution to Gamma Ray Waste Assay

Provides quantitative assay of gamma-emitting waste samples with an emphasis on ease of use and practicality.
Analyzes all types of gamma-emitting waste, fissile and non-fissile.
Measure containers of many shapes and sizes, surfaces and even soils; via independently verified analysis methods; new algorithms for CLOSE geometry measurements.
Use your own HPGe detector(s) and electronics or as part of an integrated ISO-CART™ system.
Calibrate ANY detector on site, TRACEABLY, in minutes.
Ideal for use with the revolutionary ORTEC trans-SPEC-100 portable HPGe spectrometer.
Multiple measurements on a single object easily combined.
Easy system expansion.
New algorithm includes detector characterization parameters for improved accuracy.

ISOTOPIC V4 provides a practical solution to a wide range of gamma-ray measurement problems encountered in site characterization prior to remediation and decontamination and decommissioning (D&D) operations. ISOTOPIC is based on work done originally at several US DOE sites in the analysis of thousands of fissile waste containers1 and in methods developed at the US Energy Measurements Laboratory2,3 (EML-NYC) to measure wide-area contamination of soils and surfaces. In version 4, algorithms have been refined, user interaction has been simplified and reporting has been greatly improved in response to user suggestions.

Download the ISOTOPIC-32 brochure.

MGA-B32 Advanced Gamma-Ray Isotopic-Ratio Actinide Analysis from Ge Detector Spectra

A Suite of Three Advanced Analysis programs:
    MGA analyzes Pu with a single planar, or one planar and one coaxial Ge detector
    MGAHI analyzes Pu with a single coaxial Ge detector
    U235 analyzes U only with a planar Ge detector

No calibration standards necessary to correct for matrix or container effects
Rapid operation with display of spectra, results, and peak-fit residuals
Easily modified parameter sets for optimum results
Flexible reporting: Instant results and archive copy to Access® database
Integrated data collection and analysis
Easy-to-use Windows® Graphical User Interface

MGA++ is a suite of three software programs (MGA, U235 and MGAHI) for analysis of Actinide spectra acquired by germanium detectors. MGA++ is the result of years of continuing development at Lawrence Livermore National Laboratory.

The original MGA code was developed to determine plutonium isotopic abundances for gamma-ray data taken with germanium detectors. MGA-B32 consists of 1) an upgraded version of the original MGA code, which relies on the 100-keV region; 2) U235, a uranium isotopic analysis code that uses gamma rays less than 300 keV; and 3) MGAHI, a plutonium isotopic analysis code that uses the 200 keV–1 MeV energy region. The codes analyze gamma-ray data collected with a HPGe detector. All of the executable software is 32-bit Windows compliant.

Download the MGA-B32 data sheet.

PC/FRAM-B32 Advanced Isotopic Ratio Analysis Software for HPGe and CdTe Detector Gamma-Ray Spectra

Analyzes Pu, and a wide variety of heterogeneous samples containing Pu, Am, U, and other nuclides including 242Pu
Operates with a single HPGe or CdTe detector
No calibration standards necessary
Works with shielded samples
Select from a large number of supplied sample/geometry conditions or add more types
Dynamic selection of English or Russian Graphical-User Interface
Decay Correction for Isotopic fractions
Significant enhancements over previous versions

PC/FRAM-B32 analyzes the gamma-ray spectrum taken with a germanium detector, of plutonium-bearing, uranium-bearing, or mixed items and quantifies the distribution of plutonium or uranium isotopes 241Americium and other transuranic isotopes (including uranium in mixed uranium-plutonium oxides) that contribute measurable gamma rays to the spectrum can also be quantified relative to plutonium. In Version 4.3, use of CdTe (Cadmium Telluride) detectors is also supported. PC/FRAM-B32 analyzes spectra from items containing only uranium, and quantifies the uranium isotopic distribution. These measurements are performed on samples of arbitrary size, geometry, and physical and chemical composition.

Download the PC/FRAM-B32 data sheet.

INCC-B32 Neutron Coincidence Counting Software

Neutron Coincidence Counting Program from Los Alamos
Calibration, QA, data analysis, and report generation are included in one package
Supports a wide range of shift register hardware, including the Advanced Multiplicity Shift Register, AMSR 150
Includes a wide variety of Active and Passive Neutron Data analysis techniques
Includes Deming Curve Fitting for development of calibration curves, with graphical plotting of results
Measurement results stored in standard format database files
Built-in Quality Assurance testing

INCC-B32 is the latest PC version of the Los Alamos general-purpose Neutron Coincidence Counting program (INCC). It runs under Microsoft Windows 2000/XP. INCC is suitable for nondestructive passive and active neutron applications for U and Pu. Passive neutron verification techniques include known alpha, known multiplication, add-a-source, multiplicity, curium ratio, and truncated multiplicity.

Active techniques include multiplicity, collar, and active/passive. Active multiplicity presently determines the neutron multiplication of a uranium item, but does not determine the uranium mass.

Items may be verified using multiple methods simultaneously. For example, plutonium items may be verified via the passive calibration curve and the known alpha techniques simultaneously. (Collar verifications may not be combined with other verification techniques.)

Download the INCC-B32 data sheet.

HMS4-B32 Holdup Measurement System 4 Software

"Holdup" refers to the accumulation of special nuclear material (SNM) inside the processing equipment of nuclear facilities. Holdup must be minimized and quantified: for radiation and criticality safety, safeguarding against theft or diversion, and economic reasons.

Accurate holdup measurements, while simple in principle, are demanding on the operator. The measurements by their nature are made in situ at specified points in the plant — often in awkward locations where SNM may be deposited, such as valves and ducts. The operator often must wear protective clothing, resulting in additional discomfort during the performance of the measurement under already unpleasant conditions of high temperature and humidity — perhaps up a ladder while holding a detector against a pipe with an outstretched arm. Beside those physical demands, the operator must keep track of the nuclear counting data and associated parameters (e.g., wall thickness, measurement distance). The HMS4-B32 software integrates a suite of hardware into a simple to use holdup data management system

The HMS4 software includes two sets of programs; the main program that runs on a host personal computer (PC), and others running on a bar-code reader or portable PC, referred to as the Controller. The Host computer program performs setup and calibration of multichannel analyzer/detector pairs, loads the controller with operational parameters, receives measurement data from the controller, maintains measurements and derived results in databases, and prints reports. The Controller programs control multichannel analyzer (MCA) setup functions, data acquisition, store measurement data as accumulated, and allow the user to review previous collected data and spectra.

ORTEC offers a complete HMS4 holdup system through our Integrated Systems Group which should be contacted for detailed system specifications and a price quote.

Download the HMS4-B32 data sheet.