MGA++ Gamma Ray Isotopic Ratio Actinide Analysis

MGA ++ for Nuclear Radiation SafeguardsMGA++ is a suite of three programs (MGA, U235 and MGAHI) for analysis of actinide spectra acquired by germanium radiation 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. MGA-B32 consists of an upgraded version of the original MGA code (which relies on the 100-keV region), U235, a uranium isotopic analysis code that uses gamma rays less than 300 keV, and MGAHI, a plutonium isotopic analysis code that uses the 200 keV–1 MeV energy region. The programs, requiring no special calibration sources or calculations, use only information obtained from the sample spectra to determine the isotopic ratios. MGA++ includes the control of the data collection, using any MCB, for one or two HPGe radiation detectors, including the Detective and Micro-Detective.
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    • 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
    • The latest LLNL algorithms for actinide analysis.
    • 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.
    • ORTEC CONNECTIONS compliant.
    • Operates with all ORTEC and many non-ORTEC MCAs.
    • Developer’s toolkit options aid custom system development.

    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.1

    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.

    The programs, requiring no special calibration sources or calculations, use only information obtained from the sample spectra to determine the isotopic ratios.

    A full member of the CONNECTIONS software family, MGA++ can display the data being acquired, then rapidly analyze and report results — all from a single, easy-to-use program.

    User Interface
    For each operational mode, separate “viewer” programs (MGAView, MGAHIView and U235View) and analysis modules (MGA.EXE, MGAHI.EXE and U235.EXE) ensure the integrity of the analytical methods. The Viewer program provides the user interface and the hardware control function. In MGA++ it is possible to suppress all spectral display.

    MGAView, MGAHIView and U235View present the same friendly user interface. The current status of the detector is shown on the right. A special count-rate meter mode shows the instantaneous count rate of a selected region. The spectrum may be viewed during acquisition.

    The Start/Save/Report feature provides one-button collection and analysis — via keyboard or mouse — easing the task for operators in protective suits! When additional counts are deemed necessary, “Restart/Save/Report” continues the current count.

    Reanalysis of spectra from disk or in the MCB is easy — just click and select. All the spectra collected by the MGA++ programs are stored in the ORTEC standard spectrum (SPC) format, which can be read by many programs. The file includes analysis parameters and hardware description records — everything needed to verify the results.

    Spectra stored on disk may be analyzed by MGA++ from a wide variety of input file formats in addition to the primary ORTEC SPC file format.

    The analysis results can be displayed, with zoom function capabilities, for visual confirmation of the analysis.

    Peak fit results may be scrutinized along with fit residuals for visual assurance of analysis quality. To aid comprehension, individual peaks on the display can be turned on or off.

    Flexible Analysis

    Analysis parameters are specified in clear, easy-to-understand dialog boxes. Analysis parameters may be saved to disk for use on similar samples and recalled as required.

    At the end of each analysis the results are automatically stored in the Access format database and are also printed or displayed for the operator. The three database tables (Analysis, Acquisition, and Isotope) can be viewed by MGAView (using the record function) or by Access. This powerful data storage method makes summary reports, exception reports, and other useful outputs which are easy to create.

    CONNECTIONS Integration
    The MGA++ programs, operating under Windows 2000/XP, are completely integrated into the ORTEC CONNECTIONS environment. All ORTEC multichannel buffer hardware, including DigiDART and DSPEC MCAs, are supported — whether networked or standalone.

    The CONNECTIONS structure facilitates development of custom applications, e.g., automated measuring systems. (Developer’s toolkits are available from ORTEC to aid this process.)

    Common benefits of all CONNECTIONS products are multi-tasking, multi-threading support for concurrent analysis processes under Windows 2000/XP, simultaneous support of both locally connected and remotely connected MCAs over Ethernet links, and detector locking by security password.

    MGA++ will operate correctly on any system supporting ORTEC multichannel buffer hardware under Windows 2000/XP. While MGA++ can control compatible MCA hardware directly, MAESTRO is a prerequisite for instrument setup.

    MGA Analysis Mode

    • Produces weight percent results for 238,239,240,241Pu, 241,243Am, 237,239Np, and 235,238U.
    • Determines 242Pu.
    • Operates with a single-planar HPGe detector for 0–300 keV or with a planar and a coaxial HPGe detector for 0–1000 keV.
    • No calibration standards needed to correct for matrix or container effects.
    • Automatic energy and peak shape recalibration.

    MGA mode has two data analysis configurations: one-detector mode and two-detector mode. In one-detector mode, MGA is designed to operate with a planar HPGe detector for the energy range 0–300 keV to obtain the Pu isotopic information. In two-detector mode, intended for highly-attenuated samples, the measurement may be aided by higher energy data up to ~1000 keV obtained from a coaxial HPGe detector. This coaxial detector allows measurement of gamma-ray energies to ~1 MeV. With this additional information, sample homogeneity and isotopic content can be refined. However, in the two-detector mode, the information from the planar detector is required, the coaxial information alone is insufficient. This requirement adds significant limitations when applying the original MGA code to the gamma-ray spectra of heavily shielded samples. This has to some extent been mitigated by the introduction of the ORTEC SGD GEM detectors, which in some cases can be used to perform the function of the planar and coaxial detector in one, by the use of two separate spectra, low and high energy.

    There are about ten energy regions in a plutonium gamma-ray spectrum which may be used to calculate isotopic abundances. Those in the 94-104 keV region and the peaks at 129 and 148 keV are the most intense. Although those regions are difficult to analyze, yield precision of 1% or better can be achieved.

    Sample Age Since Processing

    MGA handles both freshly-separated and aged samples — important because recently-processed plutonium samples are usually very low in 237U and 241Am. The 237U increases in activity for about 2 months after processing, at which time it reaches equilibrium with the alpha-decay rate of its 241Pu parent. Any analysis method that always assumes an established decay equilibrium between these two isotopes cannot be used on freshly-processed samples.

    Presence of Other Radioactive Materials
    Other radioactive materials may be present in plutonium samples as decay products, as contaminants from previous processes, or as a result of blending. Uranium is one common radioactive material which is blended with plutonium to form mixed-oxide (MOX) fuels. MGA can accurately determine the relative abundance of 235U in a sample. Other radioactive materials sometimes encountered are 237Np-233Pa, 243Am-239Np, and low levels of some fission products such as 95Zr-95Nb and 137Cs. If a two-detector system is employed, 237Np can be detected down to about 50 ppm by analysis of the 312 keV peak of 233Pa, the daughter of 237Np. MGA automatically recognizes the presence of interference from 243Am and 239Np isotopes, the fluorescence of x-rays of thorium in the sample, and the presence of 137Cs (if the two-detector system is used).

    MGAHI Mode
    MGAHI uses physical parameters to take into account both attenuation and emission of gamma rays, and does not require a detector efficiency calibration. The gamma-ray information between 50 keV and 200 keV is not required. MGAHI is useful when sources are heavily shielded, and in a high background, space-limited environment. With too much shielding, the 100-keV energy region could be completely attenuated. In a high-background environment, the detector could see gamma rays from other nearby sources. Also, the spectrometry system could have a very high dead time. Lead shielding can be used in this situation to reduce the dead time, but this could also cut out the low-energy gamma rays. MGAHI employs the original MGA methodology in that it: 1) uses physical parameters to take into account both attenuation and emission of the gamma rays, and 2) does not require detector efficiency calibration. However, unlike the "original MGA", the planar information is no longer required. The MGA analysis relies very heavily on the 100 keV energy region detector efficiencies, absorber thickness and Pu thickness are calculated from the spectral data using known gamma-ray peaks from the decay of 239Pu.

    MGAHI Mode Performance
    MGAHI Pu weight % results of the two Pu (PIDIE) standards. Data was collected using a 75% coaxial detector for 3 hours. Two absorbers (5 mm stainless steel (ss) and 2 mm Pb) were used. Results from destructive analysis (DA) are also tabulated.

       238Pu  239Pu  240Pu  241Pu
     PIDIE#1 +ss  0.012±18%    93.79±1%    6.02±4%  0.19±7%
     PIDIE#1 +Pb    0.011±15%  93.85±1%  5.98±3%  0.18±5%
     PIDIE#1 DA  0.01108  93.822  5.969  0.1975
     PIDIE#3 +ss  0.042±14%  84.65±1%  14.34±3%    0.97±4%  
     PIDIE#3 +Pb  0.044±13%  84.91±1%  14.04±3%  1.01±3%
     PIDIE#3 DA  0.0475  84.835  14.128  0.99

    U235 Analysis Mode
    • Relative ratios for 235U, 234U, and 238U.
    • Automatically checks for the presence of Pu using the 129 keV peak.
    • Operates with a single-planar HPGe detector from 0–300 keV.
    • No calibration standards necessary to correct for matrix or container effects.
    • Corrects for internal sample absorption and absorbers placed between sample and detector.
    • Peak shape calibration determined from user-defined spectral peaks, reloadable from file, or from default values.

    U235 uses a single planar HPGe detector and operates in the energy range 0–300 keV. It determines the relative isotopic ratios for Uranium. In a similar fashion to MGA and MGAHI, no primary calibration is required for efficiency or for absorbers in the matrix or in the sample container.

    Typical U235 Mode Performance

    U235 gives weight percent results for 234,235,238U.

     Isotope   Range (wt.%)   Absolute Accuracy (%) 
     234U  0.02-2  5.0
     235U  0.02-0.5  5.0
       0.5-70  0.5
       70-93  1.5
       93-99  5.0
     238U  99-99.5  5.0

    The U235 analysis mode gives relative ratios for 235U, 234U, and 238U; and when operating in this mode, it can warn the user of the possible presence of Pu.

    Absolute accuracy depends on the statistics of the sample.

    General Considerations

    Sample Size and Matrix
    In practical terms, the lower limit on sample size is about 100 mg — determined by count time and required statistical accuracy. While in principle there is no upper limit to the size, only the surface of a large sample is actually measured ­­because plutonium and uranium have short mean-free-paths for low-energy photons. Increasing the sample thickness beyond the “saturation thickness” will not increase the count rate because photons from the back of the sample are fully absorbed.

    The extent of fluorescence from uranium or plutonium by their own alpha or gamma emission is much lower than from solid materials. Entering details about the solution will assist the analysis in dealing with the x-rays.

    A shield or collimator should be used to reduce or eliminate the counts in the spectrum from nearby materials. Cadmium, copper, lead, or tantalum foils are used to reduce the presence of the low-energy gamma rays, specifically those at 59 keV. This reduces the dead time from unusable counts for plutonium samples. These low-energy gamma rays are hardly ever present in uranium samples. Unless they are present, preferential filtering of low-energy photons is almost never required and is of no value.

    Germanium Detector
    For measurements up to 300 keV with either MGA or U235, a planar HPGe detector with a nominal resolution of 550 eV at 122 keV is required. While this requirement may in some cases be relaxed, the 122-keV resolution should not exceed 700 eV.

    A thicker planar detector will have a higher peak-to-Compton (p/C) ratio, so that, assuming that it has an area and 122-keV resolution consistent with the other requirements specific to the measurement, it may deliver superior performance at low energies.

    To use the higher energy regions in the analysis of samples containing only plutonium, in two detector MGA mode or in MGAHI mode, a coaxial detector with a resolution of less than 2.0 keV at 1332 keV is adequate. For MGAHI, a detector resolution of 1.1 keV or better at 208 keV is required. The 203-keV gamma ray from 239Pu must be visible. Up to 5 mm of Pb absorber can be placed in front of the detector.

    ORTEC’s Safeguard (SGD) Series of coaxial and planar detectors, specifically optimized for the purpose, are highly recommended for use with MGA++.

    ORTEC Signs MGA++ Licensing and Development Agreement with LLNL
    ORTEC and Lawrence Livermore National Laboratory have entered into licensing and development agreements in the area of specialized software for nuclear safeguards applications. The license covers the existing versions of the MGA ++ suite of codes which analyze HPGe detector gamma-ray spectra from a wide variety of nuclear safeguards samples in order to determine relative plutonium isotopic abundances and/or uranium enrichment. The development agreement (CRADA) relates to further improvements to the code and an improved “seamless” integration within the ORTEC CONNECTIONS Windows 2000/XP spectroscopy environment for maximum ease-of-use and reliability.

    1 It is the subject of a cooperative research and development agreement (CRADA TSV-1368-96) and license (License Number TL-1375-96) between ORTEC and the University of California under which ORTEC is integrating those programs into the ORTEC software environment to enhance usability.
    2 K. Debertin and R.G. Helmer, “Gamma- and X-Ray Spectrometry with Semiconductor Detectors,” p. 185, Elsevier Science Publishers B.V., The Netherlands, 1988.
  • Ordering Information +

    Model Description
    MGA-B32 MGA++ Safeguards Software
    MGA-U32 Update for MGA-B32
    MGA-G32 Documentation for MGA-B32