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Series 3800 Tomographic Gamma Scanner
  
QED Low-Level Waste Assay and Segregation System
  
ISO-CART
  
ISOTOPIC-32
  
Holdup Measurement System (HMS-4)
  
Hybrid K-Edge Densitometer
  
Model 2203 Very High Efficiency Neutron Counter
  
Model 2200 Passive Neutron/Gamma Multiplicity Drum Monitor
  
Model 2442 Active Well Coincidence Counter
  
Model 200 High Sensitivity Large Sample Calorimeter

Non-Destructive Assay Solutions for Special Nuclear Material Accountability and Radioactive Waste Measurements

ORTEC and ANTECH are partners in the area of non-destructive assay instruments and systems for waste assay and nuclear safeguards applications. ORTEC distributes and supports ANTECH-manufactured Gamma-Ray, Neutron and Calorimetry Systems along with its own ORTEC products.

Here, we summarize the combined product range now available through ORTEC Sales and Service Centers, world-wide for a wide range of NDA needs.

Gamma-Ray Systems

Which NDA System is Right for Your Application?

nda8.jpg (15461 bytes)Series 3800 Tomographic Gamma Scanner1  (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.

  • One instrument provides total Assay result combining TGS measurement of U, Pu and other Radionuclides with Pu isotopic ratio analysis using LANL PC/FRAM code
  • TGS technique meets both safeguards and WIPP measurement and QA requirements
  • Provides tomographic maps of absorbers and sources in heterogeneous matrices
  • Extends range of SGS technique to hertogenious samples. For homogeneous samples the ANTECH TGS can operate as an SGS using ANTECH ARTEMIS-2 software
  • A single calibration constant can be employed for each radio nuclide determined due to the bias reduction inherent in the TGS technique
  • Measures samples with Am-241 content which cannot be measured with neutron techniques
  • Accuracy and precision sufficient to meet safeguards, shipping and disposal requirements
  • Gamma-ray based NDA technique for the assay of U, Pu and radio nuclides in waste, based on licensed LANL TGS technology
  • Incorporates Tomographic Gamma Scanner (TGS) Segmented Gamma Scanner (SGS) and plutonium Isotopic Ratio Measurement capability in one instrument
  • Automatic gamma-ray energy calibration using the Se-75 transmission source
  • Transmission corrections are achieved using SE-75 transmission source to develop a 3D spatial map of the attenuation coefficient of the sample
  • Manual or automatic drum loading
  • Measurement time of typically less than one hour. Increased accuracy and precision can be achieved by extending the measurement time
  • Mobile operator control console which is compatible with both Drum TGS and UGS for cans, which can be local or remote from the instrument
  • Accuracy is typically better than 10% for measurement of cans and 20% for matrices with average density 2g/cm3. It is better than 10% for metal scrap matrices
  • QED Low-Level Waste Assay and Segregation System

    An easy to use, reliable and robust solution to free release sentencing of containerized radioactive waste.

    This gamma-ray system is designed for measurements down to very low levels of activity. It consists of three HPGe coaxial detectors housed in a steel shield which will accommodate a 208 litre drum.

    • Detection limits easily meet free release levels resultingin 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
    isocart3.jpg (18373 bytes)ISO-CART 4

    For: In-situ assay of large containers, pipes, surfaces, etc.

    • Cart-mounted mobile system for in-situ measurement of surfaces and objects
    • Handles a wide variety of container sizes and densities
    • Simple point-source calibration
    • Models geometry and matrix corrections
    • "Fine-tune" interative graphic plot validates configuration assumptions
    • Typical counting times vary from 15 to 30 minutes
    • Also applicable to process holdup measurements of special nuclear material
    • ISO-CART at Work
    • Turntable option
    M-1.jpg (20822 bytes)ISOTOPIC-32  for Soils

    For: Wide-area assays of soil contamination

    • Rapid estimates of contamination on and/or in soils over a wide-area with unshielded HPGe detector
    • Authoritative EML methodology5, handles surface and "washed-in" contamination
    • Point source calibration
    nda3.gif (25696 bytes)Holdup Measurement System (HMS-4)6

    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
    • Gathers data, analyzes and documents
    • Highly automated, measurement points are identified using bar codes
    • Incorporates the Los Alamos (LANL) Generalized Geometry Holdup (GGH) methodology
    Hybrid K-Edge Densitometer

    For:
    kedge.jpg (18392 bytes)(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.
    • Available as laboratory instrument or as input solution instrument.
    • Custom configurations to match to existing hot cell with suitable fail safe sampling handling methods available.
    • Physics and Engineering consulting design support available.
    • Flexible choice of standards for calibration purposes, including ability to use suites of standards having different enrichment factors.
    • Superior attenuation correction algorithm permits good calibrations with small numbers of calibration standards.
    • Measurement range from 100mg to 100’s of g of the 6 major Actinides (U, Pu, etc), with ratios of major to minor to 100’s.
    • Ease of sample preparation, especially when compared to destructive methods.

    Neutron Measurement Systems

    Model 2203 Very High Efficiency Neutron Counter (VHEnC)

    nda4.gif (19603 bytes)For: measurement of Plutonium bearing intermediate and low level waste in 220 litre (55 gallon) drums
    • Decagon shaped measurement chamber approximates the cylindrical geometry of the drum eliminating the need to rotate the drum during neutron counting
    • AMSR-150 data is analysed by an optimised version of the LANL INCC code based on super-HENC technology for cosmic-ray reduction.
    • Can be operated in conventional coincidence mode to eliminate the (a,n) neutron signal and in multiplicity mode, where larger quantities of plutonium are present, to achieve matrix correction
    • 160 He-3 tubes (25 mm diameter x 1 m length, 6 atmospheres fill pressure) arranged in two rows of 80 tubes close coupled to the waste drum.

    • Optional ‘Add-a-Source’ Cf-252 available for matrix correction which complements the matrix correction by neutron multiplicity counting
    • Lower Limit of Detection of between 1.3–15 mg 240Pueffective in totals mode equivalent to between ~20 and 250 mg total Pu (military grade)

    Model 2200 Passive Neutron/Gamma Multiplicity Drum Monitor

    nda5.gif (12675 bytes)For:  measurement of Plutonium bearing intermediate and low level waste in 220 litre (55 gallon) drums

    • Optimised for use with ANTECH 1000 Series TCA (multiplicity counter) electronics using 3 trigger methods and 16 simultaneous observation intervals (gate widths)
    • 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
    nda6.gif (16636 bytes)Model 2442 Active Well Coincidence Counter (AWCC)

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

    • Robust Construction
    • Reproduces the physics and measurement characteristics of the original LANL AWCC design
    • Adjustable size measurement chamber
    • High detection efficiency of 31% in large sample configuration
    • Employs two Americium-Lithium (Am-Li) neutron sources for Uranium determination.
    • 42 He-3 detectors at 4 atm. pressure with six Amptek charge sensitive amplifiers
    • 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
    • Built in totals counters which can be read out independently
    • Provides complete passive and active assay system when used with the ANTECH/ORTEC AMSR 1507 Neutron Coincidence/Multiplicity Counter
    nda7.gif (12511 bytes)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 from ANTECH for different size and dimensions of sample containers and measurement sensitivities
  • Software selectable redundant measurement sensors and operation modes to optimise accuracy or measurement time
  • Sample lifting device with fail safe hoist
  • Short delivery time of less than six months for custom designs
  • Summary of System Applicability

    Instrument

    Uranium

    Plutonium

    Fission/Activation Products

    Comments

    QED * * * Most sensitive; for light waste
    Calorimeter   *  

    Most accurate, also for tritium

    ISO-CART * * * Handles large badly characterized samples
    Passive Neutron   *   Spontaneous Fission Nuclides
    Active Well * *   Passive or Active modes
    HMS-3 * *    
    TGS * * * Large or small container; highest accuracy

    The ORTEC -ANTECH Advantage
    All of the gamma-ray measurement systems described herein are based on ORTEC component instruments. For more than 25 years, the ORTEC name has become synonymous with quality, innovation and reliability in gamma-ray measurement instruments. The systems employ the latest ORTEC DIGITAL spectrometers, DSPEC Plus and the portable digiDART MCA. SGD series "Safeguards-tuned" HPGe detectors feature extensively. All of the HPGe gamma-ray systems listed here may optionally be supplied with the revolutionary X-COOLER for cost effective LN2-free operation. The AMSR-150 Advanced Multiplicity Shift Register is a joint ORTEC-ANTECH product. The combination of ORTEC products and subsystems with ANTECH advanced system engineering and innovative measurement technology results in solutions across a broad range of NDA needs. All systems may be fully supported world-wide.

    1 LANL License 99-53-00559
    2 High Resolution Gamma Spectrometry
    3 LANL License 97-53-00241 and additions
    4 Software License LMES PLA-190
    5 HASL 258 et.seq.
    6 LMES License 0248
    7 LANL License 99-53-00581