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Logiciel systèmes

CANBERRA Systems Software offers a standard platform for use with all systems. Various counter arrangements, detector arrangements, analysis sequences, hardware control, and reports can be generated from the standard software. This provides the advantage that as the customer's assay requirements change, the software can be easily adapted to handle the new requirements.

Produits dans cette famille

NDA 2000 Non-Destructive Assay Software

NDA 2000 Non-Destructive Assay Software

Description

CANBERRA's NDA 2000 software is designed to be a complete acquisition, analysis and archival package for use with all CANBERRA neutron counters and gamma-ray systems. NDA 2000 offers fully integrated neutron and gamma-ray analysis for either combined or sequential assay operations. NDA 2000 is based on CANBERRA's Genie 2000 format providing the ease and flexibility of operation found in our popular gamma-ray spectroscopy applications. Various counter arrangements, detector arrangements, analysis sequences, hardware control, and reports can be generated from the standard software. This provides the advantage that as the customer's assay requirements change, the software can be easily adapted to handle the new requirements.

NDA 2000 Non-Destructive Assay Software

Features

  • Supports all CANBERRA safeguards and waste assay systems
  • Supports neutron and gamma-ray assay systems
  • Based on the CANBERRA's Genie™ 2000 platform
  • Provides full control of data acquisition electronics
  • Controls automated assay system operation
  • Menu structure for ease of operation
  • Customer editable report formats
  • Multi-level password control
  • Compliant with ISO 9001 and IEEE 730 requirements
  • Developed in compliance with the requirements of ISO 9001 and the requirements of CAO QAPP, Document number CAO-94-1012, Rev 3, which specifies the WIPP quality program to be ASME NQA-1-1989, and ASME NQA-2-1990, Part 2.7
  • Operates under Microsoft® Windows NT®, Windows® 2000, Windows XP and Windows 7 (32-bit)
Mercurad

Mercurad

Description

The MERCURAD software, with its powerful user interface that can display 3D scenes, offers a practical solution to meet the complex dose calculation requirements of health physics specialists, shielding calculation engineers, and staff involved with nuclear facility maintenance and nuclear installation dismantling projects.

The new MERCURAD software is built using the computation engines of the well known and tested MERCURE calculation code(1). It makes extensive use of a new graphical user interface, thus allowing very complex items to be easily defined and presented.

Features

  • 3D dynamic simulation of structures (sources, shielding, collimators, etc.)
  • Various 3D interactive displays modes (full, transparent, wiring, etc.)
  • Multiple sources can be defined. Each source is also an attenuator for other sources
  • Doses calculated for multiple points at the same time
  • Multi-layer shield construction can be used
  • Automatic attenuation buildup calculations - no user guesswork involved
  • Core computation method is the powerful MERCURE V6
  • Faster than Monte Carlo codes
  • Multiple layers build-up calculation (new CEA method based on neural networks)
  • Allows "what if" calculations using maximum and minimum values of key parameters
  • User friendly user interface under Windows® NT, Windows® 2000, or Windows® XP

Mercurad

Multi-Group Analysis Software (MGA)

Multi-Group Analysis Software (MGA)

Description

The determination of relative plutonium isotopic concentrations through non-destructive assay is a fundamental requirement in most waste management and safeguards applications. Yet, complex samples, varying container shapes and materials, and other complications have historically made it one of the more difficult measurements.

Multi-Group Analysis (MGA) was designed to improve the accuracy of these measurements over traditional methods. In addition to the primary application of measuring Pu isotopics, MGA can be used to determine other actinides such as 235U, 238U, 237Np and 241Am as well.

More recently, CANBERRA has added its exclusive enhancements to improve the measurement results obtained under the difficult conditions encountered in Waste and Decommissioning & Decontamination (D&D) applications. These applications often result in low-activity, low-counting statistics spectra typified by measurements on large containers. Additional enhancements have simplified or eliminated the numerous setup and calibration steps necessary with earlier MGA versions and other methodologies. Thus it can be used in a broader range of applications involving routine, repetitive measurements.

For standard 8K spectra the MGA analysis is based on the spectral information available in the 0-600 keV range of the energy spectrum. (When only 4096 channels are available the operating range is from 0-300 keV.) The primary analysis in both cases is performed using the multiplet region at 94-104 keV. While this region is the best choice for gamma line intensity (and consequently detection sensitivity) for several of the plutonium isotopes, it is a very complex region because it also consists of gamma ray peaks from plutonium progeny as well as numerous x-rays. In order to unfold this complex multiplet region, MGA automatically adjusts the energy and peak shape calibration for each spectrum using peaks that are characteristic of all plutonium samples – 59 keV, 129 keV, and 208 keV. The characteristic plutonium lines at 129 keV and 208 keV are always required to be present. For special cases where the low-energy region is not available for analysis (if the Pu sample is stored in a Pb-lined container for example), a 'high-energy-only' option exists to force the analysis. A two-detector mode is available as well, if added information from regions above 600 keV is desired in the analysis.

MGA internally develops an intrinsic efficiency curve based on several energy lines from three isotopes. The efficiency curve takes into account the physical processes that affect the observable gamma ray intensities at different energies, such as the detector efficiency as a function of energy, and gamma ray attenuation in absorbing materials between the sample and the detector as well as within the plutonium sample itself. Using the energy, shape and intrinsic efficiency information, MGA calculates a response spectrum consisting of peak energies (positions), relative peak intensities, and an accurate peak shape of each peak in the 94-104 keV peak region. Accommodation is made for the Gaussian broadening of gamma ray peaks and the Lorentzian shape of the x-ray peaks. Isotopic concentrations are directly calculated for all Pu isotopes, except 242Pu which is derived from the other isotopes.

Multi-Group Analysis Software (MGA)

Features

  • Determines relative plutonium isotopic abundances in nondestructive assay applications
  • Determines the relative amounts of certain other non-plutonium actinides
  • Optimized for spectra collected with HPGe detectors which are optimized for high resolution at low energies over a wide range of count rates
  • Incorporates a sophisticated peak fitting and multiplet deconvolution algorithm to improve the accuracy in samples with complex isotope mixtures
  • Requires no efficiency calibration for matrix density, thickness or container characteristics
  • Operates in either one or two detector mode
  • Integrated into CANBERRA waste and safeguards instruments to perform a sophisticated analysis with minimal operator interaction
  • Developed in collaboration with top experts in nondestructive safeguards applications and hardened for waste and security applications
  • Offers "Waste" and "Unusual
Multi-Group Analysis for Uranium (MGAU)

Multi-Group Analysis for Uranium (MGAU)

Introduction

The accurate non-destructive assay of uranium bearing materials to determine uranium content is vital in nuclear safeguards, waste management, and fuel cycle process control measurements. In a climate of heightened concern for the possible diversion of special nuclear materials, there is a need in the nuclear community for continued maintenance and advancement of accurate uranium detection and verification tools.

Uranium measurements are typically difficult because of varying container shapes, container wall thicknesses, uranium chemical forms and other complications. Multi-Group Analysis for Uranium (MGAU) was designed to improve the accuracy of these measurements over traditional methods, while simplifying or eliminating the setup and calibration steps necessary with other methodologies. MGAU can therefore be used with minimal setup, by operators requiring minimal training, and it is easily applied to applications involving routine, repetitive measurements.

Description

In its normal mode MGAU uses information from the low energy region which includes both gamma and X-rays from 84 to 205 keV. The primary enrichment information is derived from the 235U and 238U emissions in the 90-94 keV energy range. Several peaks detected in the measured spectrum itself are used to develop a relative efficiency curve; i.e. the detector efficiency as a function of energy is determined, taking into account the amount of attenuation caused by the sample container, and the amount of self-absorption in the uranium material itself. This process eliminates the need for an efficiency calibration prior to making sample measurements.

In the enrichment-meter mode, MGAU utilizes the 186 keV gamma line from 235U decay and requires just one calibration measurement with a reference standard of known enrichment and known container wall thickness. The results of this calibration measurement are automatically stored for further use on any samples with known container wall thicknesses. The enrichment meter mode is useful for very thick container walls where poor counting statistics in the spectrum may limit the results from the normal mode, and also can be used for analyzing uranium samples where the uranium isotopes are not in equilibrium with their daughter products (freshly separated uranium).

Applications

  • Nuclear Safeguards
  • Inventory control at enrichment facilities
  • Waste measurements

Multi-Group Analysis for Uranium (MGAU)

Features

  • Determines uranium isotopics (enrichment) accurately in non-destructive assay applications
  • Sophisticated analysis using multiplet deconvolution eliminates the need for efficiency calibration based on matrix density, matrix type, or container characteristics
  • In the enrichment meter mode, only one calibration measurement is required
  • Integrated into CANBERRA waste and safeguards instruments to perform analysis with minimal operator interaction; batch mode for repeated measurements
  • Standalone analysis mode available if expert review is needed of spectra, fit residuals, and results
  • Developed in collaboration with top experts in safeguards NDA applications

Key Benefits

  • Fast and accurate uranium isotopics measurements
  • No calibration standards required for isotopics measurements
  • Ease of use for setup and operations; minimal operator training is required
FRAM

FRAM

Description

FRAM (Fixed-Energy, Response Function Analysis with Multiple Efficiency) is a code developed by Los Alamos to analyze pulse-height spectra generated by high-resolution gamma-ray detectors. It has been used primarily to determine the isotopic composition of plutonium in special nuclear materials. Its design and flexibility allow it to easily measure ratios and distributions of isotopes other than plutonium in arbitrary items.

In nuclear safeguards, FRAM complements calorimetry and neutron coincidence counting by allowing measurements to be interpreted in terms of total plutonium mass.

Features

  • Determines relative plutonium isotopic abundances or uranium isotopic abundances in non-destructive assay applications
  • Uses spectra collected with HPGe detectors
  • Incorporates a sophisticated peak fitting and multiplet deconvolution algorithm to analyze complex peak regions
  • Requires no efficiency calibration for matrix density, thickness or container characteristics
  • Developed by Los Alamos and licensed to CANBERRA

FRAM

Material Types Measured with FRAM

  • 240Pu (2% – 95%) of total plutonium
  • 241Pu – 237U (nonequilibrium)
  • Am/Pu in heterogeneous combinations
  • 241Am (0.01% to >50%)
  • 235U/Pu mixed (MOX) ratios from 0.005 – 35
  • 243Am – 239Np
  • 244Cm
  • 237Np
  • 234U, 235U, 238U relative abundances, (no plutonium present), 0.2 to >97% 235U
  • 238Pu (80%)
  • Materials in shielded or heavy-walled containers (≥13 mm Pb for plutonium, ≥16 mm steel for uranium)