Technical Activities

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Most Recent Technical Activities Archive of Technical Activities

Ionizing Radiation Division

Technical Highlights

  • Intravascular Brachytherapy Source Dosimetry. The use of beta-particle emitting brachytherapy sources for the prevention of restenosis (re-closing) of coronary blood vessels after angioplasty continues to be actively explored. NIST has taken an early and leading role in the calibration of the sources used for this therapy, employing the NIST extrapolation chamber equipped with a 1 mm diameter collecting electrode to measure dose rate at a depth of 2 mm in water-equivalent plastic. These measurements are confirmed using radiochromic dye film, which is also used to characterize sources in the cylindrical geometry for transaxial uniformity. In addition, irradiation of planar sheets of film at various depths in water-equivalent plastic were used to construct data sets which can be used to predict the dose rate at arbitrary locations around the sources using a modified form of the AAPM Task Group 43 Protocol. A publication describing this work has been published in the journal Medical Physics. The equipment used for these studies was augmented with the addition of an automated microscintillator detection system and various well-ionization chambers. Use of all this equipment was centralized in a newly refurbished laboratory. Collaborations were continued between NIST and NeoCardia for dosimetry of a 32P wire, with Washington Hospital Center for dosimetry of various sources, with Radiance Medical Systems for dosimetry of radioactive balloon sources, and with Best Industries for 188W/Re wire and 192Ir seed sources. Collaborations were also begun with Cordis for 125I wire dosimetry. (C.G. Soares and M.G. Mitch)
  • Prostate Brachytherapy Source Characterization. There is currently great demand for low-energy photon brachytherapy seeds used in the treatment of prostate cancer. As a result, in 1999 the number of source manufacturers submitting seeds to NIST for calibration has increased from two to nine. Effective treatment planning requires accurate knowledge of source air-kerma strength, which is used to calculate the dose rate to tissue that is delivered by the seeds. The primary standard measurement of source air-kerma strength is made using the Wide-Angle Free-Air Chamber (WAFAC) for seeds containing 103Pd or 125I. On-site characterization at seed manufacturing plants for quality control, as well as at therapy clinics for treatment planning, relies on well-ionization chamber measurements. Therefore, calibration factors relating well-ionization chamber response to air-kerma strength for each seed design must be known. The responses of several different types of well-ionization chambers to the seeds were measured, and calibration factors were calculated. The significant influence of seed composition on the response of well-ionization chambers relative to measured air-kerma strength for prostate brachytherapy seeds has been demonstrated. (P.J. Lamperti, M.G. Mitch, B.E. Zimmerman, S.M. Seltzer, and B.M. Coursey)
  • LabVIEW Automation of Brachytherapy Dosimetry Measurements. Data acquisition and instrument control for all measurement stations in the NIST beta brachytherapy laboratory (including well-ionization chambers, extrapolation chamber and plastic scintillator) have been automated using LabVIEW, a graphical programming language. LabVIEW allows live data transfer between computers over the internet. This can be used in conjunction with a video teleconferencing link, providing a "virtual presence" at NIST for scientific collaborators and calibration customers. This mode of operation was demonstrated at the 1999 Council on Ionizing Radiation Measurements and Standards’ annual meeting at NIST with the cooperation of a customer in Houston, TX. Such real-time interaction between NIST scientists and their industrial colleagues during a measurement will improve the overall efficiency of the calibration process. (M.G. Mitch and C.G. Soares)
  • Mammography Calibration Facility. In an effort to meet the needs of calibration facilities that offer NIST traceable calibrations of air-kerma measuring instruments used in the mammography energy range, NIST now offers proficiency tests. The Food and Drug Administration’s Mammography Quality Standards Act "Final Rule for Quality Mammography Standards" requires that all clinical mammography units be calibrated with an instrument that is traceable to a national standard. Any facility that provides the NIST traceable calibration must participate in a biennial proficiency program directly with NIST. A replacement Mo anode x-ray tube was purchased and has been characterized for the NIST mammography proficiency testing and for routine calibrations. Upon repair, the previous Mo anode will be characterized and integrated into the calibration system. The data-acquisition software upgrade is in the final testing stage and is being used to calibrate NIST reference chambers for proficiency testing. (C.M. O’Brien)
  • Electron Detector Calibrations. In collaboration with Physical Sciences Inc. of Andover, MA, a series of charged-particle sensor calibrations was conducted using the electron Van de Graaff accelerator. To facilitate this work it was necessary to restore beam to the zero-degree beam line in the south target room. The investigators had strict beam quality requirements, including high resolution and low fluence rate, which we were able to meet in tuning the beam. The calibrations were completed at several energies ranging from 500 keV to about 2 MeV, enabling the users to conduct a thorough test of the detector’s performance. These sensors were designed to be used in space-flight applications to measure light charged-particle spectra encountered in Earth orbit. Some of these detectors have been placed aboard commercial and government satellites, and there are plans to use them on the International Space Station. Consisting of solid state and scintillator elements, these Light Particle Monitors are able to identify and energy-analyze electrons, protons and alpha particles simultaneously over a wide range in energy. Previously separate sensors had to be used to monitor electrons and protons. Knowledge gained from these calibrations will help researchers refine the present generation of detectors and aid them in the design of future prototypes. The researchers plan to return to NIST over the next several months to test a new prototype detector currently under development. (F.B. Bateman and M.R. McClelland)
  • Photon and Charged-Particle Data Center. The Data Center compiles, evaluates, and disseminates data on the interaction of ionizing radiation with matter. The data on photons and charged particles, with energies above about 1 keV, include fundamental information on interaction cross sections as well as transport data pertaining to the penetration of radiation through bulk material. Databases are developed and maintained on attenuation coefficients for x rays and gamma rays, including cross sections for Compton and Rayleigh scattering, atomic photo-effect, and electron-positron pair production, as well as on energy-transfer, energy-absorption and related coefficients relevant to radiation dosimetry. Work on charged-particle cross sections and of radiation transport data has entailed significant effort on the evaluation of the stopping powers and ranges of electrons, positrons, protons, and alpha particles, the elastic scattering of electrons and positrons, and the cross section for the production of bremsstrahlung by electrons. Current work includes the development of new standard reference data for the elastic scattering of electrons and positrons from neutral atoms; comprehensive evaluations of the doubly differential cross section for inelastic Compton scattering of photons, including the effects of Doppler broadening due to the motion of the orbital electrons; and comprehensive evaluations of the photon mass energy-absorption coefficient, a quantity widely used in radiation dosimetry. With the help of the NIST Physics Laboratory’s Office of Electronic Commerce in Scientific and Engineering Data, a number of the Center’s databases can be accessed on the www. (S.M. Seltzer, J.H. Hubbell, M.J. Berger, and D.V. Rao)
  • Alanine-EPR Film Dosimeter. A new polymer-based film dosimeter containing alanine has been tested. The film, obtained from Gamma Service (Germany), is produced in commercial quantities in a variety of thicknesses. The first films tested were 100 µm in thickness and irradiated over a range of 1 kGy to 100 kGy. The relative standard deviation of the response over this range was on average 0.8 %. Comparative measurements of radiochromic films and alanine films irradiated at MIRF produced similar dose values within the relative uncertanities of the two systems. A more comprehensive study of the alanine system is planned. A small batch of 10 µm alanine films was recently received and will be tested for use with low-energy electron beams. (M.F. Desrosiers, J. Puhl, F.B. Bateman and M.R. McClelland)
  • International Gamma-Ray High-Dose Comparison. The national metrology institutes of the United States (NIST), France (BIPM), Great Britain (NPL), Germany (PTB), Italy (INMRI-ENEA), National Institute of Metrology (China), and the International Atomic Energy Agency, have undertaken a high-dose comparison. The BIPM coordinated the comparison, analyzed the results and will prepare the publication of the results. The protocol was created through consultation with the two issuing laboratories, NIST and NPL. The irradiating laboratories processed the dosimeters and returned them to the issuing laboratories for evaluation. NPL more closely correlated with the testing laboratories than NIST; the average deviation from NIST ~1.5 %. The comparison was dose dependent with the best correlation between all labs occurring at the highest dose (30 kGy). (M.F. Desrosiers, V. Nagy and J. Puhl).
  • Techa River Study. One of the most massive 90Sr releases in mankind’s history was produced by the first Soviet nuclear weapon plant Mayak near the Techa River, Urals, Russia. In 1949-1956 about 7.6 x 107 m3 of liquid radioactive wastes with a total activity of 1017 Bq (2.7 × 106 Ci) was released into the Techa River, with an 11.6 % contribution of 90Sr to the total activity. As a result of Mayak’s radioactive discharges, the population of the Techa riverside (about 28,000 people) was exposed to high levels of ionizing radiation. An extensive EPR dose reconstruction study (Institute of Metal Physics, Russia) with 29 teeth of the Middle and Lower Techa riverside population was carried out. It revealed ultrahigh doses (up to 15 Gy) absorbed in tooth enamel of the individuals born in 1945 tp 1949. The introduction of corrections developed at NIST based on the effective time of the onset of dose accumulation and dose attenuation effects has eliminated serious contradictions of the original reconstructed doses. The tooth most sensitive to 90Sr internal exposure is the first molar (both tooth enamel and dentin). A tooth from this position can give an additional enhancement factor of 4 to 6. Thus, selection by age group and tooth position at sample collection can improve the detection and measurement of former 90Sr releases by a factor of 200. (A.A. Romanyukha, S.M. Seltzer, and M.F. Desrosiers)
  • Asymmetries of the Weak Interaction and the Neutron Lifetime. The cold neutron guide hall at the NIST Center for Neutron Research (NCNR) provides a unique opportunity for the U.S. to compete for a leading role in research on the physics of fundamental particles. High precision measurements at very low neutron energies complement high-energy research at national and international particle accelerator laboratories. Measurement techniques developed for this research improve NIST’s ability to provide measurement services and calibrations. The Neutron Interactions and Dosimetry Group pursues a research program of its own as well as supporting a national user facility for industrial and university researchers.

    Two different neutron lifetime experiments, one a Harvard-led ultra cold neutron (UCN) experiment, the other a NIST-led cold neutron beam experiment, have taken data on our polychromatic neutron beam at the NCNR this year. In an experiment using a cryogenic lithium calorimeter at our adjacent monochromatic neutron beam, collaborative work with Indiana University is aimed at determination of the efficiency of the neutron fluence monitor belonging to the neutron lifetime experiment.

    Complete three-dimensional magnetic trapping of ultracold neutrons was demonstrated by the Harvard/NIST collaboration this year for the first time anywhere. A report of this work has been accepted for publication in the journal Nature. Trapping of neutral and charged particles is an invaluable tool for the study of both composite and elementary particles. The main advantages of trapping are long interaction times and isolation from perturbing environments. In the present work, inelastic scattering in superfluid 4He is used to load neutrons into the trap and also to act as a scintillator for detection of neutron decay. This work verifies the theoretical predictions of the loading process and the technique of magnetic trapping of neutrons. Further refinement of this method should lead to improved precision in the measurement of the beta-decay lifetime of the neutron.

    In CY99 the large collaborations responsible for two previous experiments on our polychromatic beam continued major drives to upgrade those experiments in preparation for further running on our beam. Both projects, a search for time-reversal symmetry violating correlations in neutron decay and a search for parity violating spin rotation of neutrons in bulk media, are expecting to be ready for beam time sometime in late CY2000. These projects have produced three recent Ph.D. theses and have already made modest improvements on the best preceding results. (M.S. Dewey, J. Nico, P. Huffman, F. Wietfeldt, J. Adams, M. Arif, T. Gentile, D. Gilliam, D. Jacobson, G. Jones, and A. Thompson)
  • Polarized 3He for Neutron Spin Filters and MRI Applications. The primary focus of the polarized 3He program is the development and application of neutron polarizers for both condensed matter science and fundamental physics. As a spin-off of this technology, the program also includes collaboration with medical researchers in polarized gas magnetic resonance imaging (MRI). A unique feature of the 3He effort is the concurrent development of the spin-exchange and metastability-exchange optical pumping methods. These two methods have different strengths and weaknesses, and pursuit of both allows for a versatile approach to the needs of different applications.

    Last year we demonstrated separation of coherent scattering from incoherent scattering using 3He-based polarization analysis on the NIST Center for Neutron Research (NCNR) NG7 small angle scattering spectrometer (SANS). Following upon this work, we have established a series of experiments to be done in collaboration with NCNR staff to investigate separation of magnetic from nuclear scattering.

    Recently we have obtained a significant improvement in the achievable optical pumping cell pressure in the diaphragm compressor apparatus which is used for the metastability-exchange polarization method. This improvement should allow us to reliably fill cells with over 40 % polarization, and we hope to push up towards 50 % with more efficient optical pumping. (T. Gentile, A. Thompson, G. Jones, and D. Rich)
  • Neutron Interferometry and Optics Facility (NIOF). During the past year at the NIOF a number of fundamental and applied physics experiments have been carried out and new collaborations with Indiana University, the University of North Carolina, and the Nuclear Physics Institute (Czech Republic) have been established. Three-dimensional neutron imaging of industrial specimens has been developed under ATP sponsorship. Five refereed articles have been published (or are in press). Invited presentations were also made at the SPIE and AOS (Australian Optical Society) organized conferences.

    Major progress has been made in the design and construction of a highly sensitive experimental assembly for the precision measurement of the neutron-electron interaction length bne and in the actual conduct of the experiment. This very fundamental quantity bne is critical to the understanding of the charge structure of the neutron and of the deuteron charge structure in atomic physics. After four decades of sustained effort discrepancies between different experimental values and between experiment and theory persist. Using a novel dynamical diffraction effect for a perfect single crystal inside a neutron interferometer, we are attempting to measure bne directly and accurately.

    Researchers from the University of Innsbruck, Austria, have successfully completed experiments involving dynamical diffraction of neutrons from macroscopic objects. These experiments are also the primary component of the Ph.D. dissertation of a student (Annette Lacroix) of Prof. A. Zeilinger from the University of Vienna.

    After successful neutron interferometric measurement of the mass density of a thin polymer film (~0.4 µm) in 1998, the measurement was extended to measure film thickness between (0.01 µm and 0.05 µm). For the first time an effectively "zero" phase shift substrate was used to enhance the sensitivity of the experiment. This interferometeric technique may provide an alternative, highly accurate and self-calibrating method for the routine measurement of polymer thin film mass density. The experiment was carried out in collaboration with the NIST Polymers Division. (M. Arif, D. Jacobson, A. Ioffe, P. Huffman, T. Gentile, and A. Thompson)
  • Neutron Dosimetry. An unusual amount of measurement service work was provided this year at the request of U.S. Navy contractors from Bettis and Knolls laboratories. Special irradiation facilities were constructed for testing neutron fluence monitors in the presence of high level gamma-ray fields.

    Developments in metrology services and consultation services on behalf of the Nuclear Regulatory Commission Office of Regulatory Research included development and successful balloting of a new ASTM standard on reactor dosimetry and major supporting efforts for the Tenth International Symposium on Reactor Dosimetry in Osaka, Japan.

    Calibration services for isotopic neutron sources and for neutron radiation protection survey instruments were both upgraded and continued to have a steady customer base. The Manganese Bath facility for comparing customers’ sources with the national standard NBS-I was generally refurbished and modernized with improvements including new highly reproducible source positioning fixtures and a new shield window. Continued progress was also made in the automation of the survey instrument calibration range. (J. Adams, A. Thompson, J. Nico, and D. Gilliam)
  • Neutron Cross Section Standards. The NIST Neutron Cross Section Standards Project has played an important role in the improvement of the neutron cross section standards through both evaluation and experimental work. We are leading an effort that will result in a new international evaluation of the neutron cross section standards. This has involved motivating and coordinating new standards measurements, examining the standards database, and pursuing the extension of the standards over a larger energy range. This work is taking place through participation in the U.S. Cross Section Evaluation Working Group and two international committees, the International Nuclear Data Committee and the Nuclear Energy Agency Nuclear Science Committee. An objective is to complete the evaluation in time for the major international cross section evaluation projects to use the improved standards in forming new versions of their libraries. (A. Carlson and D. Gilliam)
  • Dissemination of National Standards of Radioactivity. The Radioactivity Group disseminated the National Standards of Radioactivity mainly through the following three activities: (1) Over 550 radioactivity Standard Reference Materials (SRMs) were sold in 1999. (2) Over 200 comparative measurements and Reports of Traceability were provided to federal regulatory agencies, radiopharmaceutical manufacturers, commercial suppliers of calibration sources and services, and the nuclear-power industry. Industrial steering committees guided the work of four research associates in cooperative testing programs. (3) Over 112 calibrations of customer sources were provided. (L.L. Lucas, J.C. Cessna, and L.R. Karam)
  • Glow-Discharge Resonance Ionization Mass Spectrometry (GDRIMS). GDRIMS was successfully tested for the first time with cw lasers during this period. Three papers summarizing the work have been submitted for publication or are in preparation. Cesium was used to test the system. At present it is estimated that the system can be used to determine trace amounts of radioactivity at normal environmental levels directly, without chemical analysis, with half-lives in the 105 year range. This would include the important radionuclide 239Pu at somewhat elevated levels. It is anticipated that improvements in the near future could improve this by 2 to 3 orders of magnitude. This new capability was established through several steps taken this year. The regime in the glow discharge for which atomization, which is needed for selective laser ionization, dominates over ionization was investigated and parameter choices were made for which the efficiency is increased and the background is reduced. Generally this occurred in the pressure range of 120 mTorr. Also, the optimal sizes and shapes of the exit aperture and repeller were tested for maximum signal strength and ion background rejection, and a new diode laser was installed to perform the excitation step. This allowed us to examine different ionization schemes and optimize them for efficiency. Depletion measurements which involve optical pumping into the 6p 6 2P3/2(F=5) state resulted in the enhancement of the selectivity on the order of three orders of magnitude and measurements were performed to reduce Doppler broadening by careful alignment of the lasers with respect to atomic beam. The overall efficiency, that is the number of ions detected divided by the number of atoms emitted, was measured to be 10-8 while the selectivity (the detectable signal of a nuclide divided by the background tail interference from an adjacent nuclide) was estimated to be 1011. Finally, the 135Cs/137Cs ratio of a NIST standard was measured in collaboration with Pacific Northwest National Laboratory over a two-week period using their system that uses a graphite furnace in place of the glow discharge. We conclude that we are now in a position to predict the operation of the system when applied to a particular radionuclide. (L. Pibida, L.R. Karam, and J.M.R. Hutchinson)
  • NIST Radiochemistry Intercomparison Program (NRIP). The NIST Radiochemistry Intercomparison Program NRIP marks the successful completion of the second year of its measurement traceability program for low-level environmental radioactivity measurements. Four rounds of testing were completed (five total matrices were offered: water, air-filters, synthetic urine, and synthetic feces). The analyte list was expanded for year two to include 90Sr, 234U, 238U, 238Pu, and 241Am, at 0.03 to 0.3 Bq per sample. Participation in the program has expanded from six to include: Environmental Evaluation Group (Carlsbad, NM), Westinghouse WID (Carlsbad, NM), Oak Ridge Associated Universities (ORAU), Carlsbad Environmental Monitoring and Research Center (Carlsbad, NM), Sandia National Laboratory (Albuquerque, NM), Los Alamos National Laboratory (Los Alamos, NM), National Air and Radiation Environmental Laboratory (Montgomery, AL), Oak Ridge National Laboratory (Oak Ridge, TN), Bechtel Nevada Test Site (Mercury, NV), Lockheed Martin Idaho Technologies Co. (Idaho Falls, ID). The program is vital for relating low-level radioanalytical measurements to the National Standards.

    The program has been implemented to meet the demand for traceability as defined under ANSI N42.23. This voluntary standard defines a hierarchy of traceability with an unbroken linkage from service laboratories to NIST. Under the standard, the testing materials must be (1) of appropriate matrices (i.e., matrix categories commonly analyzed by the laboratory), and (2) of appropriate (ambient) activity concentration ranges for these matrices. Currently NRIP is the only traceability program providing performance evaluation materials at environmental levels. In year two, acceptance criteria as defined in ANSI N42.22 "Traceability of Radioactive Sources to the National Institute of Standards and Technology and Associated Instrument Quality Control" were adopted by the NRIP group. The ANSI N42.22 standard defines the requirements for traceability for radioactivity-source manufacturers. The NRIP group has adopted the performance testing criteria of the standard, which states that -- for traceability -- the difference between reported results and the NIST certified values must be less than three times the total propagated uncertainty for the measurement. The standard establishes further the quantity "three times the total propagated uncertainty" as the "Traceability Limit" -- the limit to which a source manufacturer may claim traceability to NIST. Following each test, participating laboratories are issued Reports of Traceability, which reflect both the relative bias (compared to the NIST values) and the Traceability Limit of the measurements as defined in ANSI N42.22.

    The test matrices and analytes for each fiscal year are to be determined at the upcoming Annual Conference on Bioassay, Analytical and Environmental Radiochemistry. Continued growth in the number of participating laboratories is anticipated from the commercial national and international communities. (K.G.W. Inn, C. McMahon, Z.Y. Wu, and Z.C. Lin).
  • Development of New Standards and Metrology for Measuring Low-Level Radionuclides in Bioassay Materials. The program is to develop the capabilities in preparation of in-vitro and in-vivo radiobioassay standards required by the ANSI 13.30 standard. The program focuses on the preparation and verification techniques needed in developing ultra-low level reference materials for the assessment of quality of radionuclide measurement in urine, feces, lung, and BOMAB and anthropomorphic phantoms. A wide array of nuclear detection methods including mass spectrometry, liquid scintillator, proportional counter, solid-state alpha detectors, HPGC detectors and MCNP have been applied to the measurements. (Z.Y. Wu and K.G.W. Inn)
  • Development of Low-Level Radioactivity Natural Matrix Standard Reference Material. The program provides various standard reference materials that closely matched the matrix and activity of radionuclides presented in different environmental samples. Seven such SRMs are currently used by environmental, bioassay, and oceanographic communities in their radiochemical method evaluation and validation. The SRMs provide a basis for measurement comparability between laboratories. Current projects include Ashed Bone, Rocky Flats Soil-2, and Ocean Shellfish. Each of these SRMs provides the radiochemist with different analytical challenges. (Z.C. Lin, C. MacMahon, K.G.W. Inn, and Z.Y. Wu)
  • Traceability and Standards for the Environment. As part of our efforts to provide traceability and standards for environmental remediation and waste handling, we have provided field sampling, on-site assessment, internal QC PE in-vitro radiobioassay materials, and assessment of transuranic (TRU) waste drum assay traceability to Westinghouse Waste Isolation Pilot Plant (WIPP) and technical radiobioassay monitoring laboratory service program with on-site assessment, PE traceability testing, calibration of in-house reference material to ORNL. In addition, we provide technical radiobioassay reference laboratory service programs for RESL and PNNL with on-site assessment, PE traceability testing, and calibrations of in-house reference material. We also provide technical support for EPA/NVLAP efforts to accredit external radiochemistry Performance Training (PT) suppliers. We have provided CEMRC technical training for spiking soil in preparation for seeking Reference Laboratory status for CAO. Our NIST Radiochemistry Intercomparison Program (NRIP) provides 12 national laboratory, university, and federal agency laboratories with low-level radionuclide PE programs for radiobioassay, soil, air filter, and aqueous matrices. (K.G.W. Inn, C. McMahon, Z.C. Lin, and J. Wu)
  • Radioanalytical Traceability. Over the past several years, NIST has been working with the American National Standards Institute’s nuclear instrumentation N42 and N13 committees to establish widely accepted criteria for radioanalytical traceability. Three standards have been published: 1) ANSI N42.23 (Measurement and Associated Instrumentation Quality Assurance for Radioassay Laboratories), 2) ANSI N42.22 (Traceability of Radioactive Sources to the National Institute of Standards and Technology and Associated Instrument Quality Control), and 3) ANSI N13.30 (Performance Criteria for Radiobioassay). Each of these standards were developed through consensus participation among industrial, commercial, utility, federal, state, and national laboratory representatives to strengthen the credibility of national radioanalytical programs. ANSI N42.23 envisions the accreditation of a small group of program-specific reference laboratories that participate directly in a traceability-testing program with NIST, technical document reviews and on-site assessments. These reference laboratories would act as intermediaries in the establishment of the traceability testing link to the service laboratories through Performance Testing (PT) programs. One current driving force to establish reference laboratories is the privatization of the EPA Drinking Water Crosscheck Program that will require the NVLAP accreditation of PT Providers for drinking water laboratories. The traceability testing criteria for radiobioassay PT reference laboratories defined by ANSI N13.30 are similar. A third sector that will be establishing traceability testing for its reference laboratories is DOE-EM for its environmental remediation work. The ANSI N42.22 standard provides additional and more specific criteria for source manufacturers, including those reference laboratories that will be producing PT materials. In addition to the criteria for quality assurance, facilities and equipment, and certificates, ANSI N42.22 provides very specific criteria for the acceptance of testing results:

    |VR - VN< 3 × (σN2 + σR2)1/2

    where the absolute value of the bias between the reported value, VR, and the NIST value, VN, shall be less than or equal to three times the total propagated NIST uncertainty, σN, and the reported uncertainty, σR.

    Furthermore, the right hand side of the equation defines the "traceability limit" to which a source manufacturer could claim traceability. It is anticipated that traceability testing for the reference laboratories supporting these four national sectors will be initiated by the end of 1999. (Z.C. Lin, K.G.W. Inn, J. Wu, and C. McMahon)
  • Re-Calibration of the Mixed Gaseous Radioactive Measurement System. The p-type intrinsic Ge detector was calibrated for activity of the Nobel gas radioisotopes 85Kr, 127Xe and 133Xe. The latter two gaseous radioisotopes were activity calibrated by internal gas counting of gas samples that were quantitatively related to nominal 33 mL glass spherical sources. These spherical sources were then measured on the Ge detector, and a response factor determined. The 85Kr activity standard K300 was concurrently measured to re-evaluate that response factor. This measurement system is used in the NIST-NEI traceability program for these radioactivities. (F.J. Schima and M.P. Unterweger)
  • Calibration by Gamma-ray Counting. The gamma-ray detector systems continue to be used to standardize solution and gas sources for the NEI measurement assurance programs. Efficiency curves for several energy regions for three of the Group’s gamma-ray detectors are being reinvestigated and, when needed, redetermined. (F.J. Schima, L.R. Karam, L. Pibida, J.T. Cessna, and B.E. Zimmerman)
  • Upgrade of Gamma-ray Spectroscopy Facilities. The Radioactivity Group is upgrading its gamma-ray spectroscopy facilities in order to allow them to keep pace with the growing demand for source analysis using this technique. The non-networked, UNIX-based data acquisition system currently in use is being converted to PC-based systems, which are on the NIST network. Some of the analysis software is being ported to the Windows environment, while other programs will be replaced by commercially available versions currently being evaluated. The detectors themselves are being moved to a larger laboratory to minimize interferences between detectors and to allow for the installation of additional detectors. These changes and subsequent recalibrations are being carried out in such a way as to not disrupt normal operations. (B.E. Zimmerman, L.R. Karam, J.T. Cessna, and L. Pibida)
  • Phosphor Plate Imaging for Standards Development. The SPP imaging plate detector, with pixel sizes as small as 25 µm x 25 µm, was originally developed for diagnostic radiography and they are sensitive to all types of ionizing radiation. Its usage ranges from the field of biomedical research to material science and now is being applied for environmental radiation monitoring purposes. A typical SPP plate stores a radiation image as a distribution of F-centers in a thin coating of photostimulable phosphor (BaFBr:Eu2+). The latent image is read out by measuring the intensity of fluorescence stimulated by scanning a He-Ne laser beam over the surface of the plate for a few minutes. We have been conducting measurements using a Fuji BAS 2000 SPP system to determine its applicable measurement limits for various types of radioactivity and to suggest operation procedures tailored to different types of radiation and radioactivity levels. These measurements are designed to realize the potential of this SPP system as a radiation imaging device, a quantitative measurement instrument and a research tool to design counters for ultra low level radioactivity measurement required by the electronics and aerospace industries. (Y.T. Cheng, L.R. Karam, and M.P. Unterweger)
  • Application of SPP to Cell-Radiolabelling Efficiency. In collaboration with members of CSTL, and as part of a contract effort for the Air Force, we have studied the application of SPP to monitor the efficiency of bacterial cell labelling with radioactive isotopes. We have measured the activity of 32P-labelled bacillus on air sampling filters with the SPP system, obtaining results 2 orders of magnitude more sensitive than previously used methods. (L.R. Karam with C. O’Connell and H. Rodriguez of CSTL)
  • Novel Approaches in Nuclear Medicine. We continue several ongoing research projects involving various aspects of nuclear medicine, including investigations of novel delivery methods of radiopharmaceuticals. Using our previously constructed fullerene production apparatus, we have developed extensive protocols for the incorporation of 125I inside the fullerene cage. Since fullerene cages are capable of physically and chemically isolating radioisotopes from their associated pharmaceutical, the incorporation of 125I would allow for a more stable carbon-carbon bond in a radiopharmaceutical. Using modified (for safety) protocols developed for the incorporation of non-radioactive iodine in fullerenes and detection methods use for measuring the electron-beam activated 126I; we have demonstrated the feasibility of incorporating the medically common isotope 125I in fullerenes of different sizes. Yield and purity of 125I endofullerenes have been determined by high-pressure liquid chromatography (HPLC), MultiPhoton Detection and Fuji phosphoimaging. We have used exhaustive procedures to determine whether or not the iodine is located within the cage cavity, by heating and trapping volatiles of iodinated samples to remove any iodine trapped within the soot of particulates or attached to the outside of fullerenes ("exofullerenes") with subsequent extraction, purification and isolation of the volatile species. (L.R. Karam, M.G. Mitch, and B.M. Coursey)
  • Counting Yields for Beta and Alpha Particle Sources. Using the results of Monte Carlo calculations, the counting yields of beta- and alpha-particle sources have been determined and tabulated. The counting yield is defined as the fraction of the emitted particles that emerge from the source and are counted by a 2π detector, and takes into account backscattering and self-absorption in the source. The results apply to sources consisting of a thin layer of radioactive material placed on top of, or distributed in a top layer of, a thick metal backing. (M.J. Berger, L.R. Karam, M.P. Unterweger, and J.M.R. Hutchinson)
  • Holmium-166m. 166mHo is a long-lived radionuclide (the half-life is 1200 years) that emits a large number of gamma rays with energies from 80 keV to more than 1400 keV. The large number of gamma rays, the wide energy range, and the long half life make 166mHo a very desirable gamma-ray source for determining the detection efficiency of germanium detectors and for monitoring their long-term stability. High-purity stable 165Ho was neutron irradiated to produce 166mHo, which is now being calibrated in terms of activity. The gamma-ray emission probabilities and their uncertainties are also being evaluated. SRM 4274, 166mHo solution, will be issued in FY 2000. (L.L. Lucas, F.J. Schima, and B.E. Zimmerman)
  • Standardization of 177Lu. Accurate measurements of the amount of radioactivity present in radiopharmaceuticals rely on standards developed by the Radioactivity Group at NIST. These standards are critical for ensuring accurate measurements of administered dose, determining reaction yields, and for normalizing dosimetry measurements. Moreover, a radioactivity measurement standard for new radiopharmaceuticals is required by the United States Food and Drug Administration prior to giving approval to the drug for human use. One such radionuclide that shows great promise for use in radiotherapy against cancer is the rare earth isotope 177Lu (t1/2 = 6.7 d). The Radioactivity Group has recently developed a new standard for this radionuclide, working in collaboration with Mallinckrodt, Inc.

    The radioactivity in each of several solutions submitted by Mallinckrodt was calibrated using 4πβ liquid scintillation (LS) counting, with confirmatory measurements made with "4π" γ-ray spectrometry. The expanded (k=2) uncertainty on the activity measurements was 0.6 %. Impurity measurements were carried out using HPGe γ-ray spectrometry and indicated that the only impurity present was the long-lived (160.4 d) 177mLu isomer at an activity level of approximately 0.03 % that of the 177Lu, as of the reference time. Measurements were then carried out to determine a calibration factor for the NIST 4πγ ionization chamber that can be used to make rapid activity determinations of additional solutions that may be submitted. (B.E. Zimmerman)

  • Development of "Transfer Standards" for Solutions of 186Re. Rhenium-186 is currently being investigated for a wide variety of applications in nuclear medicine. Currently, there is no recommended dial setting for measuring 186Re in a Capintec dose calibrator, which is the de facto standard measurement device for performing radioassays in the clinical and manufacturing settings. Furthermore, Mallinckrodt, Inc. is investigating the use of conical v-vials for shipping products containing 186Re solutions for use in a new intravascular brachytherapy device. It is hoped that dose calibrators can be used to perform assays of the solutions in the v-vials as part of their quality assurance procedures. Attenuation of radiation emitted from radioactive solutions plays a vital role in predicting the response of ionization chambers ("dose calibrators") to these sources. This is especially true when the solution is contained in conical v-vials, in which neither the solution height nor glass thickness vary linearly with volume. For this reason, we have undertaken an investigation to empirically determine the dose calibrator settings for measuring 186Re solutions in both the standard NIST geometry and in conical v-vials with variable volumes. (B.E. Zimmerman)
  • Calibration of High-level 125I Solution Sources for Use in Intracavitary Brachytherapy. The American Cancer Society projects 18,000 U.S. patients will be diagnosed each year with malignant brain tumors and nearly all experience tumor re-growth after initial treatment. Most tumors recur within a short period of time and more than 80 % are located within two centimeters of the original cancer site. Proxima Therapeutics, Inc. (PTI) is developing a device that it hopes will decrease the incidence of recurrence. This new treatment modality involves the implantation of a small balloon in the cavity that remains after the tumor is removed. The balloon is subsequently filled with a solution containing radioactive 125I. The short range of the low-energy radiation from the 125I kills the remaining cancer cells while sparing healthy tissue. This particular approach has the advantage over external beam therapy in that multiple treatments can be performed to ensure complete eradication of the cancer cells. The high dose delivered to healthy brain tissue by external beams usually precludes such multiple treatments. One of the important issues in treatment planning is accurate calculation of the dose being delivered to the patient, which requires accurate standards of the nuclide being used. NIST is developing "transfer standards" in the form of calibration factors for measuring high-level (> 4 GBq) solutions in conical v-vials using commercially available re-entrant ionization chambers. (B.E. Zimmerman and J.T. Cessna)
  • Quantitative Destructive Assay Technique For Radioactive Coronary Stents. Nearly one-half million coronary angioplasty procedures are performed every year in the United States. In up to 50 % of these cases, the patient will experience restenosis, or re-closing, of the artery walls. One method used to prevent this phenomenon is the permanent placement of a metal stent that expands to form scaffolding to hold the artery walls open. Unfortunately, this procedure has not proven effective in every case, and a re-examination of the site will find scar tissue growing through the stent. Another method employed is intravascular brachytherapy, where the area is subjected to a dose of radiation at a level known to inhibit proliferative cells, such as scar tissue. Recently a Belmont, California company, IsoStent, has combined these two methods by developing a stainless steel stent containing the beta emitter 32P. The Radioactivity Group has developed quantitative destructive assay techniques for this type of source. (J.T. Cessna)
  • Calibration of 32P "Hot Wall" Angioplasty-Balloon-Catheter Sources by Destructive Radionuclidic Assays. A quantitative, destructive-analysis procedure was devised for assaying the 32P activity content of "hot-wall" angioplasty-balloon catheters. These sources are developed by Radiance Medical Systems, Inc. (Irvine, CA), are intended for use in the prophylactic inhibition of restenosis following balloon angioplasty in heart-disease patients. They consist of a thin source of 32P which is incorporated directly into the balloon wall of the angioplasty catheter. As a pure beta-particle emitter, the 32P content can not be assayed by nondestructive means since it has no distinctive, external, radioactive signature. The assay was based on performing a physicochemical digestion of the balloon catheter to extract the 32P activity followed by liquid scintillation (LS) spectrometry of the resultant solutions. The calibration results were also used to link Monte-Carlo-based theoretic modeling of the absorbed dose spatial distributions to radiochromic-film dosimetric measurements that were performed by the Dosimetry Group. (R. Collé)
  • Re-Evaluations and Upgrades of the 222Rn Pulse-Ionization-Chamber Measurement System. The national standard for radon measurements is embodied in a primary radon measurement system that has been maintained for nearly sixty years to accurately measure radon (222Rn) against international and national radium (226Ra) standards. All of the radon measurements made at NIST, and the radon transfer standards and calibration services provided by NIST, are directly related to this national radon standard. This primary radon measurement system consists of pulse ionization chambers and ancillary gas handling and gas purification equipment. The system was last modernized (with replacement ionization chambers) nearly a decade ago and several shortcomings in its performance have recently become evident. As a result, a major re-evaluation and upgrade of the system is underway. This work includes conducting extensive systematic evaluations of the system’s performance under a variety of operating and sample conditions, re-designing the operating protocols, replacing the data acquisition and analysis hardware, and re-writing the software codes. (R. Collé, J.T. Cessna, M.P. Unterweger, P. Hodge, and L. Karam)
  • Standardization of New Tritiated-water Standards. The calibration of the new tritiated-water standard, SRM 4927F, by internal-gas counting and liquid scintillation counting has been completed. This standard and the lower activity SRM 4926E and SRM 4361C will be used extensively worldwide. The standards and their predecessors will continue to be used as the basis for a uniform measurement scale for environmental tritium studies. The NIST tritiated-water standards are also used extensively in liquid scintillation counting. A remeasurement of the half-life of tritium has also been done and a reevaluation of the half-life using all reported values is in progress. An accurate value for the half-life is very important in extending the useful lifetime of the tritium standards. (L.L. Lucas and M.P. Unterweger)

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