Fundamentals of passive nondestructive assay of fissionable material: laboratory workbook

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Reilly, T.D.; Augustson, R.H.; Parker, J.L. Walton, R.B.; Atwell, T.L.; Umbarger, C.J.; Burns, C.E.

1975-02-01

This workbook is a supplement to LA-5651-M, ''Fundamentals of Passive Nondestructive Assay of Fissionable Material'' which is the text used during the Nondestructive Assay Training Session given by Group A-1 of the Los Alamos Scientific Laboratory. It contains the writeups used during the six laboratory sessions covering basic gamma-ray principles, quantitative gamma-ray measurements, uranium enrichment measurements, equipment holdup measurements, basic neutron principles, and quantitative neutron assay.

Californium interrogation prompt neutron (CIPN) instrument for non-destructive assay of spent nuclear fuel—Design concept and experimental demonstration

International Nuclear Information System (INIS)

Henzlova, D.; Menlove, H.O.; Rael, C.D.; Trellue, H.R.; Tobin, S.J.; Park, Se-Hwan; Oh, Jong-Myeong; Lee, Seung-Kyu; Ahn, Seong-Kyu; Kwon, In-Chan; Kim, Ho-Dong

2016-01-01

This paper presents results of the first experimental demonstration of the Californium Interrogation Prompt Neutron (CIPN) instrument developed within a multi-year effort launched by the Next Generation Safeguards Initiative Spent Fuel Project of the United States Department of Energy. The goals of this project focused on developing viable non-destructive assay techniques with capabilities to improve an independent verification of spent fuel assembly characteristics. For this purpose, the CIPN instrument combines active and passive neutron interrogation, along with passive gamma-ray measurements, to provide three independent observables. This paper describes the initial feasibility demonstration of the CIPN instrument, which involved measurements of four pressurized-water-reactor spent fuel assemblies with different levels of burnup and two initial enrichments. The measurements were performed at the Post-Irradiation Examination Facility at the Korea Atomic Energy Institute in the Republic of Korea. The key aim of the demonstration was to evaluate CIPN instrument performance under realistic deployment conditions, with the focus on a detailed assessment of systematic uncertainties that are best evaluated experimentally. The measurements revealed good positioning reproducibility, as well as a high degree of insensitivity of the CIPN instrument's response to irregularities in a radial burnup profile. Systematic uncertainty of individual CIPN instrument signals due to assembly rotation was found to be <4.5%, even for assemblies with fairly extreme gradients in the radial burnup profile. These features suggest that the CIPN instrument is capable of providing a good representation of assembly average characteristics, independent of assembly orientation in the instrument.

Californium interrogation prompt neutron (CIPN) instrument for non-destructive assay of spent nuclear fuel—Design concept and experimental demonstration

Energy Technology Data Exchange (ETDEWEB)

Henzlova, D., E-mail: henzlova@lanl.gov [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Menlove, H.O.; Rael, C.D.; Trellue, H.R.; Tobin, S.J. [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Park, Se-Hwan; Oh, Jong-Myeong; Lee, Seung-Kyu; Ahn, Seong-Kyu; Kwon, In-Chan; Kim, Ho-Dong [Korea Atomic Energy Research Institute, Daejeong (Korea, Republic of)

2016-01-11

This paper presents results of the first experimental demonstration of the Californium Interrogation Prompt Neutron (CIPN) instrument developed within a multi-year effort launched by the Next Generation Safeguards Initiative Spent Fuel Project of the United States Department of Energy. The goals of this project focused on developing viable non-destructive assay techniques with capabilities to improve an independent verification of spent fuel assembly characteristics. For this purpose, the CIPN instrument combines active and passive neutron interrogation, along with passive gamma-ray measurements, to provide three independent observables. This paper describes the initial feasibility demonstration of the CIPN instrument, which involved measurements of four pressurized-water-reactor spent fuel assemblies with different levels of burnup and two initial enrichments. The measurements were performed at the Post-Irradiation Examination Facility at the Korea Atomic Energy Institute in the Republic of Korea. The key aim of the demonstration was to evaluate CIPN instrument performance under realistic deployment conditions, with the focus on a detailed assessment of systematic uncertainties that are best evaluated experimentally. The measurements revealed good positioning reproducibility, as well as a high degree of insensitivity of the CIPN instrument's response to irregularities in a radial burnup profile. Systematic uncertainty of individual CIPN instrument signals due to assembly rotation was found to be <4.5%, even for assemblies with fairly extreme gradients in the radial burnup profile. These features suggest that the CIPN instrument is capable of providing a good representation of assembly average characteristics, independent of assembly orientation in the instrument.

Nondestructive assay of fluorine in geological and other materials by instrumental photon activation analysis with a microtron

Energy Technology Data Exchange (ETDEWEB)

Krausová, Ivana [Nuclear Physics Institute, Academy of Sciences of the Czech Republic, Řež 130, 25068 Řež (Czech Republic); Mizera, Jiří, E-mail: mizera@ujf.cas.cz [Nuclear Physics Institute, Academy of Sciences of the Czech Republic, Řež 130, 25068 Řež (Czech Republic); Institute of Rock Structure and Mechanics, Academy of Sciences of the Czech Republic, V Holešovičkách 41, 182 09 Praha 8 (Czech Republic); Řanda, Zdeněk; Chvátil, David; Krist, Pavel [Nuclear Physics Institute, Academy of Sciences of the Czech Republic, Řež 130, 25068 Řež (Czech Republic)

2015-01-01

Reliable determination of low concentrations of fluorine in geological and coal samples is difficult. It usually requires tedious decomposition and dissolution of the sample followed by chemical conversion of fluorine into its anionic form. The present paper examines possibilities of non-destructive determination of fluorine, mainly in minerals, rocks and coal, by instrumental photon activation analysis (IPAA) using the MT-25 microtron. The fluorine assay consists of counting the positron–electron annihilation line of {sup 18}F at 511 keV, which is a product of the photonuclear reaction {sup 19}F(γ, n){sup 18}F and a pure positron emitter. The assay is complicated by the simultaneous formation of other positron emitters. The main contributors to interference in geological samples are from {sup 45}Ti and {sup 34m}Cl, whereas those from {sup 44}Sc and {sup 89}Zr are minor. Optimizing beam energy and irradiation-decay-counting times, together with using interfering element calibration standards, allowed reliable IPAA determination of fluorine in selected USGS and CRPG geochemical reference materials, NIST coal reference materials, and NIST RM 8414 Bovine Muscle. In agreement with the published data obtained by PIGE, the results of the F assay by IPAA have revealed erroneous reference values provided for the NIST reference materials SRM 1632 Bituminous Coal and RM 8414 Bovine Muscle. The detection limits in rock and coal samples are in the range of 10–100 μg g{sup −1}.

Passive nondestructive assay of nuclear materials

International Nuclear Information System (INIS)

Reilly, D.; Ensslin, N.; Smith, H. Jr.; Kreiner, S.

1991-03-01

The term nondestructive assay (NDA) is applied to a series of measurement techniques for nuclear fuel materials. The techniques measure radiation induced or emitted spontaneously from the nuclear material; the measurements are nondestructive in that they do not alter the physical or chemical state of the nuclear material. NDA techniques are characterized as passive or active depending on whether they measure radiation from the spontaneous decay of the nuclear material or radiation induced by an external source. This book emphasizes passive NDA techniques, although certain active techniques like gamma-ray absorption densitometry and x-ray fluorescence are discussed here because of their intimate relation to passive assay techniques. The principal NDA techniques are classified as gamma-ray assay, neutron assay, and calorimetry. Gamma-ray assay techniques are treated in Chapters 1--10. Neutron assay techniques are the subject of Chapters 11--17. Chapters 11--13 cover the origin of neutrons, neutron interactions, and neutron detectors. Chapters 14--17 cover the theory and applications of total and coincidence neutron counting. Chapter 18 deals with the assay of irradiated nuclear fuel, which uses both gamma-ray and neutron assay techniques. Chapter 19 covers perimeter monitoring, which uses gamma-ray and neutron detectors of high sensitivity to check that no unauthorized nuclear material crosses a facility boundary. The subject of Chapter 20 is attribute and semiquantitative measurements. The goal of these measurements is a rapid verification of the contents of nuclear material containers to assist physical inventory verifications. Waste and holdup measurements are also treated in this chapter. Chapters 21 and 22 cover calorimetry theory and application, and Chapter 23 is a brief application guide to illustrate which techniques can be used to solve certain measurement problems

Statistical precision of delayed-neutron nondestructive assay techniques

International Nuclear Information System (INIS)

Bayne, C.K.; McNeany, S.R.

1979-02-01

A theoretical analysis of the statistical precision of delayed-neutron nondestructive assay instruments is presented. Such instruments measure the fissile content of nuclear fuel samples by neutron irradiation and delayed-neutron detection. The precision of these techniques is limited by the statistical nature of the nuclear decay process, but the precision can be optimized by proper selection of system operating parameters. Our method is a three-part analysis. We first present differential--difference equations describing the fundamental physics of the measurements. We then derive and present complete analytical solutions to these equations. Final equations governing the expected number and variance of delayed-neutron counts were computer programmed to calculate the relative statistical precision of specific system operating parameters. Our results show that Poisson statistics do not govern the number of counts accumulated in multiple irradiation-count cycles and that, in general, maximum count precision does not correspond with maximum count as first expected. Covariance between the counts of individual cycles must be considered in determining the optimum number of irradiation-count cycles and the optimum irradiation-to-count time ratio. For the assay system in use at ORNL, covariance effects are small, but for systems with short irradiation-to-count transition times, covariance effects force the optimum number of irradiation-count cycles to be half those giving maximum count. We conclude that the equations governing the expected value and variance of delayed-neutron counts have been derived in closed form. These have been computerized and can be used to select optimum operating parameters for delayed-neutron assay devices

Nondestructive Assay Options for Spent Fuel Encapsulation

Energy Technology Data Exchange (ETDEWEB)

Tobin, Stephen J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Jansson, Peter [Uppsala Univ. (Sweden)

2014-10-02

This report describes the role that nondestructive assay (NDA) techniques and systems of NDA techniques may have in the context of an encapsulation and deep geological repository. The potential NDA needs of an encapsulation and repository facility include safeguards, heat content, and criticality. Some discussion of the facility needs is given, with the majority of the report concentrating on the capability and characteristics of individual NDA instruments and techniques currently available or under development. Particular emphasis is given to how the NDA techniques can be used to determine the heat production of an assembly, as well as meet the dual safeguards needs of 1) determining the declared parameters of initial enrichment, burn-up, and cooling time and 2) detecting defects (total, partial, and bias). The report concludes with the recommendation of three integrated systems that might meet the combined NDA needs of the encapsulation/repository facility.

Nondestructive assay of boxed radioactive waste

International Nuclear Information System (INIS)

Gilles, W.P.; Roberts, R.J.; Jasen, W.G.

1992-12-01

This paper describes the problems related to the nondestructive assay (NDA) of boxed radioactive waste at the Hanford Site and how Westinghouse Hanford company (WHC) is solving the problems. The waste form and radionuclide content are described. The characteristics of the combined neutron and gamma-based measurement system are described

Selection of non-destructive assay methods: Neutron counting or calorimetric assay?

International Nuclear Information System (INIS)

Cremers, T.L.; Wachter, J.R.

1994-01-01

The transition of DOE facilities from production to D ampersand D has lead to more measurements of product, waste, scrap, and other less attractive materials. Some of these materials are difficult to analyze by either neutron counting or calorimetric assay. To determine the most efficacious analysis method, variety of materials, impure salts and hydrofluorination residues have been assayed by both calorimetric assay and neutron counting. New data will be presented together with a review of published data. The precision and accuracy of these measurements are compared to chemistry values and are reported. The contribution of the gamma ray isotopic determination measurement to the overall error of the calorimetric assay or neutron assay is examined and discussed. Other factors affecting selection of the most appropriate non-destructive assay method are listed and considered

Nondestructive verification and assay systems for spent fuels

International Nuclear Information System (INIS)

Cobb, D.D.; Phillips, J.R.; Bosler, G.E.; Eccleston, G.W.; Halbig, J.K.; Hatcher, C.R.; Hsue, S.T.

1982-04-01

This is an interim report of a study concerning the potential application of nondestructive measurements on irradiated light-water-reactor (LWR) fuels at spent-fuel storage facilities. It describes nondestructive measurement techniques and instruments that can provide useful data for more effective in-plant nuclear materials management, better safeguards and criticality safety, and more efficient storage of spent LWR fuel. In particular, several nondestructive measurement devices are already available so that utilities can implement new fuel-management and storage technologies for better use of existing spent-fuel storage capacity. The design of an engineered prototype in-plant spent-fuel measurement system is approx. 80% complete. This system would support improved spent-fuel storage and also efficient fissile recovery if spent-fuel reprocessing becomes a reality

Radiometric measurements on the fabrication of non-destructive assay standards for WIPP-Performance Demonstration Program

International Nuclear Information System (INIS)

Wong, A.S.; Marshall, R.S.

1997-04-01

The Inorganic Elemental Analysis Group of LANL has prepared several different sets of working reference materials (WRMs). These WRMs are prepared by blending quantities of nuclear materials (plutonium, americium, and enriched uranium) with diatomaceous earth. The blends are encapsulated in stainless steel cylinders. These WRMs are being measured as blind controls in neutron and gamma based non-destructive assay (NDA) instruments. Radiometric measurements on the blending homogeneity and verification on a set of sixty three plutonium based WRMs are discussed in this paper

Do's and dont's of nondestructive assay measurements

International Nuclear Information System (INIS)

Menlove, H.O.

Some of the problem areas and recommended procedures in the application of nondestructive analysis (NDA) instrumentation are discussed. To limit the scope of the present guide, only radiometric NDA techniques employing neutron and gamma signatures are considered. Thus, measurement techniques which primarily make use of alpha particles, beta particles, muonic x rays, heat signatures, etc., are not included. (U.S.)

Nondestructive assay of special nuclear material for uranium fuel-fabrication facilities

International Nuclear Information System (INIS)

Smith, H.A. Jr.; Schillebeeckx, P.

1997-01-01

A high-quality materials accounting system and effective international inspections in uranium fuel-fabrication facilities depend heavily upon accurate nondestructive assay measurements of the facility's nuclear materials. While item accounting can monitor a large portion of the facility inventory (fuel rods, assemblies, storage items), the contents of all such items and mass values for all bulk materials must be based on quantitative measurements. Weight measurements, combined with destructive analysis of process samples, can provide highly accurate quantitative information on well-characterized and uniform product materials. However, to cover the full range of process materials and to provide timely accountancy data on hard-to-measure items and rapid verification of previous measurements, radiation-based nondestructive assay (NDA) techniques play an important role. NDA for uranium fuel fabrication facilities relies on passive gamma spectroscopy for enrichment and U isotope mass values of medium-to-low-density samples and holdup deposits; it relies on active neutron techniques for U-235 mass values of high-density and heterogeneous samples. This paper will describe the basic radiation-based nondestructive assay techniques used to perform these measurements. The authors will also discuss the NDA measurement applications for international inspections of European fuel-fabrication facilities

Operational experience in the non-destructive assay of fissile material in General Electric's nuclear fuel fabrication facility

International Nuclear Information System (INIS)

Stewart, J.P.

1976-01-01

Operational experience in the non-destructive assay of fissile material in a variety of forms and containers and incorporation of the assay devices into the accountability measurement system for General Electric's Wilmington Fuel Fabrication Facility measurement control programme is detailed. Description of the purpose and related operational requirements of each non-destructive assay system is also included. In addition, the accountability data acquisition and processing system is described in relation to its interaction with the various non-destructive assay devices and scales used for accountability purposes within the facility. (author)

Nondestructive assay methodologies in nuclear forensics analysis

International Nuclear Information System (INIS)

Tomar, B.S.

2016-01-01

In the present chapter, the nondestructive assay (NDA) methodologies used for analysis of nuclear materials as a part of nuclear forensic investigation have been described. These NDA methodologies are based on (i) measurement of passive gamma and neutrons emitted by the radioisotopes present in the nuclear materials, (ii) measurement of gamma rays and neutrons emitted after the active interrogation of the nuclear materials with a source of X-rays, gamma rays or neutrons

Nondestructive assay methods for irradiated nuclear fuels

International Nuclear Information System (INIS)

Hsue, S.T.; Crane, T.W.; Talbert, W.L. Jr.; Lee, J.C.

1978-01-01

This report is a review of the status of nondestructive assay (NDA) methods used to determine burnup and fissile content of irradiated nuclear fuels. The gamma-spectroscopy method measures gamma activities of certain fission products that are proportional to the burnup. Problems associated with this method are migration of the fission products and gamma-ray attenuation through the relatively dense fuel material. The attenuation correction is complicated by generally unknown activity distributions within the assemblies. The neutron methods, which usually involve active interrogation and prompt or delayed signal counting, are designed to assay the fissile content of the spent-fuel elements. Systems to assay highly enriched spent-fuel assemblies have been tested extensively. Feasibility studies have been reported of systems to assay light-water reactor spent-fuel assemblies. The slowing-down spectrometer and neutron resonance absorption methods can distinguish between the uranium and plutonium fissile contents, but they are limited to the assay of individual rods. We have summarized the status of NDA techniques for spent-fuel assay and present some subjects in need of further investigation. Accuracy of the burnup calculations for power reactors is also reviewed

A weighted least-squares lump correction algorithm for transmission-corrected gamma-ray nondestructive assay

International Nuclear Information System (INIS)

Prettyman, T.H.; Sprinkle, J.K. Jr.; Sheppard, G.A.

1993-01-01

With transmission-corrected gamma-ray nondestructive assay instruments such as the Segmented Gamma Scanner (SGS) and the Tomographic Gamma Scanner (TGS) that is currently under development at Los Alamos National Laboratory, the amount of gamma-ray emitting material can be underestimated for samples in which the emitting material consists of particles or lumps of highly attenuating material. This problem is encountered in the assay of uranium and plutonium-bearing samples. To correct for this source of bias, we have developed a least-squares algorithm that uses transmission-corrected assay results for several emitted energies and a weighting function to account for statistical uncertainties in the assay results. The variation of effective lump size in the fitted model is parameterized; this allows the correction to be performed for a wide range of lump-size distributions. It may be possible to use the reduced chi-squared value obtained in the fit to identify samples in which assay assumptions have been violated. We found that the algorithm significantly reduced bias in simulated assays and improved SGS assay results for plutonium-bearing samples. Further testing will be conducted with the TGS, which is expected to be less susceptible than the SGS to systematic source of bias

Preliminary report of the comparison of multiple non-destructive assay techniques on LANL Plutonium Facility waste drums

International Nuclear Information System (INIS)

Bonner, C.; Schanfein, M.; Estep, R.

1999-01-01

Prior to disposal, nuclear waste must be accurately characterized to identify and quantify the radioactive content. The DOE Complex faces the daunting task of measuring nuclear material with both a wide range of masses and matrices. Similarly daunting can be the selection of a non-destructive assay (NDA) technique(s) to efficiently perform the quantitative assay over the entire waste population. In fulfilling its role of a DOE Defense Programs nuclear User Facility/Technology Development Center, the Los Alamos National Laboratory Plutonium Facility recently tested three commercially built and owned, mobile nondestructive assay (NDA) systems with special nuclear materials (SNM). Two independent commercial companies financed the testing of their three mobile NDA systems at the site. Contained within a single trailer is Canberra Industries segmented gamma scanner/waste assay system (SGS/WAS) and neutron waste drum assay system (WDAS). The third system is a BNFL Instruments Inc. (formerly known as Pajarito Scientific Corporation) differential die-away imaging passive/active neutron (IPAN) counter. In an effort to increase the value of this comparison, additional NDA techniques at LANL were also used to measure these same drums. These are comprised of three tomographic gamma scanners (one mobile unit and two stationary) and one developmental differential die-away system. Although not certified standards, the authors hope that such a comparison will provide valuable data for those considering these different NDA techniques to measure their waste as well as the developers of the techniques

Guide to nondestructive assay standards: Preparation criteria, availability, and practical considerations

International Nuclear Information System (INIS)

Stewart, J.E.; Hsue, S.T.; Sampson, T.E.

1997-01-01

For certification and measurement control, nondestructive assay (NDA) instruments and methods used for verification measurement of special nuclear materials (SNMs) require calibrations based on certified reference materials (CRMs), or working reference materials (WRMs), traceable to the national system of measurements, and adequately characteristic of the unknowns. The Department of Energy Office of Safeguards and Security is sponsoring production of a comprehensive guide to preparation of NDA standards. The scope of the report includes preparation criteria, current availability of CRMs and WRMs, practical considerations for preparation and characterization, and an extensive bibliography. In preparing the report, based primarily on experience at Los Alamos, we have found that standards preparation is highly dependent on the particular NDA method being applied. We therefore include sections that contain information specific to commonly used neutron and gamma-ray NDA techniques. 16 refs., 4 figs., 2 tabs

Expert system technology for nondestructive waste assay

International Nuclear Information System (INIS)

Becker, G.K.; Determan, J.C.

1998-01-01

Nondestructive assay waste characterization data generated for use in the National TRU Program must be of known and demonstrable quality. Each measurement is required to receive an independent technical review by a qualified expert. An expert system prototype has been developed to automate waste NDA data review of a passive/active neutron drum counter system. The expert system is designed to yield a confidence rating regarding measurement validity. Expert system rules are derived from data in a process involving data clustering, fuzzy logic, and genetic algorithms. Expert system performance is assessed against confidence assignments elicited from waste NDA domain experts. Performance levels varied for the active, passive shielded, and passive system assay modes of the drum counter system, ranging from 78% to 94% correct classifications

PANDA-A novel instrument for non-destructive sample analysis

International Nuclear Information System (INIS)

Turunen, Jani; Peraejaervi, Kari; Poellaenen, Roy; Toivonen, Harri

2010-01-01

An instrument known as PANDA (Particles And Non-Destructive Analysis) for non-destructive sample analysis has been designed and built at the Finnish Radiation and Nuclear Safety Authority (STUK). In PANDA the measurement techniques and instruments designed for the basic research are applied to the analysis of environmental samples. PANDA has two vacuum chambers, one for loading samples and the other for measurements. In the measurement chamber there are two individual measurement positions. Currently the first one hosts an HPGe gamma detector and a position-sensitive alpha detector. The second measurement position is intended for precise characterization of found particles. PANDA's data are recorded in event mode and events are timestamped. In the present article the technical design of PANDA is presented in detail. In addition, its performance using depleted uranium particles and an air filter is demonstrated.

Nondestructive assay of plutonium residue in horizontal storage tanks

International Nuclear Information System (INIS)

Marsh, S.F.

1985-01-01

Aqueous plutonium recovery and purification processes often involve the temporary storage of plutonium solutions in holding tanks. Because plutonium is known to precipitate from aqueous solutions under certain conditions, there is a continuing need to assay emptied tanks for plutonium residue. A portable gamma spectrometer system, specifically designed for this purpose, provides rapid assay of such plutonium residues in horizontal storage tanks. A means is thus available for the nondestructive analysis of these tanks on a regular schedule to ensure that significant deposits of plutonium are not allowed to accumulate. 5 figs

Guide to nondestructive assay standards: Preparation criteria, availability, and practical considerations

International Nuclear Information System (INIS)

Hsue, S.T.; Stewart, J.E.; Sampson, T.E.; Butler, G.W.; Rudy, C.R.; Rinard, P.M.

1997-10-01

For certification and measurement control, nondestructive assay (NDA) instruments and methods used for verification measurements of special nuclear materials (SNMs) require calibrations based on certified reference materials (CRMs), or working reference materials (WRMs), traceable to the national system of measurements, and adequately characteristic of the unknowns. The Department of Energy Office of Safeguards and Security is sponsoring production of a comprehensive guide to preparation of NDA standards. The scope of the report includes preparation criteria, current availability of CRMs and WRMs, practical considerations for preparation and characterization, and an extensive bibliography. In preparing the report, based primarily on experience at Los Alamos, they have found that standards preparation is highly dependent on the particular NDA method being applied. They therefore include sections that contain information specific to commonly used neutron and gamma-ray NDA techniques. They also present approaches that are alternatives to, or minimize requirements for physical standards

ARIES nondestructive assay system operation and performance

International Nuclear Information System (INIS)

Cremers, Teresa L.; Hansen, Walter J.; Herrera, Gary D.; Nelson, David C.; Sampson, Thomas E.; Scheer, Nancy L.

2000-01-01

The ARIES (Advanced Recovery and Integrated Extraction System) Project is an integrated system at the Los Alamos Plutonium Facility for the dismantlement of nuclear weapons. The plutonium produced by the ARIES process was measured by an integrated nondestructive assay (NDA) system. The performance of the NDA systems was monitored by a measurement control program which is a part of a nuclear material control and accountability system. In this paper we will report the results of the measurements of the measurement control standards as well as an overview of the measurement of the ARIES process materials

Fiscal Year (FY) 2017 Activities for the Spent Fuel Nondestructive Assay Project

Energy Technology Data Exchange (ETDEWEB)

Trellue, Holly Renee [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Trahan, Alexis Chanel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); McMath, Garrett Earl [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Swinhoe, Martyn Thomas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hu, Jianwei [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Worrall, Andrew [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Ilas, Germina [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Grogan, Brandon [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-09-11

The main focus of research in the NA-241 spent fuel nondestructive assay (NDA) project in FY17 has been completing the fabrication and testing of two prototype instruments for upcoming spent fuel measurements at the Clab interim storage facility in Sweden. One is a passive instrument: Differential Die-away Self Interrogation-Passive Neutron Albedo Reactivity (DDSI), and one is an active instrument: Differential Die-Away-Californium Interrogation with Prompt Neutron (DDA). DDSI was fabricated and tested with fresh fuel at Los Alamos National Laboratory in FY15 and FY16, then shipped to Sweden at the beginning of FY17. Research was performed in FY17 to simplify results from the data acquisition system, which is complex because signals from 56 different 3He detectors must be processed using list mode data. The DDA instrument was fabricated at the end of FY16. New high count rate electronics better suited for a spent fuel environment (i.e., KM-200 preamplifiers) were built specifically for this instrument in FY17, and new Tygon tubing to house electrical cables was purchased and installed. Fresh fuel tests using the DDA instrument with numerous configurations of fuel rods containing depleted uranium (DU), low enriched uranium (LEU), and LEU with burnable poisons (Gd) were successfully performed and compared to simulations.1 Additionally, members of the spent fuel NDA project team travelled to Sweden for a “spent fuel characterization and decay heat” workshop involving simulations of spent fuel and analysis of uncertainties in decay heat calculations.

Portable calorimeter system for nondestructive assay of mixed-oxide fuels

International Nuclear Information System (INIS)

Roche, C.T.; Perry, R.B.; Lewis, R.N.; Jung, E.A.; Haumann, J.R.

1978-04-01

Calorimetric assay provides a precise, nondestructive method to determine sample Pu content based on the heat emitted by decaying radionuclides. This measurement, in combination with a gamma-spectrometer analysis of sample isotopic content, yields the total sample Pu mass. The technique is applicable to sealed containers and is essentially independent of sample matrix configuration and elemental composition. Conventional calorimeter designs employ large water-bath heat sinks and lack the portability needed by inspection personnel. The ANL air-chamber isothermal calorimeters are low-thermal-capacitance devices which eliminate the need for large constant-temperature heat sinks. These instruments are designed to use a feedback system that applies power to maintain the sample chamber at a constant electrical resistance and, therefore, at a constant temperature. The applied-power difference between a Pu-containing sample and a blank determines the radioactive-decay power. The operating characteristics of a calorimeter designed for assaying mixed-oxide powders, fuel pellets, and Pu-containing solutions are discussed. This device consists of the calorimeter, sample preheatr, and a microprocessor-controlled data-acquisition system. The small-sample device weighs 18 kg and has a measurement cycle of 20 min, with a precision of 0.1% at 10 mW. A 100-min gamma-ray measurement gives the specific power with a precision of better than 1% for samples containing 1 to 2 g of plutonium

Nondestructive Assay Data Integration with the SKB-50 Assemblies - FY16 Update

International Nuclear Information System (INIS)

Tobin, Stephen Joseph; Fugate, Michael Lynn; Trellue, Holly Renee; DeBaere, Paul; Sjoland, Anders; Liljenfeldt, Henrik; Hu, Jianwei; Backstrom, Ulrika; Bengtsson, Martin; Burr, Tomas; Eliasson, Annika; Favalli, Andrea; Gauld, Ian; Grogan, Brandon; Jansson, Peter; Junell, Henrik; Schwalbach, Peter; Vaccaro, Stefano; Vo, Duc Ta; Wildestrand, Henrik

2016-01-01

A project to research the application of non-destructive assay (NDA) techniques for spent fuel assemblies is underway at the Central Interim Storage Facility for Spent Nuclear Fuel (for which the Swedish acronym is Clab) in Oskarshamn, Sweden. The research goals of this project contain both safeguards and non-safeguards interests. These nondestructive assay (NDA) technologies are designed to strengthen the technical toolkit of safeguard inspectors and others to determine the following technical goals more accurately; Verify initial enrichment, burnup, and cooling time of facility declaration for spent fuel assemblies; Detect replaced or missing pins from a given spent fuel assembly to confirm its integrity; and Estimate plutonium mass and related plutonium and uranium fissile mass parameters in spent fuel assemblies. Estimate heat content, and measure reactivity (multiplication).

Nondestructive Assay Data Integration with the SKB-50 Assemblies - FY16 Update

Energy Technology Data Exchange (ETDEWEB)

Tobin, Stephen Joseph [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Fugate, Michael Lynn [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Trellue, Holly Renee [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); DeBaere, Paul [DG Energy, Luxembourg (Germany); Sjoland, Anders [Swedish Nuclear Fuel and Waste Management Company, Stockholm (Sweden); Liljenfeldt, Henrik [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Hu, Jianwei [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Backstrom, Ulrika [Swedish Nuclear Fuel and Waste Management Company, Stockholm (Sweden); Vattenfall AB, Stockholm (Sweden); Bengtsson, Martin [Swedish Nuclear Fuel and Waste Management Company, Stockholm (Sweden); Vattenfall AB, Stockholm (Sweden); Burr, Tomas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); International Atomic Energy Agency, Vienna (Austria); Eliasson, Annika [Swedish Nuclear Fuel and Waste Management Company, Stockholm (Sweden); Favalli, Andrea [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Gauld, Ian [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Grogan, Brandon [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Jansson, Peter [Uppsala Univ. (Sweden); Junell, Henrik [Swedish Nuclear Fuel and Waste Management Company, Stockholm (Sweden); Schwalbach, Peter [DG Energy, Luxembourg (Germany); Vaccaro, Stefano [DG Energy, Luxembourg (Germany); Vo, Duc Ta [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Wildestrand, Henrik [Swedish Nuclear Fuel and Waste Management Company, Stockholm (Sweden); Vattenfall AB, Stockholm (Sweden)

2016-10-28

A project to research the application of non-destructive assay (NDA) techniques for spent fuel assemblies is underway at the Central Interim Storage Facility for Spent Nuclear Fuel (for which the Swedish acronym is Clab) in Oskarshamn, Sweden. The research goals of this project contain both safeguards and non-safeguards interests. These nondestructive assay (NDA) technologies are designed to strengthen the technical toolkit of safeguard inspectors and others to determine the following technical goals more accurately; Verify initial enrichment, burnup, and cooling time of facility declaration for spent fuel assemblies; Detect replaced or missing pins from a given spent fuel assembly to confirm its integrity; and Estimate plutonium mass and related plutonium and uranium fissile mass parameters in spent fuel assemblies. Estimate heat content, and measure reactivity (multiplication).

Soil monitoring instrumentation

International Nuclear Information System (INIS)

Umbarger, C.J.

1981-01-01

The Los Alamos Scientific Laboratory (LASL) has an extensive program for the development of nondestructive assay instrumentation for the quantitative analysis of transuranic (TRU) materials found in bulk solid wastes generated by Department of Energy facilities and by the commercial nuclear power industry. Included are wastes generated in decontamination and decommissioning of outdated nuclear facilities, as well as from old waste-burial-ground exhumation programs. The assay instrumentation is designed to have detection limits below 10 nCi/g wherever practicable. The assay instrumentation that is applied specifically to soil monitoring is discussed

Feasibility of nondestructive assay measurements in uranium enrichment plants

Energy Technology Data Exchange (ETDEWEB)

Walton, R.B.

1978-04-01

Applications of nondestructive assay methods to measurement problems in uranium enrichment facilities are reviewed. The results of a number of test and evaluation projects that were performed over the last decade at ORGDP and Portsmouth are presented. Measurements of the residual holdup in the top enrichment portion of the shut-down K-25 cascade were made with portable neutron and gamma-ray detectors, and inventory estimates based on these data were in good agreement with ORGDP estimates. In the operating cascade, the tests showed that portable NaI detectors are effective for monitoring NaF and alumina media for gaseous effluent traps and that gas phase enrichments and inventories, as well as large deposits of uranium, can be detected with portable neutron and gamma-ray instrumentation. A wide variety of scrap and waste materials, including barrier and compressor blades, incinerator ash and trapping media, and miscellaneous waste, were measured using passive gamma-ray and neutron methods and 14-MeV neutron interrogation. Methods developed for rapid verification of UF/sub 6/ in shipping containers with portable neutron and gamma-ray instruments are now used routinely by safeguards inspectors. Passive assay methods can also be used to measure continuously the enrichments of /sup 235/U and /sup 234/U in the UF/sub 6/ product and tails withdrawals of a gaseous diffusion plant. A system that was developed and installed in the extended-range product withdrawal station of the Portsmouth facility measures enrichment with a relative accuracy of 0.5%. A stand-alone neutron detector has also been successfully evaluated for the measurement of the isotopic abundance of /sup 234/U in UF/sub 6/ in sample cylinders, an application of potential importance to Minor Isotope Safeguards Technology. Recommendations are made on the role of NDA measurements for enrichment plant safeguards, including additional tests and evaluations that may be needed, particularly for advanced uranium

Guidance on meeting DOE order requirements for traceable nondestructive assay measurements

International Nuclear Information System (INIS)

1994-05-01

Purpose of this guide is to facilitate accuracy and precision of nondestructive assay measurements through improvement of the materials and process of traceability. This document provides DOE and its contractor facilities with guidance to establish traceability to the national measurement base for site-prepared NDA working reference materials

Development of an analytical theory to describe the PNAR and CIPN nondestructive assay techniques

International Nuclear Information System (INIS)

Bolind, Alan Michael

2014-01-01

Highlights: • Neutron albedo is modeled by a discrete and iterative reflection process. • The theory enables the PNAR and CIPN NDA techniques to be compared quantitatively. • Improvements to the data analysis and to the CIPN instrument design are suggested. • A correction to translate real no-reflection PNAR data into ideal data is provided. - Abstract: This paper develops an analytical theory to describe how neutron albedo (reflection) increases the multiplication of neutrons by a used fuel assembly. With this theory, the two nondestructive assay (NDA) techniques of Passive Neutron Albedo Reactivity (PNAR) and Californium-252 Interrogation with Prompt Neutron Detection (CIPN) can be compared directly. Specifically, the theory derives expressions for the PNAR and CIPN metrics in terms of the physical properties of the used fuel assembly, such as the neutron multiplications and fate probabilities. The theory thus clarifies the interpretation of these two NDA techniques and suggests ways to improve both the design of the NDA instruments and the algorithms for analyzing the measurement results

NDA [nondestructive assay] training for new IAEA inspectors at Los Alamos

International Nuclear Information System (INIS)

Stewart, J.E.; Reilly, T.D.; Belew, W.; Woelfl, E.; Fager, J.

1987-01-01

The history of the evolution of nondestructive assay (NDA) training for international inspectors at Los Alamos is described. The current NDA training course for International Atomic Energy Agency inspectors is presented in terms of structure, content, and rationale. Results of inspector measurement exercises are given along with projections for future developments in NDA inspector training. 3 refs

Soil monitoring instrumentation

International Nuclear Information System (INIS)

Umbarger, C.J.

1980-01-01

The Los Alamos Scientific Laboratory (LASL) has an extensive program for the development of nondestructive assay instrumentation for the quantitative analysis of transuranic (TRU) materials found in bulk solid wastes generated by Department of Energy facilities and by the commercial nuclear power industry. Included are wastes generated in decontamination and decommissioning of outdated nuclear facilities as well as wastes from old waste burial ground exhumation programs. The assay instrumentation is designed to have detection limits below 10 nCi/g wherever practicable. Because of the topic of this workshop, only the assay instrumentation applied specifically to soil monitoring will be discussed here. Four types of soil monitors are described

Making transuranic assay measurements using modern controllers

International Nuclear Information System (INIS)

Kuckertz, T.H.; Caldwell, J.T.; Medvick, P.A.; Kunz, W.E.; Hastings, R.D.

1987-01-01

This paper describes methodology and computer-controlled instrumentation developed at the Los Alamos National Laboratory that accurately performs nondestructive assays of large containers bearing transuranic wastes and nonradioactive matrix materials. These assay systems can measure fissile isotopes with 1-mg sensitivity and spontaneous neutron-emitting isotopes at a 10-mg sensitivity. The assays are performed by neutron interrogation, detection, and counting in a custom assay chamber. An International Business Machines Personal Computer (IBM-PC) is used to control the CAMAC-based instrumentation system that acquires the assay data. 6 refs., 7 figs

A maximum-likelihood reconstruction algorithm for tomographic gamma-ray nondestructive assay

International Nuclear Information System (INIS)

Prettyman, T.H.; Estep, R.J.; Cole, R.A.; Sheppard, G.A.

1994-01-01

A new tomographic reconstruction algorithm for nondestructive assay with high resolution gamma-ray spectroscopy (HRGS) is presented. The reconstruction problem is formulated using a maximum-likelihood approach in which the statistical structure of both the gross and continuum measurements used to determine the full-energy response in HRGS is precisely modeled. An accelerated expectation-maximization algorithm is used to determine the optimal solution. The algorithm is applied to safeguards and environmental assays of large samples (for example, 55-gal. drums) in which high continuum levels caused by Compton scattering are routinely encountered. Details of the implementation of the algorithm and a comparative study of the algorithm's performance are presented

Evalution of NDA techniques and instruments for assay of nuclear waste at a waste terminal storage facility

International Nuclear Information System (INIS)

Blakeman, E.D.; Allen, E.J.; Jenkins, J.D.

1978-05-01

The use of Nondestructive Assay (NDA) instrumentation at a nuclear waste terminal storage facility for purposes of Special Nuclear Material (SNM) accountability is evaluated. Background information is given concerning general NDA techniques and the relative advantages and disadvantages of active and passive NDA methods are discussed. The projected characteristics and amounts of nuclear wastes that will be delivered to a waste terminal storage facility are presented. Wastes are divided into four categories: High Level Waste, Cladding Waste, Intermediate Level Waste, and Low Level Waste. Applications of NDA methods to the assay of these waste types is discussed. Several existing active and passive NDA instruments are described and, where applicable, results of assays performed on wastes in large containers (e.g., 55-gal drums) are given. It is concluded that it will be difficult to routinely achieve accuracies better than approximately 10--30% with ''simple'' NDA devices or 5--20% with more sohpisticated NDA instruments for compacted wastes. It is recommended that NDA instruments not be used for safeguards accountability at a waste storage facility. It is concluded that item accountability methods be implemented. These conclusions and recommendations are detailed in a concurrent report entitled ''Recommendations on the Safeguards Requirements Related to the Accountability of Special Nuclear Material at Waste Terminal Storage Facilities'' by J.D. Jenkins, E.J. Allen and E.D. Blakeman

System for nondestructive assay of spent fuel subassemblies: comparison of calculations and measurements

International Nuclear Information System (INIS)

Ragan, G.L; Ricker, C.W.; Chiles, M.M.; Ingersoll, D.T.; Slaughter, G.G.; Williams, L.R.

1979-01-01

A nondestructive assay system was developed for determining the total fissile content of spent fuel subassemblies at the head end of a reprocessing plant. The system can perform an assay in 20 min with an uncertainty of <5%. Antimony-beryllium neutrons interrogate the subassemblies, and proton recoil counters detect the resulting fission neutrons. Pulse-height discrimination differentiates between the low-energy interrogation neutrons and the higher-energy fission neutrons. Calculated and measured results were compared for (1) interrogation-neutron penetrability, (2) fission-neutron detectability, (3) radial variation of assay sensitivity, (4) axial variation of assay sensitivity, and (5) the variation of detector count rate as a function of the number of fuel rods in a special 61-rod, LMFBR-type subassembly

Instrumentation: Nondestructive Examination for Verification of Canister and Cladding Integrity. FY2014 Status Update

Energy Technology Data Exchange (ETDEWEB)

Meyer, Ryan M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Suter, Jonathan D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jones, Anthony M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2014-09-12

This report documents FY14 efforts for two instrumentation subtasks under storage and transportation. These instrumentation tasks relate to developing effective nondestructive evaluation (NDE) methods and techniques to (1) verify the integrity of metal canisters for the storage of used nuclear fuel (UNF) and to (2) verify the integrity of dry storage cask internals.

Nondestructive assay uncertainties - present status and future possibilities

International Nuclear Information System (INIS)

Parker, J.L.; Ensslin, N.

1989-01-01

Nondestructive assay (NDA) techniques play an important role in nuclear safeguards by providing rapid, noninvasive measurements of many nuclear materials. The development of these techniques has proceeded in parallel with the increasing need for near-real-time accountability and the increasing use of automation and robotics to save time and labor in all aspects of nuclear materials processing. Gamma-ray counting, neutron counting, and calorimetry are the most common NDA techniques. This paper discusses the random and systematic measurement uncertainties associated with the first two. It is worth nothing that the random and systematic error components encountered in NDA often have a very different origin from those encountered in destructive analysis; the random component in NDA, for example, is dominated by counting statistics

Comparison of destructive and nondestructive assay of heterogeneous salt residues

International Nuclear Information System (INIS)

Fleissner, J.G.; Hume, M.W.

1986-01-01

To study problems associated with nondestructive assay (NDA) measurements of molten salt residues, a joint study was conducted by the Rocky Flats Plant, Golden, CO and Mound Laboratories, Miamisburg, OH. Extensive NDA measurements were made on nine containers of molten salt residues by both Rocky Flats and Mound followed by dissolution and solution quantification at Rocky Flats. Results of this study verify that plutonium and americium can be measured in such salt residues by a new gamma-ray spectral analysis technique coupled with calorimetry. Biases with respect to the segmented gamma-scan technique were noted

Instrumentation. Nondestructive Examination for Verification of Canister and Cladding Integrity - FY2013 Status Update

Energy Technology Data Exchange (ETDEWEB)

Meyer, Ryan M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jones, Anthony M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Pardini, Allan F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Denslow, Kayte M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Crawford, Susan L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Larche, Michael R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2013-09-30

This report documents FY13 efforts for two instrumentation subtasks under storage and transportation. These instrumentation tasks relate to developing effective nondestructive evaluation (NDE) methods and techniques to (1) verify the integrity of metal canisters for the storage of used nuclear fuel (UNF) and to (2) characterize hydrogen effects in UNF cladding to facilitate safe storage and retrieval.

Nondestructive assay of subassemblies of various spent or fresh fuels by active neutron interrogation

International Nuclear Information System (INIS)

Ragan, G.L.; Ricker, C.W.; Chiles, M.M.; Ingersoll, D.T.; Slaughter, G.G.

1979-01-01

Recent studies show that subassemblies containing various spent fuels could be assayed rapidly and accurately by a nondestructive assay system using active neutron interrogation and prompt-neutron detection. Subassembly penetration is achieved by 24-keV (Sb--Be) interrogation neutrons; the spent-fuel neutron background is overridden by using strong interrogating sources and prompt-neutron signals, and background gammas are absorbed by lead. Experiments have demonstrated the potential for assaying with better than 5% accuracy, three spent plutonium-fueled subassemblies per hour. Calculations, validated by experiments, predict even better performance for fresh or uranium-fueled subassemblies; several performance estimates are given

The states of the art of the nondestructive assay of spent nuclear fuel assemblies. A critical review of the Spent Fuel NDA Project of the U.S. Department of Energy's Next Generation Safeguards Initiative

International Nuclear Information System (INIS)

Bolind, Alan Michael; Seya, Michio

2015-12-01

The state of the art of the nondestructive assay of spent nuclear fuel assemblies is represented by the results of the Spent Fuel Nondestructive Assay Project of the Next Generation Safeguards Initiative (NGSI) of the U.S. Department of Energy / National Nuclear Security Administration. This report surveys the fourteen advanced nondestructive assay (NDA) techniques that were examined by the NGSI. For each technique, it explains how the technique operates, the NGSI's design of an instrument that uses the technique, how the data are analyzed, and the technique's chief limitations. After this survey of the NDA techniques, the report then discusses and critiques the current paradigm of the practice of NDA of spent fuel assemblies. It shows how the current main problem in the NDA of spent fuel assemblies—namely, an unacceptably large uncertainty in the assay results—is caused primarily by using too few independent NDA measurements. Because the physics of the NDA of spent fuel assemblies is three dimensional, at least three independent NDA measurements are required. Thus, NDA results should be able to be improved dramatically by combining the fourteen advanced NDA techniques plus other existing NDA techniques into appropriate combinations of three techniques. This report evaluates the NGSI's proposed NDA combinations according to these principles. (author)

Nondestructive radioassay for waste management: an assessment

Energy Technology Data Exchange (ETDEWEB)

Lehmkuhl, G.D.

1981-06-01

Nondestructive Assay (NDA) for Transuranic Waste Management is used to mean determining the amount of transuranic (TRU) isotopes in crates, drums, boxes, cans, or other containers without having to open the container. It also means determining the amount of TRU in soil, bore holes, and other environmental testing areas without having to go through extensive laboratory wet chemistry analyses. it refers to radioassay techniques used to check for contamination on objects after decontamination and to determine amounts of TRU in waste processing streams without taking samples to a laboratory. Gednerally, NDA instrumentation in this context refers to all use of radioassay which does not involve taking samples and using wet chemistry techniques. NDA instruments have been used for waste assay at some sites for over 10 years and other sites are just beginning to consider assay of wastes. The instrumentation used at several sites is discussed in this report. Almost all these instruments in use today were developed for special nuclear materials safeguards purposes and assay TRU waste down to the 500 nCi/g range. The need for instruments to assay alpha particle emitters at 10 nCi/g or less has risen from the wish to distinguish between Low Level Waste (LLW) and TRU Waste at the defined interface of 10 nCi/g. Wastes have historically been handled as TRU wastes if they were just suspected to be transuranically contaminated but their exact status was unknown. Economic and political considerations make this practice undesirable since it is easier and less costly to handle LLW. This prompted waste generators to want better instrumentation and led the Transuranic Waste Management Program to develop and test instrumentation capable of assaying many types of waste at the 10 nCi/g level. These instruments are discussed.

Design of an error-free nondestructive plutonium assay facility

International Nuclear Information System (INIS)

Moore, C.B.; Steward, W.E.

1987-01-01

An automated, at-line nondestructive assay (NDA) laboratory is installed in facilities recently constructed at the Savannah River Plant. The laboratory will enhance nuclear materials accounting in new plutonium scrap and waste recovery facilities. The advantages of at-line NDA operations will not be realized if results are clouded by errors in analytical procedures, sample identification, record keeping, or techniques for extracting samples from process streams. Minimization of such errors has been a primary design objective for the new facility. Concepts for achieving that objective include mechanizing the administrative tasks of scheduling activities in the laboratory, identifying samples, recording and storing assay data, and transmitting results information to process control and materials accounting functions. These concepts have been implemented in an analytical computer system that is programmed to avoid the obvious sources of error encountered in laboratory operations. The laboratory computer exchanges information with process control and materials accounting computers, transmitting results information and obtaining process data and accounting information as required to guide process operations and maintain current records of materials flow through the new facility

Applying thermal neutron radiography to non-destructive assays of dynamic systems

International Nuclear Information System (INIS)

Silvani, Maria I.; Almeida, Gevaldo L. de; Goncalves, Marcelo J.; Lopes, Ricardo T.

2008-01-01

Dynamic processes or systems frequently can not have their behavior directly analyzed due to safety reasons or because they require destructive assays, which can not be always afforded when high-cost equipment, devices and components are involved. Under these circumstances, some kind of non-destructive technique should be applied to preserve the safety of the personnel performing the assay, as well as the integrity of the piece being inspected. Thermal neutrons are specially suited as a tool for this purpose, thanks to their capability to pass through metallic materials, which could be utterly opaque to X-rays. This paper describes the accomplishments achieved at the Instituto de Engenharia Nuclear / CNEN, Brazil, aiming at the development of an Image Acquisition System capable to perform non-destructive assays using thermal neutrons. It is comprised of a thermal neutron source provided by the Argonauta research reactor, a converter-scintillating screen, and a CCD-based video camera optically coupled to the screen through a dark chamber equipped with a mirror. The developed system has been used to acquire 2D neutron radiographic images of static devices to reveal their inner structure, as well as movies of running systems and working devices to verify its functioning and soundness. Radiographic images of objects taken at different angles would be later on used as projections to retrieve - through a proper unfolding software - their 3D images expressed as attenuation coefficients for thermal neutrons. A quantitative performance of the system has been assessed through its Modulation Transfer Function - MTF. In order to determine this curve, unique collimators designed to simulate different spatial frequencies have been manufactured. Besides that, images of some objects have been acquired with the system being developed as well as using the conventional radiographic film, allowing thus a qualitative comparison between them. (author)

Integrated nondestructive assay solutions for plutonium measurement problems of the 21st century

International Nuclear Information System (INIS)

Sampson, T.E.; Cremers, T.L.

1997-01-01

The authors describe automated and integrated NDA systems configured to measure many of the materials that will be found in the DOE complex in the dismantlement, disposition, residue stabilization, immobilization, and MOX fuel programs. These systems are typified by the ARIES (Advanced Recovery and Integrated Extraction System) nondestructive assay system which is under construction at Los Alamos to measure the outputs of a weapon component dismantlement system

Reference materials for nondestructive assay of special nuclear material. Volume 1. Uranium oxide plus graphite powder

International Nuclear Information System (INIS)

Sprinkle, J.K.; Likes, R.N.; Parker, J.L.; Smith, H.A.

1983-10-01

This manual describes the fabrication of reference materials for use in gamma-ray-based nondestructive assay of low-density uranium-bearing samples. The sample containers are 2-l bottles. The reference materials consist of small amounts of UO 2 spread throughout a graphite matrix. The 235 U content ranges from 0 to 100 g. The manual also describes the far-field assay procedure used with low-resolution detectors

APNEA/WIT system nondestructive assay capability evaluation plan for select accessibly stored INEL RWMC waste forms

International Nuclear Information System (INIS)

Becker, G.K.

1997-01-01

Bio-Imaging Research Inc. (BIR) and Lockheed Martin Speciality Components (LMSC) are engaged in a Program Research and Development Agreement and a Rapid Commercialization Initiative with the Department of Energy, EM-50. The agreement required BIR and LMSC to develop a data interpretation method that merges nondestructive assay and nondestructive examination (NDA/NDE) data and information sufficient to establish compliance with applicable National TRU Program (Program) waste characterization requirements and associated quality assurance performance criteria. This effort required an objective demonstration of the BIR and LMSC waste characterization systems in their standalone and integrated configurations. The goal of the test plan is to provide a mechanism from which evidence can be derived to substantiate nondestructive assay capability and utility statement for the BIT and LMSC systems. The plan must provide for the acquisition, compilation, and reporting of performance data thereby allowing external independent agencies a basis for an objective evaluation of the standalone BIR and LMSC measurement systems, WIT and APNEA respectively, as well as an expected performance resulting from appropriate integration of the two systems. The evaluation is to be structured such that a statement regarding select INEL RWMC waste forms can be made in terms of compliance with applicable Program requirements and criteria

A portable nondestructive assay measurement control system

International Nuclear Information System (INIS)

Palmer, M.E.

1984-01-01

Portable nondestructive assay (NDA) of plutonium processing hoods, solvent extraction columns, glove boxes, filters, and other items is required for both nuclear materials accountability and criticality control purposes. The Plutonium Finishing Plant has hundreds of such items that require routine portable NDA measurement. Previous recordkeeping of NDA measurements consisted of boxes of papers containing results and notebooks containing notes for each item to be measured. If the notes for any item were lost, new measurement parameters had to be calculated for that item. As a result, subsequent measurements could no longer be directly compared with previous results for that item due to possible changes in measurement parameters. The new portable NDA management system keeps all the necessary information in a computerized data base. Technicians are provided with a computer-generated drawing of each item to be measured, which also contains comments, measurement points, measurement parameters, and a form for filling in the raw data. After the measurements are made, the technician uses the computer to calculate and print out the results

Integrated nondestructive assay solutions for plutonium measurement problems of the 21st century

International Nuclear Information System (INIS)

Sampson, T.E.; Cremers, T.L.

1997-12-01

The authors describe automated and integrated nondestructive assay (NDA) systems configured to measure many of the materials that will be found in the Department of Energy complex in the dismantlement, disposition, residue stabilization, immobilization, and mixed oxide fuel programs. These systems are typified by the Advanced Recovery and Integrated Extraction System NDA system which is under construction at Los Alamos National Laboratory to measure the outputs of a weapon component dismantlement system

Field nondestructive assay measurements as applied to process inventories

International Nuclear Information System (INIS)

Westsik, G.A.

1979-08-01

An annual process equipment holdup inventory measurement program for a plutonium processing plant was instituted by Rockwell Hanford Operations (Rockwell) at Richland, Washington. The inventories, performed in 1977 and 1978, were designed to improve plutonium accountability and control. The inventory method used field nondestructive assay (NDA) measurement techniques with portable electronics and sodium iodide detectors. Access to and movement of plutonium in work areas was curtailed during the inventory process using administrative controls. Comparison of the two annual inventories showed good reproducibility of results within the calculated error ranges. For items where no plutonium movement occurred and which contained greater than 20 grams plutonium, the average measurement difference between the two inventories was 22%. The procedures and equipment used and the operational experience from the inventories are described

A study of the effect of measurement error in predictor variables in nondestructive assay

International Nuclear Information System (INIS)

Burr, Tom L.; Knepper, Paula L.

2000-01-01

It is not widely known that ordinary least squares estimates exhibit bias if there are errors in the predictor variables. For example, enrichment measurements are often fit to two predictors: Poisson-distributed count rates in the region of interest and in the background. Both count rates have at least random variation due to counting statistics. Therefore, the parameter estimates will be biased. In this case, the effect of bias is a minor issue because there is almost no interest in the parameters themselves. Instead, the parameters will be used to convert count rates into estimated enrichment. In other cases, this bias source is potentially more important. For example, in tomographic gamma scanning, there is an emission stage which depends on predictors (the 'system matrix') that are estimated with error during the transmission stage. In this paper, we provide background information for the impact and treatment of errors in predictors, present results of candidate methods of compensating for the effect, review some of the nondestructive assay situations where errors in predictors occurs, and provide guidance for when errors in predictors should be considered in nondestructive assay

Automated nondestructive assay system for the measurement of irradiated Rover fuel

International Nuclear Information System (INIS)

Augustson, R.H.; Menlove, H.O.; Smith, D.B.; Bond, A.L.; Durrill, D.C.; Hollowell, W.P.; Bromley, C.P.

1975-01-01

With the termination of the Nuclear Rocket Propulsion (Rover) Program, and associated reactor testing at the Nuclear Rocket Development Station (NRDS), Nevada, plans are progressing to recover the 93 percent enriched uranium contained in irradiated fuel from twenty various test reactors. This fuel is being packaged into 7-cm-dia by 137-cm-long cardboard tubes, using the remote handling facilities (E-MAD Bldg) of NRDS. After packaging, the fuel is shipped to Allied Chemical Corporation, Idaho Falls, Idaho, for uranium recovery. About 4000 tubes will be needed to package and ship the inventory of fuel elements presently at NRDS. This represents a total of approximately 2500 kg of enriched uranium. To complete the accounting records each tube is being nondestructively assayed and records kept on a reactor-by-reactor basis where possible. The assayed values for a reactor are then compared with original input inventory values and discrepancies resolved. The tubes are being assayed by an active neutron interrogation system designed and fabricated by Los Alamos Scientific Laboratory (LASL) and operated by Westinghouse Astronuclear Laboratory (WANL)-Nevada Operations personnel. WANL is the operating contractor in charge of loading and shipping this fuel. (U.S.)

Bremsstrahlung-induced highly penetrating probes for nondestructive assay and defect analysis

CERN Document Server

Selim, F A; Harmon, J F; Kwofie, J; Spaulding, R; Erickson, G; Roney, T

2002-01-01

Nondestructive assay and defect analysis probes based on bremsstrahlung-induced processes have been developed to identify elements and probe defects in large volume samples. Bremsstrahlung beams from (electron accelerators) with end-point energies both above and below neutron emission threshold have been used. Below neutron emission threshold these beams (from 6 MeV small pulsed linacs), which exhibit high penetration, create positrons via pair production inside the material and produce X-ray fluorescence (XRF) radiation. Chemical assays of heavy elements in thick samples up to 10 g/cm sup 2 thick are provided by energy dispersive XRF measurements. The pair-produced positrons annihilate within the material, thereby emitting 511 keV gamma radiation. Doppler broadening spectroscopy of the 511 keV radiation can be performed to characterize the material and measure defects in samples of any desired thickness. This technique has successfully measured induced strain due to tensile stress in steel samples of 0.64 cm...

Nondestructive techniques for assaying fuel debris in piping at Three Mile Island Unit 2

International Nuclear Information System (INIS)

Vinjamuri, K.; McIsaac, C.V.; Beller, L.S.; Isaacson, L.; Mandler, J.W.; Hobbins, R.R. Jr.

1981-11-01

Four major categories of nondestructive techniques - ultrasonic, passive gamma ray, infrared detection, and remote video examination - have been determined to be feasible for assaying fuel debris in the primary coolant system of the Three Mile Island Unit 2 (TMI-2) Reactor. Passive gamma ray detection is the most suitable technique for the TMI-2 piping; however, further development of this technique is needed for specific application to TMI-2

Survey of EEC solid waste arisings and performance of non-destructive assay systems

International Nuclear Information System (INIS)

Bremner, W.B.; Adaway, D.W.; Yates, A.

1992-01-01

This report covers the work carried out during an one-year contract which surveyed the radioactive solid waste arisings in EEC Member States and also tabulated information on the performance of the non-destructive assay (NDA) system used. The work was jointly carried out with CEA partners at Cadarache and Paris. The tabulated data give information on types, packaging, associated activity, and NDA capability of the utilities or research organisations. Some short comings in NDA capabilities are identified and possible solutions are given

Standard test method for nondestructive assay of radioactive material by tomographic gamma scanning

CERN Document Server

American Society for Testing and Materials. Philadelphia

2010-01-01

1.1 This test method describes the nondestructive assay (NDA) of gamma ray emitting radionuclides inside containers using tomographic gamma scanning (TGS). High resolution gamma ray spectroscopy is used to detect and quantify the radionuclides of interest. The attenuation of an external gamma ray transmission source is used to correct the measurement of the emission gamma rays from radionuclides to arrive at a quantitative determination of the radionuclides present in the item. 1.2 The TGS technique covered by the test method may be used to assay scrap or waste material in cans or drums in the 1 to 500 litre volume range. Other items may be assayed as well. 1.3 The test method will cover two implementations of the TGS procedure: (1) Isotope Specific Calibration that uses standards of known radionuclide masses (or activities) to determine system response in a mass (or activity) versus corrected count rate calibration, that applies to only those specific radionuclides for which it is calibrated, and (2) Respo...

Evaluation of Nondestructive Assay/Nondestructive Examination Capabilities for Department of Energy Spent Nuclear Fuel

International Nuclear Information System (INIS)

Luptak, A.J.; Bulmahn, K.D.

1998-01-01

This report summarizes an evaluation of the potential use of nondestructive assay (NDA) and nondestructive examination (NDE) technologies on DOE spent nuclear fuel (SNF). It presents the NDA/NDE information necessary for the National Spent Nuclear Fuel Program (NSNFP) and the SNF storage sites to use when defining that role, if any, of NDA/NDE in characterization and certification processes. Note that the potential role for NDA/NDE includes confirmatory testing on a sampling basis and is not restricted to use as a primary, item-specific, data collection method. The evaluation does not attempt to serve as a basis for selecting systems for development or deployment. Information was collected on 27 systems being developed at eight DOE locations. The systems considered are developed to some degree, but are not ready for deployment on the full range of DOE SNF and still require additional development. The system development may only involve demonstrating performance on additional SNF, packaging the system for deployment, and developing calibration standards, or it may be as extensive as performing additional basic research. Development time is considered to range from one to four years. We conclude that NDA/NDE systems are capable of playing a key role in the characterization and certification of DOE SNF, either as the primary data source or as a confirmatory test. NDA/NDE systems will be able to measure seven of the nine key SNF properties and to derive data for the two key properties not measured directly. The anticipated performance goals of these key properties are considered achievable except for enrichment measurements on fuels near 20% enrichment. NDA/NDE systems can likely be developed to measure the standard canisters now being considered for co-disposal of DOE SNF. This ability would allow the preparation of DOE SNF for storage now and the characterization and certification to be finalize later

Cryogenic gamma detectors enable direct detection of 236U and minor actinides for non-destructive assay

International Nuclear Information System (INIS)

Miguel Velazquez; Jonathan Dreyer; Drury, O.B.; Friedrich, Stephan; Saleem Salaymeh

2016-01-01

We demonstrate the utility of a superconducting transition edge sensor (TES) γ-ray detector with high energy resolution and low Compton background for nondestructive assay (NDA) of a uranium sample from reprocessed nuclear fuel. We show that TES γ-detectors can separate low-energy actinide γ-emissions from the background and nearby lines, even from minor isotopes whose signals are often obscured in NDA with conventional Ge detectors. Superconducting γ-detectors may therefore bridge the gap between high-accuracy destructive assay (DA) and easier-to-use NDA. (author)

Commissioning of calorimeter in radiochemical laboratory for non-destructive assay of special nuclear materials

International Nuclear Information System (INIS)

Patra, S.; Mhatre, A.M.; Agarwal, C.; Chaudhury, S.; Pujari, P.K.

2017-01-01

Accounting of special nuclear materials (SNM) in every stages of nuclear fuel cycle is a necessity where one needs the quantitative estimation of SNM in variety of samples like sealed containers or finished products without altering its physical and chemical form. Non-destructive assay (NDA) techniques are capable of assaying such samples by the way of measuring passive/active neutrons/gamma rays or by the measurement of decay heat. Radiochemistry Division has been actively involved in the development and deployment of various NDA methodologies for meeting the demand of nuclear material accounting as and when required. Recently a radiometric calorimeter, developed by Reactor Control Division, E and I Group, BARC, has been installed in Lab C-33, Radiochemistry Division

Experimental 233U nondestructive assay with a random driver

International Nuclear Information System (INIS)

Goris, P.

1979-01-01

Nondestructive assay (NDA) of 233 U in quantities up to 15 grams containing 7 ppM 232 U age 2 years was investigated with a random driver. A passive singles counting technique showed a reproducibility within 0.2% at the 95% confidence level. This technique would be applicable throughout a process in which all of the 233 U had the same 232 U content at the same age. Where the 232 U content varies, determination of 233 U fissile content would require active NDA. Active coincidence counting utilizing a 238 Pu, Li neutron source and a plastic scintillator detector system showed a reproducibility limit within 15% at the 95% confidence limit. The active technique was found to be very dependent on the detector system resolving time in order to make proper random coincidence corrections associated with the high gamma activity from the 232 U decay chain

Application of expert system technology to nondestructive waste assay - initial prototype model

Energy Technology Data Exchange (ETDEWEB)

Becker, G.K.; Determan, J.C. [Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States)

1997-11-01

Expert system technology has been identified as a technique useful for filling certain types of technology/capability gaps in existing waste nondestructive assay (NDA) applications. In particular, expert system techniques are being investigated with the intent of providing on-line evaluation of acquired data and/or directed acquisition of data in a manner that mimics the logic and decision making process a waste NDA expert would employ. The space from which information and data sources utilized in this process is much expanded with respect to the algorithmic approach typically utilized in waste NDA. Expert system technology provides a mechanism to manage and reason with this expanded information/data set. The material presented in this paper concerns initial studies and a resultant prototype expert system that incorporates pertinent information, and evaluation logic and decision processes, for the purpose of validating acquired waste NDA measurement assays. 6 refs., 6 figs.

Application of expert system technology to nondestructive waste assay - initial prototype model

International Nuclear Information System (INIS)

Becker, G.K.; Determan, J.C.

1997-01-01

Expert system technology has been identified as a technique useful for filling certain types of technology/capability gaps in existing waste nondestructive assay (NDA) applications. In particular, expert system techniques are being investigated with the intent of providing on-line evaluation of acquired data and/or directed acquisition of data in a manner that mimics the logic and decision making process a waste NDA expert would employ. The space from which information and data sources utilized in this process is much expanded with respect to the algorithmic approach typically utilized in waste NDA. Expert system technology provides a mechanism to manage and reason with this expanded information/data set. The material presented in this paper concerns initial studies and a resultant prototype expert system that incorporates pertinent information, and evaluation logic and decision processes, for the purpose of validating acquired waste NDA measurement assays. 6 refs., 6 figs

Multimodality characterization of nuclear waste drums using emerging techniques for nondestructive examination and assay

International Nuclear Information System (INIS)

Bernardi, R.T.

1993-01-01

We are developing an x-ray imaging system that incorporates several inspection technologies for complete, nondestructive evaluation of containers of nuclear waste. In Phase I and Phase II SBIR programs for the DOE, we proved the feasibility of using x-ray computed tomography (CT) and digital radiography (DR)-imaging techniques using x-rays transmitted through the object-for container inspection. Now, with further funding from DOE and working with scientists at Lawrence Livermore National Lab., we are designing a mobile inspection system that will use CT and DR as well as two x-ray emission imaging techniques-single photon emission computed tomography and nondestructive assay. This system will provide much more information about the contents of containers than currently used inspection methods, and will provide archiving of digital data. In this paper, we describe inspection system and present recent results from the CT and DR evaluations

Nondestructive assay of spent fuel rods from a Light Water Breeder Reactor (LWBR Development Program)

International Nuclear Information System (INIS)

Tessler, G.; Beaudoin, B.R.; Beggs, W.J.; Freeman, L.B.; Schick, W.C. Jr.

1987-09-01

A gauge, called the Production Irradiated Fuel Assay Gauge (PIFAG), has been developed and utilized to measure, nondestructively, the fissile fuel content of spent fuel rods from the Light Water Breeder Reactor (LWBR) core. The PIFAG was in operation from November 1983 to May 1987. During this period, assay data were obtained for two irradiated test rods used for initial qualification of the gauge and 524 spent LWBR core rods. A review of PIFAG operations is given, including hot cell operations, calibration, assay operations, and methods used to monitor the data quality and verify the precision and accuracy of the data. The analytical model used to determine the core rod fissile fuel content from the data and the results for the 524 LWBR spent fuel rods are given

Standard guide for the selection, training and qualification of nondestructive assay (NDA) personnel

CERN Document Server

American Society for Testing and Materials. Philadelphia

2004-01-01

1.1 This guide contains good practices for the selection, training, qualification, and professional development of personnel performing analysis, calibration, physical measurements, or data review using nondestructive assay equipment, methods, results, or techniques. The guide also covers NDA personnel involved with NDA equipment setup, selection, diagnosis, troubleshooting, or repair. Selection, training, and qualification programs based on this guide are intended to provide assurance that NDA personnel are qualified to perform their jobs competently. This guide presents a series of options but does not recommend a specific course of action.

Performance Demonstration Program Plan for Nondestructive Assay for the TRU Waste Characterization Program. Revision 1

International Nuclear Information System (INIS)

1997-01-01

The Performance Demonstration Program (PDP) for Nondestructive Assay (NDA) consists of a series of tests conducted on a regular frequency to evaluate the capability for nondestructive assay of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed with TRU waste characterization systems. Measurement facility performance will be demonstrated by the successful analysis of blind audit samples according to the criteria set by this Program Plan. Intercomparison between measurement groups of the DOE complex will be achieved by comparing the results of measurements on similar or identical blind samples reported by the different measurement facilities. Blind audit samples (hereinafter referred to as PDP samples) will be used as an independent means to assess the performance of measurement groups regarding compliance with established Quality Assurance Objectives (QAOs). As defined for this program, a PDP sample consists of a 55-gallon matrix drum emplaced with radioactive standards and fabricated matrix inserts. These PDP sample components, once manufactured, will be secured and stored at each participating measurement facility designated and authorized by Carlsbad Area Office (CAO) under secure conditions to protect them from loss, tampering, or accidental damage

OR14-V-Uncertainty-PD2La Uncertainty Quantification for Nuclear Safeguards and Nondestructive Assay Final Report

Energy Technology Data Exchange (ETDEWEB)

Nicholson, Andrew D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Croft, Stephen [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); McElroy, Robert Dennis [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-08-01

The various methods of nondestructive assay (NDA) of special nuclear material (SNM) have applications in nuclear nonproliferation, including detection and identification of illicit SNM at border crossings and quantifying SNM at nuclear facilities for safeguards. No assay method is complete without “error bars,” which provide one way of expressing confidence in the assay result. Consequently, NDA specialists typically provide error bars and also partition total uncertainty into “random” and “systematic” components so that, for example, an error bar can be developed for the total mass estimate in multiple items. Uncertainty Quantification (UQ) for NDA has always been important, but it is recognized that greater rigor is needed and achievable using modern statistical methods.

Portable non-destructive assay methods for screening and segregation of radioactive waste

International Nuclear Information System (INIS)

Simpson, Alan; Jones, Stephanie; Clapham, Martin; Lucero, Randy

2011-01-01

Significant cost-savings and operational efficiency may be realised by performing rapid non-destructive classification of radioactive waste at or near its point of retrieval or generation. There is often a need to quickly categorize and segregate bulk containers (drums, crates etc.) into waste streams defined at various boundary levels (based on its radioactive hazard) in order to meet disposal regulations and consignor waste acceptance criteria. Recent improvements in gamma spectroscopy technologies have provided the capability to perform rapid in-situ analysis using portable and hand-held devices such as battery-operated medium and high resolution detectors including lanthanum halide and high purity germanium (HPGe). Instruments and technologies that were previously the domain of complex lab systems are now widely available as touch-screen 'off-the-shelf' units. Despite such advances, the task of waste stream screening and segregation remains a complex exercise requiring a detailed understanding of programmatic requirements and, in particular, the capability to ensure data quality when operating in the field. This is particularly so when surveying historical waste drums and crates containing heterogeneous debris of unknown composition. The most widely used portable assay method is based upon far-field High Resolution Gamma Spectroscopy (HRGS) assay using HPGe detectors together with a well engineered deployment cart (such as the PSC TechniCART TM technology). Hand-held Sodium Iodide (NaI) detectors are often also deployed and may also be used to supplement the HPGe measurements in locating hot spots. Portable neutron slab monitors may also be utilised in cases where gamma measurements alone are not suitable. Several case histories are discussed at various sites where this equipment has been used for in-situ characterization of debris waste, sludge, soil, high activity waste, depleted and enriched uranium, heat source and weapons grade plutonium, fission products

Standardization of portable assay instrumentation: the neutron-coincidence tree

International Nuclear Information System (INIS)

Menlove, H.O.

1983-01-01

Standardization of portable neutron assay instrumentation has been achieved by using the neutron coincidence technique as a common basis for a wide range of instruments and applications. The electronics originally developed for the High-Level Neutron Coincidence Counter has been adapted to both passive- and active-assay instrumentation for field verification of bulk plutonium, inventory samples, pellets, powders, nitrates, high-enriched uranium, and materials-testing-reactor, light-water-reactor, and mixed-oxide fuel assemblies. The family of detectors developed at Los Alamos National Laboratory and their performance under in-field conditions are described. 16 figures, 3 tables

Use of neutron-capture plastic fibers for nondestructive assay

International Nuclear Information System (INIS)

Heger, A.S.; Grazioso, R.F.; Mayo, D.R.; Ensslin, N.; Miller, M.C.; Huang, H.Y.; Russo, P.A.

1998-01-01

Neutron-capture plastic fibers can be used as a nondestructive assay tool. The detectors consist of an active region assembled from ribbons of boron-( 10 B) loaded optical fibers. The mixture of the moderator and thermal neutron absorber in the fiber yields a detector with high efficiency (var-epsilon) and a short die-away time (τ). The deposited energy of the resultant charged particles is converted to light that is collected by photomultiplier tubes mounted at both ends of the fiber. Thermal neutron coincidence counters (TNCC) made of these fibers can serve to verify fissile materials generated from the nuclear fuel cycle. This type of detector may extend the range of materials now accessible to assay by 3 He detectors. Experiments with single fibers of diameters 0.25, 0.50, and 1.00 mm test their ability to distinguish between the signals generated from neutron interactions and those from gamma rays. These results are compared with those obtained from simulation analyses for the same purpose. Light output and attenuation, neutron detection efficiency, and the signal-to-noise ratios of these fibers have also been investigated. The experimental results for light attenuation and neutron detection efficiency are consistent with the values obtained from simulation studies. A comparison of the performance of various configurations of the plastic scintillating fibers with that of other neutron-capture devices such as 3 He detectors is also discussed

Portable generator-based X RF instrument for non-destructive analysis at crime scenes

Energy Technology Data Exchange (ETDEWEB)

Schweitzer, Jeffrey S. [University of Connecticut, Department of Physics, Unit 3046 Storrs, CT 06269-3046 (United States)]. E-mail: schweitz@phys.uconn.edu; Trombka, Jacob I. [Goddard Space Flight Center, Code 691, Greenbelt Road, Greenbelt, MD 20771 (United States); Floyd, Samuel [Goddard Space Flight Center, Code 691, Greenbelt Road, Greenbelt, MD 20771 (United States); Selavka, Carl [Massachusetts State Police Crime Laboratory, 59 Horse Pond Road, Sudbury, MA 01776 (United States); Zeosky, Gerald [Forensic Investigation Center, Crime Laboratory Building, 22 State Campus, Albany, NY 12226 (United States); Gahn, Norman [Assistant District Attorney, Milwaukee County, District Attorney' s Office, 821 West State Street, Milwaukee, WI 53233-1427 (United States); McClanahan, Timothy [Goddard Space Flight Center, Code 691, Greenbelt Road, Greenbelt, MD 20771 (United States); Burbine, Thomas [Goddard Space Flight Center, Code 691, Greenbelt Road, Greenbelt, MD 20771 (United States)

2005-12-15

Unattended and remote detection systems find applications in space exploration, telemedicine, teleforensics, homeland security and nuclear non-proliferation programs. The National Institute of Justice (NIJ) and the National Aeronautics and Space Administration's (NASA) Goddard Space Flight Center (GSFC) have teamed up to explore the use of NASA developed technologies to help criminal justice agencies and professionals investigate crimes. The objective of the program is to produce instruments and communication networks that have application within both NASA's space program and NIJ, together with state and local forensic laboratories. A general-purpose X-ray fluorescence system has been built for non-destructive analyses of trace and invisible material at crime scenes. This portable instrument is based on a generator that can operate to 60 kV and a Schottky CdTe detector. The instrument has been shown to be successful for the analysis of gunshot residue and a number of bodily fluids at crime scenes.

Portable generator-based X RF instrument for non-destructive analysis at crime scenes

International Nuclear Information System (INIS)

Schweitzer, Jeffrey S.; Trombka, Jacob I.; Floyd, Samuel; Selavka, Carl; Zeosky, Gerald; Gahn, Norman; McClanahan, Timothy; Burbine, Thomas

2005-01-01

Unattended and remote detection systems find applications in space exploration, telemedicine, teleforensics, homeland security and nuclear non-proliferation programs. The National Institute of Justice (NIJ) and the National Aeronautics and Space Administration's (NASA) Goddard Space Flight Center (GSFC) have teamed up to explore the use of NASA developed technologies to help criminal justice agencies and professionals investigate crimes. The objective of the program is to produce instruments and communication networks that have application within both NASA's space program and NIJ, together with state and local forensic laboratories. A general-purpose X-ray fluorescence system has been built for non-destructive analyses of trace and invisible material at crime scenes. This portable instrument is based on a generator that can operate to 60 kV and a Schottky CdTe detector. The instrument has been shown to be successful for the analysis of gunshot residue and a number of bodily fluids at crime scenes

Application of non-destructive impedance-based monitoring technique for cyclic fatigue evaluation of endodontic nickel-titanium rotary instruments.

Science.gov (United States)

Chang, Yau-Zen; Liu, Mou-Chuan; Pai, Che-An; Lin, Chun-Li; Yen, Kuang-I

2011-06-01

This study investigates the application of non-destructive testing based on the impedance theory in the cyclic fatigue evaluation of endodontic Ni-Ti rotary instruments. Fifty Ni-Ti ProTaper instruments were divided into five groups (n=10 in Groups A to E). Groups A to D were subjected to cyclic fatigue within an artificial canal (Group E was the control group). The mean value of the total life limit (TLL), defined as the instrument being rotated until fracture occurred was found to be 104 s in Group A. Each rotary instrument in Groups B, C and D were rotated until the tested instruments reached 80% (84 s), 60% (62 s) and 40% (42 s) of the TLL. After fatigue testing, each rotary instrument was mounted onto a custom-developed non-destructive testing device to give the tip of the instrument a progressive sideways bend in four mutually perpendicular directions to measure the corresponding impedance value (including the resistance and the reactance). The results indicated that the impedance value showed the same trend as the resistance, implying that the impedance was primarily affected by the resistance. The impedance value for the instruments in the 80% and 60% TLL groups increased by about 6 mΩ (about 7.5%) more than that of the instruments in the intact and 40% TLL groups. The SEM analysis result showed that crack striations were only found at the tip of the thread on the cracked surface of the instrument, consistent with the impedance measurements that found the impedance value of the cracked surface to be significantly different from those in other surfaces. These findings indicate that the impedance value may represent an effective parameter for evaluating the micro-structural status of Ni-Ti rotary instruments subjected to fatigue loading. Copyright © 2010 IPEM. Published by Elsevier Ltd. All rights reserved.

Capability and limitation study of the DDT passive-active neutron waste assay instrument

International Nuclear Information System (INIS)

Nicholas, N.J.; Coop, K.L.; Estep, R.J.

1992-05-01

The differential-dieaway-technique passive-active neutron assay system is widely used by transuranic waste generators to certify their drummed waste for eventual shipment to the Waste Isolation Pilot Plant (WIPP). Stricter criteria being established for waste emplacement at the WIPP site has led to a renewed interest in improvements to and a better understanding of current nondestructive assay (NDA) techniques. Our study includes the effects of source position, extreme matrices, high neutron backgrounds, and source self-shielding to explore the system's capabilities and limitations and to establish a basis for comparison with other NDA systems. 11 refs

Operation of automated NDA instruments for in-line HEU accounting at Y-12

International Nuclear Information System (INIS)

Russo, P.A.; Strittmatter, R.B.; Sandford, E.L.; Jeter, I.W.; McCullough, E.; Bowers, G.L.

1983-01-01

Two automated nondestructive assay instruments developed at Los Alamos in support of nuclear materials accounting needs are currently operating in-line at the Y-12 Plant for recovery of highly enriched uranium. One instrument provides the HEU inventory in the secondary solvent extraction system, and the other monitors HEU concentration in the secondary intermediate evaporator. Both instruments were installed in December 1982. Operational evaluation of these instruments has been a joint effort of Y-12 and Los Alamos. This has included comparison of the solvent extraction system inventories with direct measurement performed on the dumped solution components of the solvent extraction system, as well as comparisons of concentration assay results with the external assays of samples withdrawn from the process. The function, design, and preliminary results of the operational evaluation are reported

Significantly improving nuclear resonance fluorescence non-destructive assay by using the integral resonance transmission method and photofission

International Nuclear Information System (INIS)

Angell, Christopher T.; Hayakawa, Takehito; Shizuma, Toshiyuki; Hajima, Ryoichi

2013-01-01

Non-destructive assay (NDA) of 239 Pu in spent nuclear fuel or melted fuel using a γ-ray beam is possible using self absorption and the integral resonance transmission method. The method uses nuclear resonance absorption where resonances in 239 Pu remove photons from the beam, and the selective absorption is detected by measuring the decrease in scattering in a witness target placed in the beam after the fuel, consisting of the isotope of interest, namely 239 Pu. The method is isotope specific, and can use photofission or scattered γ-rays to assay the 239 Pu. It overcomes several problems related to NDA of melted fuel, including the radioactivity of the fuel, and the unknown composition and geometry. This talk will explain the general method, and how photofission can be used to assay specific isotopes, and present example calculations. (author)

Measurement control program for NDA instruments

International Nuclear Information System (INIS)

Hsue, S.T.; Marks, T.

1983-01-01

Measurement control checks for nondestructive assay instruments have been a constant and continuing concern at Los Alamos National Laboratory. This paper summarizes the evolution of the measurement control checks in the various high-resolution gamma systems we have developed. In-plant experiences with these systems and checks will be discussed. Based on these experiences, a set of measurement control checks is recommended for high-resolution gamma-ray systems

Relative mass resolution technique for optimum design of a gamma nondestructive assay system

International Nuclear Information System (INIS)

Koh, Duck Joon

1995-02-01

Nondestructive assay(NDA) is a widely used nuclear technology for quantitative elemental and isotopic assay. Nondestructive assay is performed by the detection of an identifying radiation emerging from the sample, which can be unambiguously related to the element or isotope of interest. In every assay we can identify two distinct factors that lead to measurement uncertainty. We refer to these as statistical and spatial uncertainties. If the spatial distribution of the analyte and the matrix material in the sample are known and fairly constant from sample to sample, then the major source of measurement uncertainty is the statistical uncertainty resulting from randomness in the counting process. The spatial uncertainty is independent of the measurement time and therefore sets a lower limit to the measurement uncertainty, which is inherent in the assay system in conjunction with the population of samples to be measured. The only way to minimize the spatial uncertainty is an optimized design of the assay system. Therefore we have to decide on the type and number of detectors to be used, their deployment around the sample, the type of radiation to be measured, the duration of each measurement, the size and shape of the sample drum. The design procedure leading to the optimal assay system should be based on a quantitative(RMR:Relative Mass Resolution) comparison of the performance of each proposed design. For NDA system design of low level radwaste, a specific purpose Monte Carlo code has been developed to simulate point-source responses for sources within an assayed radwaste drum and to analyze the effect of scattered gammas from higher energy gammas on the spectrum of a low energy gamma-ray. We could use the well-known Monte Carlo code, such as MCNP for the simulation of NDA in the case of low level radwaste. But, MCNP is a multi-purpose Monte Carlo transport code for several geometries which requires large memory and long CPU time. For some cases in nuclear

Tour of Los Alamos Safeguards R and D laboratories: demonstration and use of NDA instruments and material control and accounting simulation

International Nuclear Information System (INIS)

Anon.

1984-01-01

A description is presented of the nondestructive assay techniques and instrumentation for measuring the fissile content of fuel assemblies and fuel components. The course participants had a hands-on tour of this instrumentation and material accounting and control systems at Los Alamos National Laboratory

Nondestructive verification and assay systems for spent fuels. Technical appendixes

International Nuclear Information System (INIS)

Cobb, D.D.; Phillips, J.R.; Baker, M.P.

1982-04-01

Six technical appendixes are presented that provide important supporting technical information for the study of the application of nondestructive measurements to spent-fuel storage. Each appendix addresses a particular technical subject in a reasonably self-contained fashion. Appendix A is a comparison of spent-fuel data predicted by reactor operators with measured data from reprocessors. This comparison indicates a rather high level of uncertainty in previous burnup calculations. Appendix B describes a series of nondestructive measurements at the GE-Morris Operation Spent-Fuel Storage Facility. This series of experiments successfully demonstrated a technique for reproducible positioning of fuel assemblies for nondestructive measurement. The experimental results indicate the importance of measuring the axial and angular burnup profiles of irradiated fuel assemblies for quantitative determination of spent-fuel parameters. Appendix C is a reasonably comprehensive bibliography of reports and symposia papers on spent-fuel nondestructive measurements to April 1981. Appendix D is a compendium of spent-fuel calculations that includes isotope production and depletion calculations using the EPRI-CINDER code, calculations of neutron and gamma-ray source terms, and correlations of these sources with burnup and plutonium content. Appendix E describes the pulsed-neutron technique and its potential application to spent-fuel measurements. Although not yet developed, the technique holds the promise of providing separate measurements of the uranium and plutonium fissile isotopes. Appendix F describes the experimental program and facilities at Los Alamos for the development of spent-fuel nondestructive measurement systems. Measurements are reported showing that the active neutron method is sensitive to the replacement of a single fuel rod with a dummy rod in an unirradiated uranium fuel assembly

Design of an integrated non-destructive plutonium assay facility

International Nuclear Information System (INIS)

Moore, C.B.

1984-01-01

The Department of Energy requires improved technology for nuclear materials accounting as an essential part of new plutonium processing facilities. New facilities are being constructed at the Savannah River Plant by the Du Pont Company, Operating Contractor, to recover plutonium from scrap and waste material generated at SRP and other DOE contract processing facilities. This paper covers design concepts and planning required to incorporate state-of-the-art plutonium assay instruments developed at several national laboratories into an integrated, at-line nuclear material accounting facility operating in the production area. 3 figures

Thermophysical instruments for non-destructive examination of tightness and internal gas pressure or irradiated power reactor fuel rods

International Nuclear Information System (INIS)

Pastoushin, V.V.; Novikov, A.Yu.; Bibilashvili, Yu.K.

1998-01-01

The developed thermophysical method and technical instruments for non-destructive leak-tightness and gas pressure inspection inside irradiated power reactor fuel rods and FAs under poolside and hot cell conditions are described. The method of gas pressure measuring based on the examination of parameters of thermal convection that aroused in gas volume of rod plenum by special technical instruments. The developed method and technique allows accurate value determination of not only one of the main critical rod parameters, namely total internal gas pressure, that forms rod mean life in the reactor core, but also the partial pressure of every main constituent of gaseous mixture inside irradiated fuel rod, that provides the feasibility of authentic and reliable leak-tightness detection. The described techniques were experimentally checked during the examination of all types power reactor fuel rods existing in Russia (WWER, BN, RBMK) and could form the basis for new technique development for non-destructive examination of PWR (and other) type rods and FAs having gas plenum filled with spring or another elements of design. (author)

Neutron and gamma-ray nondestructive examination of contact-handled transuranic waste at the ORNL TRU Waste Drum Assay Facility

International Nuclear Information System (INIS)

Schultz, F.J.; Coffey, D.E.; Norris, L.B.; Haff, K.W.

1985-03-01

A nondestructive assay system, which includes the Neutron Assay System (NAS) and the Segmented Gamma Scanner (SGS), for the quantification of contact-handled (<200 mrem/h total radiation dose rate at contact with container) transuranic elements (CH-TRU) in bulk solid waste contained in 208-L and 114-L drums has been in operation at the Oak Ridge National Laboratory since April 1982. The NAS has been developed and demonstrated by Los Alamos National Laboratory (LANL) and the Oak Ridge National Laboratory (ORNL) for use by most US Department of Energy Defense Plant (DOE-DP) sites. More research and development is required, however, before the NAS can provide complete assay results for other than routine defense waste. To date, 525 ORNL waste drums have been assayed, with varying degrees of success. The isotopic complexity of the ORNL waste creates a correspondingly complex assay problem. The NAS and SGS assay data are presented and discussed. Neutron matrix effects, the destructive examination facility, and enriched uranium fuel-element assays are also discussed

Non-destructive assay of leached hulls in a nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Hofstetter, K.J.; Henderson, B.C.; Gray, J.H.; Huff, G.A.

1978-01-01

The hull monitor at the Barnwell Nuclear Fuels Plant (BNFP) will be a remotely controlled, fully automated system designed to quantitatively assay leached hulls for undissolved U and Pu. The hull monitor will assay the hulls from one metric ton of fuel per dissolver basket with the design goal of detecting 0.1% undissolved fuel and yet remain within the framework of the BNFP materials flow of five hull baskets per day. The non-destructive assay will be accomplished using a computer-based gamma-ray pulse height analysis system employing a 5 x 5 inch NaI(Tl) scintillation detector. The intense radiations from the fission product isotopes and the activation product isotopes produced in the reactor prevent direct assay of the undissolved fuel left in the hulls. The measurement will be made indirectly by demonstrating a correlation between the amount of 144 Ce undissolved and the remaining U. The isotope 144 Ce is a direct fission product with high cumulative yield. The daughter isotope 144 Pr has a gamma ray at 2.18 MeV well above other predominant radiations in the spectrum from the major interferences 60 Co, 58 Co, 95 Zr( 95 Nb), 137 Cs and 106 Ru( 106 Rh). Segmented scanning operation of the hull monitor is accomplished by rotation and vertical transversal of the hulls container past the detector station. Proper collimation and absorbers are required to maximize the 144 Ce( 144 Pr) to background ratio. A basket indexer is provided which monitors the scanning rate and ensures repositioning. The leached hull monitor system will be interfaced to a computer-based multichannel analyzer for ease of operation and data handling. A calibration basket has been fabricated to accomodate radioactive sources and inactive Zircaloy hulls

Development of a plutonium solution-assay instrument with isotopic capability

International Nuclear Information System (INIS)

Hsue, S.T.; Marks, T.

1992-01-01

A new generation of solution-assay instrument has been developed to satisfy all the assay requirements of an aqueous plutonium-recovery operation. The assay is based on a transmission-corrected passive assay technique. We have demonstrated that the system can cover a concentration range of 0.5--300 g/ell with simultaneous isotopic determination. The system can be used to assay input and eluate streams of the recovery operation. The system can be modified to measure low-concentration effluent solutions from the recovery operation covering 0.01--40 g/ell. The same system has also been modified to assay plutonium solutions enriched in 242 Pu. 6 refs

Spectral Shifting in Nondestructive Assay Instrumentation

Energy Technology Data Exchange (ETDEWEB)

Trellue, Holly Renee [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Nettleton, Anthony Steven [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Tutt, James Robert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Menlove, Howard Olsen [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); LaFleur, Adrienne Marie [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Tobin, Stephen Joseph [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-11-17

This project involves spectrum tailoring research that endeavors to better distinguish energies of gamma rays using different spectral material thicknesses and determine neutron energies by coating detectors with various materials.

Design of an electron-accelerator-driven compact neutron source for non-destructive assay

Science.gov (United States)

Murata, A.; Ikeda, S.; Hayashizaki, N.

2017-09-01

The threat of nuclear and radiological terrorism remains one of the greatest challenges to international security, and the threat is constantly evolving. In order to prevent nuclear terrorism, it is important to avoid unlawful import of nuclear materials, such as uranium and plutonium. Development of technologies for non-destructive measurement, detection and recognition of nuclear materials is essential for control at national borders. At Tokyo Institute of Technology, a compact neutron source system driven by an electron-accelerator has been designed for non-destructive assay (NDA). This system is composed of a combination of an S-band (2.856 GHz) RF-gun, a tungsten target to produce photons by bremsstrahlung, a beryllium target, which is suitable for use in generating neutrons because of the low threshold energy of photonuclear reactions, and a moderator to thermalize the fast neutrons. The advantage of this system can accelerate a short pulse beam with a pulse width less than 1 μs which is difficult to produce by neutron generators. The amounts of photons and neutron produced by electron beams were simulated using the Monte Carlo simulation code PHITS 2.82. When the RF-gun is operated with an average electron beam current of 0.1 mA, it is expected that the neutron intensities are 1.19 × 109 n/s and 9.94 × 109 n/s for incident electron beam energies of 5 MeV and 10 MeV, respectively.

Performance in the WIPP nondestructive assay performance demonstration program

Energy Technology Data Exchange (ETDEWEB)

Marcinkiewicz, C.J. [Consolidated Technical Services, Inc., Frederick, MD (United States); Connolly, M.J.; Becker, G.K. [Lockheed Martin Idaho Technologies Company, Idaho Falls, ID (United States)

1997-11-01

Measurement facilities performing nondestructive assay (NDA) of wastes intended for disposal at the United States Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) are required to demonstrate their ability to meet specific Quality Assurance Objectives (QAOs). This demonstration is performed, in part, by participation in the NDA Performance Demonstration Program (PDP). The PDP is funded and managed by the Carlsbad Area Office (CAO) of DOE and is conducted by the Idaho National Engineering Laboratory. It tests the characteristics of precision, system bias and/or total uncertainty through the measurement of variable, blind combinations of simulated waste drums and certified radioactive standards. Each facility must successfully participate in the PDP using each different type of measurement system planned for use in waste characterization. The first cycle of the PDP using each different type of measurement system planned for use in waste characterization. The first cycle of the PDP was completed in July 1996 and the second is scheduled for completion by December 1996. Seven sites reported data in cycle 1 for 11 different measurement systems. This paper describes the design and operation of the PDP and provides the performance data from cycle 1. It also describes the preliminary results from cycle 2 and updates the status and future plans for the NDA PDP. 4 refs., 9 figs., 11 tabs.

Automated instruments for in-line accounting of highly enriched uranium at the Oak Ridge Y-12 Plant

International Nuclear Information System (INIS)

Russo, P.A.; Strittmatter, R.B.; Sandford, E.L.; Stephens, M.M.; Brumfield, T.L.; Smith, S.E.; McCullough, E.E.; Jeter, I.W.; Bowers, G.L.

1985-02-01

Two automated nondestructive assay instruments developed at Los Alamos in support of nuclear materials accounting needs are currently operating in-line at the Oak Ridge Y-12 facility for recovery of highly enriched uranium (HEU). One instrument provides the HEU inventory in the secondary solvent extraction system, and the other monitors HEU concentration in the secondary intermediate evaporator. Both instruments were installed in December 1982. Operational evaluation of these instruments was a joint effort of Y-12 and Los Alamos personnel. This evaluation included comparison of the solvent extraction system inventories with direct measurements performed on the dumped solution components of the solvent extraction system and comparison of concentration assay results with the external assays of samples withdrawn from the process. The function and design of the instruments and detailed results of the operational evaluation are reported

Experimental program for development and evaluation of nondestructive assay techniques for plutonium holdup

International Nuclear Information System (INIS)

Brumbach, S.B.

1977-05-01

An outline is presented for an experimental program to develop and evaluate nondestructive assay techniques applicable to holdup measurement in plutonium-containing fuel fabrication facilities. The current state-of-the-art in holdup measurements is reviewed. Various aspects of the fuel fabrication process and the fabrication facility are considered for their potential impact on holdup measurements. The measurement techniques considered are those using gamma-ray counting, neutron counting, and temperature measurement. The advantages and disadvantages of each technique are discussed. Potential difficulties in applying the techniques to holdup measurement are identified. Experiments are proposed to determine the effects of such problems as variation in sample thickness, in sample distribution, and in background radiation. These experiments are also directed toward identification of techniques most appropriate to various applications. Also proposed are experiments to quantify the uncertainties expected for each measurement

Safeguards instrumentation: past, present, future

International Nuclear Information System (INIS)

Higinbotham, W.A.

1982-01-01

Instruments are essential for accounting, for surveillance and for protection of nuclear materials. The development and application of such instrumentation is reviewed, with special attention to international safeguards applications. Active and passive nondestructive assay techniques are some 25 years of age. The important advances have been in learning how to use them effectively for specific applications, accompanied by major advances in radiation detectors, electronics, and, more recently, in mini-computers. The progress in seals has been disappointingly slow. Surveillance cameras have been widely used for many applications other than safeguards. The revolution in TV technology will have important implications. More sophisticated containment/surveillance equipment is being developed but has yet to be exploited. On the basis of this history, some expectations for instrumentation in the near future are presented

Transuranic and Low-Level Boxed Waste Form Nondestructive Assay Technology Overview and Assessment

International Nuclear Information System (INIS)

Becker, G.; Connolly, M.; McIlwain, M.

1999-01-01

The Mixed Waste Focus Area (MWFA) identified the need to perform an assessment of the functionality and performance of existing nondestructive assay (NDA) techniques relative to the low-level and transuranic waste inventory packaged in large-volume box-type containers. The primary objectives of this assessment were to: (1) determine the capability of existing boxed waste form NDA technology to comply with applicable waste radiological characterization requirements, (2) determine deficiencies associated with existing boxed waste assay technology implementation strategies, and (3) recommend a path forward for future technology development activities, if required. Based on this assessment, it is recommended that a boxed waste NDA development and demonstration project that expands the existing boxed waste NDA capability to accommodate the indicated deficiency set be implemented. To ensure that technology will be commercially available in a timely fashion, it is recommended this development and demonstration project be directed to the private sector. It is further recommended that the box NDA technology be of an innovative design incorporating sufficient NDA modalities, e.g., passive neutron, gamma, etc., to address the majority of the boxed waste inventory. The overall design should be modular such that subsets of the overall NDA system can be combined in optimal configurations tailored to differing waste types

Synchrotron radiation microtomography of musical instruments: a non-destructive monitoring technique for insect infestations

Directory of Open Access Journals (Sweden)

Beatrice Bentivoglio-Ravasio

2011-08-01

Full Text Available X-ray computed tomography is becoming a common technique for the structural analysis of samples of cultural relevance, providing luthiers, art historians, conservators and restorators with a unique tool for the characterization of musical instruments. Synchrotron-radiation phase-contrast microtomography is an ideal technique for the non-destructive 3D analysis of samples where small lowabsorbing details such as larvae and eggs can be detected. We report results from the first feasibility studies performed at the Elettra synchrotron laboratory, where the 1494 organ by Lorenzo Gusnasco da Pavia has been studied. Together with important information about the structural conditions, the presence of xylophages could be detected and characterized.

Use of calibration standards and the correction for sample self-attenuation in gamma-ray nondestructive assay

International Nuclear Information System (INIS)

Parker, J.L.

1984-08-01

The efficient use of appropriate calibration standards and the correction for the attenuation of the gamma rays within an assay sample by the sample itself are two important and closely related subjects in gamma-ray nondestructive assay. Much research relating to those subjects has been done in the Nuclear Safeguards Research and Development program at the Los Alamos National Laboratory since 1970. This report brings together most of the significant results of that research. Also discussed are the nature of appropriate calibration standards and the necessary conditions on the composition, size, and shape of the samples to allow accurate assays. Procedures for determining the correction for the sample self-attenuation are described at length including both general principles and several specific useful cases. The most useful concept is that knowing the linear attenuation coefficient of the sample (which can usually be determined) and the size and shape of the sample and its position relative to the detector permits the computation of the correction factor for the self-attenuation. A major objective of the report is to explain how the procedures for determining the self-attenuation correction factor can be applied so that calibration standards can be entirely appropriate without being particularly similar, either physically or chemically, to the items to be assayed. This permits minimization of the number of standards required to assay items with a wide range of size, shape, and chemical composition. 17 references, 18 figures, 2 tables

Statistical signal processing and artificial intelligence applications in the nondestructive assay of U/Pu bearing materials

International Nuclear Information System (INIS)

Aumeier, S.E.; Forsmann, J.H.

1997-01-01

Over the years a number of techniques have been developed to determine the quantity and distribution of radiative isotopes contained in given assay samples through the measurement and analysis of penetrating characteristic radiations. An active technique of particular utility when assaying samples containing very small quantities of fissionable material or when high gamma ray backgrounds are encountered is the delayed neutron nondestructive assay (DN-NDA) technique. Typically, analysis of the delayed neutron signal involves relating the gross delayed neutron count observed following neutron irradiation of an assay sample to total fissionable material present via a linear calibration curve. In this way, the technique is capable of yielding the mass of a single dominant fissionable isotope or the total fissionable mass contained in a sample. Using this approach the only way to determine the mass of individual fissionable isotopes contained in a sample is to correlate total fissionable mass to individual isotopics via calculations or other means, yielding an indirect measure of isotopics. However, there is isotope specific information in the temporal delayed neutron signal due to differences in the delayed neutron precursor yields resulting from the fissioning of different isotopes. The authors present the results of an analysis to evaluate the feasibility of using Kalman filters and genetic algorithms to determine multiple specific fissionable isotopic masses contained in an assay sample from a cumulative delayed neutron signal measured following neutron irradiation of the sample

Nondestructive evaluation of a new hydrolytically degradable and photo-clickable PEG hydrogel for cartilage tissue engineering.

Science.gov (United States)

Neumann, Alexander J; Quinn, Timothy; Bryant, Stephanie J

2016-07-15

increase in mechanical properties. Nondestructive assays based on mechanical and ultrasonic properties were also investigated using a novel instrument and found to correlate with matrix deposition and evolution. In sum, this study presents a new hydrogel platform combined with nondestructive assessments, which together have potential for in vitro cartilage tissue engineering. Copyright © 2016 Acta Materialia Inc. All rights reserved.

A technical study of alloy compositions of "brass" wind musical instruments (1651-1867) utilizing non-destructive X-ray fluorescence

Science.gov (United States)

Bacon, Alice Louise

This thesis represents a new interdisciplinary approach to the conservation, care and curatorial study of 'brass' wind musical instruments. It attempts to combine metallurgical, chronological and historical aspects for a selection of instruments. The research consists of the systematic study of seventy-seven musical instruments, by known makers, using standardised non-destructive energy dispersive x-ray fluorescence (XRF). Such compositional data are virtually non-existent for historical 'brass' instruments in Britain and what few technical data that do exist are sporadic in quantity and quality. The development of brass instruments is interwoven with the history of brass making, but because there are a limited number of appropriate examples such links can be difficult to identify. This thesis describes the development of brass production from the cementation process to the commercial production of zinc and modern brass. Its relationship to the musical instrument industry in Britain is linked with historical evidence. It will be shown that innovation and known historical metallurgical achievements are reflected in the compositional changes of the alloys used for musical instruments. This thesis focuses on specific named brass wind musical instrument makers. This thesis sets out to investigate the extent to which a single analytical technique such as non-destructive analysis utilising XRF could be useful in the curatorial and conservation care of musical instruments. The results of the analyses revealed new aspects to the use of metals for making musical instruments. They give new information on approximate alloy compositions and, in particular, the results have shown that in the seventeenth-century in England, a ternary alloy of copper/tin/zinc was used, and that it was, perhaps, only superseded by brass (copper/zinc alloy) in the eighteenth century. It has been possible to arrange the results into a chronology of alloys particularly reflecting the change from the

Gamma ray scanner systems for nondestructive assay of heterogeneous waste barrels

International Nuclear Information System (INIS)

Martz, H.E.; Decman, B.J.; Roberson, G.P.; Levai, F.

1997-01-01

Traditional gamma safeguards measurements have usually been performed using a segmented gamma scanning (SGS) system. The accuracy of this technique relies on the assumption that the sample matrix and the activity are both uniform for a segment. Waste barrels are often highly heterogeneous, span a wide range of composition and matrix type. The primary sources of error are all directly or indirectly related to a non-uniform measurement response associated with unknown radioactive source spatial distribution and heterogeneity of the matrix. These errors can be significantly reduced by some imaging techniques that measure exact spatial locations of sources and attenuation maps. In this paper we describe a joint R ampersand D effort between the Lawrence Livermore National Laboratory (LLNL) and the Institute of Nuclear Techniques (INT) of the Technical University, Budapest, to compare results obtained by two different gamma-ray nondestructive assay (NDA) systems used for imaging waste barrels. The basic principles are the same, but the approaches are different. Key factors to judge the adequacy of a method are the detection limit and the accuracy. Test drums representing waste to be measured are used to determine basic parameters of these techniques

Non-destructive elecrochemical monitoring of reinforcement corrosion

DEFF Research Database (Denmark)

Nygaard, Peter Vagn

been widely accepted as a non-destructive ”state of the art” technique for detection of corrosion in concrete structures. And, over the last decade, the trend in corrosion monitoring has moved towards quantitative non-destructive monitoring of the corrosion rate of the steel reinforcement. A few...... corrosion rate measurement instruments have been developed and are commercially available. The main features of these instruments are the combined use of an electrochemical technique for determining the corrosion rate and a so-called ”confinement technique”, which in principle controls the polarised surface...... area of the reinforcement, i.e. the measurement area. Both on-site investigations and laboratory studies have shown that varying corrosion rates are obtained when the various commercially available instruments are used. And in the published studies, conflicting explanations are given illustrating...

Conceptual design of the special nuclear material nondestructive assay and accountability system for the HTGR fuel refabrication pilot plant

International Nuclear Information System (INIS)

Jenkins, J.D.; McNeany, S.R.; Rushton, J.E.

1975-07-01

The conceptual design of the fissile material assay and accountability system for the HTGR refabrication pilot plant has been established. The primary feature affecting the design is the high, time varying, gamma activity of the process material due to the unavoidable presence of uranium-232. This imposes stringent requirements for remote operation and remote maintainability of system components. At the same time, the remote operation lends itself to implementation of an automated data collection and processing system for real-time accountability. The high time-varying gamma activity of the material also precludes application of a number of techniques presently employed for light-water reactor fuel assay. The techniques selected for application in the refabrication facility are (1) active thermal neutron interrogation with fast-fission or delayed-neutron counting for fuel-rod and small-sample assay, (2) calorimetry for high-level waste assay, and (3) passive gamma scanning for low-level waste assay, and rapid on-line relative rod-loading measurements. The principal nondestructive assay subsystems are identified as (1) on-line devices for 100 percent product fuel rod assay and quality control, (2) a multipurpose device in the sample inspection laboratory for small- sample assay and secondary standards calibration, and (3) equipment for assay of high- and low-uranium content scrap and waste materials. A data processing system, which coordinates data from these subsystems with information from other process control sensors, is included to provide real-time material balance information. (U.S.)

Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program

International Nuclear Information System (INIS)

2009-01-01

Each testing and analytical facility performing waste characterization activities for the Waste Isolation Pilot Plant (WIPP) participates in the Performance Demonstration Program (PDP) to comply with the Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC) (DOE/WIPP-02-3122) and the Quality Assurance Program Document (QAPD) (CBFO-94-1012). The PDP serves as a quality control check for data generated in the characterization of waste destined for WIPP. Single blind audit samples are prepared and distributed to each of the facilities participating in the PDP. The PDP evaluates analyses of simulated headspace gases, constituents of the Resource Conservation and Recovery Act (RCRA), and transuranic (TRU) radionuclides using nondestructive assay (NDA) techniques.

Possible checking of technical parameters in nondestructive materials and products testing

International Nuclear Information System (INIS)

Kesl, J.

1987-01-01

The requirements are summed up for partial technical parameters of instruments and facilities for nondestructive testing by ultrasound, radiography, by magnetic, capillary and electric induction methods. The requirements and procedures for testing instrument performance are presented for the individual methods as listed in domestic and foreign standards, specifications and promotional literature. The parameters to be tested and the methods of testing, including the testing and calibration instruments are shown in tables. The Czechoslovak standards are listed currently valid for nondestructive materials testing. (M.D.)

The use of calibration standards and the correction for sample self-attenuation in gamma-ray nondestructive assay

International Nuclear Information System (INIS)

Parker, J.L.

1986-11-01

The efficient use of appropriate calibration standards and the correction for the attenuation of the gamma rays within an assay sample by the sample itself are two important and closely related subjects in gamma-ray nondestructive assay. Much research relating to those subjects has been done in the Nuclear Safeguards Research and Development program at the Los Alamos National Laboratory since 1970. This report brings together most of the significant results of that research. Also discussed are the nature of appropriate calibration standards and the necessary conditions on the composition, size, and shape of the samples to allow accurate assays. Procedures for determining the correction for the sample self-attenuation are described at length including both general principles and several specific useful cases. The most useful concept is that knowing the linear attenuation coefficient of the sample (which can usually be determined) and the size and shape of the sample and its position relative to the detector permits the computation of the correction factor for the self-attenuation. A major objective of the report is to explain how the procedures for determining the self-attenuation correction factor can be applied so that calibration standards can be entirely appropriate without being particularly similar, either physically or chemically, to the items to be assayed. This permits minimization of the number of standards required to assay items with a wide range of size, shape, and chemical composition

Nondestructive assay of HTGR fuel rods

International Nuclear Information System (INIS)

Menlove, H.O.

1974-01-01

Performance characteristics of three different radioactive source NDA systems are compared for the assay of HTGR fuel rods and stacks of rods. These systems include the fast neutron Sb-Be assay system, the 252 Cf ''Shuffler,'' and the thermal neutron PAPAS assay system. Studies have been made to determinethe perturbation on the measurements from particle size, kernel Th/U ratio, thorium content, and hydrogen content. In addition to the total 235 U determination, the pellet-to-pellet or rod-to-rod uniformity of HTGR fuel rod stacks has been measured by counting the delayed gamma rays with a NaI through-hole in the PAPAS system. These measurements showed that rod substitutions can be detected easily in a fuel stack, and that detailed information is available on the loading variations in a uniform stack. Using a 1.0 mg 252 Cf source, assay rates of 2 to 4 rods/s are possible, thus facilitating measurement of 100 percent of a plant's throughput. (U.S.)

Delayed Gamma-Ray Spectroscopy for Non-Destructive Assay of Nuclear Materials

International Nuclear Information System (INIS)

Ludewigt, Bernhard; Mozin, Vladimir; Campbell, Luke; Favalli, Andrea; Hunt, Alan W.; Reedy, Edward T.E.; Seipel, Heather

2015-01-01

High-energy, beta-delayed gamma-ray spectroscopy is a potential, non-destructive assay techniques for the independent verification of declared quantities of special nuclear materials at key stages of the fuel cycle and for directly assaying nuclear material inventories for spent fuel handling, interim storage, reprocessing facilities, repository sites, and final disposal. Other potential applications include determination of MOX fuel composition, characterization of nuclear waste packages, and challenges in homeland security and arms control verification. Experimental measurements were performed to evaluate fission fragment yields, to test methods for determining isotopic fractions, and to benchmark the modeling code package. Experimental measurement campaigns were carried out at the IAC using a photo-neutron source and at OSU using a thermal neutron beam from the TRIGA reactor to characterize the emission of high-energy delayed gamma rays from 235 U, 239 Pu, and 241 Pu targets following neutron induced fission. Data were collected for pure and combined targets for several irradiation/spectroscopy cycle times ranging from 10/10 seconds to 15/30 minutes.The delayed gamma-ray signature of 241 Pu, a significant fissile constituent in spent fuel, was measured and compared to 239 Pu. The 241 Pu/ 239 Pu ratios varied between 0.5 and 1.2 for ten prominent lines in the 2700-3600 keV energy range. Such significant differences in relative peak intensities make it possible to determine relative fractions of these isotopes in a mixed sample. A method for determining fission product yields by fitting the energy and time dependence of the delayed gamma-ray emission was developed and demonstrated on a limited 235 U data set. De-convolution methods for determining fissile fractions were developed and tested on the experimental data. The use of high count-rate LaBr 3 detectors was investigated as a potential alternative to HPGe detectors. Modeling capabilities were added to an

Methods for nondestructive assay holdup measurements in shutdown uranium enrichment facilities

International Nuclear Information System (INIS)

Hagenauer, R.C.; Mayer, R.L. II.

1991-09-01

Measurement surveys of uranium holdup using nondestructive assay (NDA) techniques are being conducted for shutdown gaseous diffusion facilities at the Oak Ridge K-25 Site (formerly the Oak Ridge Gaseous Diffusion Plant). When in operation, these facilities processed UF 6 with enrichments ranging from 0.2 to 93 wt % 235 U. Following final shutdown of all process facilities, NDA surveys were initiated to provide process holdup data for the planning and implementation of decontamination and decommissioning activities. A three-step process is used to locate and quantify deposits: (1) high-resolution gamma-ray measurements are performed to generally define the relative abundances of radioisotopes present, (2) sizable deposits are identified using gamma-ray scanning methods, and (3) the deposits are quantified using neutron measurement methods. Following initial quantitative measurements, deposit sizes are calculated; high-resolution gamma-ray measurements are then performed on the items containing large deposits. The quantitative estimates for the large deposits are refined on the basis of these measurements. Facility management is using the results of the survey to support a variety of activities including isolation and removal of large deposits; performing health, safety, and environmental analyses; and improving facility nuclear material control and accountability records. 3 refs., 1 tab

Analysis of Radiation Accident of Non-destructive Inspection and Rational Preparing Bills

International Nuclear Information System (INIS)

Bae, Junwoo; Yoo, Donghan; Kim, Hee Reyoung

2013-01-01

After 2006, according to enactment of Non-destructive Inspection Promotion Act, the number of non-destructive inspection companies and corresponding accident is increased sharply. In this research, it includes characteristic analysis of field of the non-destructive inspection. And from the result of analysis, the purpose of this research is discovering reason for 'Why there is higher accident ratio in non-destructive inspection field, relatively' and preparing effective bill for reducing radiation accidents. The number of worker for non-destructive inspect is increased steadily and non-destructive inspect worker take highest dose. Corresponding to these, it must be needed to prepare bills to protect non-destructive inspect workers. By analysis of accident case, there are many case of carelessness that tools are too heavy to carry it everywhere workers go. And there are some cases caused by deficiency of education that less understanding of radiation and poor operation by less understanding of structure of tools. Also, there is no data specialized to non-destructive inspect field. So, it has to take information from statistical data. Because of this, it is hard to analyze nondestructive inspect field accurately. So, it is required to; preparing rational bills to protect non-destructive inspect workers nondestructive inspect instrument lightening and easy manual which can understandable for low education background people accurate survey data from real worker. To accomplish these, we needs to do; analyze and comprehend the present law about non-destructive inspect worker understand non-destructive inspect instruments accurately and conduct research for developing material developing rational survey to measuring real condition for non-destructive inspect workers

Stationary and protable instruments for assay of HEU [highly enriched uranium] solids holdup

International Nuclear Information System (INIS)

Russo, P.A.; Sprinkle, J.K. Jr.; Stephens, M.M.; Brumfield, T.L.; Gunn, C.S.; Watson, D.R.

1987-01-01

Two NaI(Tl)-based instruments, one stationary and one portable, designed for automated assay of highly enriched uranium (HEU) solids holdup, are being evaluated at the scrap recovery facility of the Oak Ridge Y-12 Plant. The stationary instrument, a continuous monitor of HEU within the filters of the chip burner exhaust system, measures the HEU deposits that accumulate erratically and rapidly during chip burner operation. The portable system was built to assay HEU in over 100 m of elevated piping used to transfer UO 3 , UO 2 , and UF 4 powder to, from, and between the fluid bed conversion furnances and the powder storage hoods. Both instruments use two detector heads. Both provide immediate automatic readout of accumulated HEU mass. The 186-keV 235 U gamma ray is the assay signature, and the 60-keV gamma ray from an 241 Am source attached to each detector is used to normalize the 186-keV rate. The measurement geometries were selected for compatibility with simple calibration models. The assay calibrations were calculated from these models and were verified and normalized with measurements of HEU standards built to match geometries of uniform accumulations on the surfaces of the process equipment. This instrumentation effort demonstrates that simple calibration models can often be applied to unique measurement geometries, minimizing the otherwise unreasonable requirements for calibration standards and allowing extension of the measurements to other process locations

Non destructive assay (NDA) techniques

International Nuclear Information System (INIS)

Mafra Guidicini, Olga; Llacer, Carlos D.; Rojo, Marcelo

2001-01-01

In the IAEA Safeguards System the basic verification method used is nuclear material accountancy, with containment and surveillance as important complementary measures. If nuclear material accountancy is to be effective, IAEA inspectors have to make independent measurements to verify declared material quantities. Most of the equipment available to the inspectors is designed to measure gamma rays and/or neutrons emitted by various nuclear materials. Equipment is also available to measure the gross weight of an item containing nuclear material. These types of measurement techniques are generally grouped under the title of nondestructive assay (NDA). The paper describes the NDA techniques and instruments used to verify the total amount of nuclear material held at a nuclear facility. (author)

Quality Assistance Objectives for Nondestructive Assay at the Waste Receiving and Processing (WRAP) Facility

International Nuclear Information System (INIS)

CANTALOUB, M.G.

2000-01-01

The Waste Receiving and Processing (WRAP) facility, located on the Word Site in southeast Washington, is a key link in the certification of transuranic (TRU) waste for shipment to the Waste Isolation Pilot Plant (WIPP). Waste characterization is one of the vital functions performed at WRAP, and nondestructive assay (NDA) measurements of TRU waste containers is one of two required methods used for waste characterization. The Waste Acceptance Criteria for the Waste Isolation Pilot Plant, DOE/WIPP-069 (WIPP-WAC) delineates the quality assurance objectives which have been established for NDA measurement systems. Sites must demonstrate that the quality assurance objectives can be achieved for each radioassay system over the applicable ranges of measurement. This report summarizes the validation of the WRAP NDA systems against the radioassay quality assurance objectives or QAOs. A brief description of the each test and significant conclusions are included. Variables that may have affected test outcomes and system response are also addressed

Transuranic waste assay instrumentation: new developments and directions at the Los Alamos Scientific Laboratory

Energy Technology Data Exchange (ETDEWEB)

Close, D.A.; Umbarger, C.J.; West, L.; Smith, W.J.; Cates, M.R.; Noel, B.W.; Honey, F.J.; Franks, L.A.; Pigg, J.L.; Trundle, A.S.

1978-01-01

The Los Alamos Scientific Laboratory is developing assay instrumentation for the quantitative analysis of transuranic materials found in bulk solid wastes generated by Department of Energy facilities and by the commercial nuclear power industry. This also includes wastes generated in the decontamination and decommissioning of facilities and wastes generated during burial ground exhumation. The assay instrumentation will have a detection capability for the transuranics of less than 10 nCi of activity per gram of waste whenever practicable.

Transuranic waste assay instrumentation: new developments and directions at the Los Alamos Scientific Laboratory

International Nuclear Information System (INIS)

Close, D.A.; Umbarger, C.J.; West, L.; Smith, W.J.; Cates, M.R.; Noel, B.W.; Honey, F.J.; Franks, L.A.; Pigg, J.L.; Trundle, A.S.

1978-01-01

The Los Alamos Scientific Laboratory is developing assay instrumentation for the quantitative analysis of transuranic materials found in bulk solid wastes generated by Department of Energy facilities and by the commercial nuclear power industry. This also includes wastes generated in the decontamination and decommissioning of facilities and wastes generated during burial ground exhumation. The assay instrumentation will have a detection capability for the transuranics of less than 10 nCi of activity per gram of waste whenever practicable

Analytical evaluation of the automated galectin-3 assay on the Abbott ARCHITECT immunoassay instruments.

Science.gov (United States)

Gaze, David C; Prante, Christian; Dreier, Jens; Knabbe, Cornelius; Collet, Corinne; Launay, Jean-Marie; Franekova, Janka; Jabor, Antonin; Lennartz, Lieselotte; Shih, Jessie; del Rey, Jose Manuel; Zaninotto, Martina; Plebani, Mario; Collinson, Paul O

2014-06-01

Galectin-3 is secreted from macrophages and binds and activates fibroblasts forming collagen. Tissue fibrosis is central to the progression of chronic heart failure (CHF). We performed a European multicentered evaluation of the analytical performance of the two-step routine and Short Turn-Around-Time (STAT) galectin-3 immunoassay on the ARCHITECT i1000SR, i2000SR, and i4000SR (Abbott Laboratories). We evaluated the assay precision and dilution linearity for both routine and STAT assays and compared serum and plasma, and fresh vs. frozen samples. The reference interval and biological variability were also assessed. Measurable samples were compared between ARCHITECT instruments and between the routine and STAT assays and also to a galectin-3 ELISA (BG Medicine). The total assay coefficient of variation (CV%) was 2.3%-6.2% and 1.7%-7.4% for the routine and STAT assays, respectively. Both assays demonstrated linearity up to 120 ng/mL. Galectin-3 concentrations were higher in plasma samples than in serum samples and correlated well between fresh and frozen samples (R=0.997), between the routine and STAT assays, between the ARCHITECT i1000 and i2000 instruments and with the galectin-3 ELISA. The reference interval on 627 apparently healthy individuals (53% male) yielded upper 95th and 97.5th percentiles of 25.2 and 28.4 ng/mL, respectively. Values were significantly lower in subjects younger than 50 years. The galectin-3 routine and STAT assays on the Abbott ARCHITECT instruments demonstrated good analytical performance. Further clinical studies are required to demonstrate the diagnostic and prognostic potential of this novel marker in patients with CHF.

Intelligent data-acquisition instrumentation for special nuclear material assay data analysis

International Nuclear Information System (INIS)

Ethridge, C.D.

1980-01-01

The Detection, Surveillance, Verification, and Recovery Group of the Los Alamos Scientific Laboratory Energy Division/Nuclear Safeguards Programs is now utilizing intelligent data-acquisition instrumentation for assay data analysis of special nuclear material. The data acquisition and analysis are enabled by the incorporation of a number-crunching microprocessor sequenced by a single component microcomputer. Microcomputer firmware establishes the capability for processing the computation of several selected functions and also the ability of instrumentation self-diagnostics

Developing Spent Fuel Assembly for Advanced NDA Instrument Calibration - NGSI Spent Fuel Project

Energy Technology Data Exchange (ETDEWEB)

Hu, Jianwei [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gauld, Ian C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Banfield, James [GE Hitachi Nuclear Energy, Wilmington, NC (United States); Skutnik, Steven [Univ. of Tennessee, Knoxville, TN (United States)

2014-02-01

This report summarizes the work by Oak Ridge National Laboratory to investigate the application of modeling and simulation to support the performance assessment and calibration of the advanced nondestructive assay (NDA) instruments developed under the Next Generation Safeguards Initiative Spent Fuel (NGSI-SF) Project. Advanced NDA instrument calibration will likely require reference spent fuel assemblies with well-characterized nuclide compositions that can serve as working standards. Because no reference spent fuel standard currently exists, and the practical ability to obtain direct measurement of nuclide compositions using destructive assay (DA) measurements of an entire fuel assembly is prohibitive in the near term due to the complexity and cost of spent fuel experiments, modeling and simulation will be required to construct such reference fuel assemblies. These calculations will be used to support instrument field tests at the Swedish Interim Storage Facility (Clab) for Spent Nuclear Fuel.

Quality evaluation of fish and other seafood by traditional and nondestructive instrumental methods: Advantages and limitations.

Science.gov (United States)

Hassoun, Abdo; Karoui, Romdhane

2017-06-13

Although being one of the most vulnerable and perishable products, fish and other seafoods provide a wide range of health-promoting compounds. Recently, the growing interest of consumers in food quality and safety issues has contributed to the increasing demand for sensitive and rapid analytical technologies. Several traditional physicochemical, textural, sensory, and electrical methods have been used to evaluate freshness and authentication of fish and other seafood products. Despite the importance of these standard methods, they are expensive and time-consuming, and often susceptible to large sources of variation. Recently, spectroscopic methods and other emerging techniques have shown great potential due to speed of analysis, minimal sample preparation, high repeatability, low cost, and, most of all, the fact that these techniques are noninvasive and nondestructive and, therefore, could be applied to any online monitoring system. This review describes firstly and briefly the basic principles of multivariate data analysis, followed by the most commonly traditional methods used for the determination of the freshness and authenticity of fish and other seafood products. A special focus is put on the use of rapid and nondestructive techniques (spectroscopic techniques and instrumental sensors) to address several issues related to the quality of these products. Moreover, the advantages and limitations of each technique are reviewed and some perspectives are also given.

Nondestructive characterization of low-level transuranic waste

International Nuclear Information System (INIS)

Barna, B.A.; Reinhardt, W.W.

1981-10-01

The use of nondestructive evaluation (NDE) methods is proposed for characterization of transuranic (TRU) waste stored at the Radioactive Waste Management Complex. These NDE methods include real-time x-ray radiography, real-time neutron radiography, x-ray and neutron computed tomography, thermal imaging, container weighing, visual examination, and acoustic measurements. An integrated NDE system is proposed for characterization and certification of TRU waste destined for eventual shipment to the Waste Isolation Pilot Plant in New Mexico. Methods for automating both the classification waste and control of a complete nondestructive evaluation/nondestructive assay system are presented. Feasibility testing of the different NDE methods, including real-time x-ray radiography, and development of automated waste classification techniques are covered as part of a five year effort designed to yield a production waste characterization system

Quantifying the passive gamma signal from spent nuclear fuel in support of determining the plutonium content in spent nuclear fuel with nondestructive assay

Energy Technology Data Exchange (ETDEWEB)

Fensin, Michael L [Los Alamos National Laboratory; Tobin, Steven J [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory

2009-01-01

The objective of safeguarding nuclear material is to deter diversions of significant quantities of nuclear materials by timely monitoring and detection. There are a variety of motivations for quantifying plutonium in spent fuel (SF), by means of nondestructive assay (NDA), in order to meet this goal. These motivations include the following: strengthening the capabilities of the International Atomic Energy Agencies ability to safeguard nuclear facilities, shipper/receiver difference, input accountability at reprocessing facilities and burnup credit at repositories. Many NDA techniques exist for measuring signatures from SF; however, no single NDA technique can, in isolation, quantify elemental plutonium in SF. A study has been undertaken to determine the best integrated combination of 13 NDA techniques for characterizing Pu mass in spent fuel. This paper focuses on the development of a passive gamma measurement system in support the spent fuel assay system. Gamma ray detection for fresh nuclear fuel focuses on gamma ray emissions that directly coincide with the actinides of interest to the assay. For example, the 186-keV gamma ray is generally used for {sup 235}U assay and the 384-keV complex is generally used for assaying plutonium. In spent nuclear fuel, these signatures cannot be detected as the Compton continuum created from the fission products dominates the signal in this energy range. For SF, the measured gamma signatures from key fission products ({sup 134}Cs, {sup 137}Cs, {sup 154}Eu) are used to ascertain burnup, cooling time, and fissile content information. In this paper the Monte Carlo modeling set-up for a passive gamma spent fuel assay system will be described. The set-up of the system includes a germanium detector and an ion chamber and will be used to gain passive gamma information that will be integrated into a system for determining Pu in SF. The passive gamma signal will be determined from a library of {approx} 100 assemblies that have been

Authentication of nuclear-material assays made with in-plant instruments

International Nuclear Information System (INIS)

Hatcher, C.R.; Hsue, S.T.; Russo, P.A.

1982-01-01

This paper develops a general approach for International Atomic Energy Agency (IAEA) authentication of nuclear material assays made with in-plant instruments under facility operator control. The IAEA is evaluating the use of in-plant instruments as a part of international safeguards at large bulk-handling facilities, such as reprocessing plants, fuel fabrication plants, and enrichment plants. One of the major technical problems associated with IAEA use of data from in-plant instruments is the need to show that there has been no tampering with the measurements. Two fundamentally different methods are discussed that can be used by IAEA inspectors to independently verify (or authenticate) measurements made with in-plant instruments. Method 1, called external authentication, uses a protected IAEA measurement technique to compare in-plant instrument results with IAEA results. Method 2, called internal authentication, uses protected IAEA standards, known physical constants, and special test procedures to determine the performance characteristics of the in-plant instrument. The importance of measurement control programs to detect normally expected instrument failures and procedural errors is also addressed. The paper concludes with a brief discussion of factors that should be considered by the designers of new in-plant instruments in order to facilitate IAEA authentication procedures

Method for nondestructive fuel assay of laser fusion targets

Science.gov (United States)

Farnum, Eugene H.; Fries, R. Jay

1976-01-01

A method for nondestructively determining the deuterium and tritium content of laser fusion targets by counting the x rays produced by the interaction of tritium beta particles with the walls of the microballoons used to contain the deuterium and tritium gas mixture under high pressure. The x rays provide a direct measure of the tritium content and a means for calculating the deuterium content using the initial known D-T ratio and the known deuterium and tritium diffusion rates.

Edward's sword? - A non-destructive study of a medieval king's sword

Science.gov (United States)

Segebade, Chr.

2013-04-01

Non-destructive and instrumental methods including photon activation analysis were applied in an examination of an ancient sword. It was tried to find indication of forgery or, if authentic, any later processing and alteration. Metal components of the hilt and the blade were analysed by instrumental photon activation. Non-destructive metallurgical studies (hardness measurements, microscopic microstructure analysis) are briefly described, too. The results of these investigations did not yield indication of non-authenticity. This stood in agreement with the results of stylistic and scientific studies by weapon experts.

Delayed Gamma-Ray Spectroscopy for Non-Destructive Assay of Nuclear Materials

Energy Technology Data Exchange (ETDEWEB)

Ludewigt, Bernhard [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Mozin, Vladimir [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Campbell, Luke [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Favalli, Andrea [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hunt, Alan W. [Idaho State Univ., Pocatello, ID (United States); Reedy, Edward T. [Idaho State Univ., Pocatello, ID (United States); Seipel, Heather A. [Idaho State Univ., Pocatello, ID (United States)

2015-06-01

Modeling capabilities were added to an existing framework and codes were adapted as needed for analyzing experiments and assessing application-specific assay concepts including simulation of measurements over many short irradiation/spectroscopy cycles. The code package was benchmarked against the data collected at the IAC for small targets and assembly-scale data collected at LANL. A study of delayed gamma-ray spectroscopy for nuclear safeguards was performed for a variety of assemblies in the extensive NGSI spent fuel library. The modeling results indicate that delayed gamma-ray responses can be collected from spent fuel assemblies with statistical quality sufficient for analyzing their isotopic composition using a 10¹¹ n/s neutron generator and COTS detector instrumentation.

Calorimetric systems designed for in-field nondestructive assay of plutonium-bearing materials

International Nuclear Information System (INIS)

Roche, C.T.; Perry, R.B.; Lewis, R.N.; Jung, E.A.; Haumann, J.R.

1978-01-01

Conventional calorimetric design measures the temperature rise of a plutonium-containing sample chamber in contact with a large water-bath heat sink. This design lacks the mobility needed by inspection personnel. The Argonne National Laboratory air-chamber isothermal calorimeters are low-thermal capacitance devices which eliminate the need for large, constant-temperature heat sinks. A bulk calorimeter designed to measure sealed containers holding up to 3 kg Pu, and a small-sample calorimeter designed to measure mixed-oxide fuel pellets and powders are discussed. The operational characteristics of these instruments are described, and the results of sample assays are presented

Method for nondestructive fuel assay of laser fusion targets

International Nuclear Information System (INIS)

Farnum, E.H.; Fries, R.J.

1976-01-01

A method is described for nondestructively determining the deuterium and tritium content of laser fusion targets by counting the x rays produced by the interaction of tritium beta particles with the walls of the microballoons used to contain the deuterium and tritium gas mixture under high pressure. The x rays provide a direct measure of the tritium content and a means for calculating the deuterium content using the initial known D-T ratio and the known deuterium and tritium diffusion rates

TRU waste-assay instrumentation and application in nuclear-facility decommissioning

International Nuclear Information System (INIS)

Umbarger, C.J.

1982-01-01

The Los Alamos TRU waste assay program is developing measurement techniques for TRU and other radioactive waste materials generated by the nuclear industry, including decommissioning programs. Systems are now being fielded for test and evaluation purposes at DOE TRU waste generators. The transfer of this technology to other facilities and the commercial instrumentation sector is well in progress. 6 figures

SQUID-based Nondestructive Testing Instrument of Dished Niobium Sheets for SRF Cavities

International Nuclear Information System (INIS)

Q. S. Shu; I. Ben-Zvi; G. Cheng; I. M. Phipps; J. T. Susta; P. Kneisel; G. Myneni; J. Mast; R. Selim

2007-01-01

Currently available technology can only inspect flat sheets and allow the elimination of defective flat sheets before the expensive forming and machining of the SRF cavity half-cells, but it does not eliminate the problem of remaining or uncovered surface impurities after partial chemical etching of the half-cells, nor does it detect any defects that may have been added during the fabrication of the half-cells. AMAC has developed a SQUID scanning system based on eddy current technique that allows the scanning of curved Nb samples that are welded to make superconducting RF cavity half-cells. AMAC SQUID scanning system successfully located the defects (Ta macro particles about 100 mm diameter) in a flat Nb sample (top side) and was able to also locate the defects in a cylindrical surface sample (top side). It is more significant that the system successfully located the defects on the backside of the flat sample and curved sample or 3-mm from the top surface. The 3-D SQUID-based Nondestructive instrument will be further optimized and improved in making SRF cavities and allow inspection and detection during cavity manufacturing for achieving highest accelerating fields

Statistical uncertainties of nondestructive assay for spent nuclear fuel by using nuclear resonance fluorescence

Energy Technology Data Exchange (ETDEWEB)

Shizuma, Toshiyuki, E-mail: shizuma.toshiyuki@jaea.go.jp [Quantum Beam Science Directorate, Japan Atomic Energy Agency, Tokai, Ibaraki 319-1195 (Japan); Hayakawa, Takehito; Angell, Christopher T.; Hajima, Ryoichi [Quantum Beam Science Directorate, Japan Atomic Energy Agency, Tokai, Ibaraki 319-1195 (Japan); Minato, Futoshi; Suyama, Kenya [Nuclear Science and Engineering Directorate, Japan Atomic Energy Agency, Tokai, Ibaraki 319-1195 (Japan); Seya, Michio [Integrated Support Center for Nuclear Nonproliferation and Nuclear Security, Japan Atomic Energy Agency, Tokai, Ibaraki 319-1198 (Japan); Johnson, Micah S. [Lawrence Livermore National Laboratory, 7000 East Ave. Livermore, CA 94550 (United States); Department of Physics and Astronomy, San Jose State University, One Washington Square, San Jose, CA 9519 (United States); McNabb, Dennis P. [Lawrence Livermore National Laboratory, 7000 East Ave. Livermore, CA 94550 (United States)

2014-02-11

We estimated statistical uncertainties of a nondestructive assay system using nuclear resonance fluorescence (NRF) for spent nuclear fuel including low-concentrations of actinide nuclei with an intense, mono-energetic photon beam. Background counts from radioactive materials inside the spent fuel were calculated with the ORIGEN2.2-UPJ burn-up computer code. Coherent scattering contribution associated with Rayleigh, nuclear Thomson, and Delbrück scattering was also considered. The energy of the coherent scattering overlaps with that of NRF transitions to the ground state. Here, we propose to measure NRF transitions to the first excited state to avoid the coherent scattering contribution. Assuming that the total NRF cross-sections are in the range of 3–100 eV b at excitation energies of 2.25, 3.5, and 5 MeV, statistical uncertainties of the NRF measurement were estimated. We concluded that it is possible to assay 1% actinide content in the spent fuel with 2.2–3.2% statistical precision during 4000 s measurement time for the total integrated cross-section of 30 eV b at excitation energies of 3.5–5 MeV by using a photon beam with an intensity of 10{sup 6} photons/s/eV. We also examined both the experimental and theoretical NRF cross-sections for actinide nuclei. The calculation based on the quasi-particle random phase approximation suggests the existence of strong magnetic dipole resonances at excitation energies ranging from 2 to 6 MeV with the scattering cross-sections of tens eV b around 5 MeV in {sup 238}U.

Use of fuel reprocessing plant instrumentation for international safeguards

International Nuclear Information System (INIS)

Ayers, A.L.

1977-01-01

The International Atomic Energy Agency has a program for developing instrumentation to be used by safeguards inspectors at reprocessing facilities. These instruments have generally been individual pieces of equipment for improving the accuracy of existing measurement instrumentation or equipment to perform nondestructive assay on a selected basis. It is proposed that greater use be made of redundant plant instrumentation and data recovery systems that could augment plant instrumentation to verify the validity of plant measurements. Use of these methods for verfication must be proven as part of an operating plant before they can be relied upon for safeguards surveillance. Inspectors must be qualified in plant operations, or have ready access to those so qualified, if the integrity of the operation is to be properly assessed. There is an immediate need for the development and in-plant proof testing of an integrated gamma, passive neutron, and active neutron measurement system for drum quantities of radioactive trash. The primary safeguards effort should be limited to plutonium and highly enriched uranium

The use of calorimetry for plutonium assay

International Nuclear Information System (INIS)

Mason, J.A.

1982-12-01

Calorimetry is a technique for measuring the thermal power of heat-producing substances. The technique may be applied to the measurement of plutonium-bearing materials which evolve heat as a result of alpha and beta decay. A calorimetric measurement of the thermal power of a plutonium sample, combined with a knowledge or measurement of the plutonium isotopic mass ratios of the sample provides a convenient and accurate, non-destructive measure of the total plutonium mass of the sample. The present report provides a description, and an assessment of the calorimetry technique applied to the assay of plutonium-bearing materials. Types and characteristics of plutonium calorimeters are considered, as well as calibration and operating procedures. The instrumentation used with plutonium calorimeters is described and the use of computer control for calorimeter automation is discussed. A critical review and assessment of plutonium calorimetry literature since 1970 is presented. Both fuel element and plutonium-bearing material calorimeters are considered. The different types of plutonium calorimeters are evaluated and their relative merits are discussed. A combined calorimeter and gamma-ray measurement assay system is considered. The design principles of plutonium assay calorimeters are considered. An automatic, computer-based calorimeter control system is proposed in conjunction with a general plutonium assay calorimeter design. (author)

A comparison of conventional and prototype nondestructive measurements on molten salt extraction residues

International Nuclear Information System (INIS)

Longmire, V.L.; Hurd, J.R.; Sedlacek, W.E.; Scarborough, A.M.

1987-01-01

Fourteen molten salt extraction residues were assayed by conventional and prototype nondestructive assay (NDA) techniques to be compared with destructive chemical analysis in an effort to identify acceptable NDA measurement methods for this matrix. NDA results on seven samples and destructive results on four samples are presented

Determination of the radionuclide release factor for an evaporator process using nondestructive assay

International Nuclear Information System (INIS)

Johnson, R.E.

1998-01-01

The 242-A Evaporator is the primary waste evaporator for the Hanford Site radioactive liquid waste stored in underground double-shell tanks. Low pressure evaporation is used to remove water from the waste, thus reducing the amount of tank space required for storage. The process produces a concentrated slurry, a process condensate, and an offgas. The offgas exhausts through two stages of high-efficiency particulate air (HEPA) filters before being discharged to the atmosphere 40 CFR 61 Subpart H requires assessment of the unfiltered exhaust to determine if continuous compliant sampling is required. Because potential (unfiltered) emissions are not measured, methods have been developed to estimate these emissions. One of the methods accepted by the Environmental Protection Agency is the measurement of the accumulation of radionuclides on the HEPA filters. Nondestructive assay (NDA) was selected for determining the accumulation on the HEPA filters. NDA was performed on the HEPA filters before and after a campaign in 1997. NDA results indicate that 2.1 E+4 becquerels of cesium-137 were accumulated on the primary HEPA 1700 filter during the campaign. The feed material processed in the campaign contained a total of 1.4 E+l6 Bq of cesium-137. The release factor for the evaporator process is 1.5 E-12. Based on this release factor, continuous compliant sampling is not required

Nondestructive assay of fluorine in geological and other materials by instrumental photon activation analysis with a microtron

Czech Academy of Sciences Publication Activity Database

Krausová, I.; Mizera, Jiří; Řanda, Z.; Chvátil, D.; Krist, P.

2015-01-01

Roč. 342, JAN (2015), s. 82-86 ISSN 0168-583X Institutional support: RVO:67985891 Keywords : fluorine * instrumental photon activation analysis * IPAA * coal Subject RIV: BG - Nuclear , Atomic and Molecular Physics, Colliders Impact factor: 1.389, year: 2015

A comparison of spent fuel assembly control instruments: The Cadarache PYTHON and the Los Alamos Fork

International Nuclear Information System (INIS)

Bignan, G.; Capsie, J.; Romeyer-Dherbey, J.

1991-01-01

Devices to monitor spent fuel assemblies while stored under water with nondestructive assay methods, have been developed in France and in the United States. Both devices are designed to verify operator's declared values of exposures and cooling-time but the applications and thus the designs of the systems differ. A study, whose results are presented in this paper, has been conducted to compare the features and the performances of the two instruments. 4 refs., 9 figs

Edward’s sword? – A non-destructive study of a medieval king’s sword

International Nuclear Information System (INIS)

Segebade, Chr.

2013-01-01

Non-destructive and instrumental methods including photon activation analysis were applied in an examination of an ancient sword. It was tried to find indication of forgery or, if authentic, any later processing and alteration. Metal components of the hilt and the blade were analysed by instrumental photon activation. Non-destructive metallurgical studies (hardness measurements, microscopic microstructure analysis) are briefly described, too. The results of these investigations did not yield indication of non-authenticity. This stood in agreement with the results of stylistic and scientific studies by weapon experts.

Evaluation of Kalman filters and genetic algorithms for delayed-neutron nondestructive assay data analyses

International Nuclear Information System (INIS)

Aumeier, S.E.; Forsmann, J.H.

1998-01-01

The ability to nondestructively determine the presence and quantity of fissile/fertile nuclei in various matrices is important in several areas of nuclear applications, including international and domestic safeguards, radioactive waste characterization, and nuclear facility operations. An analysis was performed to determine the feasibility of identifying the masses of individual fissionable isotopes from a cumulative delayed-neutron signal resulting form the neutron irradiation of several uranium and plutonium isotopes. The feasibility of two separate data-processing techniques was studied: Kalman filtering and genetic algorithms. The basis of each technique is reviewed, and the structure of the algorithms as applied to the delayed-neutron analysis problem is presented. The results of parametric studies performed using several variants of the algorithms are presented. The effect of including additional constraining information such as additional measurements and known relative isotopic concentration is discussed. The parametric studies were conducted using simulated delayed-neutron data representative of the cumulative delayed-neutron response following irradiation of a sample containing 238 U, 235 U, 239 Pu, and 240 Pu. The results show that by processing delayed-neutron data representative of two significantly different fissile/fertile fission ratios, both Kalman filters and genetic algorithms are capable of yielding reasonably accurate estimates of the mass of individual isotopes contained in a given assay sample

Fast and nondestructive method for leaf level chlorophyll estimation using hyperspectral LiDAR

NARCIS (Netherlands)

Nevalainen, O.; Hakala, T.; Suomalainen, J.M.; Mäkipää, R.; Peltoniemi, M.; Krooks, A.; Kaasalainen, S.

2014-01-01

We propose an empirical method for nondestructive estimation of chlorophyll in tree canopies. The first prototype of a full waveform hyperspectral LiDAR instrument has been developed by the Finnish Geodetic Institute (FGI). The instrument efficiently combines the benefits of passive and active

Standard test method for non-destructive assay of nuclear material in waste by passive and active neutron counting using a differential Die-away system

CERN Document Server

American Society for Testing and Materials. Philadelphia

2009-01-01

1.1 This test method covers a system that performs nondestructive assay (NDA) of uranium or plutonium, or both, using the active, differential die-away technique (DDT), and passive neutron coincidence counting. Results from the active and passive measurements are combined to determine the total amount of fissile and spontaneously-fissioning material in drums of scrap or waste. Corrections are made to the measurements for the effects of neutron moderation and absorption, assuming that the effects are averaged over the volume of the drum and that no significant lumps of nuclear material are present. These systems are most widely used to assay low-level and transuranic waste, but may also be used for the measurement of scrap materials. The examples given within this test method are specific to the second-generation Los Alamos National Laboratory (LANL) passive-active neutron assay system. 1.1.1 In the active mode, the system measures fissile isotopes such as 235U and 239Pu. The neutrons from a pulsed, 14-MeV ne...

Edward's sword? - A non-destructive study of a medieval king's sword

Energy Technology Data Exchange (ETDEWEB)

Segebade, Chr. [Idaho Accelerator Centre, Idaho State University, 1500 Alvin Ricken Drive, Pocatello, ID 83201 (United States)

2013-04-19

Non-destructive and instrumental methods including photon activation analysis were applied in an examination of an ancient sword. It was tried to find indication of forgery or, if authentic, any later processing and alteration. Metal components of the hilt and the blade were analysed by instrumental photon activation. Non-destructive metallurgical studies (hardness measurements, microscopic microstructure analysis) are briefly described, too. The results of these investigations did not yield indication of non-authenticity. This stood in agreement with the results of stylistic and scientific studies by weapon experts.

Design of a nondestructive two-in-one instrument for measuring the polarization and energy spectrum at an X-ray FEL facility

Science.gov (United States)

Zhang, Qingmin; Deng, Bangjie; Chen, Yuanmiaoliang; Liu, Bochao; Chen, Shaofei; Fan, Jinquan; Feng, Lie; Deng, Haixiao; Liu, Bo; Wang, Dong

2017-10-01

The free electron laser (FEL), as a next-generation light source, is an attractive tool in scientific frontier research because of its advantages of full coherence, ultra-short pulse duration, and controllable polarization. Owing to the demand of real-time bunch diagnosis during FEL experiments, precise nondestructive measurements of the polarization and X-ray energy spectrum using one instrument are preferred. In this paper, such an instrument based on the electron time-of-flight technique is proposed. By considering the complexity and nonlinearity, a numerical model in the framework of Geant4 has been developed for optimization. Taking the Shanghai Soft X-ray FEL user facility as an example, its measurement performances' dependence on the critical parameters was studied systematically, and, finally, an optimal design was obtained, achieving resolutions of 0.5% for the polarization degree and 0.3 eV for the X-ray energy spectrum.

Nondestructive assay of fluorine in geological and other materials by instrumental photon activation analysis with a microtron

Czech Academy of Sciences Publication Activity Database

Krausová, Ivana; Mizera, Jiří; Řanda, Zdeněk; Chvátil, David; Krist, Pavel

2015-01-01

Roč. 342, JAN (2015), s. 82-86 ISSN 0168-583X R&D Projects: GA ČR(CZ) GBP108/12/G108; GA ČR GA13-27885S Institutional support: RVO:61389005 Keywords : Fluorine * instrumental photon activation analysis * IPAA * coal Subject RIV: BG - Nuclear , Atomic and Molecular Physics, Colliders Impact factor: 1.389, year: 2015

Nondestructive testing methods in building industry '83. Part 1

International Nuclear Information System (INIS)

1983-10-01

The conference heard 52 papers of which 11 were incorporated in INIS. The subject of these was the use of radiometric methods and instruments for nondestructive testing of building materials and ways of testing the quality of concrete during nuclear power plant construction. (J.P.)

Neutron Based Non-Destructive Assay (NDA) Measurement Systems for Safeguard

Energy Technology Data Exchange (ETDEWEB)

Swinhoe, Martyn Thomas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-09-21

The objectives of this project are to introduce the assay methods for plutonium measurements using the HLNC; introduce the assay method for bulk uranium measurements using the AWCC; and introduce the assay method for fuel assembly measurements using the UNCL.

Non-destructive isotopic uranium assay by multiple delayed neutron measurements

International Nuclear Information System (INIS)

Papadopoulos, N.N.; Tsagas, N.F.

1991-01-01

The high accuracy and precision required in nuclear safeguards measurements can be achieved by an improved neutron activation technique based on multiple delayed fission neutron counting under various experimental conditions. For the necessary ultrahigh counting statistics required, cyclic activation of multiple subsamples has been applied. The home-made automated flexible analytical system with neutron flux and spectrum differentiation by irradiation position adjustment and cadmium screening, permits the non-destructive determination of the U235 abundance and the total U element concentration needed in nuclear safeguards sample analysis, with a high throughout and a low operational cost. Careful experimental optimization led to considerable improvement of the results

Field experience with a mobile tomographic nondestructive assay system

International Nuclear Information System (INIS)

Prettyman, T.H.; Betts, S.E.; Taggart, D.P.; Estep, R.J.; Nicholas, N.J.; Lucas, M.C.; Harlan, R.A.

1995-01-01

A mobile tomographic gamma-ray scanner (TGS) developed by Los Alamos National Laboratory was recently demonstrated at the Rocky Flats Environmental Technology Site and is currently in use at Los Alamos waste storage areas. The scanner was developed to assay radionuclides in low-level, transuranic, and mixed waste in containers ranging in size from 2 ft 3 boxes to 83-gallon overpacks. The tomographic imaging capability provides a complete correction for source distribution and matrix attenuation effects, enabling accurate assays of Pu-239 and other gamma-ray emitting isotopes. In addition, the system can reliably detect self-absorbing material such as plutonium metal shot, and can correct for bias caused by self-absorption. The system can be quickly configured to execute far-field scans, segmented gamma-ray scans, and a host of intermediate scanning protocols, enabling higher throughput (up to 20 drums per 8-hour shift). In this paper, we will report on the results of field trials of the mobile system at Rocky Flats and Los Alamos. Assay accuracy is confirmed for cases in which TGS assays can be compared with assays (e.g. with calorimetry) of individual packages within the drums. The mobile tomographic technology is expected to considerably reduce characterization costs at DOE production and environmental technology sites

MC and A instrumentation catalog

Energy Technology Data Exchange (ETDEWEB)

Neymotin, L. [ed.] [Brookhaven National Lab., Upton, NY (United States); Sviridova, V. [ed.] [All-Russian Research Inst. of Automatics, Moscow (Russian Federation)

1998-06-01

In 1981 and 1985, two editions of a catalog of non-destructive nuclear measurement instrumentation, and material control and surveillance equipment, were published by Brookhaven National Laboratory (BNL). The last edition of the catalog included one hundred and twenty-five entries covering a wide range of devices developed in the US and abroad. More than ten years have elapsed since the publication of the more recent Catalog. Devices described in it have undergone significant modifications, and new devices have been developed. Therefore, in order to assist specialists in the field of Material Control and Accounting (MC and A), a new catalog has been created. Work on this instrumentation catalog started in 1997 as a cooperative effort of Brookhaven National Laboratory (BNL), operated by Brookhaven Science Associates under contract to the US Department of Energy, and the All-Russian Research Institute of Automatics (VNIIA), subordinate institute of the Atomic Energy Ministry of the Russian Federation, within the collaborative US-Russia Material Protection, Control, and Accounting (MPC and A) Program. Most of the equipment included in the Catalog are non-destructive assay (NDA) measurement devices employed for purposes of accounting, confirmation, and verification of nuclear materials. Other devices also included in the Catalog are employed in the detection and deterrence of unauthorized access to or removal of nuclear materials (material control: containment and surveillance). Equipment found in the Catalog comprises either: (1) complete devices or systems that can be used for MC and A applications; or (2) parts or components of complete systems, such as multi-channel analyzers, detectors, neutron generators, and software. All devices are categorized by their status of development--from prototype to serial production.

MC and A instrumentation catalog

International Nuclear Information System (INIS)

Neymotin, L.; Sviridova, V.

1998-01-01

In 1981 and 1985, two editions of a catalog of non-destructive nuclear measurement instrumentation, and material control and surveillance equipment, were published by Brookhaven National Laboratory (BNL). The last edition of the catalog included one hundred and twenty-five entries covering a wide range of devices developed in the US and abroad. More than ten years have elapsed since the publication of the more recent Catalog. Devices described in it have undergone significant modifications, and new devices have been developed. Therefore, in order to assist specialists in the field of Material Control and Accounting (MC and A), a new catalog has been created. Work on this instrumentation catalog started in 1997 as a cooperative effort of Brookhaven National Laboratory (BNL), operated by Brookhaven Science Associates under contract to the US Department of Energy, and the All-Russian Research Institute of Automatics (VNIIA), subordinate institute of the Atomic Energy Ministry of the Russian Federation, within the collaborative US-Russia Material Protection, Control, and Accounting (MPC and A) Program. Most of the equipment included in the Catalog are non-destructive assay (NDA) measurement devices employed for purposes of accounting, confirmation, and verification of nuclear materials. Other devices also included in the Catalog are employed in the detection and deterrence of unauthorized access to or removal of nuclear materials (material control: containment and surveillance). Equipment found in the Catalog comprises either: (1) complete devices or systems that can be used for MC and A applications; or (2) parts or components of complete systems, such as multi-channel analyzers, detectors, neutron generators, and software. All devices are categorized by their status of development--from prototype to serial production

Standard test method for nondestructive assay of nuclear material in scrap and waste by passive-Active neutron counting using 252Cf shuffler

CERN Document Server

American Society for Testing and Materials. Philadelphia

2008-01-01

1.1 This test method covers the nondestructive assay of scrap and waste items for U, Pu, or both, using a 252Cf shuffler. Shuffler measurements have been applied to a variety of matrix materials in containers of up to several 100 L. Corrections are made for the effects of matrix material. Applications of this test method include measurements for safeguards, accountability, TRU, and U waste segregation, disposal, and process control purposes (1, 2, 3). 1.1.1 This test method uses passive neutron coincidence counting (4) to measure the 240Pu-effective mass. It has been used to assay items with total Pu contents between 0.03 g and 1000 g. It could be used to measure other spontaneously fissioning isotopes such as Cm and Cf. It specifically describes the approach used with shift register electronics; however, it can be adapted to other electronics. 1.1.2 This test method uses neutron irradiation with a moveable Cf source and counting of the delayed neutrons from the induced fissions to measure the 235U equiva...

Nondestructive Testing

Energy Technology Data Exchange (ETDEWEB)

Berger, Harold [Argonne National Laboratory

1969-01-01

A nondestructive test is an examination of an object in any manner which will not impair the future usefulness of the object. This booklet discusses a few basic methods of nondestructive testing, and some of their characteristics. In addition, it discusses possible future methods for nondestructive testing by taking a quick look at some of the methods now under study.

Non-destructive Engineering

International Nuclear Information System (INIS)

Ko, Jin Hyeon; Ryu, Taek In; Ko, Jun Bin; Hwang, Yong Hwa

2006-08-01

This book gives descriptions of non-destructive engineering on outline of non-destructive test, weld defects, radiographic inspection radiography, ultrasonic inspection, magnetic particle testing, liquid penetrant testing, eddy current inspection method, strain measurement, acoustic emission inspection method, other non-destructive testing like leakage inspection method, and non-destructive mechanics for fault analysis such as Griffiths creaking theory, and stress analysis of creaking.

Uranium and thorium loadings determined by chemical and nondestructive methods in HTGR fuel rods for the Fort St. Vrain Early Validation Irradiation Experiment

International Nuclear Information System (INIS)

Angelini, P.; Rushton, J.E.

1979-01-01

The Fort St. Vrain Early Validation Irradiation Experiment is an irradiation test of reference and of improved High-Temperature Gas-Cooled Reactor fuels in the Fort St. Vrain Reactor. The irradiation test includes fuel rods fabricated at ORNL on an engineering scale fuel rod molding machine. Fuel rods were nondestructively assayed for 235 U content by a technique based on the detection of prompt-fission neutrons induced by thermal-neutron interrogation and were later chemically assayed by using the modified Davies Gray potentiometric titration method. The chemical analysis of the thorium content was determined by a volumetric titration method. The chemical assay method for uranium was evaluated and the results from the as-molded fuel rods agree with those from: (1) large samples of Triso-coated fissile particles, (2) physical mixtures of the three particle types, and (3) standard solutions to within 0.05%. Standard fuel rods were fabricated in order to evaluate and calibrate the nondestructive assay device. The agreement of the results from calibration methods was within 0.6%. The precision of the nondestructive assay device was established as approximately 0.6% by repeated measurements of standard rods. The precision was comparable to that estimated by Poisson statistics. A relative difference of 0.77 to 1.5% was found between the nondestructive and chemical determinations on the reactor grade fuel rods

Non-Destructive Techniques Based on Eddy Current Testing

Science.gov (United States)

García-Martín, Javier; Gómez-Gil, Jaime; Vázquez-Sánchez, Ernesto

2011-01-01

Non-destructive techniques are used widely in the metal industry in order to control the quality of materials. Eddy current testing is one of the most extensively used non-destructive techniques for inspecting electrically conductive materials at very high speeds that does not require any contact between the test piece and the sensor. This paper includes an overview of the fundamentals and main variables of eddy current testing. It also describes the state-of-the-art sensors and modern techniques such as multi-frequency and pulsed systems. Recent advances in complex models towards solving crack-sensor interaction, developments in instrumentation due to advances in electronic devices, and the evolution of data processing suggest that eddy current testing systems will be increasingly used in the future. PMID:22163754

Scoping study to expedite development of a field deployable and portable instrument for UF6 enrichment assay

Energy Technology Data Exchange (ETDEWEB)

Chan, George; Valentine, John D.; Russo, Richard E.

2017-09-14

The primary objective of the present study is to identity the most promising, viable technologies that are likely to culminate in an expedited development of the next-generation, field-deployable instrument for providing rapid, accurate, and precise enrichment assay of uranium hexafluoride (UF6). UF6 is typically involved, and is arguably the most important uranium compound, in uranium enrichment processes. As the first line of defense against proliferation, accurate analytical techniques to determine the uranium isotopic distribution in UF6 are critical for materials verification, accounting, and safeguards at enrichment plants. As nuclear fuel cycle technology becomes more prevalent around the world, international nuclear safeguards and interest in UF6 enrichment assay has been growing. At present, laboratory-based mass spectrometry (MS), which offers the highest attainable analytical accuracy and precision, is the technique of choice for the analysis of stable and long-lived isotopes. Currently, the International Atomic Energy Agency (IAEA) monitors the production of enriched UF6 at declared facilities by collecting a small amount (between 1 to 10 g) of gaseous UF6 into a sample bottle, which is then shipped under chain of custody to a central laboratory (IAEA’s Nuclear Materials Analysis Laboratory) for high-precision isotopic assay by MS. The logistics are cumbersome and new shipping regulations are making it more difficult to transport UF6. Furthermore, the analysis is costly, and results are not available for some time after sample collection. Hence, the IAEA is challenged to develop effective safeguards approaches at enrichment plants. In-field isotopic analysis of UF6 has the potential to substantially reduce the time, logistics and expense of sample handling. However, current laboratory-based MS techniques require too much infrastructure and operator expertise for field deployment and operation. As outlined in the IAEA Department of Safeguards Long

A 252Cf based nondestructive assay system for fissile material

International Nuclear Information System (INIS)

Menlove, H.O.; Crane, T.W.

1978-01-01

A modulated 252 Cf source assay system 'Shuffler' based on fast-or-thermal-neutron interrogation combined with delayed-neutron counting has been developed for the assay of fissile material. The 252 Cf neutron source is repetitively transferred from the interrogation position to a shielded position while the delayed neutrons are counted in a high efficiency 3 He neutron well-counter. For samples containing plutonium, this well-counter is also used in the passive coincidence mode to assay the effective 240 Pu content. The design of an optimized neutron tailoring assembly for fast-neutron interrogation using a Monte Carlo Neutron Computer Code is described. The Shuffler system has been applied to the assay of fuel pellets, inventory samples, irradiated fuel and plutonium mixed-oxide fuel. The system can assay samples with fissile contents from a few milligrams up to several kilograms using thermal-neutron interrogation for the low mass samples and fast-neutron interrogation for the high mass samples. Samples containing 235 U- 238 U, or 233 U-Th, or UO 2 -PuO 2 fuel mixtures have been assayed with the Shuffler system. (Auth.)

Integrated five station nondestructive assay system for the support of decontamination and decommissioning of a former plutonium mixed oxide fuel fabrication facility

International Nuclear Information System (INIS)

Caldwell, J.T.; Bieri, J.M.; Hastings, R.D.; Horton, W.S.; Kuckertz, T.H.; Kunz, W.E.; Plettenberg, K.; Smith, L.D.

1990-01-01

The goal of a safe, efficient and economic decontamination and decommissioning of plutonium facilities can be greatly enhanced through the intelligent use of an integrated system of nondestructive assay equipment. We have designed and fabricated such a system utilizing five separate NDA stations integrated through a single data acquisition and management personal computer-based controller. The initial station utilizes a passive neutron measurement to determine item Pu inventory to the 0.1 gm level prior to insertion into the decontamination cell. A large active neutron station integrated into the cell is used to measure decontamination effectiveness at the 10 nci/gm level. Cell Pu buildup at critical points is monitored with passive neutron detectors. An active neutron station having better than 1 mg Pu assay sensitivity is used to quantify final compacted waste pucks outside the cell. Bulk Pu in various forms and isotopic enrichments is quantified in a combined passive neutron coincidence and high resolution gamma ray spectrometer station outside the cell. Item control and Pu inventory are managed with bar code labeling and a station integrating algorithm. Overall economy is achieved by multiple station use of the same expensive hardware such as the neutron generator

Degradation of the ethyl glucuronide content in hair by hydrogen peroxide and a non-destructive assay for oxidative hair treatment using infra-red spectroscopy.

Science.gov (United States)

Ammann, Dominic; Becker, Roland; Kohl, Anka; Hänisch, Jessica; Nehls, Irene

2014-11-01

The assessment of quantification results of the alcohol abuse marker ethyl glucuronide (EtG) in hair in comparison to the cut-off values for the drinking behavior may be complicated by cosmetic hair bleaching. Thus, the impact of increasing exposure to hydrogen peroxide on the EtG content of hair was investigated. Simultaneously, the change of absorbance in the range of 1000-1100 cm(-1) indicative for the oxidation of cystine was investigated non-destructively by attenuated total reflectance Fourier transform infrared spectroscopy (ATR-FTIR) using pulverized portions of the respective hair samples. Hair samples treated with hydrogen peroxide consistently displayed a significantly increased absorbance at 1040 cm(-1) associated with the formation of cysteic acid. The EtG content decreased significantly if the hair was treated with alkaline hydrogen peroxide as during cosmetic bleaching. It could be shown that ATR-FTIR is capable of detecting an exposure to hydrogen peroxide when still no brightening was visible and already before the EtG content deteriorated significantly. Thus, hair samples suspected of having been exposed to oxidative treatment may be checked non-destructively by a readily available technique. This assay is also possible retrospectively after EtG extraction and using archived samples. Copyright © 2014 Elsevier Ireland Ltd. All rights reserved.

The role of Monte Carlo burnup calculations in quantifying plutonium mass in spent fuel assemblies with non-destructive assay

Energy Technology Data Exchange (ETDEWEB)

Galloway, Jack D.; Tobin, Stephen J.; Trellue, Holly R.; Fensin, Michael L. [Los Alamos National Laboratory, Los Alamos, (United States)

2011-12-15

The Next Generation Safeguards Initiate (NGSI) of the United States Department of Energy has funded a multi-laboratory/university collaboration to quantify plutonium content in spent fuel (SF) with non-destructive assay (NDA) techniques and quantify the capability of these NDA techniques to detect pin diversions from SF assemblies. The first Monte Carlo based spent fuel library (SFL) developed for the NGSI program contained information for 64 different types of SF assemblies (four initial enrichments, burnups, and cooling times). The maximum amount of fission products allowed to still model a 17x17 Westinghouse pressurized water reactor (PWR) fuel assembly with four regions per fuel pin was modelled. The number of fission products tracked was limited by the available memory. Studies have since indicated that additional fission product inclusion and asymmetric burning of the assembly is desired. Thus, an updated SFL has been developed using an enhanced version of MCNPX, more powerful computing resources, and the Monte Carlo-based burnup code Monteburns, which links MCNPX to a depletion code and models a representative 1 Division-Slash 8 core geometry containing one region per fuel pin in the assemblies of interest, including a majority of the fission products with available cross sections. Often in safeguards, the limiting factor in the accuracy of NDA instruments is the quality of the working standard used in calibration. In the case of SF this is anticipated to also be true, particularly for several of the neutron techniques. The fissile isotopes of interest are co-mingled with neutron absorbers that alter the measured count rate. This paper will quantify how well working standards can be generated for PWR spent fuel assemblies and also describe the spatial plutonium distribution across an assembly. More specifically we will demonstrate how Monte Carlo gamma measurement simulations and a Monte Carlo burnup code can be used to characterize the emitted gamma

Comparative analysis of non-destructive methods to control fissile materials in large-size containers

Directory of Open Access Journals (Sweden)

Batyaev V.F.

2017-01-01

Full Text Available The analysis of various non-destructive methods to control fissile materials (FM in large-size containers filled with radioactive waste (RAW has been carried out. The difficulty of applying passive gamma-neutron monitoring FM in large containers filled with concreted RAW is shown. Selection of an active non-destructive assay technique depends on the container contents; and in case of a concrete or iron matrix with very low activity and low activity RAW the neutron radiation method appears to be more preferable as compared with the photonuclear one.

A new facility for non-destructive assay using a 252Cf source.

Science.gov (United States)

Stevanato, L; Caldogno, M; Dima, R; Fabris, D; Hao, Xin; Lunardon, M; Moretto, S; Nebbia, G; Pesente, S; Pino, F; Sajo-Bohus, L; Viesti, G

2013-03-01

A new laboratory facility for non-destructive analysis (NDA) using a time-tagged (252)Cf source is presented. The system is designed to analyze samples having maximum size of about 20 × 25 cm(2), the material recognition being obtained by measuring simultaneously total and energy dependent transmission of neutrons and gamma rays. The equipment technical characteristics and performances of the NDA system are presented, exploring also limits due to the sample thickness. Some recent applications in the field of cultural heritage are presented. Copyright © 2012 Elsevier Ltd. All rights reserved.

Review of research on non-destructive analysis of reactor fuel elements

Energy Technology Data Exchange (ETDEWEB)

Ruby, S L; Gardner, D G [Westinghouse Electric Corp. (United States). Atomic Power Dept.

1959-01-01

This report contains a selected bibliography on the nondestructive assay of irradiated and unirradiated reactor fuel assemblies. The report also includes a discussion and evaluation of these papers in the light of the problems presented by variations in enrichment, alloying, cladding, geometrical arrangement, etc., among the many kinds of fuel assemblies. Suggestions for further development work are made. (author).

Assessment of decay in standing timber using stress wave timing nondestructive evaluation tools : a guide for use and interpretation

Science.gov (United States)

Xiping Wang; Ferenc Divos; Crystal Pilon; Brian K. Brashaw; Robert J. Ross; Roy F. Pellerin

2004-01-01

This guide was prepared to assist field foresters in the use of stress wave timing instruments to locate and define areas of decay in standing timber. The first three sections provide background information, the principles of stress wave nondestructive testing, and measurement techniques for stress wave nondestructive testing. The last section is a detailed description...

Nondestructive evaluation of reinforced plastics by a radiometric measurement technique

International Nuclear Information System (INIS)

Entine, Gerald; Afshari, Sia; Verlinden, Matt

1990-01-01

The demand for new high-performance plastics has greatly increased with advances in the performance characteristics of sophisticated reinforced engineering resins. However, conventional methods for the evaluation of the glass and filler contents of reinforced plastics are destructive, labor intensive, and time consuming. We have developed a new instrument, to address this problem, which provides for the rapid, accurate, and nondestructive measurement of glass or filler content in reinforced plastics. This instrument utilizes radiation transmission and scattering techniques for analytical measurement of glass, graphite and other fillers used in reinforced plastics. (author)

Korean round-robin result for new international program to assess the reliability of emerging nondestructive techniques

Energy Technology Data Exchange (ETDEWEB)

Kim, Kyung Cho; Kim, Jin Gyum; Kang, Sung Sik; Jhung, Myung Jo [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2017-04-15

The Korea Institute of Nuclear Safety, as a representative organization of Korea, in February 2012 participated in an international Program to Assess the Reliability of Emerging Nondestructive Techniques initiated by the U.S. Nuclear Regulatory Commission. The goal of the Program to Assess the Reliability of Emerging Nondestructive Techniques is to investigate the performance of emerging and prospective novel nondestructive techniques to find flaws in nickel-alloy welds and base materials. In this article, Korean round-robin test results were evaluated with respect to the test blocks and various nondestructive examination techniques. The test blocks were prepared to simulate large-bore dissimilar metal welds, small-bore dissimilar metal welds, and bottom-mounted instrumentation penetration welds in nuclear power plants. Also, lessons learned from the Korean round-robin test were summarized and discussed.

Computer-based instrumentation for partial discharge detection in GIS

International Nuclear Information System (INIS)

Md Enamul Haque; Ahmad Darus; Yaacob, M.M.; Halil Hussain; Feroz Ahmed

2000-01-01

Partial discharge is one of the prominent indicators of defects and insulation degradation in a Gas Insulated Switchgear (GIS). Partial discharges (PD) have a harmful effect on the life of insulation of high voltage equipment. The PD detection using acoustic technique and subsequent analysis is currently an efficient method of performing non-destructive testing of GIS apparatus. A low cost PC-based acoustic PD detection instrument has been developed for the non-destructive diagnosis of GIS. This paper describes the development of a PC-based instrumentation system for partial discharge detection in GIS and some experimental results have also presented. (Author)

Performance values of nondestructive analysis techniques in safeguards and nuclear materials management

International Nuclear Information System (INIS)

Guardini, S.

1989-01-01

Nondestructive assay (NDA) techniques have, in the past few years, become more and more important in nuclear material accountancy and control. This is essentially due to two reasons: (1) The improvements made in most NDA techniques led some of them to have performances close to destructive analysis (DA) (e.g., calorimetry and gamma spectrometry). (2) The parallel improvement of statistical tools and procedural inspection approaches led to abandoning the following scheme: (a) NDA for semiqualitative or consistency checks only (b) DA for quantitative measurements. As a consequence, NDA is now frequently used in scenarios that involve quantitative (by variable) analysis. On the other hand, it also became evident that the performances of some techniques were different depending on whether they were applied in the laboratory or in the field. It has only recently been realized that, generally speaking, this is due to objective reasons rather than to an incorrect application of the instruments. Speaking of claimed and actual status of NDA performances might be in this sense misleading; one should rather say: performances in different conditions. This paper provides support for this assumption

Comparative analysis of non-destructive methods to control fissile materials in large-size containers

Science.gov (United States)

Batyaev, V. F.; Sklyarov, S. V.

2017-09-01

The analysis of various non-destructive methods to control fissile materials (FM) in large-size containers filled with radioactive waste (RAW) has been carried out. The difficulty of applying passive gamma-neutron monitoring FM in large containers filled with concreted RAW is shown. Selection of an active non-destructive assay technique depends on the container contents; and in case of a concrete or iron matrix with very low activity and low activity RAW the neutron radiation method appears to be more preferable as compared with the photonuclear one. Note to the reader: the pdf file has been changed on September 22, 2017.

Nondestructive analysis of plutonium contaminated soil

International Nuclear Information System (INIS)

Smith, H.E.; Taylor, L.H.

1977-01-01

Plutonium contaminated soil is currently being removed from a covered liquid waste disposal trench near the Pu Processing facility on the Hanford Project. This soil with the plutonium is being mined using remote techniques and equipment. The mined soil is being packaged for placement into retrievable storage, pending possible recovery. To meet the requirements of criticality safety and materials accountability, a nondestructive analysis program has been developed to determine the quantity of plutonium in each packing-storage container. This paper describes the total measurement program: equipment systems, calibration techniques, matrix assumption, instrument control program and a review of laboratory operating experience

Nondestructive testing: Neutron radiography and neutron activation. (Latest citations from the INSPEC: Information services for the physics and engineering communities database). Published Search

International Nuclear Information System (INIS)

1993-08-01

The bibliography contains citations concerning the technology of neutron radiography and neutron activation for nondestructive testing of materials. The development and evaluation of neutron activation analysis and neutron diffraction examination of liquids and solids are presented. Citations also discuss nondestructive assay, verification, evaluation, and multielement analysis of biomedical, environmental, industrial, and geological materials. Nondestructive identification of chemical agents, explosives, weapons, and drugs in sealed containers are explored. (Contains a minimum of 83 citations and includes a subject term index and title list.)

Nondestructive evaluation of metallic structures using a SQUID magnetometer

International Nuclear Information System (INIS)

Weinstock, H.; Nisenoff, M.

1985-01-01

We present one of the first reports of the use of SQUID instrumentation for nondestructive evaluation of electrically conducting and ferromagnetic specimens. We report preliminary experiments on the use of SQUIDs for the detection of defects (such as cracks, holes, weld seams, variations in wall thickness, effects of corrosion, etc.) in the walls of a hollow pipe, and for monitoring the magnetic state of a ferromagnetic sample under stress-strain loading conditions. (orig./BUD)

Techniques for laser processing, assay, and examination of spent fuel

International Nuclear Information System (INIS)

Gray, J.H.; Mitchell, R.C.; Rogell, M.L.

1981-11-01

Fuel examination studies were performed which have application to interim spent fuel storage. These studies were in three areas, i.e., laser drilling and rewelding demonstration, nondestructive assay techniques survey, and fuel examination techniques survey

Standard test method for nondestructive assay of special nuclear material in low density scrap and waste by segmented passive gamma-Ray scanning

CERN Document Server

American Society for Testing and Materials. Philadelphia

2010-01-01

1.1 This test method covers the transmission-corrected nondestructive assay (NDA) of gamma-ray emitting special nuclear materials (SNMs), most commonly 235U, 239Pu, and 241Am, in low-density scrap or waste, packaged in cylindrical containers. The method can also be applied to NDA of other gamma-emitting nuclides including fission products. High-resolution gamma-ray spectroscopy is used to detect and measure the nuclides of interest and to measure and correct for gamma-ray attenuation in a series of horizontal segments (collimated gamma detector views) of the container. Corrections are also made for counting losses occasioned by signal processing limitations (1-3). 1.2 There are currently several systems in use or under development for determining the attenuation corrections for NDA of radioisotopic materials (4-8). A related technique, tomographic gamma-ray scanning (TGS), is not included in this test method (9, 10, 11). 1.2.1 This test method will cover two implementations of the Segmented Gamma Scanning ...

Radiation control in the nondestructive inspection

International Nuclear Information System (INIS)

Kariya, Yukihiro

1982-01-01

In the early days of radiation nondestructive inspection about ten years ago, the loss of radiation sources and careless radiation exposure gave the impression of radiography inspection being immediately slipshod management. In this problem, the peculiar nature of the business in this field is involved. In Nondestructive Inspection Co., Ltd., besides the safety management of radioisotopes, the radiation exposure control of personnel in the regular inspection of nuclear power plants has become increasingly important. The following matters are described: radiation utilization in nondestructive inspection (X- and #betta#-ray radiography, #betta#-ray leak test on shield), radiation control problems in nondestructive inspection business (the peculiar aspects of the business, the analysis of the incidents related with nondestructive inspection), and the practice of radiation control in nondestructive inspection in Nondestructive Inspection Co., Ltd. (Mori, K.)

Nondestructive multielement analyses of airborne particulates by combined uses of instrumental neutron activation analysis and energy dispersive X-ray fluorescence analysis

International Nuclear Information System (INIS)

Mamuro, Tetsuo; Matsuda, Yatsuka; Mizohata, Akira

1974-01-01

Combined uses of instrumental neutron activation analysis and energy dispersive X-ray fluorescence analysis make it possible to analyze nondestructively a considerably large number of elements in airborne particulates. We have confirmed that up to 45 elements can be analyzed without any chemical procedures for urban airborne particulate samples. As the radiation spectrometry by semiconductor detectors and the automatic data reduction by electronic computation are quite common to the two techniques, combined uses of them produce no special annoyance. Several elements can be analyzed by both of them and therefore the reliability of the analytical results can be comfirmed by comparing the data obtained by them with each other. It is noted that this confirmation can be made for the very same sample. In this article are described our experiences of multielement analyses of airborne particulates and some problems to be solved in further studies. (auth.)

Matrix effects corrections in DDT assay of {sup 239}Pu with the CTEN instrument

Energy Technology Data Exchange (ETDEWEB)

Hollas, C.L.; Arnone, G.; Brunson, G.; Coop, K. [Los Alamos National Lab., NM (United States)

1997-11-01

The accuracy of transuranic (TRU) waste assay using the differential die-away technique depends upon significant corrections to compensate for the effects of the matrix material in which the TRU waste is located. We have used a new instrument, the combined thermal/epithermal neutron (CTEN) instrument for the assay of TRU waste, to develop methods to improve the accuracy of these corrections. Neutrons from a pulsed 14-MeV neutron generator are moderated in the walls of the CTEN cavity and induce fission in the TRU material. The prompt neutrons from these fission events are detected in cadmium-wrapped {sup 3}He neutron detectors. We have developed methods of data acquisition and analysis to extract correlation in the neutron signals resulting from fission during active interrogation. This correlation information, in conjunction with the total number of neutrons detected, is used to determine the fraction of fission neutrons transmitted through the matrix material into the {sup 3}He detectors. This determination allows us to cleanly separate the matrix effects into two processes: matrix modification upon the neutron interrogating flux and matrix modification upon the fraction of fission neutrons transmitted to the neutron detectors. Recent results indicate that for some matrix systems, corrections for position dependent effects within the matrix are possible. 7 refs., 7 figs., 1 tab.

Rover waste assay system

International Nuclear Information System (INIS)

Akers, D.W.; Stoots, C.M.; Kraft, N.C.; Marts, D.J.

1997-01-01

The Rover Waste Assay System (RWAS) is a nondestructive assay system designed for the rapid assay of highly-enriched 235 U contaminated piping, tank sections, and debris from the Rover nuclear rocket fuel processing facility at the Idaho Chemical Processing Plant. A scanning system translates a NaI(Tl) detector/collimator system over the structural components where both relative and calibrated measurements for 137 Cs are made. Uranium-235 concentrations are in operation and is sufficiently automated that most functions are performed by the computer system. These functions include system calibration, problem identification, collimator control, data analysis, and reporting. Calibration of the system was done through a combination of measurements on calibration standards and benchmarked modeling. A description of the system is presented along with the methods and uncertainties associated with the calibration and analysis of the system for components from the Rover facility. 4 refs., 2 figs., 4 tabs

Nuclear safeguards research. Program status report. Progress report, September--December 1975

International Nuclear Information System (INIS)

1976-04-01

This report presents the status of the Nondestructive Assay R and D program of the LASL Nuclear Safeguards Research Group, R-1, covering the period September-December 1975. It covers: holdup measurements at the Kerr-McGee Pu facility at Crescent, Okla.; calculations for Random Driver; instrument development and measurement controls; ERDA nondestructive assay training program; and in-plant dynamic materials control (DYMAC) program. 22 figures, 5 tables

Radioactive waste package assay facility. Final report - V. A

International Nuclear Information System (INIS)

Molesworth, T.V.; Strachan, N.R.; Findlay, D.J.S.; Wise, M.O.; Forrest, K.R.; Rogers, J.D.

1993-01-01

This report provides a summary of research work carried out in support of the development of an integrated assay system for the quality checking of Intermediate Level Waste encapsulated in cement. Four non-destructive techniques were originally identified as being viable methods for obtaining radiometric inventory data from a cemented 500 litre ILW package. The major part of the programme was devoted to the development of two interrogation techniques; active neutron for measuring the total fissile content and active gamma for measuring the total actinide content. An electron linear accelerator was used to supply the interrogating beam for these two methods. In addition the linear accelerator beam could be used for high energy radiography. The results of this work are described and the performances and limitations of the non-destructive methods are summarised. The main engineering and operational features which influence the design of an integrated assay facility are outlined and a conceptual layout for a facility to inspect 750 ILW drums a year is described. Details of the detection methods, data processing and potential application of the assay facility are given in three associated HMIP reports. (Author)

Inspection with non destructive assay techniques of the aluminium coating of the TRIGA Mark III reactor vat

International Nuclear Information System (INIS)

Reyes A, A.I.; Gonzalez M, A.; Castaneda J, G.; Rivera M, H.; Sandoval G, I.

2001-01-01

In June 2000, the Reactor Department assigned to the Scientific Research Direction of the National Institute of Nuclear Research requested to the Non-destructive Assays Laboratory (LEND), assigned to the Materials Science Management, the inspection and measurement of thickness of the aluminium coating (liner) of the TRIGA Mark III reactor vat with non-destructive assay techniques, due to that the aluminium coating is exposed mainly to undergo slimming on its back side due to corrosion phenomena. Activity that was able to be carried out from april until august 2001. It is worth pointing out that this type of inspection with these techniques was realized by first time. The non-destructive assays (NDA) are techniques which use indirect physical methods for inspecting the sanitation of components in process or in service, for detect lack of continuity or defects which affect their quality or usefulness. The application of those do not alter the physical, chemical, mechanical or dimensional properties of the part subject of inspection. The results of the application of the ultrasound inspection techniques, industrial radiography and penetrating liquids are presented. (Author)

Proceedings of symposium on intelligent nuclear instrumentation-2001

International Nuclear Information System (INIS)

Kataria, S.K.; Vaidya, P.P.; Das, Debashis; Narurkar, P.V.

2001-02-01

Advances in the field of instrumentation are relevant to many areas of importance such as nuclear and accelerator based research, reactor monitoring and control, non-destructive testing and evaluation, laser programme and health and environment monitoring etc. The nuclear instrumentation is a specialized field with very specific expertise in detection, processing and its analysis. The symposium covers various fields of nuclear interest such as radiation detectors, application of ASICs and FPGA in instruments, field instruments, nuclear instrumentation for basic research, accelerator, reactor, health and environmental monitoring instrumentation, medical instrumentation, instrument net working inclusive of field buses, WEB based and wireless technologies, software tools, AI technique in instrumentation etc., in this specialized area. Papers relevant to INIS are indexed separately

Performance Demonstration Program Plan for Nondestructive Assay of Boxed Wastes for the TRU Waste Characterization Program

International Nuclear Information System (INIS)

2001-01-01

The Performance Demonstration Program (PDP) for nondestructive assay (NDA) consists of a series of tests to evaluate the capability for NDA of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements obtained from NDA systems used to characterize the radiological constituents of TRU waste. The primary documents governing the conduct of the PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC; DOE 1999a) and the Quality Assurance Program Document (QAPD; DOE 1999b). The WAC requires participation in the PDP; the PDP must comply with the QAPD and the WAC. The WAC contains technical and quality requirements for acceptable NDA. This plan implements the general requirements of the QAPD and applicable requirements of the WAC for the NDA PDP for boxed waste assay systems. Measurement facilities demonstrate acceptable performance by the successful testing of simulated waste containers according to the criteria set by this PDP Plan. Comparison among DOE measurement groups and commercial assay services is achieved by comparing the results of measurements on similar simulated waste containers reported by the different measurement facilities. These tests are used as an independent means to assess the performance of measurement groups regarding compliance with established quality assurance objectives (QAO's). Measurement facilities must analyze the simulated waste containers using the same procedures used for normal waste characterization activities. For the boxed waste PDP, a simulated waste container consists of a modified standard waste box (SWB) emplaced with radioactive standards and fabricated matrix inserts. An SWB is a waste box with ends designed specifically to fit the TRUPACT-II shipping container. SWB's will be used to package a substantial volume of the TRU waste for disposal. These PDP sample components

Rover waste assay system

Energy Technology Data Exchange (ETDEWEB)

Akers, D.W.; Stoots, C.M.; Kraft, N.C.; Marts, D.J. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

1997-11-01

The Rover Waste Assay System (RWAS) is a nondestructive assay system designed for the rapid assay of highly-enriched {sup 235}U contaminated piping, tank sections, and debris from the Rover nuclear rocket fuel processing facility at the Idaho Chemical Processing Plant. A scanning system translates a NaI(Tl) detector/collimator system over the structural components where both relative and calibrated measurements for {sup 137}Cs are made. Uranium-235 concentrations are in operation and is sufficiently automated that most functions are performed by the computer system. These functions include system calibration, problem identification, collimator control, data analysis, and reporting. Calibration of the system was done through a combination of measurements on calibration standards and benchmarked modeling. A description of the system is presented along with the methods and uncertainties associated with the calibration and analysis of the system for components from the Rover facility. 4 refs., 2 figs., 4 tabs.

New generation pharmacogenomic tools: a SNP linkage disequilibrium Map, validated SNP assay resource, and high-throughput instrumentation system for large-scale genetic studies.

Science.gov (United States)

De La Vega, Francisco M; Dailey, David; Ziegle, Janet; Williams, Julie; Madden, Dawn; Gilbert, Dennis A

2002-06-01

Since public and private efforts announced the first draft of the human genome last year, researchers have reported great numbers of single nucleotide polymorphisms (SNPs). We believe that the availability of well-mapped, quality SNP markers constitutes the gateway to a revolution in genetics and personalized medicine that will lead to better diagnosis and treatment of common complex disorders. A new generation of tools and public SNP resources for pharmacogenomic and genetic studies--specifically for candidate-gene, candidate-region, and whole-genome association studies--will form part of the new scientific landscape. This will only be possible through the greater accessibility of SNP resources and superior high-throughput instrumentation-assay systems that enable affordable, highly productive large-scale genetic studies. We are contributing to this effort by developing a high-quality linkage disequilibrium SNP marker map and an accompanying set of ready-to-use, validated SNP assays across every gene in the human genome. This effort incorporates both the public sequence and SNP data sources, and Celera Genomics' human genome assembly and enormous resource ofphysically mapped SNPs (approximately 4,000,000 unique records). This article discusses our approach and methodology for designing the map, choosing quality SNPs, designing and validating these assays, and obtaining population frequency ofthe polymorphisms. We also discuss an advanced, high-performance SNP assay chemisty--a new generation of the TaqMan probe-based, 5' nuclease assay-and high-throughput instrumentation-software system for large-scale genotyping. We provide the new SNP map and validation information, validated SNP assays and reagents, and instrumentation systems as a novel resource for genetic discoveries.

Nondestructive testing 89

International Nuclear Information System (INIS)

1989-01-01

The proceedings contain 24 contributions, out of which 14 have been inputted in INIS. These deal with materials for nondestructive testing and various nondestructive testing systems, with the evaluation of radiograms and with the application of radiographic, ultrasonic and eddy current methods to the detection of defects in materials, to the inspection of nuclear reactor components and in other fields of technology. (B.S.)

Assay of low-level plutonium effluents

International Nuclear Information System (INIS)

Hsue, S.T.; Hsue, F.; Bowersox, D.F.

1981-01-01

In the plutonium recovery section at the Los Alamos National Laboratory, an effluent solution is generated that contains low plutonium concentration and relatively high americium concentration. Nondestructive assay of this solution is demonstrated by measuring the passive L x-rays following alpha decay. Preliminary results indicate that an average deviation of 30% between L x-ray and alpha counting can be achieved for plutonium concentrations above 10 mg/L and Am/Pu ratios of up to 3; for plutonium concentrations less than 10 mg/L, the average deviation is 40%. The sensitivity of the L x-ray assay is approx. 1 mg Pu/L

Nondestructive and quantitative characterization of TRU and LLW mixed-waste using active and passive gamma-ray spectrometry and computed tomography

Energy Technology Data Exchange (ETDEWEB)

Camp, D.C.; Martz, H.E.

1991-11-12

The technology being proposed by LLNL is an Active and Passive Computed Tomography (A P CT) Drum Scanner for contact-handled (CH) wastes. It combines the advantages offered by two well-developed nondestructive assay technologies: gamma-ray spectrometry and computed tomography (CT). Coupled together, these two technologies offer to nondestructively and quantitatively characterize mixed- wastes forms. Gamma-ray spectroscopy uses one or more external radiation detectors to passively and nondestructively measure the energy spectrum emitted from a closed container. From the resulting spectrum one can identify most radioactivities detected, be they transuranic isotopes, mixed-fission products, activation products or environmental radioactivities. Spectral libraries exist at LLNL for all four. Active (A) or transmission CT is a well-developed, nondestructive medical and industrial technique that uses an external-radiation beam to map regions of varying attenuation within a container. Passive (P) or emission CT is a technique mainly developed for medical application, e.g., single-photon emission CT. Nondestructive industrial uses of PCT are under development and just coming into use. This report discuses work on the A P CT Drum Scanner at LLNL.

A digital instrument for nondestructive measurements of coating thicknesses by beta backscattering

Science.gov (United States)

Farcasiu, D. M.; Apostolescu, T.; Bozdog, H.; Badescu, E.; Bohm, V.; Stanescu, S. P.; Jianu, A.; Bordeanu, C.; Cracium, M. V.

1992-02-01

The elements of nondestructive gauging of coatings applied on various metal bases are presented. The intensity of the backscattered beta radiations is related to the thickness of the coating. With a fixed measuring geometry and radioactive sources (147Pm, 204Tl, 90Sr+90Y) the intensity of the backscattered beta particles is dependent on the following parameters: coating thickness, atomic number of the coating material and of the base, the beta particle energy and the surface finish. It can be used for the measurement of a wide range of coating thicknesses provided that the difference between the coating and the support atomic numbers is at least 20%. Fields of application include electronics, electrotechnique and so on.

A digital instrument for nondestructive measurements of coating thicknesses by beta backscattering

International Nuclear Information System (INIS)

Farcasiu, D.M.; Apostolescu, T.; Bozdog, H.; Badescu, E.; Bohm, V.; Stanescu, S.P.; Jianu, A.; Bordeanu, C.; Craciun, M.V.

1992-01-01

The elements of nondestructive gauging of coatings applied on various metal bases are presented. The intensity of the backscattered beta radiations is related to the thickness of the coating. With a fixed measuring geometry and radioactive sources ( 147 Pm, 204 Tl, 90 Sr+ 90 Y) the intensity of the backscattered beta particles is dependent on the following parameters: Coating thickness, atomic number of the coating material and of the base, the beta particle energy and the surface finish. It can be used for the measurement of a wide range of coating thicknesses provided that the difference between the coating and the support atomic numbers is at least 20%. Fields of application include electronics, electrotechnique and so on. (orig.)

Non-destructive inservice inspections

International Nuclear Information System (INIS)

Kauppinen, P.; Sarkimo, M.; Lahdenperae, K.

1998-01-01

In order to assess the possible damages occurring in the components and structures of operating nuclear power plants during service the main components and structures are periodically inspected by non-destructive testing techniques. The reliability of non-destructive testing techniques applied in these inservice inspections is of major importance because the decisions concerning the needs for repair of components are mainly based on the results of inspections. One of the targets of this research program has been to improve the reliability of non-destructive testing. This has been addressed in the sub-projects which are briefly summarised here. (author)

A new facility for non-destructive assay using a 252Cf source

International Nuclear Information System (INIS)

Stevanato, L.; Caldogno, M.; Dima, R.; Fabris, D.; Hao, Xin; Lunardon, M.; Moretto, S.; Nebbia, G.; Pesente, S.; Pino, F.; Sajo-Bohus, L.; Viesti, G.

2013-01-01

A new laboratory facility for non-destructive analysis (NDA) using a time-tagged 252 Cf source is presented. The system is designed to analyze samples having maximum size of about 20×25 cm 2 , the material recognition being obtained by measuring simultaneously total and energy dependent transmission of neutrons and gamma rays. The equipment technical characteristics and performances of the NDA system are presented, exploring also limits due to the sample thickness. Some recent applications in the field of cultural heritage are presented. - Highlights: ► Tagged 252 Cf source setup. ► Material recognition and sample imaging with measurements of gamma ray and neutron transmission. ► Material identification via energy dependent neutron and gamma ray transmission measurements. ► Identification of layered material. ► Effects due to the sample thickness on the above identification techniques

An integrated approach for determining plutonium mass in spent fuel assemblies with nondestructive assay

International Nuclear Information System (INIS)

Swinhoe, Martyn T.; Tobin, Stephen J.; Fensin, Mike L.; Menlove, Howard O.

2009-01-01

be part of a system that cost-effectively meets the burnup credit needs of a repository. Behind each of these reasons is a regulatory structure with MC and A requirements. In the case of the IAEA, the accountable quantity is elemental plutonium. The material in spent fuel (fissile isotopes, fission products, etc.) emits signatures that provide information about the content and history of the fuel. A variety of nondestructive assay (NDA) techniques are available to quantify these signatures. The effort presented in this paper is investigation of the capabilities of 12 NDA techniques. For these 12, none is conceptually capable of independently determining the Pu content in a spent fuel assembly while at the same time being able to detect the diversion of a significant quantity of rods. For this reason the authors are investigating the capability of 12 NDA techniques with the end goal of integrating a few techniques together into a system that is capable of measuring Pu mass in an assembly. The work described here is the beginning of what is anticipated to be a five year effort: (1) two years of modeling to select the best technologies, (2) one year fabricating instruments and (3) two years measuring spent fuel. This paper describes the first two years of this work. In order to cost effectively and robustly model the performance of the 12 NDA techniques, an 'assembly library' was created. The library contains the following: (a) A diverse range of PWR spent fuel assemblies (burnup, enrichment, cooling time) similar to that which exists in spent pools today and in the future. (b) Diversion scenarios that capture a range of possible rod removal options. (c) The spatial and isotopic detail needed to accurately quantify the capability of all the NDA techniques so as to enable integration. It is our intention to make this library available to other researchers in the field for inter-comparison purposes. The performance of each instrument will be quantified for the full

Educational ultrasound nondestructive testing laboratory.

Science.gov (United States)

Genis, Vladimir; Zagorski, Michael

2008-09-01

The ultrasound nondestructive evaluation (NDE) of materials course was developed for applied engineering technology students at Drexel University's Goodwin College of Professional Studies. This three-credit, hands-on laboratory course consists of two parts: the first part with an emphasis on the foundations of NDE, and the second part during which ultrasound NDE techniques are utilized in the evaluation of parts and materials. NDE applications are presented and applied through real-life problems, including calibration and use of the latest ultrasonic testing instrumentation. The students learn engineering and physical principles of measurements of sound velocity in different materials, attenuation coefficients, material thickness, and location and dimensions of discontinuities in various materials, such as holes, cracks, and flaws. The work in the laboratory enhances the fundamentals taught during classroom sessions. This course will ultimately result in improvements in the educational process ["The greater expectations," national panel report, http://www.greaterexpectations.org (last viewed February, 2008); R. M. Felder and R. Brent "The intellectual development of Science and Engineering Students. Part 2: Teaching to promote growth," J. Eng. Educ. 93, 279-291 (2004)] since industry is becoming increasingly reliant on the effective application of NDE technology and the demand on NDE specialists is increasing. NDE curriculum was designed to fulfill levels I and II NDE in theory and training requirements, according to American Society for Nondestructive Testing, OH, Recommended Practice No. SNT-TC-1A (2006).

A technical review of non-destructive assay research for the characterization of spent nuclear fuel assemblies being conducted under the US DOE NGSI

Energy Technology Data Exchange (ETDEWEB)

Croft, Stephen [Los Alamos National Laboratory; Tobin, Stephen J [Los Alamos National Laboratory

2010-12-06

There is a growing belief that expansion of nuclear energy generation will be needed in the coming decades as part of a mixed supply chain to meet global energy demand. At stake is the health of the economic engine that delivers human prosperity. As a consequence renewed interest is being paid to the safe management of spent nuclear fuel (SNF) and the plutonium it contains. In addition to being an economically valuable resource because it can be used to construct explosive devices, Pu must be placed on an inventory and handled securely. A multiinstitutional team of diverse specialists has been assembled under a project funded by the US Department of Energy (DOE) Next Generation Safeguards Initiative (NGSI) to address ways to nondestructively quantify the plutonium content of spent nuclear fuel assemblies, and to also detect the potential diversion of pins from those assemblies. Studies are underway using mostly Monte Carlo tools to assess the feasibility, individual and collective performance capability of some fourteen nondestructive assay methods. Some of the methods are familiar but are being applied in a new way against a challenging target which is being represented with a higher degree of realism in simulation space than has been done before, while other methods are novel. In this work we provide a brief review of the techniques being studied and highlight the main achievements to date. We also draw attention to the deficiencies identified in for example modeling capability and available basic nuclear data. We conclude that this is an exciting time to be working in the NDA field and that much work, both fundamental and applied, remains ahead if we are to advance the state of the practice to meet the challenges posed to domestic and international safeguards by the expansion of nuclear energy together with the emergence of alternative fuel cycles.

A technical review of non-destructive assay research for the characterization of spent nuclear fuel assemblies being conducted under the US DOE NGSI

International Nuclear Information System (INIS)

Croft, Stephen; Tobin, Stephen J.

2010-01-01

There is a growing belief that expansion of nuclear energy generation will be needed in the coming decades as part of a mixed supply chain to meet global energy demand. At stake is the health of the economic engine that delivers human prosperity. As a consequence renewed interest is being paid to the safe management of spent nuclear fuel (SNF) and the plutonium it contains. In addition to being an economically valuable resource because it can be used to construct explosive devices, Pu must be placed on an inventory and handled securely. A multiinstitutional team of diverse specialists has been assembled under a project funded by the US Department of Energy (DOE) Next Generation Safeguards Initiative (NGSI) to address ways to nondestructively quantify the plutonium content of spent nuclear fuel assemblies, and to also detect the potential diversion of pins from those assemblies. Studies are underway using mostly Monte Carlo tools to assess the feasibility, individual and collective performance capability of some fourteen nondestructive assay methods. Some of the methods are familiar but are being applied in a new way against a challenging target which is being represented with a higher degree of realism in simulation space than has been done before, while other methods are novel. In this work we provide a brief review of the techniques being studied and highlight the main achievements to date. We also draw attention to the deficiencies identified in for example modeling capability and available basic nuclear data. We conclude that this is an exciting time to be working in the NDA field and that much work, both fundamental and applied, remains ahead if we are to advance the state of the practice to meet the challenges posed to domestic and international safeguards by the expansion of nuclear energy together with the emergence of alternative fuel cycles.

49 CFR 192.243 - Nondestructive testing.

Science.gov (United States)

2010-10-01

... 49 Transportation 3 2010-10-01 2010-10-01 false Nondestructive testing. 192.243 Section 192.243... BY PIPELINE: MINIMUM FEDERAL SAFETY STANDARDS Welding of Steel in Pipelines § 192.243 Nondestructive testing. (a) Nondestructive testing of welds must be performed by any process, other than trepanning, that...

International cooperation program on non-destructive inspection. Overview of PINC and PARENT

International Nuclear Information System (INIS)

Komura, Ichiro

2016-01-01

PINC (The Program for the Inspection of Nickel Alloy Components) and its successor program PARENT (The Program to Assess the Reliability of Emerging Nondestructive Techniques) are the programs on the verification of nondestructive inspection technology for detecting / dimension-evaluating the stress corrosion cracking (SCC) generated in the weld zone of nickel-based alloy. The US Nuclear Regulatory Commission plays a leading role, and the institutions of the United States, Japan, Korea, Sweden, Finland, and Switzerland participate in them. PINC was run from 2003 to 2009, and PARENT is currently underway with a schedule from 2010 to July 2017, including the extension period after July 2015. This paper outlined the implementation items and test results / achievements of PINC and PARENT programs. The target parts of PINC were a safe-end reducer and a reactor bottom instrument tube rest, and the flaw detection test and its analytical evaluation were carried out with a focus on the detectability and the sizing accuracy of defects. As a feature of the verification test of the non-destructive inspection technology in PARENT, two kinds of flaw detection tests, namely blind test and open test, are distinctively carried out. (A.O.)

Neutron Resonance Transmission Analysis (NRTA): A Nondestructive Assay Technique for the Next Generation Safeguards Initiative’s Plutonium Assay Challenge

Energy Technology Data Exchange (ETDEWEB)

J. W. Sterbentz; D. L. Chichester

2010-12-01

This is an end-of-year report for a project funded by the National Nuclear Security Administration's Office of Nuclear Safeguards (NA-241). The goal of this project is to investigate the feasibility of using Neutron Resonance Transmission Analysis (NRTA) to assay plutonium in commercial light-water-reactor spent fuel. This project is part of a larger research effort within the Next-Generation Safeguards Initiative (NGSI) to evaluate methods for assaying plutonium in spent fuel, the Plutonium Assay Challenge. The first-year goals for this project were modest and included: 1) developing a zero-order MCNP model for the NRTA technique, simulating data results presented in the literature, 2) completing a preliminary set of studies investigating important design and performance characteristics for the NRTA measurement technique, and 3) documentation of this work in an end of the year report (this report). Research teams at Los Alamos National Laboratory (LANL), Lawrence Berkeley National Laboratory (LBNL), Pacific Northwest National Laboratory (PNNL), and at several universities are also working to investigate plutonium assay methods for spent-fuel safeguards. While the NRTA technique is well proven in the scientific literature for assaying individual spent fuel pins, it is a newcomer to the current NGSI efforts studying Pu assay method techniques having just started in March 2010; several analytical techniques have been under investigation within this program for two to three years or more. This report summarizes a nine month period of work.

Nondestructive indication of fatigue damage and residual lifetime in ferromagnetic construction materials

Czech Academy of Sciences Publication Activity Database

Tomáš, Ivan; Kovářík, O.; Vértesy, G.; Kadlecová, Jana

2014-01-01

Roč. 25, č. 6 (2014), "065601-1"-"065601-10" ISSN 0957-0233. [International Symposium on Measurement Technology and Intelligent Instruments /11./ (ISMTII). Aachen, 01.07.2013-03.07.2013] R&D Projects: GA ČR(CZ) GAP108/12/1872 Institutional support: RVO:68378271 Keywords : fatigue * residual lifetime * magnetic nondestructive evaluation * ferromagnetic construction materials Subject RIV: BM - Solid Matter Physics ; Magnetism Impact factor: 1.433, year: 2014

Nondestructive testing method

International Nuclear Information System (INIS)

Porter, J.F.

1996-01-01

Nondestructive testing (NDT) is the use of physical and chemical methods for evaluating material integrity without impairing its intended usefulness or continuing service. Nondestructive tests are used by manufaturer's for the following reasons: 1) to ensure product reliability; 2) to prevent accidents and save human lives; 3) to aid in better product design; 4) to control manufacturing processes; and 5) to maintain a uniform quality level. Nondestructive testing is used extensively on power plants, oil and chemical refineries, offshore oil rigs and pipeline (NDT can even be conducted underwater), welds on tanks, boilers, pressure vessels and heat exchengers. NDT is now being used for testing concrete and composite materials. Because of the criticality of its application, NDT should be performed and the results evaluated by qualified personnel. There are five basic nondestructive examination methods: 1) liquid penetrant testing - method used for detecting surface flaws in materials. This method can be used for metallic and nonmetallic materials, portable and relatively inexpensive. 2) magnetic particle testing - method used to detect surface and subsurface flaws in ferromagnetic materials; 3) radiographic testing - method used to detect internal flaws and significant variation in material composition and thickness; 4) ultrasonic testing - method used to detect internal and external flaws in materials. This method uses ultrasonics to measure thickness of a material or to examine the internal structure for discontinuities. 5) eddy current testing - method used to detect surface and subsurface flaws in conductive materials. Not one nondestructive examination method can find all discontinuities in all of the materials capable of being tested. The most important consideration is for the specifier of the test to be familiar with the test method and its applicability to the type and geometry of the material and the flaws to be detected

Non destructive assay techniques applied to nuclear materials

International Nuclear Information System (INIS)

Gavron, A.

2001-01-01

Nondestructive assay is a suite of techniques that has matured and become precise, easily implementable, and remotely usable. These techniques provide elaborate safeguards of nuclear material by providing the necessary information for materials accounting. NDA techniques are ubiquitous, reliable, essentially tamper proof, and simple to use. They make the world a safer place to live in, and they make nuclear energy viable. (author)

Physical standards and valid caibration

International Nuclear Information System (INIS)

Smith, D.B.

1975-01-01

The desire for improved nuclear material safeguards has led to the development and use of a number and techniques and instruments for the nondestructive assay (NDA) of special nuclear material. Sources of potential bias in NDA measurements are discussed and methods of eliminating the effects of bias in assay results are suggested. Examples are given of instruments in which these methods have been successfully applied. The results of careful attention to potential sources of assay bias are a significant reduction in the number and complexity of standards required for valid instrument calibration and more credible assay results. (auth)

Nondestructive and quantitative characterization of TRU and LLW mixed-waste using active and passive gamma-ray spectrometry and computed tomography

International Nuclear Information System (INIS)

Camp, D.C.; Martz, H.E.

1991-01-01

The technology being proposed by LLNL is an Active and Passive Computed Tomography (A ampersand P CT) Drum Scanner for contact-handled (CH) wastes. It combines the advantages offered by two well-developed nondestructive assay technologies: gamma-ray spectrometry and computed tomography (CT). Coupled together, these two technologies offer to nondestructively and quantitatively characterize mixed- wastes forms. Gamma-ray spectroscopy uses one or more external radiation detectors to passively and nondestructively measure the energy spectrum emitted from a closed container. From the resulting spectrum one can identify most radioactivities detected, be they transuranic isotopes, mixed-fission products, activation products or environmental radioactivities. Spectral libraries exist at LLNL for all four. Active (A) or transmission CT is a well-developed, nondestructive medical and industrial technique that uses an external-radiation beam to map regions of varying attenuation within a container. Passive (P) or emission CT is a technique mainly developed for medical application, e.g., single-photon emission CT. Nondestructive industrial uses of PCT are under development and just coming into use. This report discuses work on the A ampersand P CT Drum Scanner at LLNL

The passive nondestructive assay of the plutonium content of spent-fuel assemblies from the BN-350 fast-breeder reactor in the city of Aqtau, Kazakhstan

CERN Document Server

Lestone, J P; Rennie, J A; Sprinkle, J K; Staples, P; Grimm, K N; Hill, R N; Cherradi, I; Islam, N; Koulikov, J; Starovich, Z

2002-01-01

The International Atomic Energy Agency is presently interested in developing equipment and techniques to measure the plutonium content of breeder reactor spent-fuel assemblies located in storage ponds before they are relocated to more secure facilities. We present the first quantitative nondestructive assay of the plutonium content of fast-breeder reactor spent-fuel assemblies while still underwater in their facility storage pond. We have calibrated and installed an underwater neutron coincidence counter (Spent Fuel Coincidence Counter (SFCC)) in the BN-350 reactor spent-fuel pond in Aqtau, Kazakhstan. A procedure has been developed to convert singles and doubles (coincidence) neutron rates observed by the SFCC into the total plutonium content of a given BN-350 spent-fuel assembly. The plutonium content has been successfully determined for spent-fuel assemblies with a contact radiation level as high as approx 10 sup 5 Rads/h. Using limited facility information and multiple measurements along the length of spe...

ORO appraisal strategy involving use of NDA instrumentation

International Nuclear Information System (INIS)

Lux, C.R.

1977-12-01

ORO has used the following nondestructive assay (NDA) systems for verifying uranium inventories at contractor-operated installations: gamma spectroscopy, thickness-corrected gamma spectroscopy, passive neutron measurement, and random driver measurement. A brief description of each system is given and results of in-field measurements performed on contractors' inventories utilizing each system are discussed

46 CFR 151.03-38 - Nondestructive testing.

Science.gov (United States)

2010-10-01

... CARRYING BULK LIQUID HAZARDOUS MATERIAL CARGOES Definitions § 151.03-38 Nondestructive testing. Nondestructive testing includes ultrasonic examination, liquid penetrant examination, magnetic particle... 46 Shipping 5 2010-10-01 2010-10-01 false Nondestructive testing. 151.03-38 Section 151.03-38...

Assessment of the measurement control program for solution assay instruments at the Los Alamos National Laboratory Plutonium Facility

International Nuclear Information System (INIS)

Goldman, A.S.

1985-05-01

This report documents and reviews the measurement control program (MCP) over a 27-month period for four solution assay instruments (SAIs) Facility. SAI measurement data collected during the period January 1982 through March 1984 were analyzed. The sources of these data included computer listings of measurements emanating from operator entries on computer terminals, logbook entries of measurements transcribed by operators, and computer listings of measurements recorded internally in the instruments. Data were also obtained from control charts that are available as part of the MCP. As a result of our analyses we observed agreement between propagated and historical variances and concluded instruments were functioning properly from a precision aspect. We noticed small, persistent biases indicating slight instrument inaccuracies. We suggest that statistical tests for bias be incorporated in the MCP on a monthly basis and if the instrument bias is significantly greater than zero, the instrument should undergo maintenance. We propose the weekly precision test be replaced by a daily test to provide more timely detection of possible problems. We observed that one instrument showed a trend of increasing bias during the past six months and recommend a randomness test be incorporated to detect trends in a more timely fashion. We detected operator transcription errors during data transmissions and advise direct instrument transmission to the MCP to eliminate these errors. A transmission error rate based on those errors that affected decisions in the MCP was estimated as 1%. 11 refs., 10 figs., 4 tabs

Scoping study to expedite development of a field deployable and portable instrument for UF6 enrichment assay

OpenAIRE

Chan, CYG; Valentine, JD; Russo, RE

2017-01-01

The primary objective of the present study is to identity the most promising, viable technologies that are likely to culminate in an expedited development of the next-generation, field-deployable instrument for providing rapid, accurate, and precise enrichment assay of uranium hexafluoride (UF6). UF6 is typically involved, and is arguably the most important uranium compound, in uranium enrichment processes. As the first line of defense against proliferation, accurate analytical techniques t...

Technical regulation of nondestructive inspection

International Nuclear Information System (INIS)

1995-01-01

It starts with the explanation of definition of nondestructive inspection and qualifications for a inspection. It lists the technical regulations of nondestructive inspections which are radiographic testing, ultrasonic flaw detecting test, liquid penetrant test, magnetic particle inspection, eddy current test visual inspection and leakage test.

Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program

International Nuclear Information System (INIS)

DOE Carlsbad Field Office

2001-01-01

The Performance Demonstration Program (PDP) for nondestructive assay (NDA) consists of a series of tests to evaluate the capability for NDA of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements obtained from NDA systems used to characterize the radiological constituents of TRU waste. The primary documents governing the conduct of the PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC; DOE 1999a) and the Quality Assurance Program Document (QAPD; DOE 1999b). The WAC requires participation in the PDP; the PDP must comply with the QAPD and the WAC. The WAC contains technical and quality requirements for acceptable NDA. This plan implements the general requirements of the QAPD and applicable requirements of the WAC for the NDA PDP. Measurement facilities demonstrate acceptable performance by the successful testing of simulated waste containers according to the criteria set by this PDP Plan. Comparison among DOE measurement groups and commercial assay services is achieved by comparing the results of measurements on similar simulated waste containers reported by the different measurement facilities. These tests are used as an independent means to assess the performance of measurement groups regarding compliance with established quality assurance objectives (QAO's). Measurement facilities must analyze the simulated waste containers using the same procedures used for normal waste characterization activities. For the drummed waste PDP, a simulated waste container consists of a 55-gallon matrix drum emplaced with radioactive standards and fabricated matrix inserts. These PDP sample components are distributed to the participating measurement facilities that have been designated and authorized by the Carlsbad Field Office (CBFO). The NDA Drum PDP materials are stored at these sites under secure conditions to

Characterization of legacy low level waste at the Svafo facility using gamma non-destructive assay and X-ray non-destructive examination techniques - 59289

International Nuclear Information System (INIS)

Halliwell, Stephen; Mottershead, Gary; Ekenborg, Fredrik

2012-01-01

Document available in abstract form only. Full text of publication follows: Over 7000 drums containing legacy, low level radioactive waste are stored at four SVAFO facilities on the Studsvik site which is located near Nykoeping, Sweden. The vast majority of the waste drums (>6000) were produced between 1969 and 1979. The remainder were produced from 1980 onwards. Characterization of the waste was achieved using a combination of non-destructive techniques via mobile equipment located in the AU building at the Studsvik site. Each drum was weighed and a dose rate measurement was recorded. Gamma spectroscopy was used to measure and estimate radionuclide content. Real time xray examination was performed to identify such prohibited items as free liquids. (authors)

Nondestructive assay of TRU waste using gamma-ray active and passive computed tomography

International Nuclear Information System (INIS)

Roberson, G.P.; Decman, D.; Martz, H.; Keto, E.R.; Johansson, E.M.

1995-01-01

The authors have developed an active and passive computed tomography (A and PCT) scanner for assaying radioactive waste drums. Here they describe the hardware components of their system and the software used for data acquisition, gamma-ray spectroscopy analysis, and image reconstruction. They have measured the performance of the system using ''mock'' waste drums and calibrated radioactive sources. They also describe the results of measurements using this system to assay a real TRU waste drum with relatively low Pu content. The results are compared with X-ray NDE studies of the same TRU waste drum as well as assay results from segmented gamma scanner (SGS) measurements

Polychromatic X-ray Micro- and Nano-Beam Science and Instrumentation

Science.gov (United States)

Ice, G. E.; Larson, B. C.; Liu, W.; Barabash, R. I.; Specht, E. D.; Pang, J. W. L.; Budai, J. D.; Tischler, J. Z.; Khounsary, A.; Liu, C.; Macrander, A. T.; Assoufid, L.

2007-01-01

Polychromatic x-ray micro- and nano-beam diffraction is an emerging nondestructive tool for the study of local crystalline structure and defect distributions. Both long-standing fundamental materials science issues, and technologically important questions about specific materials systems can be uniquely addressed. Spatial resolution is determined by the beam size at the sample and by a knife-edge technique called differential aperture microscopy that decodes the origin of scattering from along the penetrating x-ray beam. First-generation instrumentation on station 34-ID-E at the Advanced Photon Source (APS) allows for nondestructive automated recovery of the three-dimensional (3D) local crystal phase and orientation. Also recovered are the local elastic-strain and the dislocation tensor distributions. New instrumentation now under development will further extend the applications of polychromatic microdiffraction and will revolutionize materials characterization.

Polychromatic X-ray Micro- and Nano-Beam Science and Instrumentation

International Nuclear Information System (INIS)

Ice, G.E.; Larson, Ben C.; Liu, Wenjun; Barabash, Rozaliya; Specht, Eliot D; Pang, Judy; Budai, John D.; Tischler, Jonathan Zachary; Khounsary, Ali; Liu, Chian; Macrander, Albert T.; Assoufid, Lahsen

2007-01-01

Polychromatic x-ray micro- and nano-beam diffraction is an emerging nondestructive tool for the study of local crystalline structure and defect distributions. Both long-standing fundamental materials science issues, and technologically important questions about specific materials systems can be uniquely addressed. Spatial resolution is determined by the beam size at the sample and by a knife-edge technique called differential aperture microscopy that decodes the origin of scattering from along the penetrating x-ray beam. First-generation instrumentation on station 34-ID-E at the Advanced Photon Source (APS) allows for nondestructive automated recovery of the three-dimensional (3D) local crystal phase and orientation. Also recovered are the local elastic-strain and the dislocation tensor distributions. New instrumentation now under development will further extend the applications of polychromatic microdiffraction and will revolutionize materials characterization

Addition of magnetic markers for non-destructive evaluation of polymer composites

Directory of Open Access Journals (Sweden)

Ana Paula Pereira Fulco

2011-12-01

Full Text Available Polymer composite pipes are an appealing option as a substitute for conventional steel pipes, particularly due to their inherent corrosion resistance. However, the composite pipes currently used do not allow non-destructive evaluation (NDE using instrumented devices which operate with magnetic sensors. The present work aims at the development of polymer composites with the addition magnetic markers to allow the application non-destructive evaluation techniques which use magnetic sensors. Glass-polyester composite flat, circular plates were fabricated with the addition of ferrite particles (barium ferrite and strontium ferrite and four types of notches were introduced on the plates' surfaces. The influence of these notches on the measured magnetic properties of each material was measured. X-ray diffraction (XRD, X-ray fluorescence (XRF and Brunauer, Emmett, and Teller (BET nitrogen adsorption were used for the characterization of the ferrite particles. Particle dispersion in the polymer matrix was analyzed by scanning electron microscopy (SEM. According to the results, a particular variation in magnetic field was detected over the region surrounding each type of notch. The results suggest that the proposed technique has great potential for damage detection in polymer composites using magnetic sensors and thus constitute a valuable contribution which may ultimately lead to the development of non-destructive evaluation techniques for assessing the structural integrity polymer composite pipes.

49 CFR 195.234 - Welds: Nondestructive testing.

Science.gov (United States)

2010-10-01

... 49 Transportation 3 2010-10-01 2010-10-01 false Welds: Nondestructive testing. 195.234 Section 195... HAZARDOUS LIQUIDS BY PIPELINE Construction § 195.234 Welds: Nondestructive testing. (a) A weld may be... weld. (b) Any nondestructive testing of welds must be performed— (1) In accordance with a written set...

Monte Carlo calculational design of an NDA instrument for the assay of waste products from high enriched uranium spent fuels

International Nuclear Information System (INIS)

Eccleston, G.W.; Schrandt, R.G.; MacDonald, J.L.; Cverna, F.H.

1979-01-01

The Monte Carlo design of the waste assay region of a dual assay system, to be installed at the Fluorinal and Storage Facility, is described. The instrument will be used by the facility operator to assay high-enriched spent fuel packages and waste solids produced from dissolution of the fuels. The fissile content discharged in the waste is expected to vary between 0 and 400 g of 235 U. Material accountability measurements of the waste must be obtained in the presence of large neutron (0.5 x 10 6 n/s) and gamma (50,000 R/hr) backgrounds. The assay system employs fast-neutron irradiation of the sample, using a 5 mg 252 Cf source, followed by delayed neutron counting after the source is transferred to storage. Calculations indicate a +-4-g (2 sigma) assay for a waste canister containing 300 g of 235 U is achievable with an end-of-life (1 mg) 252 Cf source and a background rate of 0.5 x 10 6 n/s

Geosciences research: development of techniques and instruments for investigation geological environments

International Nuclear Information System (INIS)

1993-01-01

In order to understand the geological environment in Japan, new investigation techniques have been developed. These include: 1) Geological techniques for fracture characterization, 2) Nondestructive investigation techniques for detailed geological structure, 3) Instruments for hydraulic characterization, 4) Instruments for hydrochemical characterization. Results so far obtained are: 1) Fractures can be classified by their patterns, 2) The applicability and limitations of conventional geophysical methods were defined, 3) Instruments for measuring very low permeability were successfully developed, 4) Instruments for sampling formation water without changing in-situ conditions were developed. (author)

The development of an expert system for the characterization of waste assay data

Energy Technology Data Exchange (ETDEWEB)

Bridges, S.; Hodges, J.; Sparrow, C. [Mississippi State Univ., Mississippi State, MS (United States)] [and others

1997-11-01

Containers of transuranic and low-level alpha contaminated waste generated as a byproduct of Department of Energy defense-related programs must be characterized before their proper disposition can be determined. Nondestructive assay methods are the most desirable means for assessing the mass and activity of the entrained transuranic radionuclides. However, there are other sources of information that may be useful in the characterization of the entrained waste (e.g., container manifests, information about the generation process, and destructive assay techniques performed on representative samples). This paper describes initial work on an expert system being developed to analyze and characterize containerized radiological waste. This system is being developed by scientists at the Mississippi State University Diagnostic and Instrumentation Laboratory (DIAL) in collaboration with scientists at the Idaho National Engineering Laboratory. The DIAL scientists are responsible for (1) the development of techniques to represent and reason with evidence from a variety of sources, and (2) the development of appropriate method(s) to represent and reason with confidence levels associated with that evidence. This paper describes exploratory versions of the expert system developed to evaluate four techniques for representing and reasoning with the confidence in the evidence: MYCIN-style certainty factors, Dempster-Shafer Theory, Bayesian networks, and fuzzy logic. 16 refs., 8 figs., 4 tabs.

The development of an expert system for the characterization of waste assay data

International Nuclear Information System (INIS)

Bridges, S.; Hodges, J.; Sparrow, C.

1997-01-01

Containers of transuranic and low-level alpha contaminated waste generated as a byproduct of Department of Energy defense-related programs must be characterized before their proper disposition can be determined. Nondestructive assay methods are the most desirable means for assessing the mass and activity of the entrained transuranic radionuclides. However, there are other sources of information that may be useful in the characterization of the entrained waste (e.g., container manifests, information about the generation process, and destructive assay techniques performed on representative samples). This paper describes initial work on an expert system being developed to analyze and characterize containerized radiological waste. This system is being developed by scientists at the Mississippi State University Diagnostic and Instrumentation Laboratory (DIAL) in collaboration with scientists at the Idaho National Engineering Laboratory. The DIAL scientists are responsible for (1) the development of techniques to represent and reason with evidence from a variety of sources, and (2) the development of appropriate method(s) to represent and reason with confidence levels associated with that evidence. This paper describes exploratory versions of the expert system developed to evaluate four techniques for representing and reasoning with the confidence in the evidence: MYCIN-style certainty factors, Dempster-Shafer Theory, Bayesian networks, and fuzzy logic. 16 refs., 8 figs., 4 tabs

Non-destructive assay system for uranium and plutonium in reprocessing input solutions. Hybrid K-edge/XRF Densitometer. JASPAS JC-11 final report

International Nuclear Information System (INIS)

Surugaya, N.; Abe, K.; Kurosawa, A.; Ikeda, H.; Kuno, Y.

1997-05-01

As a part of JASPAS programme, a non-radioactive assay system for the accountability of uranium and plutonium in input dissolver solutions of a spent fuel reprocessing plant, called Hybrid K-edge/XRF Densitometer, has been developed at the Tokai Reprocessing plant (TRP) since 1991. The instrument is the one of the hybrid type combined K-edge densitometry (KED) and X-ray fluorescence (XRF) analysis. The KED is used to determine the uranium concentration and the XRF is used to determine the U/Pu ratio. These results give the plutonium concentration in consequence. It is considered that the instrument has the capability of timely on-site verification for input accountancy. The instrument had been installed in the analytical hot cell at the TRP and the experiments comparing with Isotope Dilution Mass Spectrometry (IDMS) method have been carried out. As the results of measurements for the actual input solutions in the acceptance and performance tests, it was typically confirmed that the precision for determining uranium concentration by the KED was within 0.2%, whereas the XRF for plutonium performed within 0.7%. This final report summarizes the design information and performance data so as to end the JASPAS programme. (author)

Determining Plutonium Mass in Spent Fuel with Nondestructive Assay Techniques -- Preliminary Modeling Results Emphasizing Integration among Techniques

International Nuclear Information System (INIS)

Tobin, S.J.; Fensin, M.L.; Ludewigt, B.A.; Menlove, H.O.; Quiter, B.J.; Sandoval, N.P.; Swinhoe, M.T.; Thompson, S.J.

2009-01-01

There are a variety of motivations for quantifying Pu in spent (used) fuel assemblies by means of nondestructive assay (NDA) including the following: strengthen the capabilities of the International Atomic Energy Agencies to safeguards nuclear facilities, quantifying shipper/receiver difference, determining the input accountability value at reprocessing facilities and providing quantitative input to burnup credit determination for repositories. For the purpose of determining the Pu mass in spent fuel assemblies, twelve NDA techniques were identified that provide information about the composition of an assembly. A key point motivating the present research path is the realization that none of these techniques, in isolation, is capable of both (1) quantifying the elemental Pu mass of an assembly and (2) detecting the diversion of a significant number of pins. As such, the focus of this work is determining how to best integrate 2 or 3 techniques into a system that can quantify elemental Pu and to assess how well this system can detect material diversion. Furthermore, it is important economically to down-select among the various techniques before advancing to the experimental phase. In order to achieve this dual goal of integration and down-selection, a Monte Carlo library of PWR assemblies was created and is described in another paper at Global 2009 (Fensin et al.). The research presented here emphasizes integration among techniques. An overview of a five year research plan starting in 2009 is given. Preliminary modeling results for the Monte Carlo assembly library are presented for 3 NDA techniques: Delayed Neutrons, Differential Die-Away, and Nuclear Resonance Fluorescence. As part of the focus on integration, the concept of 'Pu isotopic correlation' is discussed and the role of cooling time determination.

Non-destructive assay of 242Pu by resonance neutron capture

International Nuclear Information System (INIS)

Kane, W.R.; Lu, Ming-Shih; Aronson, A.; Forman, L.; Vanier, P.E.

1995-01-01

For the accurate assay of plutonium by neutron correlation measurements, especially for material derived from high-burnup reactor fuel, the content of 242 Pu in a sample must be determined. Since 242 Pu has a long half-life (387,000 yr) and decays to 238 U by alpha particle emission with the accompanying emission of only weak, low-energy gamma rays, gamma-ray spectrometry methods which are ordinarily employed to determine the isotopic composition of a plutonium sample are not feasible for 242 Pu. The existence of a resonance in the neutron capture cross section of 242 Pu at an energy of 2.67 electron volts (eV) with a large (72, 000 barn) cross section affords the possibility for the quantitative assay of this isotope by epithermal neutron capture. Essential for this purpose is an appropriately designed geometry of neutron moderators and absorbers which will provide maximum flux in the eV region while suppressing thermal neutron capture by the fissile plutonium isotopes. Signatures for neutron capture in 242 Pu include the decay of 243 Pu (4.9 hr), prompt capture gamma rays (total energy 5.034 MeV), and the decay of an isomeric state (330 nanosecond). Experiments to determine the feasibility of this approach are currently in progress

Non-destructive measurement technologies for nuclear safeguards

International Nuclear Information System (INIS)

Gavron, A.

1998-04-01

There are three aspects that need to be in place in order to maintain a valid safeguards system: (1) Physical protection; guarding the access to nuclear materials using physical protection and surveillance. (2) Accounting systems; computer based accounting systems that provide the current location of nuclear materials, quantities, and the uncertainty in the assayed values. (3) Measurement systems; detectors, data acquisition systems and data analysis methods that provide accurate assays of nuclear material quantities for the accounting system. The authors expand on this third aspect, measurement systems, by discussing nondestructive assay (NDA) techniques. NDA is defined as the quantitative or qualitative determination of the kind and/or amount of nuclear material in an item without alteration or invasion of the item. This is contrasted with destructive analysis which is the process of taking small samples from the item in question, analyzing those samples by chemical analysis, destroying the original nature of the samples in the process (hence the term destructive), and applying the results to the entire item. Over the past 30 years, numerous techniques, using the atomic and nuclear properties of the actinides, have been developed for reliable, rapid, accurate, and tamper-proof NDA of nuclear materials. The authors distinguish between two types of measurements: the first involving the detection of spontaneously emitted radiation, produced by the natural radioactive decay processes; the second involving the detection of induced radiation, produced by irradiating the sample with an external radiation source

Nondestructive and intuitive determination of circadian chlorophyll rhythms in soybean leaves using multispectral imaging

Science.gov (United States)

Pan, Wen-Juan; Wang, Xia; Deng, Yong-Ren; Li, Jia-Hang; Chen, Wei; Chiang, John Y.; Yang, Jian-Bo; Zheng, Lei

2015-01-01

The circadian clock, synchronized by daily cyclic environmental cues, regulates diverse aspects of plant growth and development and increases plant fitness. Even though much is known regarding the molecular mechanism of circadian clock, it remains challenging to quantify the temporal variation of major photosynthesis products as well as their metabolic output in higher plants in a real-time, nondestructive and intuitive manner. In order to reveal the spatial-temporal scenarios of photosynthesis and yield formation regulated by circadian clock, multispectral imaging technique has been employed for nondestructive determination of circadian chlorophyll rhythms in soybean leaves. By utilizing partial least square regression analysis, the determination coefficients R2, 0.9483 for chlorophyll a and 0.8906 for chlorophyll b, were reached, respectively. The predicted chlorophyll contents extracted from multispectral data showed an approximately 24-h rhythm which could be entrained by external light conditions, consistent with the chlorophyll contents measured by chemical analyses. Visualization of chlorophyll map in each pixel offers an effective way to analyse spatial-temporal distribution of chlorophyll. Our results revealed the potentiality of multispectral imaging as a feasible nondestructive universal assay for examining clock function and robustness, as well as monitoring chlorophyll a and b and other biochemical components in plants. PMID:26059057

Innovative Applications of In Situ Gamma Spectroscopy for Non-destructive Assay of Transuranic Wastes

International Nuclear Information System (INIS)

Watters, D.J.; Weismann, J.J.; Duke, S.J.; Nicosia, W.C.

2009-01-01

Cabrera Services (CABRERA), under contract to National Security Technologies, LLC (NSTec), supported the transuranic (TRU) waste reduction initiative at the Radioactive Waste Management Complex of the Nevada Test Site (NTS). CABRERA developed advanced NDA techniques for oversized boxes (OSB) and drums using in situ gamma spectroscopy during several phases of the project. A more thorough characterization method was employed during the planning phase of the project to better understand the TRU content and distribution within each container, while a comprehensive NDA program was designed and implemented during the intrusive phase that guided waste segregation and re-packaging of both TRU and low-level wastes (LLW). NSTec took receipt of 58 oversized boxes of suspect TRU waste from Lawrence Livermore National Lab (LLNL). TRU waste is defined as greater than 3.7 kilobecquerels per gram [kBq/g] (100 nanocuries (nCi)/g) activity from alpha-emitting radionuclides with atomic number greater than 92 having a half-life greater than 20 years. Each box was custom-made to house a variety of suspect TRU wastes resulting from years of weapons program research, development, and testing. Since their arrival at NTS, the boxes have undergone several iterations of non-destructive assay (NDA) in preparation for the comprehensive repackaging effort. NDA has included two rounds of in situ gamma spectroscopy and real-time radiography (RTR) scans that were videotaped. Contents have been confirmed to include glove boxes, HEPA filters and their housings, and assorted process equipment and piping. TRU content was determined via directly measuring plutonium-239 (Pu-239), americium-241 (Am-241), and other radionuclides, while adding calculated results for non-measurable nuclides using reliable scaling factors developed from acceptable knowledge (AK). Advantages of CABRERA's NDA methods included: - More NDA information is available in the same amount of counting time, allowing NSTec to make more

The 30 Years of the Korean Society for Nondestructive Testing

International Nuclear Information System (INIS)

2010-05-01

The contents of this book are development of nondestructive testings; the origin of nondestructive testing, history of Korea on nondestructive testing and present condition of nondestructive testing in Korea, history of society, activity of society; structure and activity of society, publication of society academic project, educational work, international exchange, and the future and direction of development of the Korean society for nondestructive testing.

Beam diagnostic instruments of TARN

International Nuclear Information System (INIS)

Watanabe, Shin-ichi.

1987-09-01

The paper summarizes the beam diagnostic instruments of the low energy ion accumulation ring; TARN. With these monitors, position, profiles, bunch structure, intensity, emittance and momentum spread were measured to evaluate the injection and stacking experiments. The monitors provide the sensitivity of a few μA for the nondestructive and a few nA for the destructive monitors. Discussions on monitor probe and electronics are presented on the basis of an achievement of the beam stacking experiments. (author)

Nuclear materials safeguards. volume 2. 1975-February 1978 (a bibliography with abstracts). Report for 1975-feb 78

International Nuclear Information System (INIS)

Reimherr, G.W.

1978-03-01

Citations cover the methods of safeguarding nuclear materials through effective management, accountability, nondestructive assays, instrumentation, and automated continuous inventory systems. Problem areas and recommendations for improving the management of nuclear materials are included

Nondestructive nuclear measurement in the fuel cycle. Part 1

International Nuclear Information System (INIS)

Lyoussi, A.

2005-01-01

Nondestructive measurement techniques are today widely used in practically all steps of the fuel cycle. This article is devoted to the presentation of the control and characterization needs and to the main passive nondestructive nuclear methods used: 1 - nondestructive nuclear measurement, needs and motivation: nuclear fuel cycle, nondestructive nuclear measurements (passive and active methods), comments; 2 - main passive nondestructive nuclear measurement methods: gamma spectroscopy (principle, detectors, electronic systems, data acquisition and signal processing, domains of application, main limitations), passive neutronic measurements (needs and motivations, neutron detectors, total neutronic counting, neutronic coincidences counting, neutronic multiplicities counting, comments). (J.S.)

Tutoring system for nondestructive testing using computer

Energy Technology Data Exchange (ETDEWEB)

Kim, Jin Koo; Koh, Sung Nam [Joong Ang Inspection Co.,Ltd., Seoul (Korea, Republic of); Shim, Yun Ju; Kim, Min Koo [Dept. of Computer Engineering, Aju University, Suwon (Korea, Republic of)

1997-10-15

This paper is written to introduce a multimedia tutoring system for nondestructive testing using personal computer. Nondestructive testing, one of the chief methods for inspecting welds and many other components, is very difficult for the NDT inspectors to understand its technical basis without a wide experience. And it is necessary for considerable repeated education and training for keeping their knowledge. The tutoring system that can simulate NDT works is suggested to solve the above problem based on reasonable condition. The tutoring system shows basic theories of nondestructive testing in a book-style with video images and hyper-links, and it offers practices, in which users can simulate the testing equipment. The book-style and simulation practices provide effective and individual environments for learning nondestructive testing.

Tutoring system for nondestructive testing using computer

International Nuclear Information System (INIS)

Kim, Jin Koo; Koh, Sung Nam; Shim, Yun Ju; Kim, Min Koo

1997-01-01

This paper is written to introduce a multimedia tutoring system for nondestructive testing using personal computer. Nondestructive testing, one of the chief methods for inspecting welds and many other components, is very difficult for the NDT inspectors to understand its technical basis without a wide experience. And it is necessary for considerable repeated education and training for keeping their knowledge. The tutoring system that can simulate NDT works is suggested to solve the above problem based on reasonable condition. The tutoring system shows basic theories of nondestructive testing in a book-style with video images and hyper-links, and it offers practices, in which users can simulate the testing equipment. The book-style and simulation practices provide effective and individual environments for learning nondestructive testing.

Non-destructive analysis of museum objects by fibre-optic Raman spectroscopy.

Science.gov (United States)

Vandenabeele, Peter; Tate, Jim; Moens, Luc

2007-02-01

Raman spectroscopy is a versatile technique that has frequently been applied for the investigation of art objects. By using mobile Raman instrumentation it is possible to investigate the artworks without the need for sampling. This work evaluates the use of a dedicated mobile spectrometer for the investigation of a range of museum objects in museums in Scotland, including antique Egyptian sarcophagi, a panel painting, painted surfaces on paper and textile, and the painted lid and soundboard of an early keyboard instrument. The investigations of these artefacts illustrate some analytical challenges that arise when analysing museum objects, including fluorescing varnish layers, ambient sunlight, large dimensions of artefacts and the need to handle fragile objects with care. Analysis of the musical instrument (the Mar virginals) was undertaken in the exhibition gallery, while on display, which meant that interaction with the public and health and safety issues had to be taken into account. Experimental set-up for the non-destructive Raman spectroscopic investigation of a textile banner in the National Museums of Scotland.

Can non-destructive inspection be reliable

International Nuclear Information System (INIS)

Silk, M.G.; Stoneham, A.M.; Temple, J.A.G.

1988-01-01

The paper on inspection is based on the book ''The reliability of non-destructive inspection: assessing the assessment of structures under stress'' by the present authors (published by Adam Hilger 1987). Emphasis is placed on the reliability of inspection and whether cracks in welds or flaws in components can be detected. The need for non-destructive testing and the historical attitudes to non-destructive testing are outlined, along with the case of failure. Factors influencing reliable inspection are discussed, and defect detection trials involving round robin tests are described. The development of reliable inspection techniques and the costs of reliability and unreliability are also examined. (U.K.)

Prospects on the application of HTS SQUID magnetometry to nondestructive evaluation (NDE)

Science.gov (United States)

Weinstock, H.

1993-04-01

In light of recent advances in the fabrication of low-noise HTS SQUIDs, a review is presented on the use of LTS SQUID magnetometry for nondestructive evaluation (NDE). Examples are given on applications relating to defects in steel, subsurface cracks in aircraft frames, and voids in non-metallic structures. HTS SQUIDs may make a significant difference in the acceptance of these applications because sensing coils will be closer to a sample under test, there will be greater instrument portability and the problem of bringing liquid helium to remote locations will be eliminated.

Non-destructive controls

International Nuclear Information System (INIS)

Nouvet, A.

1978-01-01

The non-destructive controls permit, while respecting their integrity, the direct and individual examination of parts or complete objects as they are manufactured, as well as to follow the evolution of their eventual defects while in operation. The choice of control methods depends on the manufacturing process and shapes of parts, on the physical properties of their components as well as the nature, position and size of the defects which are likely to be detected. Whether it is a question of controls by means of ionizing radiation, flux of neutrons, ultrasons, acoustic source, sweating, magnetoscopy. Foucault currents, thermography, detection of leaks or non-destructive metallography, each has a limited field of application such that they are less competitive than complementary [fr

Instruments for non-destructive evaluation of advanced test reactor inpile tubes

International Nuclear Information System (INIS)

Livingston, R.A.; Beller, L.S.; Edgett, S.M.

1986-01-01

The Advanced Test Reactor is a 250 MW LWR used primarily for irradiation testing of materials contained in inpile tubes that pass through the reactor core. These tubes provided the high pressure and temperature water environment required for the test specimens. The reactor cooling water surrounding the inpile tubes is at much lower pressure and temperature. The structural integrity of the inpile tubes is monitored by routine surveillance to ensure against unplanned reactor shutdowns to replace defective inpile tubes. The improved instruments developed for inpile tube surveillance include a bore profilometer, ultrasonic flaw detetion system and bore diameter gauges. The design and function of these improved instruments is presented

Non-destructive testing at Chalk River

International Nuclear Information System (INIS)

Hilborn, J.W.

1976-01-01

In 1969 CRNL recognized the need for a strong group skilled in non-destructive test procedures. Within two years a new branch called Quality Control Branch was staffed and working. This branch engages in all aspects of non-destructive testing including development of new techniques, new applications of known technology, and special problems in support of operating reactors. (author)

The validation of waste assay systems during active test at Rokkasho Reprocessing Plant

International Nuclear Information System (INIS)

Tamura, Takayuki; Miura, Yasushi; Iwamoto, Tomonori

2007-01-01

In order to implement accurate material accountancy at Rokkasho Reprocessing Plant (RRP) as a large scale reprocessing plant, it is necessary to introduce accurate measurement systems not only for mainstream material, but also appropriate measurement systems for solid waste materials. In this sense, the generated wastes by the active test operation have been measured with the Non-Destructive Assay Systems, such as Rokkasho Hulls Measurement System (RHMS) and Waste Crate Assay System (WCAS) for accountancy. This paper describes the experience of the NDA operation and the evaluation results for accountancy. (author)

Local defect resonance for sensitive non-destructive testing

Science.gov (United States)

Adebahr, W.; Solodov, I.; Rahammer, M.; Gulnizkij, N.; Kreutzbruck, M.

2016-02-01

Ultrasonic wave-defect interaction is a background of ultrasound activated techniques for imaging and non-destructive testing (NDT) of materials and industrial components. The interaction, primarily, results in acoustic response of a defect which provides attenuation and scattering of ultrasound used as an indicator of defects in conventional ultrasonic NDT. The derivative ultrasonic-induced effects include e.g. nonlinear, thermal, acousto-optic, etc. responses also applied for NDT and defect imaging. These secondary effects are normally relatively inefficient so that the corresponding NDT techniques require an elevated acoustic power and stand out from conventional ultrasonic NDT counterparts for their specific instrumentation particularly adapted to high-power ultrasonic. In this paper, a consistent way to enhance ultrasonic, optical and thermal defect responses and thus to reduce an ultrasonic power required is suggested by using selective ultrasonic activation of defects based on the concept of local defect resonance (LDR). A strong increase in vibration amplitude at LDR enables to reliably detect and visualize the defect as soon as the driving ultrasonic frequency is matched to the LDR frequency. This also provides a high frequency selectivity of the LDR-based imaging, i.e. an opportunity of detecting a certain defect among a multitude of other defects in material. Some examples are shown how to use LDR in non-destructive testing techniques, like vibrometry, ultrasonic thermography and shearography in order to enhance the sensitivity of defect visualization.

Savannah River Plant Californium-252 Shuffler software manual

International Nuclear Information System (INIS)

Johnson, S.S.; Crane, T.W.; Eccleston, G.W.

1979-03-01

A software manual for operating the Savannah River Plant Shuffler nondestructive assay instrument is presented. The procedures for starting up the instrument, making assays, calibrating, and checking the performance of the hardware units are described. A list of the error messages with an explanation of the circumstances prompting the message and possible corrective measures is given. A summary of the software package is included showing the names and contents of the files and subroutines. The procedure for modifying the software package is outlined

In-line measurement of plutonium and americium in mixed solutions

International Nuclear Information System (INIS)

Li, T.K.

1981-01-01

A solution assay instrument (SAI) has been developed at the Los Alamos National Laboratory and installed in the plutonium purification and americium recovery process area in the Los Alamos Plutonium Processing Facility. The instrument is designed for accurate, timely, and simultaneous nondestructive analysis of plutonium and americium in process solutions that have a wide range of concentrations and Am/Pu ratios. For a 25-mL sample, the assay precision is 5 g/L within a 2000-s count time

An Intelligent Tutoring System for Nondestructive Testing Training

Energy Technology Data Exchange (ETDEWEB)

Kim, J. K.; Koh, S. N. [Joong Ang Inspection Co., Seoul (Korea, Republic of); Kim, M. K.; Shim, Y. J. [Ajou University, Suwon (Korea, Republic of)

1998-02-15

This paper is written to introduce a multimedia tutoring system for nondestructive testing using personal computer. Nondestructive testing, one of the chief methods for inspecting welds and many other components, is very difficult for the NDT inspectors to understand its technical basis without a wide experience. And it is necessary for considerable repeated education and training for keeping their knowledge. The tutoring system that can simulate NDT works is suggested to solve the above problem based on reasonable condition. The tutoring system shows basic theories of nondestructive testing in a book-style with video images and hyper-links, and it offers practices, in which users can simulate the testing equipment. The book-style and simulation practices provide effective and individual environments for learning nondestructive testing

An Intelligent Tutoring System for Nondestructive Testing Training

International Nuclear Information System (INIS)

Kim, J. K.; Koh, S. N.; Kim, M. K.; Shim, Y. J.

1998-01-01

This paper is written to introduce a multimedia tutoring system for nondestructive testing using personal computer. Nondestructive testing, one of the chief methods for inspecting welds and many other components, is very difficult for the NDT inspectors to understand its technical basis without a wide experience. And it is necessary for considerable repeated education and training for keeping their knowledge. The tutoring system that can simulate NDT works is suggested to solve the above problem based on reasonable condition. The tutoring system shows basic theories of nondestructive testing in a book-style with video images and hyper-links, and it offers practices, in which users can simulate the testing equipment. The book-style and simulation practices provide effective and individual environments for learning nondestructive testing

Non-destructive testing. V. 2

International Nuclear Information System (INIS)

Farley, J.M.; Nichols, R.W.

1988-01-01

The book entitled 'Non-destructive Testing' Volume 2, contains the proceedings of the fourth European Conference, organized by the British Institute of Non-Destructive Testing and held in London, September 1987. The volume contains seven chapters which examine the reliability of NDT, the economics of NDT and the use of NDT in:- civil engineering; oil, gas, coal and petrochemical industries; iron and steel industries; aerospace industry; and the nuclear and electricity supply industries. The seven chapters contain 78 papers, of which 19 are selected for INIS and indexed separately. (U.K.)

Quantitative radiological characterization of waste. Integration of gamma spectrometry and passive/active neutron assay

Energy Technology Data Exchange (ETDEWEB)

Simone, Gianluca; Mauro, Egidio; Gagliardi, Filippo; Gorello, Edoardo [Nucleco S.p.A., Rome (Italy)

2016-06-15

The radiological characterization of drums through Non-Destructive Assay (NDA) techniques commonly relies on gamma spectrometry. This paper introduces the procedure developed in Nucleco for the NDA radiological characterization of drums when the presence of Special Nuclear Material (SNM) is expected/observed. The procedure is based on the integration of a gamma spectrometry in SGS mode (Segmented Gamma Scanner) and a passive/active neutron assay. The application of this procedure is discussed on a real case of drums. The extension of the integration procedure to other gamma spectrometry systems is also discussed.

Monte-Carlo Application for Nondestructive Nuclear Waste Analysis

Science.gov (United States)

Carasco, C.; Engels, R.; Frank, M.; Furletov, S.; Furletova, J.; Genreith, C.; Havenith, A.; Kemmerling, G.; Kettler, J.; Krings, T.; Ma, J.-L.; Mauerhofer, E.; Neike, D.; Payan, E.; Perot, B.; Rossbach, M.; Schitthelm, O.; Schumann, M.; Vasquez, R.

2014-06-01

Radioactive waste has to undergo a process of quality checking in order to check its conformance with national regulations prior to its transport, intermediate storage and final disposal. Within the quality checking of radioactive waste packages non-destructive assays are required to characterize their radio-toxic and chemo-toxic contents. The Institute of Energy and Climate Research - Nuclear Waste Management and Reactor Safety of the Forschungszentrum Jülich develops in the framework of cooperation nondestructive analytical techniques for the routine characterization of radioactive waste packages at industrial-scale. During the phase of research and development Monte Carlo techniques are used to simulate the transport of particle, especially photons, electrons and neutrons, through matter and to obtain the response of detection systems. The radiological characterization of low and intermediate level radioactive waste drums is performed by segmented γ-scanning (SGS). To precisely and accurately reconstruct the isotope specific activity content in waste drums by SGS measurement, an innovative method called SGSreco was developed. The Geant4 code was used to simulate the response of the collimated detection system for waste drums with different activity and matrix configurations. These simulations allow a far more detailed optimization, validation and benchmark of SGSreco, since the construction of test drums covering a broad range of activity and matrix properties is time consuming and cost intensive. The MEDINA (Multi Element Detection based on Instrumental Neutron Activation) test facility was developed to identify and quantify non-radioactive elements and substances in radioactive waste drums. MEDINA is based on prompt and delayed gamma neutron activation analysis (P&DGNAA) using a 14 MeV neutron generator. MCNP simulations were carried out to study the response of the MEDINA facility in terms of gamma spectra, time dependence of the neutron energy spectrum

Handbook of nondestructive evaluation

National Research Council Canada - National Science Library

Hellier, Charles

2013-01-01

"Fully revised to cover the latest nondestructive testing (NDT) procedures, this practical resource reviews established and emerging methods for examining materials without destroying them or altering their structure...

Neutron CSI: Integrated platform for non-destructive composition and stress imaging with neutrons

International Nuclear Information System (INIS)

Materna, T.; Pirling, T.

2011-01-01

We propose to build an interdisciplinary platform for non-destructive analysis and imaging with neutrons. The project regroups an instrument already available at ILL (Laue-Langevin Institute), SALSA, with a new one for Neutron Tomography coupled to Prompt-Gamma Neutron Activation (PGNA) as well as partial usage of another proposed instrument, FIPPS. The focus of the proposition is the versatility of high spatial resolution and energy-selective neutron tomography to provide a rapid and precise 3D morphological map of an object as well as indirect information on its 3D elemental and structural composition through the scan of Bragg-edges in transmission. Coupled to PGNA imaging and the strain analysis power of SALSA, the aim of the platform is to answer key questions occurring in geological, metallurgical, engineering and medical fields, material research and cultural heritage. (authors)

Delayed Gamma-Ray Spectroscopy for Non-Destructive Assay of Nuclear Materials

Energy Technology Data Exchange (ETDEWEB)

Ludewigt, Bernhard [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Mozin, Vladimir [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Campbell, Luke [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Favalli, Andrea [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hunt, Alan W. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Reedy, Edward T.E. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Seipel, Heather [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-06-01

High-­energy, beta-delayed gamma-­ray spectroscopy is a potential, non-­destructive assay techniques for the independent verification of declared quantities of special nuclear materials at key stages of the fuel cycle and for directly assaying nuclear material inventories for spent fuel handling, interim storage, reprocessing facilities, repository sites, and final disposal. Other potential applications include determination of MOX fuel composition, characterization of nuclear waste packages, and challenges in homeland security and arms control verification. Experimental measurements were performed to evaluate fission fragment yields, to test methods for determining isotopic fractions, and to benchmark the modeling code package. Experimental measurement campaigns were carried out at the IAC using a photo-­neutron source and at OSU using a thermal neutron beam from the TRIGA reactor to characterize the emission of high-­energy delayed gamma rays from ²³⁵U, ²³⁹Pu, and ²⁴¹Pu targets following neutron induced fission. Data were collected for pure and combined targets for several irradiation/spectroscopy cycle times ranging from 10/10 seconds to 15/30 minutes.The delayed gamma-ray signature of ²⁴¹Pu, a significant fissile constituent in spent fuel, was measured and compared to ²³⁹Pu. The ²⁴¹Pu/²³⁹Pu ratios varied between 0.5 and 1.2 for ten prominent lines in the 2700-­3600 keV energy range. Such significant differences in relative peak intensities make it possible to determine relative fractions of these isotopes in a mixed sample. A method for determining fission product yields by fitting the energy and time dependence of the delayed gamma-­ray emission was developed and demonstrated on a limited ²³⁵U data set. De-­convolution methods for determining fissile fractions were developed and tested on the experimental data. The use of high count-­rate LaBr₃ detectors

Development of a portable ambient temperature radiometric assaying instrument

International Nuclear Information System (INIS)

Lavietes, A.D.; McQuaid, J.H.; Ruhter, W.D.; Paulus, T.J.

1995-01-01

There is a strong need for portable radiometric instrumentation that can accurately confirm the presence of nuclear materials and allow isotopic analysis of radionuclides in the field. To fulfill this need, the authors are developing a hand-held, non-cryogenic, low-power gamma- and X-ray measurement and analysis instrument that can both search and then accurately verify the presence of nuclear materials. The authors report on the use of cadmium zinc telluride detectors, signal processing electronics, and the new field-portable instrument based on the MicroNOMAD Multichannel Analyzer from EG and G ORTEC. They will also describe the isotopic analysis that allows uranium enrichment measurements to be made accurately in the field. The benefits of this work are realized in a wide spectrum of applications that include Arms Control, Nuclear Safeguards, Environmental Management, Emergency Response, and Treaty Verification

Nondestructive quality evaluation technology of agricultural products

International Nuclear Information System (INIS)

Noh, Sang Ha

1997-01-01

Quality evaluation of agricultural products has been interested to many researchers for many years and as the result, several nondestructive techniques and so many papers have been reported for quality evaluation of agricultural products. These nondestructive techniques are based on the detection of mechanical, optical, electrical, electro-magnetical, dielectric and vibrational properties of agricultural products that are well correlated with certain quality factors of the products such as color, shape, firmness, sugar content, external or internal defects, moisture content, etc. The sophistication of nondestructive methods has evolved rapidly with modem technologies. In this paper an emphasis was put on reviewing some of those papers and techniques which could be led to on-line measurement for practical use.

Optical surface contouring for non-destructive inspection of turbomachinery

Science.gov (United States)

Modarress, Dariush; Schaack, David F.

1994-03-01

Detection of stress cracks and other surface defects during maintenance and in-service inspection of propulsion system components, including turbine blades and combustion compartments, is presently performed visually. There is a need for a non-contact, miniaturized, and fully fieldable instrument that may be used as an automated inspection tool for inspection of aircraft engines. During this SBIR Phase 1 program, the feasibility of a ruggedized optical probe for automatic and nondestructive inspection of complex shaped objects will be established. Through a careful analysis of the measurement requirements, geometrical and optical constraints, and consideration of issues such as manufacturability, compactness, simplicity, and cost, one or more conceptual optical designs will be developed. The proposed concept will be further developed and a prototype will be fabricated during Phase 2.

A comparison of conventional and prototype nondestructive measurements on molten salt extraction residues

International Nuclear Information System (INIS)

Longmire, V.L.; Scarborough, A.M.

1987-01-01

Impure plutonium metal is routinely processed by molten salt extraction (MSE) to reduce the amount of americium in the metal product. Individuals form four technical groups at the Los Alamos National Laboratory (LANL) participated in a study designed to evaluate the accuracy of various nondestructive assay (NDA) techniques for measuring the plutonium content in MSE residues. This study was performed to improve in-house accountability of these items and to identify assay methods that would be acceptable for determining receiver's values for MSE salts from off-site sources. Recent upgrades have been made in a segmented gamma scan system, in a thermal neutron coincidence counter, and in the software of a gamma isotopic system that supports the calorimeters at LAPF. The authors evaluated the newer systems against the older systems versus destructive qualitative analyses. Fourteen containers of MSE residues were selected to be studied. Seven of these salts originated at LAPF and seven originated at Rockwell International Rocky Flats plant. Measurements have been performed on these items in their original containers, and the items have been repackaged into a different geometry and assayed again

Uncertainty analysis of a nondestructive radioassay system for transuranic waste

International Nuclear Information System (INIS)

Harker, Y.D.; Blackwood, L.G.; Meachum, T.R.; Yoon, W.Y.

1996-01-01

Radioassay of transuranic waste in 207 liter drums currently stored at the Idaho National Engineering Laboratory is achieved using a Passive Active Neutron (PAN) nondestructive assay system. In order to meet data quality assurance requirements for shipping and eventual permanent storage of these drums at the Waste Isolation Pilot Plant in Carlsbad, New Mexico, the total uncertainty of the PAN system measurements must be assessed. In particular, the uncertainty calculations are required to include the effects of variations in waste matrix parameters and related variables on the final measurement results. Because of the complexities involved in introducing waste matrix parameter effects into the uncertainty calculations, standard methods of analysis (e.g., experimentation followed by propagation of errors) could not be implemented. Instead, a modified statistical sampling and verification approach was developed. In this modified approach the total performance of the PAN system is simulated using computer models of the assay system and the resultant output is compared with the known input to assess the total uncertainty. This paper describes the simulation process and illustrates its application to waste comprised of weapons grade plutonium-contaminated graphite molds

Nondestructive assay system for use in decommissioning a plutonium-handling facility

International Nuclear Information System (INIS)

Roche, C.T.; Vronich, J.J.; Bellinger, F.O.; Perry, R.B.

1979-07-01

Argonne National Laboratory is decommissioning a facility used to fabricate reactor fuel elements. The equipment is contaminated with alpha emitters at levels up to 10 12 dpm/100 cm 2 . The objective of decontamination is to reduce the TRU concentrations below 10 nCi/g of waste. A portable NDA procedure using NaI(T1) gamma-spectrometric techniques was selected to measure the residual Pu and 241 Am in the glove boxes. Assays were performed at different stages in the decontamination process to estimate the detection system sensitivity and the effectiveness of the cleaning efforts

MCNP efficiency calculations of INEEL passive active neutron assay system for simulated TRU waste assays

International Nuclear Information System (INIS)

Yoon, W.Y.; Meachum, T.R.; Blackwood, L.G.; Harker, Y.D.

2000-01-01

The Idaho National Engineering and Environmental Laboratory Stored Waste Examination Pilot Plant (SWEPP) passive active neutron (PAN) radioassay system is used to certify transuranic (TRU) waste drums in terms of quantifying plutonium and other TRU element activities. Depending on the waste form involved, significant systematic and random errors need quantification in addition to the counting statistics. To determine the total uncertainty of the radioassay results, a statistical sampling and verification approach has been developed. In this approach, the total performance of the PAN nondestructive assay system is simulated using the computer models of the assay system, and the resultant output is compared with the known input to assess the total uncertainty. The supporting steps in performing the uncertainty analysis for the passive assay measurements in particular are as follows: (1) Create simulated waste drums and associated conditions; (2) Simulate measurements to determine the basic counting data that would be produced by the PAN assay system under the conditions specified; and (3) Apply the PAN assay system analysis algorithm to the set of counting data produced by simulating measurements to determine the measured plutonium mass. The validity of this simulation approach was verified by comparing simulated output against results from actual measurements using known plutonium sources and surrogate waste drums. The computer simulation of the PAN system performance uses the Monte Carlo N-Particle (MCNP) Code System to produce a neutron transport calculation for a simulated waste drum. Specifically, the passive system uses the neutron coincidence counting technique, utilizing the spontaneous fission of 240 Pu. MCNP application to the SWEPP PAN assay system uncertainty analysis has been very useful for a variety of waste types contained in 208-ell drums measured by a passive radioassay system. The application of MCNP to the active radioassay system is also feasible

Active spectral imaging nondestructive evaluation (SINDE) camera

Energy Technology Data Exchange (ETDEWEB)

Simova, E.; Rochefort, P.A., E-mail: eli.simova@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada)

2016-06-15

A proof-of-concept video camera for active spectral imaging nondestructive evaluation has been demonstrated. An active multispectral imaging technique has been implemented in the visible and near infrared by using light emitting diodes with wavelengths spanning from 400 to 970 nm. This shows how the camera can be used in nondestructive evaluation to inspect surfaces and spectrally identify materials and corrosion. (author)

Immobilisation of barley aleurone layers enables parallelisation of assays and analysis of transient gene expression in single cells

DEFF Research Database (Denmark)

Zor, Kinga; Mark, Christina; Heiskanen, Arto

2017-01-01

at a single time point. By immobilising barley aleurone layer tissue on polydimethylsiloxane pillars in the lid of a multiwell plate, continuous monitoring of living tissue is enabled using multiple non-destructive assays in parallel. Cell viability and menadione reducing capacity were monitored in the same...

Determining plutonium mass in spent fuel with non-destructive assay techniques - NGSU research overview and update on 6 NDA techniques

Energy Technology Data Exchange (ETDEWEB)

Tobin, Stephen J [Los Alamos National Laboratory; Conlin, Jeremy L [Los Alamos National Laboratory; Evans, Louise G [Los Alamos National Laboratory; Hu, Jianwei [Los Alamos National Laboratory; Blanc, Pauline C [Los Alamos National Laboratory; Lafleur, Adrienne M [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory; Schear, Melissa A [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Croft, Stephen [Los Alamos National Laboratory; Fensin, Michael L [Los Alamos National Laboratory; Freeman, Corey R [Los Alamos National Laboratory; Koehler, William E [Los Alamos National Laboratory; Mozin, V [Los Alamos National Laboratory; Sandoval, N P [Los Alamos National Laboratory; Lee, T H [KAERI; Cambell, L W [PNNL; Cheatham, J R [ORNL; Gesh, C J [PNNL; Hunt, A [IDAHO STATE UNIV; Ludewigt, B A [LBNL; Smith, L E [PNNL; Sterbentz, J [INL

2010-09-15

This poster is one of two complementary posters. The Next Generation Safeguards Initiative (NGSI) of the U.S. DOE has initiated a multi-lab/university collaboration to quantify the plutonium (Pu) mass in, and detect the diversion of pins from, spent nuclear fuel assemblies with non-destructive assay (NDA). This research effort has the goal of quantifying the capability of 14 NDA techniques as well as training a future generation of safeguards practitioners. By November of 2010, we will be 1.5 years into the first phase (2.5 years) of work. This first phase involves primarily Monte Carlo modelling while the second phase (also 2.5 years) will focus on experimental work. The goal of phase one is to quantify the detection capability of the various techniques for the benefit of safeguard technology developers, regulators, and policy makers as well as to determine what integrated techniques merit experimental work, We are considering a wide range of possible technologies since our research horizon is longer term than the focus of most regulator bodies. The capability of all of the NDA techniques will be determined for a library of 64 17 x 17 PWR assemblies [burnups (15, 30, 45, 60 GWd/tU), initial enrichments (2, 3, 4, 5%) and cooling times (1, 5, 20, 80 years)]. The burnup and cooling time were simulated with each fuel pin being comprised of four radial regions. In this paper an overview of the purpose will be given as well as a technical update on the following 6 neutron techniques: {sup 252}Cf Interrogation with Prompt Neutron Detection, Delayed Neutrons, Differential Die-Away, Differential Die-Away Self-Interrogation, Passive Neutron Albedo Reactivity, Self-Integration Neutron Resonance Densitometry. The technical update will quantify the anticipated performance of each technique for the 64 assemblies of the spent fuel library.

Determining plutonium mass in spent fuel with non-destructive assay techniques - NGSI research overview and update on 6 NDA techniques

International Nuclear Information System (INIS)

Tobin, Stephen J.; Conlin, Jeremy L.; Evans, Louise G.; Hu, Kianwei; Blanc, P.C.; Lafleur, Am; Menlove, H.O.; Schear, M.A.; Swinhoe, M.T.; Croft, S.; Fensin, M.L.; Freeman, C.R.; Koehler, W.E.; Mozin, V.; Sandoval, N.P.; Lee, T.H.; Cambell, L.W.; Cheatham, J.R.; Gesh, C.J.; Hunt, A.; Ludewigt, B.A.; Smith, L.E.; Sterbentz, J.

2010-01-01

This poster is one of two complementary posters. The Next Generation Safeguards Initiative (NGSI) of the U.S. DOE has initiated a multi-lab/university collaboration to quantify the plutonium (Pu) mass in, and detect the diversion of pins from, spent nuclear fuel assemblies with non-destructive assay (NDA). This research effort has the goal of quantifying the capability of 14 NDA techniques as well as training a future generation of safeguards practitioners. By November of 2010, we will be 1.5 years into the first phase (2.5 years) of work. This first phase involves primarily Monte Carlo modelling while the second phase (also 2.5 years) will focus on experimental work. The goal of phase one is to quantify the detection capability of the various techniques for the benefit of safeguard technology developers, regulators, and policy makers as well as to determine what integrated techniques merit experimental work, We are considering a wide range of possible technologies since our research horizon is longer term than the focus of most regulator bodies. The capability of all of the NDA techniques will be determined for a library of 64 17 x 17 PWR assemblies (burnups (15, 30, 45, 60 GWd/tU), initial enrichments (2, 3, 4, 5%) and cooling times (1, 5, 20, 80 years)). The burnup and cooling time were simulated with each fuel pin being comprised of four radial regions. In this paper an overview of the purpose will be given as well as a technical update on the following 6 neutron techniques: 252 Cf Interrogation with Prompt Neutron Detection, Delayed Neutrons, Differential Die-Away, Differential Die-Away Self-Interrogation, Passive Neutron Albedo Reactivity, Self-Integration Neutron Resonance Densitometry. The technical update will quantify the anticipated performance of each technique for the 64 assemblies of the spent fuel library.

Non-Destructive Inspection Lab (NDI)

Data.gov (United States)

Federal Laboratory Consortium — The NDI specializes in applied research, development and performance of nondestructive inspection procedures (flourescent penetrant, magnetic particle, ultrasonics,...

Relative performance of a TGS for the assay of drummed waste as function of collimator opening

International Nuclear Information System (INIS)

Kane, S.C.; Croft, S.; McClay, P.; Venkataraman, R.; Villani, M.F.

2007-01-01

Improving the safety, accuracy and overall cost effectiveness of the processes and methods used to characterize and handle radioactive waste is an on-going mission for the nuclear industry. An important contributor to this goal is the development of superior non-destructive assay instruments. The Tomographic Gamma Scanner (TGS) is a case in point. The TGS applies low spatial resolution experimental computed tomography (CT) linear attenuation coefficient maps with three-dimensional high-energy resolution single photon emission reconstructions. The results are presented as quantitative matrix attenuation corrected images and assay values for gamma-emitting radionuclides. Depending on a number of operational factors, this extends the diversity of waste forms that can be assayed, to a given accuracy, to items containing more heterogeneous matrix distributions and less uniform emission activity distributions. Recent advances have significantly extended the capability to a broader range of matrix density and to a wider dynamic range of surface dose rate. Automated systems sense the operational conditions, including the container type, and configure themselves accordingly. The TGS also provides a flexible data acquisition platform and can be used to perform far-field style measurements, classical segmented gamma scanner measurements, or to implement hybrid methods, such as reconstructions that use a priori knowledge to constrain the image reconstruction or the underlying energy dependence of the attenuation. A single, yet flexible, general purpose instrument of this kind adds several tiers of strategic and tactical value to facilities challenged by a diverse and difficult to assay waste streams. The TGS is still in the early phase of industrial uptake. There are only a small number of general purpose TGS systems operating worldwide, most being configured to automatically select between a few configurations appropriate for routine operations. For special investigations

Thickness measurement instrument with memory storage of multiple calibrations

International Nuclear Information System (INIS)

Lieber, S.; Schlesinger, J.; Lieber, D.; Baker, A.

1979-01-01

An improved backscatter instrument for the nondestructive measurement of coatings on a substrate is described. A memory having selectable memory areas, each area having stored intelligence available which is determinative of the shape of a functional plot of coating thickness versus backscatter counts per minute unique for each particular combination of emitting isotope, substrate material, coating material and physical characteristics of the measuring instrument. A memory selector switch connects a selected area of memory to a microprocessor operating under program control whereby the microprocessor reads the intelligence stored at the selected area and converts the backscattered count of the coating being measured into indicia of coating thickness

Health Physics Measurements Services

International Nuclear Information System (INIS)

Carchon, R.

2001-01-01

SCK-CEN's programme on health physics measurements includes various activities in dosimetry, calibration , instrumentation , gamma-ray spectrometry, whole body counting , the preparation of standard sources, non-destructive assay and the maintenance of Euratom Fork detectors. Main achievements in these topical areas in 2000 are summarised

Development of a numerical experiment technique to solve inverse gamma-ray transport problems with application to nondestructive assay of nuclear waste barrels

International Nuclear Information System (INIS)

Chang, C.J.; Anghaie, S.

1998-01-01

A numerical experimental technique is presented to find an optimum solution to an undetermined inverse gamma-ray transport problem involving the nondestructive assay of radionuclide inventory in a nuclear waste drum. The method introduced is an optimization scheme based on performing a large number of numerical simulations that account for the counting statistics, the nonuniformity of source distribution, and the heterogeneous density of the self-absorbing medium inside the waste drum. The simulation model uses forward projection and backward reconstruction algorithms. The forward projection algorithm uses randomly selected source distribution and a first-flight kernel method to calculate external detector responses. The backward reconstruction algorithm uses the conjugate gradient with nonnegative constraint or the maximum likelihood expectation maximum method to reconstruct the source distribution based on calculated detector responses. Total source activity is determined by summing the reconstructed activity of each computational grid. By conducting 10,000 numerical simulations, the error bound and the associated confidence level for the prediction of total source activity are determined. The accuracy and reliability of the simulation model are verified by performing a series of experiments in a 208-ell waste barrel. Density heterogeneity is simulated by using different materials distributed in 37 egg-crate-type compartments simulating a vertical segment of the barrel. Four orthogonal detector positions are used to measure the emerging radiation field from the distributed source. Results of the performed experiments are in full agreement with the estimated error and the confidence level, which are predicted by the simulation model

Neutrons and music: Imaging investigation of ancient wind musical instruments

Science.gov (United States)

Festa, G.; Tardino, G.; Pontecorvo, L.; Mannes, D. C.; Senesi, R.; Gorini, G.; Andreani, C.

2014-10-01

A set of seven musical instruments and two instruments cares from the 'Fondo Antico della Biblioteca del Sacro Convento' in Assisi, Italy, were investigated through neutron and X-ray imaging techniques. Historical and scientific interests around ancient musical instruments motivate an intense research effort for their characterization using non-destructive and non-invasive techniques. X-ray and neutron tomography/radiography were applied to the study of composite material samples containing wood, hide and metals. The study was carried out at the NEUTRA beamline, PSI (Paul Scherrer Institute, Switzerland). Results of the measurements provided new information on the composite and multi-scale structure, such as: the internal structure of the samples, position of added materials like metals, wood fiber displays, deformations, presence of adhesives and their spatial distribution and novel insight about construction methods to guide the instruments' restoration process.

Non-destructive Assessment of Relief Marking Parameters of Heat Shrinkable Installation Parts for Aviation Technology

Directory of Open Access Journals (Sweden)

Kondratov Aleksandr P.

2017-01-01

Full Text Available The article explains a new method of relief marking of heat-shrinkable tubing and sleeves made of polymer materials with “shape memory effect.” Method of instrument evaluation of relief marking stereometry of installation parts for aviation equipment, made of polyvinyl chloride, polyethyleneterephthalate and polystyrene was developed and the results were explained. Parameters of pin-point relief marking and compliance of point forms to the Braille font standard were determined with the use of the non-destructive method based on the color of interference pattern with precision of 0.02 mm.

Development of Techniques for Spent Fuel Assay - Differential Dieaway Final Report

International Nuclear Information System (INIS)

Swinhoe, Martyn Thomas; Goodsell, Alison; Ianakiev, Kiril Dimitrov; Iliev, Metodi; Desimone, David J.; Rael, Carlos D.; Henzl, Vladimir; Polk, Paul John

2016-01-01

This report summarizes the work done under a DNDO R&D funded project on the development of the differential dieaway method to measure plutonium in spent fuel. There are large amounts of plutonium that are contained in spent fuel assemblies, and currently there is no way to make quantitative non-destructive assay. This has led NA24 under the Next Generation Safeguards Initiative (NGSI) to establish a multi-year program to investigate, develop and implement measurement techniques for spent fuel. The techniques which are being experimentally tested by the existing NGSI project do not include any pulsed neutron active techniques. The present work covers the active neutron differential dieaway technique and has advanced the state of knowledge of this technique as well as produced a design for a practical active neutron interrogation instrument for spent fuel. Monte Carlo results from the NGSI effort show that much higher accuracy (1-2%) for the Pu content in spent fuel assemblies can be obtained with active neutron interrogation techniques than passive techniques, and this would allow their use for nuclear material accountancy independently of any information from the operator. The main purpose of this work was to develop an active neutron interrogation technique for spent nuclear fuel.

Reports from the Yayoi symposium on quantitative non-destructive evaluation, (1)

International Nuclear Information System (INIS)

1990-02-01

The report consists of four parts. The first part deals with nondestructive evaluation in the nuclear power industry, focusing on in-service inspection in nuclear power plant, eddy current crack detection test of steam generator heat-exchanger tube, and nondestructive test of thin-wall components. The second part discusses inverse problems and quantification for nondestructive evaluation, centering on the identification of defect by boundary element method, quantification by using supersonic wave, defect shape recognition by the electrical potential method, and a neural network applied to crack type recognition. The third part deals with the application of electromagnetic phenomena to nondestructive evaluation, focusing on a superconducting quantum interference device, electromagnetic measurement in the iron industry, and nondestructive measurement of residual stress by magnetic process. The fourth part discusses visualization techniques for nondestructive evaluation, focusing on image processing, neutron radiography, X-ray CT, defect diagnosis by infrared rays, and visualization of magnetic field. (N.K.)

X-ray L/sub III/-edge densitometer for assay of mixed S.N.M. solutions

International Nuclear Information System (INIS)

Russo, P.A.; Canada, T.R.; Langner, D.G.; Tape, J.W.; Hsue, S.T.; Cowder, L.R.; Mosley, W.C.; Reynolds, L.; Thompson, M.C.

1979-01-01

Simultaneous nondestructive analysis of uranium and plutonium in coprocessed solutions is accomplished using L/sub III/-edge densitometry in at-line instrumentation. The densitometer measures the transmission through solutions of a continuous x-ray spectrum, and gives accuracies of approximately one-half percent and three percent for uranium and plutonium concentrations respectively

Nondestructive analysis and development

Science.gov (United States)

Moslehy, Faissal A.

1993-01-01

This final report summarizes the achievements of project #4 of the NASA/UCF Cooperative Agreement from January 1990 to December 1992. The objectives of this project are to review NASA's NDE program at Kennedy Space Center (KSC) and recommend means for enhancing the present testing capabilities through the use of improved or new technologies. During the period of the project, extensive development of a reliable nondestructive, non-contact vibration technique to determine and quantify the bond condition of the thermal protection system (TPS) tiles of the Space Shuttle Orbiter was undertaken. Experimental modal analysis (EMA) is used as a non-destructive technique for the evaluation of Space Shuttle thermal protection system (TPS) tile bond integrity. Finite element (FE) models for tile systems were developed and were used to generate their vibration characteristics (i.e. natural frequencies and mode shapes). Various TPS tile assembly configurations as well as different bond conditions were analyzed. Results of finite element analyses demonstrated a drop in natural frequencies and a change in mode shapes which correlate with both size and location of disbond. Results of experimental testing of tile panels correlated with FE results and demonstrated the feasibility of EMA as a viable technique for tile bond verification. Finally, testing performed on the Space Shuttle Columbia using a laser doppler velocimeter demonstrated the application of EMA, when combined with FE modeling, as a non-contact, non-destructive bond evaluation technique.

Non-destructive testing of electronic parts

International Nuclear Information System (INIS)

Widenhorn, G.

1980-01-01

The requirements on quality, safety, faultlessness and reliability of electric components increase because of the high complexity of the appliances in which they are used. By means of examples a survey is given on the common non-destructive testing methods, testing operation and evaluation of test results on electric components which must meet in their application high requirements on quality and reliability. Defective components, especially those with hidden failures are sorted out by non-destructive testing and the failure frequency of the appliances and plants in testing and operation is greatly reduced. (orig.) [de

Nondestructive characterization of austenitic stainless steels

International Nuclear Information System (INIS)

Jayakumar, T.; Kumar, Anish

2010-01-01

The paper presents an overview of the non-destructive methodologies developed at the authors' laboratory for characterization of various microstructural features, residual stresses and corrosion in austenitic stainless steels. Various non-destructive evaluation (NDE) parameters such as ultrasonic velocity, ultrasonic attenuation, spectral analysis of the ultrasonic signals, magnetic hysteresis parameters and eddy current amplitude have been used for characterization of grain size, precipitation behaviour, texture, recrystallization, thermomechanical processing, degree of sensitization, formation of martensite from metastable austenite, assessment of residual stresses, degree of sensitization and propensity for intergranular corrosion in different austenitic steels. (author)

Bremsstrahlung-Based Imaging and Assays of Radioactive, Mixed and Hazardous Waste

Science.gov (United States)

Kwofie, J.; Wells, D. P.; Selim, F. A.; Harmon, F.; Duttagupta, S. P.; Jones, J. L.; White, T.; Roney, T.

2003-08-01

A new nondestructive accelerator based x-ray fluorescence (AXRF) approach has been developed to identify heavy metals in large-volume samples. Such samples are an important part of the process and waste streams of U.S Department of Energy sites, as well as other industries such as mining and milling. Distributions of heavy metal impurities in these process and waste samples can range from homogeneous to highly inhomogeneous, and non-destructive assays and imaging that can address both are urgently needed. Our approach is based on using high-energy, pulsed bremsstrahlung beams (3-6.5 MeV) from small electron accelerators to produce K-shell atomic fluorescence x-rays. In addition we exploit pair-production, Compton scattering and x-ray transmission measurements from these beams to probe locations of high density and high atomic number. The excellent penetrability of these beams allows assays and images for soil-like samples at least 15 g/cm2 thick, with elemental impurities of atomic number greater than approximately 50. Fluorescence yield of a variety of targets was measured as a function of impurity atomic number, impurity homogeneity, and sample thickness. We report on actual and potential detection limits of heavy metal impurities in a soil matrix for a variety of samples, and on the potential for imaging, using AXRF and these related probes.

Advanced non-destructive methods for an efficient service performance

International Nuclear Information System (INIS)

Rauschenbach, H.; Clossen-von Lanken Schulz, M.; Oberlin, R.

2015-01-01

Due to the power generation industry's desire to decrease outage time and extend inspection intervals for highly stressed turbine parts, advanced and reliable Non-destructive methods were developed by Siemens Non-destructive laboratory. Effective outage performance requires the optimized planning of all outage activities as well as modern Non-destructive examination methods, in order to examine the highly stressed components (turbine rotor, casings, valves, generator rotor) reliably and in short periods of access. This paper describes the experience of Siemens Energy with an ultrasonic Phased Array inspection technique for the inspection of radial entry pinned turbine blade roots. The developed inspection technique allows the ultrasonic inspection of steam turbine blades without blade removal. Furthermore advanced Non-destructive examination methods for joint bolts will be described, which offer a significant reduction of outage duration in comparison to conventional inspection techniques. (authors)

Non-destructive control of castings

International Nuclear Information System (INIS)

Boutault, J.; Mascre, C.

1978-01-01

The object of non-destructive control in foundries is to verify the metal structure, the absence of unacceptable discontinuity, total tightness, etc. This leads to a range of very varied controls according to the importance of the series, the quality level required by the specifications, the nature of the alloy. The originality of the solutions which are imperative for castings is shown through examples: casting of high quality complex forms in short series; very thick unit parts; very large series of parts requiring on efficient automation of non-destructive control. Lastly the publishing of testing methods and interpretating rules, which are the base of a friendly understanding between constructors and founders are recalled [fr

Computed neutron coincidence counting applied to passive waste assay

Energy Technology Data Exchange (ETDEWEB)

Bruggeman, M.; Baeten, P.; De Boeck, W.; Carchon, R. [Nuclear Research Centre, Mol (Belgium)

1997-11-01

Neutron coincidence counting applied for the passive assay of fissile material is generally realised with dedicated electronic circuits. This paper presents a software based neutron coincidence counting method with data acquisition via a commercial PC-based Time Interval Analyser (TIA). The TIA is used to measure and record all time intervals between successive pulses in the pulse train up to count-rates of 2 Mpulses/s. Software modules are then used to compute the coincidence count-rates and multiplicity related data. This computed neutron coincidence counting (CNCC) offers full access to all the time information contained in the pulse train. This paper will mainly concentrate on the application and advantages of CNCC for the non-destructive assay of waste. An advanced multiplicity selective Rossi-alpha method is presented and its implementation via CNCC demonstrated. 13 refs., 4 figs., 2 tabs.

Computed neutron coincidence counting applied to passive waste assay

International Nuclear Information System (INIS)

Bruggeman, M.; Baeten, P.; De Boeck, W.; Carchon, R.

1997-01-01

Neutron coincidence counting applied for the passive assay of fissile material is generally realised with dedicated electronic circuits. This paper presents a software based neutron coincidence counting method with data acquisition via a commercial PC-based Time Interval Analyser (TIA). The TIA is used to measure and record all time intervals between successive pulses in the pulse train up to count-rates of 2 Mpulses/s. Software modules are then used to compute the coincidence count-rates and multiplicity related data. This computed neutron coincidence counting (CNCC) offers full access to all the time information contained in the pulse train. This paper will mainly concentrate on the application and advantages of CNCC for the non-destructive assay of waste. An advanced multiplicity selective Rossi-alpha method is presented and its implementation via CNCC demonstrated. 13 refs., 4 figs., 2 tabs

Development of Multichannel Eddy Current Testing Instrument

International Nuclear Information System (INIS)

Lee, Hee Jong; Cho, Chan Hee; Nam, Min Woo; Yoon, Byung Sik; Yoo, Hyun Joo

2010-01-01

Four main techniques of electromagnetic testing are used for commercial applications: eddy current testing, alternating current field testing, magnetic flux leakage testing and remote field testing. Eddy current testing is a nondestructive evaluation method, which makes eddy current flow on a specimen by applying driving pulse to eddy current probe coil, by using eddy current testing device, and makes the change of eddy current which is dependently caused by flaws, material characteristics, testing condition, receiving through eddy current, and analyzes material properties, flaws, status on the specimen. Application of EC instrumentation varies widely in industry from the identification of metal heat treatment to the inspection of steam generator tubing in nuclear power plants. In this study, we have designed multichannel EC instrument which can be applicable to the NDE of the tube in heat exchanger for electric power facility, chemistry, and military industry, and finally confirmed the proper function of EC instrumentation

Inspection with non destructive assay techniques of the aluminium coating of the TRIGA Mark III reactor vat; Inspeccion con tecnicas de ensayos no destructivos del recubrimiento de aluminio de la tina del reactor TRIGA Mark III

Energy Technology Data Exchange (ETDEWEB)

Reyes A, A.I.; Gonzalez M, A.; Castaneda J, G.; Rivera M, H.; Sandoval G, I. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

2001-07-01

In June 2000, the Reactor Department assigned to the Scientific Research Direction of the National Institute of Nuclear Research requested to the Non-destructive Assays Laboratory (LEND), assigned to the Materials Science Management, the inspection and measurement of thickness of the aluminium coating (liner) of the TRIGA Mark III reactor vat with non-destructive assay techniques, due to that the aluminium coating is exposed mainly to undergo slimming on its back side due to corrosion phenomena. Activity that was able to be carried out from april until august 2001. It is worth pointing out that this type of inspection with these techniques was realized by first time. The non-destructive assays (NDA) are techniques which use indirect physical methods for inspecting the sanitation of components in process or in service, for detect lack of continuity or defects which affect their quality or usefulness. The application of those do not alter the physical, chemical, mechanical or dimensional properties of the part subject of inspection. The results of the application of the ultrasound inspection techniques, industrial radiography and penetrating liquids are presented. (Author)

Health Physics Measurements Services

Energy Technology Data Exchange (ETDEWEB)

Carchon, R

2001-04-01

SCK-CEN's programme on health physics measurements includes various activities in dosimetry, calibration , instrumentation , gamma-ray spectrometry, whole body counting , the preparation of standard sources, non-destructive assay and the maintenance of Euratom Fork detectors. Main achievements in these topical areas in 2000 are summarised.

Control of training instrument

International Nuclear Information System (INIS)

Seo, K. W.; Joo, Y. C.; Park, J. C.; Hong, C. S.; Choi, I. K.; Cho, B. J.; Lee, H. Y.; Seo, I. S.; Park, N. K.

1996-01-01

This report describes the annual results on control of training instrument. The scope and contents are the following: 1. Control of Compact Nuclear Simulator 2. Control of Radiation/Radioactivity Measurement 3. Control of Non-Destructive Testing Equipment 4. Control of Chemical Equipment 5. Control of Personal Computer 6. Other related Lecture Aid Equipment. Efforts were employed to upgrade the training environment through retrofitting experimental facilities, compiling teaching materials and reforcing audio-visual aids. The Nuclear Training Center executed the open-door training courses for 2,496 engineers/scientists from the nuclear regulatory, nuclear industries, research institutes and other related organizations by means of offering 45 training courses during the fiscal year 1995. (author). 15 tabs., 7 figs., 13 refs

Proceedings: 19th International Nondestructive Testing and Evaluation of Wood Symposium

Science.gov (United States)

Robert J. Ross; Raquel Gonçalves; Xiping Wang

2015-01-01

The 19th International Nondestructive Testing and Evaluation of Wood Symposium was hosted by the University of Campinas, College of Agricultural Engineering (FEAGRI/UNICAMP), and the Brazilian Association of Nondestructive Testing and Evaluation (ABENDI) in Rio de Janeiro, Brazil, on September 22–25, 2015. This Symposium was a forum for those involved in nondestructive...

Use of the virtual instrument technology in complex diagnostics of marine electrical equipment

Directory of Open Access Journals (Sweden)

Ivlev M. L.

2017-12-01

Full Text Available The assessment of the most informative methods of diagnostics of mechanisms with electric drive has been given; their realization in a measuring complex on the basis of the virtual device has been considered. The comparative analysis of vibration methods for the analysis of current spectra and the thermal method of nondestructive testing has been carried out. It has been stated that methods of vibration diagnostics are more sensitive to defects in the mechanical part of the electric drive (determination of defects in bearing assemblies, misalignment of shafts, imbalance of rotating parts. Analysis of the current spectrum at the early stage has shown the defects of rotor windings, static and dynamic rotor eccentricity. The temperature of the bearing assemblies and the stator (the thermal control method indicates the defects in lubrication and cooling systems. The set of methods of nondestructive control allows increase the completeness and reliability of diagnosis of the mechanism with electric drive. The optimal solution to realize into one measuring instrument all methods of diagnostics is to use the technology of virtual instruments. The list of components for the measuring part of the complex and the functional scheme of the program for processing the results have been given. Spectra of vibration of defective mechanisms have been obtained with the help of the measuring complex based on the virtual instrument. Some recommendations have been given on the introduction of the virtual appliance in the State register of measuring instruments.

Industrial strategy for nondestructive control

International Nuclear Information System (INIS)

Martin, P.; Michaut, J.P.

1994-01-01

For Electricite de France, the nondestructive control strategy passes by a responsibility of services, a competition between companies, a clarification of the market access and a dialogue with the companies

Development of hotcell non-destructive examination techniques

Energy Technology Data Exchange (ETDEWEB)

Kim, Young Uhn; Yu, S. C.; Kang, B. S.; Byun, K. S. [Chungbuk National University, Chungju (Korea)

2002-01-01

The purpose of this project is to establish non-destructive examination techniques which needs to determine the status of spent nuclear fuel and/or bundles. Through the project, we will establish an image reconstruction tomography which is a kind of non-destructive techniques in Hotcell. The tomography technique can be used to identify the 2-dimensional density distribution of fission products in the spent fuel rods and/or bundles. And form results of the measurement and analysis of magnetic properties of neutron irradiated material in the press vessel and reactor, we will develop some techniques to test its hardness and defects. In 2001, the first year, we have established mathematical background and necessary data and informations to develop the techniques. We will try to find some experimental results that are necessary in developing the Hotcell non-destructive examination techniques in the coming year. 14 refs., 65 figs., 5 tabs. (Author)

Nondestructive nuclear measurement in the fuel cycle. Part 2

International Nuclear Information System (INIS)

Lyoussi, A.

2005-01-01

Nondestructive measurement techniques are today widely used in practically all steps of the fuel cycle. This article is devoted to the presentation of the control and characterization needs and to the main active nondestructive nuclear methods used: 1 - main active nondestructive nuclear measurement methods: active neutronic measurement (needs and motivations, physical principle, measurement of delayed neutrons following a continuous irradiation, measurement of prompt neutrons (differential die-away technique - DDT), measurement of prompt and delayed neutrons (Sphincs method), neutronic method coupled to gamma spectroscopy), measurement by induced photo-fissions (needs and motivations, physical principle); 2 - conclusion. (J.S.)

Modelling, simulation and visualisation for electromagnetic non-destructive testing

International Nuclear Information System (INIS)

Ilham Mukriz Zainal Abidin; Abdul Razak Hamzah

2010-01-01

This paper reviews the state-of-the art and the recent development of modelling, simulation and visualization for eddy current Non-Destructive Testing (NDT) technique. Simulation and visualization has aid in the design and development of electromagnetic sensors and imaging techniques and systems for Electromagnetic Non-Destructive Testing (ENDT); feature extraction and inverse problems for Quantitative Non-Destructive Testing (QNDT). After reviewing the state-of-the art of electromagnetic modelling and simulation, case studies of Research and Development in eddy current NDT technique via magnetic field mapping and thermography for eddy current distribution are discussed. (author)

A state-of-the-art passive gamma-ray assay system

International Nuclear Information System (INIS)

Sampson, T.E.; Parker, J.L.; Cowder, L.R.; Kern, E.A.; Garcia, D.L.; Ensslin, N.

1987-01-01

We report details of the development of a high-accuracy, high-precision system for the non-destructive assay of 235 U in solution. The system can measure samples with concentrations ranging from 0.0001 to 500 g 235 U/l using 200-ml samples at low concentrations, 30-ml samples at high concentrations, and 1000-s measurement times. The accuracy and precision goals of 0.1% were essentially attained for concentrations above 100 g/l. This at-line system, designed for a production plant environment, represents a significant improvement in the state of the art

Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program

International Nuclear Information System (INIS)

2005-01-01

The Performance Demonstration Program (PDP) for Nondestructive Assay (NDA) is a test program designed to yield data on measurement system capability to characterize drummed transuranic (TRU) waste generated throughout the Department of Energy (DOE) complex. The tests are conducted periodically and provide a mechanism for the independent and objective assessment of NDA system performance and capability relative to the radiological characterization objectives and criteria of the Office of Characterization and Transportation (OCT). The primary documents requiring an NDA PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC), which requires annual characterization facility participation in the PDP, and the Quality Assurance Program Document (QAPD). This NDA PDP implements the general requirements of the QAPD and applicable requirements of the WAC. Measurement facilities must demonstrate acceptable radiological characterization performance through measurement of test samples comprised of pre-specified PDP matrix drum/radioactive source configurations. Measurement facilities are required to analyze the NDA PDP drum samples using the same procedures approved and implemented for routine operational waste characterization activities. The test samples provide an independent means to assess NDA measurement system performance and compliance per criteria delineated in the NDA PDP Plan. General inter-comparison of NDA measurement system performance among DOE measurement facilities and commercial NDA services can also be evaluated using measurement results on similar NDA PDP test samples. A PDP test sample consists of a 55-gallon matrix drum containing a waste matrix type representative of a particular category of the DOE waste inventory and nuclear material standards of known radionuclide and isotopic composition typical of DOE radioactive material. The PDP sample components are made available to participating measurement facilities as designated by the

European conference on nondestructive testing

Energy Technology Data Exchange (ETDEWEB)

Klyuev, V V

1985-01-01

Information on the 3-d European conference on nondestructive testing (NT) held in October, 1984 in Florence, is presented. Plenary reports were devoted to complex use of different NT methods, tendencies to NT automation and robotics, transition from defectoscopy to quality control, determination of phisico-mechanical properties of items using different control methods, formulation of unified international programs on professional training and qualification. Section reports cover the following directions: NT use in aviation and astronautics, construction, welding engineering, studying works of art; personnel training, economics, NT functioning, automation, calibration, standardization, quality control over metallic and nonmetallic objects. Some reports concerned nondestructive testing of items during their use. Attention is paied to radiographic testing and neutron radiography as well as to image processing. NT equipment was also discussed.

Development of Techniques for Spent Fuel Assay – Differential Dieaway Final Report

Energy Technology Data Exchange (ETDEWEB)

Swinhoe, Martyn Thomas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Goodsell, Alison [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ianakiev, Kiril Dimitrov [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Iliev, Metodi [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Desimone, David J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Rael, Carlos D. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Henzl, Vladimir [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Polk, Paul John [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-07-28

This report summarizes the work done under a DNDO R&D funded project on the development of the differential dieaway method to measure plutonium in spent fuel. There are large amounts of plutonium that are contained in spent fuel assemblies, and currently there is no way to make quantitative non-destructive assay. This has led NA24 under the Next Generation Safeguards Initiative (NGSI) to establish a multi-year program to investigate, develop and implement measurement techniques for spent fuel. The techniques which are being experimentally tested by the existing NGSI project do not include any pulsed neutron active techniques. The present work covers the active neutron differential dieaway technique and has advanced the state of knowledge of this technique as well as produced a design for a practical active neutron interrogation instrument for spent fuel. Monte Carlo results from the NGSI effort show that much higher accuracy (1-2%) for the Pu content in spent fuel assemblies can be obtained with active neutron interrogation techniques than passive techniques, and this would allow their use for nuclear material accountancy independently of any information from the operator. The main purpose of this work was to develop an active neutron interrogation technique for spent nuclear fuel.

Research process of nondestructive testing pitting corrosion in metal material

Directory of Open Access Journals (Sweden)

Bo ZHANG

2017-12-01

Full Text Available Pitting corrosion directly affects the usability and service life of metal material, so the effective nondestructive testing and evaluation on pitting corrosion is of great significance for fatigue life prediction because of data supporting. The features of pitting corrosion are elaborated, and the relation between the pitting corrosion parameters and fatigue performance is pointed out. Through introducing the fundamental principles of pitting corrosion including mainly magnetic flux leakage inspection, pulsed eddy current and guided waves, the research status of nondestructive testing technology for pitting corrosion is summarized, and the key steps of nondestructive testing technologies are compared and analyzed from the theoretical model, signal processing to industrial applications. Based on the analysis of the signal processing specificity of different nondestructive testing technologies in detecting pitting corrosion, the visualization combined with image processing and signal analysis are indicated as the critical problems of accurate extraction of pitting defect information and quantitative characterization for pitting corrosion. The study on non-contact nondestructive testing technologies is important for improving the detection precision and its application in industries.

Content addressable memories in scientific instruments

International Nuclear Information System (INIS)

Lotto, I. de; Golinelli, S.

1975-01-01

The content-addressable-memory feature of a new system designed in these laboratories for non-destructive testing of nuclear reactor pressure vessels based on acoustic emission analysis is presented. The content addressable memory is divided into two parts: the first selects the most frequent events among incoming ones (FES: Frequent Event Selection memory), the second stores the frequent events singled out (FEM: Frequent Event Memory). The statistical behaviour of FES is analyzed, and experimental results are compared with theoretical ones; the model presented proved to be a useful tool in dimensioning the instrument store capacity. (Auth.)

DOE assay methods used for characterization of contact-handled transuranic waste

Energy Technology Data Exchange (ETDEWEB)

Schultz, F.J. (Oak Ridge National Lab., TN (United States)); Caldwell, J.T. (Pajarito Scientific Corp., Los Alamos, NM (United States))

1991-08-01

US Department of Energy methods used for characterization of contact-handled transuranic (CH-TRU) waste prior to shipment to the Waste Isolation Pilot Plant (WIPP) are described and listed by contractor site. The methods described are part of the certification process. All CH-TRU waste must be assayed for determination of fissile material content and decay heat values prior to shipment and prior to storage on-site. Both nondestructive assay (NDA) and destructive assay methods are discussed, and new NDA developments such as passive-action neutron (PAN) crate counter improvements and neutron imaging are detailed. Specifically addressed are assay method physics; applicability to CH-TRU wastes; calibration standards and implementation; operator training requirements and practices; assay procedures; assay precision, bias, and limit of detection; and assay limitation. While PAN is a new technique and does not yet have established American Society for Testing and Materials. American National Standards Institute, or Nuclear Regulatory Commission guidelines or methods describing proper calibration procedures, equipment setup, etc., comparisons of PAN data with the more established assay methods (e.g., segmented gamma scanning) have demonstrated its reliability and accuracy. Assay methods employed by DOE have been shown to reliable and accurate in determining fissile, radionuclide, alpha-curie content, and decay heat values of CH-TRU wastes. These parameters are therefore used to characterize packaged waste for use in certification programs such as that used in shipment of CH-TRU waste to the WIPP. 36 refs., 10 figs., 7 tabs.

DOE assay methods used for characterization of contact-handled transuranic waste

International Nuclear Information System (INIS)

Schultz, F.J.; Caldwell, J.T.

1991-08-01

US Department of Energy methods used for characterization of contact-handled transuranic (CH-TRU) waste prior to shipment to the Waste Isolation Pilot Plant (WIPP) are described and listed by contractor site. The methods described are part of the certification process. All CH-TRU waste must be assayed for determination of fissile material content and decay heat values prior to shipment and prior to storage on-site. Both nondestructive assay (NDA) and destructive assay methods are discussed, and new NDA developments such as passive-action neutron (PAN) crate counter improvements and neutron imaging are detailed. Specifically addressed are assay method physics; applicability to CH-TRU wastes; calibration standards and implementation; operator training requirements and practices; assay procedures; assay precision, bias, and limit of detection; and assay limitation. While PAN is a new technique and does not yet have established American Society for Testing and Materials. American National Standards Institute, or Nuclear Regulatory Commission guidelines or methods describing proper calibration procedures, equipment setup, etc., comparisons of PAN data with the more established assay methods (e.g., segmented gamma scanning) have demonstrated its reliability and accuracy. Assay methods employed by DOE have been shown to reliable and accurate in determining fissile, radionuclide, alpha-curie content, and decay heat values of CH-TRU wastes. These parameters are therefore used to characterize packaged waste for use in certification programs such as that used in shipment of CH-TRU waste to the WIPP. 36 refs., 10 figs., 7 tabs

Nondestructive determination of residual fuel on leached hulls and dissolver sludges from LWR fuel reprocessing

International Nuclear Information System (INIS)

Wuerz, H.; Wagner, K.; Becker, H.J.

1990-01-01

In reprocessing plants leached hulls and dissolver sludges represent rather important intermediate level α-waste streams. A control of the Pu content of these waste streams is desirable. The nondestructive assay method to be preferred would be passive neutron counting. However, before any decision on passive neutron monitoring becomes possible a characterization of hulls and sludges in terms of Pu content and neutron emission is necessary. For the direct determination of plutonium on hulls and in sludges, as coming from reprocessing, an active neutron measurement is required. A simple, and sufficiently sensitive active neutron method which can easily be installed uses as stationary Cf-252 neutron source. This method was used for the characterization of hulls and sludges in terms of plutonium content and total neutron emission in the WAK. Meanwhile a total of 28 batches of leached hulls and 22 batches of dissolver sludges from reprocessing of PWR fuel have been assayed. The paper describes the assay method used and gives an analysis of the error sources together with a discussion of the results and the accuracies obtained in a reprocessing plant. (orig./HP)

Annual meeting 1996 'Nondestructive materials testing'. German, Austrian and Swiss nondestructive materials testing standards as mirrored by international standardization. Vol. 1. Lectures

International Nuclear Information System (INIS)

1996-01-01

The volume contains 45 lectures which were given at the annual meeting of the German Society for Nondestructive Testing on May 13-15, 1996 at Lindau. The main subjects were: Standardization of nondestructive testing, irradiation testing, ultrasonic testing and electromagnetic processes. 13 individual articles were included in the ENERGY database. (MM) [de

Annual meeting 1996 'Nondestructive material testing'. German, Austrian and Swiss nondestructive materials testing standards as mirrored by international standardization. Vol. 2. Posters

International Nuclear Information System (INIS)

1996-01-01

The volume contains 49 poster articles which were presented at the Annual Meeting of the German Society for Nondestructive Testing at Lindau on May 13-15, 1996. The main subjects were: Standardization of nondestructive testing, irradiation testing, ultrasonic testing and electromagnetic processes. 16 individual articles were included in the ENERGY databank. (MM) [de

Standard test method for nondestructive assay of special nuclear material holdup using Gamma-Ray spectroscopic methods

CERN Document Server

American Society for Testing and Materials. Philadelphia

2007-01-01

1.1 This test method describes gamma-ray methods used to nondestructively measure the quantity of 235U, or 239Pu remaining as holdup in nuclear facilities. Holdup occurs in all facilities where nuclear material is processed, in process equipment, in exhaust ventilation systems and in building walls and floors. 1.2 This test method includes information useful for management, planning, selection of equipment, consideration of interferences, measurement program definition, and the utilization of resources (1, 2, 3, 4). 1.3 The measurement of nuclear material hold up in process equipment requires a scientific knowledge of radiation sources and detectors, transmission of radiation, calibration, facility operations and error analysis. It is subject to the constraints of the facility, management, budget, and schedule; plus health and safety requirements; as well as the laws of physics. The measurement process includes defining measurement uncertainties and is sensitive to the form and distribution of the material...

New applications of old processes in nondestructive testing - irradiation and backscatter methods

International Nuclear Information System (INIS)

Segebade, C.

1995-01-01

The application of two non-destructive test processes based on photon irradiation measurement is described. The photon backscatter process and the irradiation measurement were used in the technical field and in examining artificial articles. With the aid of the two beam absorption method, wall thicknesses on large liquid containers made of polyethylene and of steel were measured. The same process with a somewhat modified test rig was used in measuring pipe wall thickness on an antique musical instrument. The components made of turbine blade material were excited to X-ray fluorescence with a source of radio nuclides and analysed with a semiconductor detector. This is particularly advantageous for elements which cannot be determined or can only be determined with difficulty by 'conventional' methods (e.g.: yttrium, rhenium). Also the wall thickness measurement for large (diameter approx. 6 m) plastic pipes with the aid of gamma backscatter is described, as is humidity measurement in brick material. Finally, there is a report on wood profile measurement in a stringed instrument with the aid of gamma backscatter. (orig./HP) [de

21 CFR 862.1660 - Quality control material (assayed and unassayed).

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Quality control material (assayed and unassayed... Test Systems § 862.1660 Quality control material (assayed and unassayed). (a) Identification. A quality... that may arise from reagent or analytical instrument variation. A quality control material (assayed and...

SWEPP PAN assay system uncertainty analysis: Passive mode measurements of graphite waste

International Nuclear Information System (INIS)

Blackwood, L.G.; Harker, Y.D.; Meachum, T.R.; Yoon, Woo Y.

1997-07-01

The Idaho National Engineering and Environmental Laboratory is being used as a temporary storage facility for transuranic waste generated by the U.S. Nuclear Weapons program at the Rocky Flats Plant (RFP) in Golden, Colorado. Currently, there is a large effort in progress to prepare to ship this waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. In order to meet the TRU Waste Characterization Quality Assurance Program Plan nondestructive assay compliance requirements and quality assurance objectives, it is necessary to determine the total uncertainty of the radioassay results produced by the Stored Waste Examination Pilot Plant (SWEPP) Passive Active Neutron (PAN) radioassay system. To this end a modified statistical sampling and verification approach has been developed to determine the total uncertainty of a PAN measurement. In this approach the total performance of the PAN nondestructive assay system is simulated using computer models of the assay system and the resultant output is compared with the known input to assess the total uncertainty. This paper is one of a series of reports quantifying the results of the uncertainty analysis of the PAN system measurements for specific waste types and measurement modes. In particular this report covers passive mode measurements of weapons grade plutonium-contaminated graphite molds contained in 208 liter drums (waste code 300). The validity of the simulation approach is verified by comparing simulated output against results from measurements using known plutonium sources and a surrogate graphite waste form drum. For actual graphite waste form conditions, a set of 50 cases covering a statistical sampling of the conditions exhibited in graphite wastes was compiled using a Latin hypercube statistical sampling approach

Proceedings CORENDE: Regional congress on nondestructive and structural evaluation

International Nuclear Information System (INIS)

1997-01-01

Works are presented at the CORENDE: Regional Congress on Nondestructive and Structural Evaluation organized by the National Atomic Energy Commission and the National Technological University (Mendoza). This congress wants to be the forum where people from research, industry and marketing might meet and discuss ideas towards the fostering of these new cultural habits. Papers covering all disciplines contributing to the evaluation of components, systems and structures are welcome: nondestructive evaluation methods and techniques (ultrasound, eddy currents and other electromagnetic methods, acoustic emission, radiography, thermography, leak testing, dye-penetrants, visual inspection, etc.), personnel certification, welding inspection, nondestructive metallography, optics and lasers, fluid-structure interaction, vibrations, extensometry, modelling of structures [es

Non-Destructive Testing for Concrete Structure

International Nuclear Information System (INIS)

Tengku Sarah Tengku Amran; Noor Azreen Masenwat; Mohamad Pauzi Ismail

2015-01-01

Nondestructive testing (NDT) is a technique to determine the integrity of a material, component or structure. It is essential in the inspection of alteration, repair and new construction in the building industry. There are a number of non-destructive testing techniques that can be applied to determine the integrity of concrete in a completed structure. Each has its own advantages and limitations. For concrete, these problems relate to strength, cracking, dimensions, delamination, and inhomogeneities. NDT is reasonably good and reliable tool to measure the property of concrete which also gives the fair indication of the compressive strength development. This paper discussed the concrete inspection using combined methods of NDT. (author)

Nondestructive testing of concrete structures

International Nuclear Information System (INIS)

Rufino, Randy R.; Relunia, Estrella

1999-01-01

Nondestructive testing of concrete is highly inhomogeneous which makes it cumbersome to setup experimental procedures and analyze experimental data. However, recent research and development activities have discovered the different methods of NDT, like the electromagnetic method, ultrasonic pulse velocity test, pulse echo/impact echo test, infrared thermography, radar or short pulse radar techniques, neutron and gamma radiometry, radiography, carbonation test and half-cell potential method available for NDT of concrete structures. NDT of concrete is emerging as a useful tool for quality control and assurance. This papers also describes the more common NDT methods discussed during the two-week course on 'Nondestructive Testing of Concrete Structures', held at the Malaysian Institute for Nuclear Technology Research (MINT) in Malaysia, which was jointly organized by MINT and the International Atomic Energy Agency (IAEA)

Basic metallurgy for nondestructive testing

International Nuclear Information System (INIS)

Abdul Nassir Ibrahim; Azali Muhammad; Ab. Razak Hamzah; Abd. Aziz Mohamed; Mohamad Pauzi Ismail

2008-01-01

For this chapter, reader will be served with the basic knowledge on metallurgy for nondestructive testing. One the main application of nondestructive testing is to detect discontinuity of mass defect in metal. As we already know, metal are widely used in many application such as in building as a system, component and engineering product. Steel and iron are metal that usually used in industry, especially heavy industry such as gas and petroleum industry, chemistry, electric generation, automobile, and military device. Based on this, basic knowledge on metallurgy must need by NDT practitioner. The combination between metallurgy and datas from radiography testing can make radiographer good interpretation on quality of the metal inspected and can used to make a good decision either to accept or not certain product, system or components.

Nondestructive techniques for characterizing mechanical properties of structural materials: An overview

Science.gov (United States)

Vary, A.; Klima, S. J.

1985-01-01

An overview of nondestructive evaluation (NDE) is presented to indicate the availability and application potentials of techniques for quantitative characterization of the mechanical properties of structural materials. The purpose is to review NDE techniques that go beyond the usual emphasis on flaw detection and characterization. Discussed are current and emerging NDE techniques that can verify and monitor entrinsic properties (e.g., tensile, shear, and yield strengths; fracture toughness, hardness, ductility; elastic moduli) and underlying microstructural and morphological factors. Most of the techniques described are, at present, neither widely applied nor widely accepted in commerce and industry because they are still emerging from the laboratory. The limitations of the techniques may be overcome by advances in applications research and instrumentation technology and perhaps by accommodations for their use in the design of structural parts.

Tokai densitometer manual

International Nuclear Information System (INIS)

Sprinkle, J.K. Jr.; Hsue, S.T.; Junck, K.

1987-01-01

In 1979, the Tokai densitometer was installed at the Tokai Reprocessing Plant in Tokai, Japan. It uses a nondestructive active technique (K-edge absorption densitometry) to assay solutions for plutonium content. The original hardware was upgraded in 1984 and 1985. This manual describes the instrument's operation after the upgrade. 2 refs

Nondestructive testing technology for measurement coatings thickness on material

International Nuclear Information System (INIS)

Yang Mingtai; Wu Lunqiang; Zhang Lianping

2008-01-01

The principle, applicability range, advantage and disadvantage of electromagnetic, eddy current method, β backscatter method and XRF methods for nondestructive testing coating thickness of material have been reviewed. The relevant apparatus and manufacturers have been summarized. And the application and developmental direction of manufacturers for nondestructive testing coatings thickness has been foreshowed. (authors)

Problems studied within the state research project New Methods of Nondestructive Materials Testing Using Ionizing Radiation

International Nuclear Information System (INIS)

Mysak, F.; Strba, J.

1979-01-01

A state research project is described divided into ten subprojects, viz.: New trends of ionizing radiation detection using television technology in nondestructive testing; the application of accelerators for thick-walled product testing; the atlas of butt welds of medium thicknesses; the application of radioanalytical methods in testing the wear of gearboxes and other components of instrument parts; multielemental analyses of combustion engine wear using radionuclides; the application of radioisotope methods in research into wear of antifriction bearings of trucks and railway cars; the application of radionuclides in assessing corrosion resistance of steels and corrosion protection systems; the application of radionuclide methods in improving the quality of high-grade steel production; the selection and testing of radionuclide instruments for building production control, intermediate and acceptance checks; and radioisotope methods for building machine and equipment control. (M.S.)

Qualifying program on Non-Destructive Testing, Visual Inspection of the welding (level 2)

International Nuclear Information System (INIS)

Shafee, M. A.

2011-01-01

Nondestructive testing is a wide group of analysis technique used in science and industry to evaluate the properties of a material, component or system without causing damage. Common Non-Destructive Testing methods include ultrasonic, magnetic-particle, liquid penetrate, radiographic, visual inspection and eddy-current testing. AAEA put the new book of the Non-Destructive Testing publication series that focused on Q ualifying program on Non-Destructive Testing, visual inspection of welding-level 2 . This book was done in accordance with the Arab standard certification of Non-Destructive Testing (ARAB-NDT-CERT-002) which is agreeing with the ISO-9712 (2005) and IAEA- TEC-DOC-487. It includes twenty one chapters dealing with engineering materials used in industry, the mechanical behavior of metals, metal forming equipments, welding, metallurgy, testing of welds, introduction to Non-Destructive Testing, defects in metals, welding defects and discontinuities, introduction to visual inspection theory, properties and tools of visual testing, visual testing, quality control regulations, standards, codes and specifications, procedures of welding inspections, responsibility of welding test inspector, qualification of Non-Destructive Testing inspector and health safety during working.

Neutrons and music: Imaging investigation of ancient wind musical instruments

Energy Technology Data Exchange (ETDEWEB)

Festa, G., E-mail: giulia.festa@roma2.infn.it [Università degli Studi di Roma Tor Vergata (Italy); Università degli Studi di Milano-Bicocca (Italy); Consiglio Nazionale delle Ricerche-IPCF, Messina (Italy); Tardino, G. [BauArt Basel, Basel (Switzerland); Pontecorvo, L. [Conservatorio di Cosenza – Cosenza Conservatory (Italy); Mannes, D.C. [Paul Scherrer Institut, Villigen (Switzerland); Senesi, R. [Università degli Studi di Roma Tor Vergata (Italy); Consiglio Nazionale delle Ricerche-IPCF, Messina (Italy); Gorini, G. [Università degli Studi di Milano-Bicocca (Italy); Andreani, C. [Università degli Studi di Roma Tor Vergata (Italy); Consiglio Nazionale delle Ricerche-IPCF, Messina (Italy)

2014-10-01

A set of seven musical instruments and two instruments cares from the ‘Fondo Antico della Biblioteca del Sacro Convento’ in Assisi, Italy, were investigated through neutron and X-ray imaging techniques. Historical and scientific interests around ancient musical instruments motivate an intense research effort for their characterization using non-destructive and non-invasive techniques. X-ray and neutron tomography/radiography were applied to the study of composite material samples containing wood, hide and metals. The study was carried out at the NEUTRA beamline, PSI (Paul Scherrer Institute, Switzerland). Results of the measurements provided new information on the composite and multi-scale structure, such as: the internal structure of the samples, position of added materials like metals, wood fiber displays, deformations, presence of adhesives and their spatial distribution and novel insight about construction methods to guide the instruments’ restoration process.

Neutrons and music: Imaging investigation of ancient wind musical instruments

International Nuclear Information System (INIS)

Festa, G.; Tardino, G.; Pontecorvo, L.; Mannes, D.C.; Senesi, R.; Gorini, G.; Andreani, C.

2014-01-01

A set of seven musical instruments and two instruments cares from the ‘Fondo Antico della Biblioteca del Sacro Convento’ in Assisi, Italy, were investigated through neutron and X-ray imaging techniques. Historical and scientific interests around ancient musical instruments motivate an intense research effort for their characterization using non-destructive and non-invasive techniques. X-ray and neutron tomography/radiography were applied to the study of composite material samples containing wood, hide and metals. The study was carried out at the NEUTRA beamline, PSI (Paul Scherrer Institute, Switzerland). Results of the measurements provided new information on the composite and multi-scale structure, such as: the internal structure of the samples, position of added materials like metals, wood fiber displays, deformations, presence of adhesives and their spatial distribution and novel insight about construction methods to guide the instruments’ restoration process

Nuclear safeguards applications of energy-dispersive absorption edge densitometry

International Nuclear Information System (INIS)

Russo, P.A.; Hsue, S.T.; Langner, D.G.; Sprinkle, J.K. Jr.

1980-01-01

The principles and techniques of absorption edge densitometry in the energy-dispersive mode are summarized as they apply to the nondestructive assay of special nuclear materials. Five existing field instruments, designed for special nuclear materials accounting measurements, are described. Results of the testing of these instruments as well as recent laboratory results are used to define the capabilities of the technique for special nuclear materials accounting. Possibilities for future applications are reviewed. 14 figures

Evaluation of gamma spectroscopy gauge for uranium-plutonium assay

International Nuclear Information System (INIS)

Notea, A.; Segal, Y.

1975-01-01

A procedure is presented for the characterization of a gamma passive method for nondestructive analysis of nuclear fuel. The approach provides an organized and systematic way for optimizing the assay system. The key function is the relative resolving power defined as the smallest relative change in the Quantity of radionuclide measured, that may be detected within a certain confidence level. This function is derived for nuclear fuel employing a model based on empirical parameters. The ability to detect changes in fuels of binary and trinary compositions with a 50 cc Ge(Li) at a 1 min counting period is discussed. As an example to a binary composition, an enriched uranium fuel was considered. The 185 keV and 1001 keV gamma lines are used for the assay of 235 U and 238 U respectively. As a trinary composition a plutonium-containing gamma line. The interference of the high energy lines is carefully analyzed, and numerical results are presented. For both cases the range of measurement under specific accuracy demands is determined. The approach described is suitable also for evaluation of other passive as well as active assay methods. (author)

Nuclear materials safeguards. Volume II. 1975--March 1976 (a bibliography with abstracts). Report for 1975--Mar 1976

International Nuclear Information System (INIS)

Grooms, D.W.

1976-03-01

Citations cover the methods of safeguarding nuclear materials through effective management, accountability, nondestructive assays, instrumentation, and automated continuous inventory systems. Problem areas and recommendations for improving the management of nuclear materials are included. (Contains 88 abstracts) See also NTIS/PS-76/0200, Nuclear Materials Safeguards. Vol. 1. 1964-1974 (A title bibliography)

Card controlled beta backscatter thickness measuring instrument

International Nuclear Information System (INIS)

Schlesinger, J.

1978-01-01

An improved beta backscatter instrument for the nondestructive measurement of the thickness of thin coatings on a substrate is described. Included therein is the utilization of a bank of memory stored data representative of isotope, substrate, coating material and thickness range characteristics in association with a control card having predetermined indicia thereon selectively representative of a particular isotope, substrate material, coating material and thickness range for conditioning electronic circuit means by memory stored data selected in accord with the predetermined indicia on a control card for converting backscattered beta particle counts into indicia of coating thickness

Nondestructive inspection of General Purpose Heat Source (GPHS) fueled clad girth welds

International Nuclear Information System (INIS)

Reimus, M. A. H.; George, T. G.; Lynch, C.; Padilla, M.; Moniz, P.; Guerrero, A.; Moyer, M. W.; Placr, A.

1998-01-01

The General-Purpose Heat Source (GPHS) provides power for space missions by transmitting the heat of 238 Pu decay to an array of thermoelectric elements. The GPHS is fabricated using an iridium-alloy to contain the 238 PuO 2 fuel pellet. GPHS capsules will be utilized in the upcoming Cassini mission to explore Saturn and its moons. The physical integrity of the girth weld is important to mission safety and performance. Because past experience had revealed a potential for initiation of small cracks in the girth weld overlap zone, a nondestructive inspection of each capsule weld is required. An ultrasonic method was used to inspect the welds of capsules fabricated for the Galileo mission. The instrument, transducer, and method used were state of the art at the time (early 1980s). The ultrasonic instrumentation and methods used to inspect the Cassini GPHSs was significantly upgraded from those used for the Galileo mission. GPHSs that had ultrasonic reflectors in excess of the reject specification level were subsequently inspected with radiography to provide additional engineering data used to accept/reject the heat source. This paper describes the Galileo-era ultrasonic instrumentation and methods and the subsequent upgrades made to support testing of Cassini GPHSs. Also discussed is the data obtained from radiographic examination and correlation to ultrasonic examination results

Nondestructive inspection of General Purpose Heat Source (GPHS) fueled clad girth welds

International Nuclear Information System (INIS)

Reimus, M.A.; George, T.G.; Lynch, C.; Padilla, M.; Moniz, P.; Guerrero, A.; Moyer, M.W.; Placr, A.

1998-01-01

The General-Purpose Heat Source (GPHS) provides power for space missions by transmitting the heat of 238 Pu decay to an array of thermoelectric elements. The GPHS is fabricated using an iridium-alloy to contain the 238 PuO 2 fuel pellet. GPHS capsules will be utilized in the upcoming Cassini mission to explore Saturn and its moons. The physical integrity of the girth weld is important to mission safety and performance. Because past experience had revealed a potential for initiation of small cracks in the girth weld overlap zone, a nondestructive inspection of each capsule weld is required. An ultrasonic method was used to inspect the welds of capsules fabricated for the Galileo mission. The instrument, transducer, and method used were state of the art at the time (early 1980s). The ultrasonic instrumentation and methods used to inspect the Cassini GPHSs was significantly upgraded from those used for the Galileo mission. GPHSs that had ultrasonic reflectors in excess of the reject specification level were subsequently inspected with radiography to provide additional engineering data used to accept/reject the heat source. This paper describes the Galileo-era ultrasonic instrumentation and methods and the subsequent upgrades made to support testing of Cassini GPHSs. Also discussed is the data obtained from radiographic examination and correlation to ultrasonic examination results. copyright 1998 American Institute of Physics

Performance Values for Non-Destructive Assay (NDA) Technique Applied to Wastes: Evaluation by the ESARDA NDA Working Group

International Nuclear Information System (INIS)

Rackham, Jamie; Weber, Anne-Laure; Chard, Patrick

2012-01-01

The first evaluation of NDA performance values was undertaken by the ESARDA Working Group for Standards and Non Destructive Assay Techniques and was published in 1993. Almost ten years later in 2002 the Working Group reviewed those values and reported on improvements in performance values and new measurement techniques that had emerged since the original assessment. The 2002 evaluation of NDA performance values did not include waste measurements (although these had been incorporated into the 1993 exercise), because although the same measurement techniques are generally applied, the performance is significantly different compared to the assay of conventional Safeguarded special nuclear material. It was therefore considered more appropriate to perform a separate evaluation of performance values for waste assay. Waste assay is becoming increasingly important within the Safeguards community, particularly since the implementation of the Additional Protocol, which calls for declaration of plutonium and HEU bearing waste in addition to information on existing declared material or facilities. Improvements in the measurement performance in recent years, in particular the accuracy, mean that special nuclear materials can now be accounted for in wastes with greater certainty. This paper presents an evaluation of performance values for the NDA techniques in common usage for the assay of waste containing special nuclear material. The main topics covered by the document are: 1- Techniques for plutonium bearing solid wastes 2- Techniques for uranium bearing solid wastes 3 - Techniques for assay of fissile material in spent fuel wastes. Originally it was intended to include performance values for measurements of uranium and plutonium in liquid wastes; however, as no performance data for liquid waste measurements was obtained it was decided to exclude liquid wastes from this report. This issue of the performance values for waste assay has been evaluated and discussed by the ESARDA

Performance Values for Non-Destructive Assay (NDA) Technique Applied to Wastes: Evaluation by the ESARDA NDA Working Group

Energy Technology Data Exchange (ETDEWEB)

Rackham, Jamie [Babcock International Group, Sellafield, Seascale, Cumbria, (United Kingdom); Weber, Anne-Laure [Institut de Radioprotection et de Surete Nucleaire Fontenay-Aux-Roses (France); Chard, Patrick [Canberra, Forss Business and Technology park, Thurso, Caithness (United Kingdom)

2012-12-15

The first evaluation of NDA performance values was undertaken by the ESARDA Working Group for Standards and Non Destructive Assay Techniques and was published in 1993. Almost ten years later in 2002 the Working Group reviewed those values and reported on improvements in performance values and new measurement techniques that had emerged since the original assessment. The 2002 evaluation of NDA performance values did not include waste measurements (although these had been incorporated into the 1993 exercise), because although the same measurement techniques are generally applied, the performance is significantly different compared to the assay of conventional Safeguarded special nuclear material. It was therefore considered more appropriate to perform a separate evaluation of performance values for waste assay. Waste assay is becoming increasingly important within the Safeguards community, particularly since the implementation of the Additional Protocol, which calls for declaration of plutonium and HEU bearing waste in addition to information on existing declared material or facilities. Improvements in the measurement performance in recent years, in particular the accuracy, mean that special nuclear materials can now be accounted for in wastes with greater certainty. This paper presents an evaluation of performance values for the NDA techniques in common usage for the assay of waste containing special nuclear material. The main topics covered by the document are: 1- Techniques for plutonium bearing solid wastes 2- Techniques for uranium bearing solid wastes 3 - Techniques for assay of fissile material in spent fuel wastes. Originally it was intended to include performance values for measurements of uranium and plutonium in liquid wastes; however, as no performance data for liquid waste measurements was obtained it was decided to exclude liquid wastes from this report. This issue of the performance values for waste assay has been evaluated and discussed by the ESARDA

K-edge densitometer (KED)

Energy Technology Data Exchange (ETDEWEB)

Sprinkle, J.K.; Hansen, W.J.

1993-02-11

In 1979, a K-edge densitometer (KED) was installed by the Safeguards Assay group from Los Alamos National Laboratory in the PNC reprocessing plant at Tokai-mura, Japan. It uses an active nondestructive assay technique, KED, to measure the plutonium concentration of the product solution. The measurement uncertainty of an assay depends on the count time chosen, but can be 0.5% or better. The computer hardware and software were upgraded in 1992. This manual describes the operation of the instrument, with an emphasis on the user interface to the software.

Nondestructive analysis of the gold quarter liras

International Nuclear Information System (INIS)

Cakir, C.; Guerol, A.; Demir, L.; Sahin, Y.

2009-01-01

In this study, we have prepared seven Au-Cu standards in the concentration range of 18-24 (as carat) for nondestructive control of gold quarter liras. Some calibration curves for quantitative analysis of Au in the gold quarter liras that commercially present in Turkey have been plotted using these standard samples. The characteristic X-rays of Au and Cu emitted from these standard samples and the test sample with known composition are recorded by using a Ge(Li) detector. These calibration curves provide a nondestructive analysis of gold quarter liras with the uncertainties about 1.18%. (author)

Lead Slowing-Down Spectrometry for Spent Fuel Assay: FY11 Status Report

International Nuclear Information System (INIS)

Warren, Glen A.; Casella, Andrew M.; Haight, R.C.; Anderson, Kevin K.; Danon, Yaron; Hatchett, D.; Becker, Bjorn; Devlin, M.; Imel, G.R.; Beller, D.; Gavron, A.; Kulisek, Jonathan A.; Bowyer, Sonya M.; Gesh, Christopher J.; O'Donnell, J.M.

2011-01-01

Executive Summary Developing a method for the accurate, direct, and independent assay of the fissile isotopes in bulk materials (such as used fuel) from next-generation domestic nuclear fuel cycles is a goal of the Office of Nuclear Energy, Fuel Cycle R and D, Material Protection and Control Technology (MPACT) Campaign. To meet this goal, MPACT supports a multi-institutional collaboration to study the feasibility of Lead Slowing Down Spectroscopy (LSDS). This technique is an active nondestructive assay method that has the potential to provide independent, direct measurement of Pu and U isotopic masses in used fuel with an uncertainty considerably lower than the approximately 10% typical of today's confirmatory assay methods. This document is a progress report for FY2011 collaboration activities. Progress made by the collaboration in FY2011 continues to indicate the promise of LSDS techniques applied to used fuel. PNNL developed an empirical model based on calibration of the LSDS to responses generated from well-characterized used fuel. The empirical model demonstrated the potential for the direct and independent assay of the sum of the masses of 239Pu and 241Pu to within approximately 3% over a wide used fuel parameter space. Similar results were obtained using a perturbation approach developed by LANL. Benchmark measurements have been successfully conducted at LANL and at RPI using their respective LSDS instruments. The ISU and UNLV collaborative effort is focused on the fabrication and testing of prototype fission chambers lined with ultra-depleted 238U and 232Th, and uranium deposition on a stainless steel disc using spiked U3O8 from room temperature ionic liquid was successful, with improving thickness obtained. In FY2012, the collaboration plans a broad array of activities. PNNL will focus on optimizing its empirical model and minimizing its reliance on calibration data, as well continuing efforts on developing an analytical model. Additional measurements are

Nondestructive testing at the CEA

International Nuclear Information System (INIS)

Colomer, J.; Lucas, G.

1976-01-01

The different nondestructive testing methods used at the CEA are presented: X-ray or gamma radiography, X-ray stress analysis, neutron radiography, ultrasonic testing, eddy currents, electrical testing, microwaves, thermal testing, acoustic emission, optical holography, tracer techniques. (102 references are cited) [fr

Integrating Nephelometer Instrument Handbook

Energy Technology Data Exchange (ETDEWEB)

Uin, J. [Brookhaven National Lab. (BNL), Upton, NY (United States)

2016-03-01

The Integrating Nephelometer (Figure 1) is an instrument that measures aerosol light scattering. It measures aerosol optical scattering properties by detecting (with a wide angular integration – from 7 to 170°) the light scattered by the aerosol and subtracting the light scattered by the carrier gas, the instrument walls and the background noise in the detector (zeroing). Zeroing is typically performed for 5 minutes every day at midnight UTC. The scattered light is split into red (700 nm), green (550 nm), and blue (450 nm) wavelengths and captured by three photomultiplier tubes. The instrument can measure total scatter as well as backscatter only (from 90 to 170°) (Heintzenberg and Charlson 1996; Anderson et al. 1996; Anderson and Ogren 1998; TSI 3563 2015) At ARM (Atmospheric Radiation Measurement), two identical Nephelometers are usually run in series with a sample relative humidity (RH) conditioner between them. This is possible because Nephelometer sampling is non-destructive and the sample can be passed on to another instrument. The sample RH conditioner scans through multiple RH values in cycles, treating the sample. This kind of setup allows to study how aerosol particles’ light scattering properties are affected by humidification (Anderson et al. 1996). For historical reasons, the two Nephelometers in this setup are labeled “wet” and “dry”, with the “dry” Nephelometer usually being the one before the conditioner and sampling ambient air (the names are switched for the MAOS measurement site due to the high RH of the ambient air).

Economic importance of non-destructive testing

International Nuclear Information System (INIS)

Loebert, P.

1979-01-01

On May 21 to 23, 1979, the annual meeting of the Deutsche Gesellschaft fuer Zerstoerungsfreie Pruefung took place in Lindau near the Bodensee lake. About 600 experts from Germany and abroad participated in the meeting, whose general subject was 'The Economic Importance of Non-Destructive Testing'. Theoretical problems and practical investigations were discussed in a number of papers on special subjects. Apart from the 33 papers, there was also a poster show with 53 stands with texts, drawings, diagrams, and figures where the authors informed those interested on the latest state of knowledge in testing. The short papers were read in six sessions under the headings of rentability of non-destructive testing, X-ray methods, electromagnetic methods, and ultrasonic methods 1 and 2. (orig.) [de

The European conference on nondestructive testing

International Nuclear Information System (INIS)

Klyuev, V.V.

1985-01-01

Information on the 3-d European conference on nondestructive testing (NT) held in October, 1984 in Florence, is presented. Plenary reports were devoted to complex use of different NT methods, tendencies to NT automation and robotics, transition from defectoscopy to quality control, determination of phisico-mechanical properties of items using different control methods, formulation of unified international programs on professional training and qualification. Section reports cover the following directions: NT use in aviation and astronautics, construction, welding engineering, studying works of art; personnel training, economics, NT functioning, automation, calibration, standardization, quality control over metallic and nonmetallic objects. Some reports concerned nondestructive testing of items during their use. Attention is paied to radiographic testing and neutron radiography as well as to image processing. NT equipment was also discussed

Nondestructive NMR technique for moisture determination in radioactive materials

International Nuclear Information System (INIS)

Aumeier, S.; Gerald, R.E. II; Growney, E.; Nunez, L.; Kaminski, M.

1998-01-01

This progress report focuses on experimental and computational studies used to evaluate nuclear magnetic resonance (NMR) spectroscopy and magnetic resonance imaging (MRI) for detecting, quantifying, and monitoring hydrogen and other magnetically active nuclei ( 3 H, 3 He, 239 Pu, 241 Pu) in Spent nuclear fuels and packaging materials. The detection of moisture by using a toroid cavity NMR imager has been demonstrated in SiO 2 and UO 2 systems. The total moisture was quantified by means of 1 H NMR detection of H 2 O with a sensitivity of 100 ppm. In addition, an MRI technique that was used to determine the moisture distribution also enabled investigators to discriminate between bulk and stationary water sorbed on the particles. This imaging feature is unavailable in any other nondestructive assay (NDA) technique. Following the initial success of this program, the NMR detector volume was scaled up from the original design by a factor of 2000. The capacity of this detector exceeds the size specified by DOE-STD-3013-96

Improvement of non-destructive fissile mass assays in α low-level waste drums: A matrix correction method based on neutron capture gamma-rays and a neutron generator

Science.gov (United States)

Jallu, F.; Loche, F.

2008-08-01

Within the framework of radioactive waste control, non-destructive assay (NDA) methods may be employed. The active neutron interrogation (ANI) method is now well-known and effective in quantifying low α-activity fissile masses (mainly 235U, 239Pu, 241Pu) with low densities, i.e. less than about 0.4, in radioactive waste drums of volumes up to 200 l. The PROMpt Epithermal and THErmal interrogation Experiment (PROMETHEE [F. Jallu, A. Mariani, C. Passard, A.-C. Raoux, H. Toubon, Alpha low level waste control: improvement of the PROMETHEE 6 assay system performances. Nucl. Technol. 153 (January) (2006); C. Passard, A. Mariani, F. Jallu, J. Romeyer-Dherber, H. Recroix, M. Rodriguez, J. Loridon, C. Denis, PROMETHEE: an alpha low level waste assay system using passive and active neutron measurement methods. Nucl. Technol. 140 (December) (2002) 303-314]) based on ANI has been under development since 1996 to reach the incinerating α low level waste (LLW) criterion of about 50 Bq[α] per gram of crude waste (≈50 μg Pu) in 118 l drums on the date the drums are conditioned. Difficulties arise when dealing with matrices containing neutron energy moderators such as H and neutron absorbents such as Cl. These components may have a great influence on the fissile mass deduced from the neutron signal measured by ANI. For example, the calibration coefficient measured in a 118 l drum containing a cellulose matrix (density d = 0.144 g cm -3) may be 50 times higher than that obtained in a poly-vinyl-chloride matrix ( d = 0.253 g cm -3). Without any information on the matrix, the fissile mass is often overestimated due to safety procedures and by considering the most disadvantageous calibration coefficient corresponding to the most absorbing and moderating calibration matrix. The work discussed in this paper was performed at the CEA Nuclear Measurement Laboratory in France. It concerns the development of a matrix effect correction method, which consists in identifying and quantifying

Improvement of non-destructive fissile mass assays in α low-level waste drums: A matrix correction method based on neutron capture gamma-rays and a neutron generator

International Nuclear Information System (INIS)

Jallu, F.; Loche, F.

2008-01-01

Within the framework of radioactive waste control, non-destructive assay (NDA) methods may be employed. The active neutron interrogation (ANI) method is now well-known and effective in quantifying low α-activity fissile masses (mainly 235 U, 239 Pu, 241 Pu) with low densities, i.e. less than about 0.4, in radioactive waste drums of volumes up to 200 l. The PROMpt Epithermal and THErmal interrogation Experiment (PROMETHEE [F. Jallu, A. Mariani, C. Passard, A.-C. Raoux, H. Toubon, Alpha low level waste control: improvement of the PROMETHEE 6 assay system performances. Nucl. Technol. 153 (January) (2006); C. Passard, A. Mariani, F. Jallu, J. Romeyer-Dherber, H. Recroix, M. Rodriguez, J. Loridon, C. Denis, PROMETHEE: an alpha low level waste assay system using passive and active neutron measurement methods. Nucl. Technol. 140 (December) (2002) 303-314]) based on ANI has been under development since 1996 to reach the incinerating α low level waste (LLW) criterion of about 50 Bq[α] per gram of crude waste (∼50 μg Pu) in 118 l drums on the date the drums are conditioned. Difficulties arise when dealing with matrices containing neutron energy moderators such as H and neutron absorbents such as Cl. These components may have a great influence on the fissile mass deduced from the neutron signal measured by ANI. For example, the calibration coefficient measured in a 118 l drum containing a cellulose matrix (density d = 0.144 g cm -3 ) may be 50 times higher than that obtained in a poly-vinyl-chloride matrix (d = 0.253 g cm -3 ). Without any information on the matrix, the fissile mass is often overestimated due to safety procedures and by considering the most disadvantageous calibration coefficient corresponding to the most absorbing and moderating calibration matrix. The work discussed in this paper was performed at the CEA Nuclear Measurement Laboratory in France. It concerns the development of a matrix effect correction method, which consists in identifying and

Improvement of non-destructive fissile mass assays in {alpha} low-level waste drums: A matrix correction method based on neutron capture gamma-rays and a neutron generator

Energy Technology Data Exchange (ETDEWEB)

Jallu, F. [Commissariat a l' Energie Atomique, CEA, DEN, Nuclear Measurement Laboratory, Bat. 224, 13108 Saint Paul lez Durance (France)], E-mail: fanny.jallu@cea.fr; Loche, F. [Commissariat a l' Energie Atomique, CEA, DEN, Nuclear Measurement Laboratory, Bat. 224, 13108 Saint Paul lez Durance (France)

2008-08-15

Within the framework of radioactive waste control, non-destructive assay (NDA) methods may be employed. The active neutron interrogation (ANI) method is now well-known and effective in quantifying low {alpha}-activity fissile masses (mainly {sup 235}U, {sup 239}Pu, {sup 241}Pu) with low densities, i.e. less than about 0.4, in radioactive waste drums of volumes up to 200 l. The PROMpt Epithermal and THErmal interrogation Experiment (PROMETHEE [F. Jallu, A. Mariani, C. Passard, A.-C. Raoux, H. Toubon, Alpha low level waste control: improvement of the PROMETHEE 6 assay system performances. Nucl. Technol. 153 (January) (2006); C. Passard, A. Mariani, F. Jallu, J. Romeyer-Dherber, H. Recroix, M. Rodriguez, J. Loridon, C. Denis, PROMETHEE: an alpha low level waste assay system using passive and active neutron measurement methods. Nucl. Technol. 140 (December) (2002) 303-314]) based on ANI has been under development since 1996 to reach the incinerating {alpha} low level waste (LLW) criterion of about 50 Bq[{alpha}] per gram of crude waste ({approx}50 {mu}g Pu) in 118 l drums on the date the drums are conditioned. Difficulties arise when dealing with matrices containing neutron energy moderators such as H and neutron absorbents such as Cl. These components may have a great influence on the fissile mass deduced from the neutron signal measured by ANI. For example, the calibration coefficient measured in a 118 l drum containing a cellulose matrix (density d = 0.144 g cm{sup -3}) may be 50 times higher than that obtained in a poly-vinyl-chloride matrix (d = 0.253 g cm{sup -3}). Without any information on the matrix, the fissile mass is often overestimated due to safety procedures and by considering the most disadvantageous calibration coefficient corresponding to the most absorbing and moderating calibration matrix. The work discussed in this paper was performed at the CEA Nuclear Measurement Laboratory in France. It concerns the development of a matrix effect correction

Possibilities of nondestructive determination of fluorine in coal and biological materials by IPAA

International Nuclear Information System (INIS)

Randa, Zdenek; Mizera, Jiri; Chvatil, David

2009-01-01

The possibilities of nondestructive determination of fluorine in coal and biological materials by instrumental photon activation analysis (IPAA) were studied. The determination was based on counting the non-specific 511 keV annihilation gamma rays of 18 F, a pure positron emitter which is the product of the photonuclear reaction 19 F(γ, n) 18 F. The simultaneous formation of some additional positron emitters, particularly 45 Ti and 34m Cl, is an interfering factor. When using correction standards for Ti and Cl and optimization of the beam energy and irradiation-decay-counting times, fluorine could be determined by IPAA in selected coal and biological samples at the ten ppm level. The feasibility of additional optimization for further improvements of the proposed IPAA procedure are discussed

Low-Level Waste Drum Assay Intercomparison Study

International Nuclear Information System (INIS)

Greutzmacher, K.; Kuzminski, J.; Myers, S. C.

2003-01-01

Nuclear waste assay is an integral element of programs such as safeguards, waste management, and waste disposal. The majority of nuclear waste is packaged in drums and analyzed by various nondestructive assay (NDA) techniques to identify and quantify the radioactive content. Due to various regulations and the public interest in nuclear issues, the analytical results are required to be of high quality and supported by a rigorous Quality Assurance (QA) program. A valuable QA tool is an intercomparison program in which a known sample is analyzed by a number of different facilities. While transuranic waste (TRU) certified NDA teams are evaluated through the Performance Demonstration Program (PDP), low-level waste (LLW) assay specialists have not been afforded a similar opportunity. NDA specialists from throughout the DOE complex were invited to participate in this voluntary drum assay intercomparison study that was organized and facilitated by the Solid Waste Operations and the Safeguards Science and Technology groups at the Los Alamos National Laboratory and by Eberline Services. Each participating NDA team performed six replicate blind measurements of two 55-gallon drums with relatively low-density matrices (a 19.1 kg shredded paper matrix and a 54.4 kg mixed metal, rubber, paper and plastic matrix). This paper presents the results from this study, with an emphasis on discussing the lessons learned as well as desirable follow up programs for the future. The results will discuss the accuracy and precision of the replicate measurements for each NDA team as well as any issues that arose during the effort

Analysis of atmospheric particulate samples via instrumental neutron activation analysis

International Nuclear Information System (INIS)

Greenberg, R.R.

1990-01-01

Instrumental neutron activation analysis (INAA) is a powerful analytical technique for the elemental characterization of atmospheric particulate samples. It is a true multielement technique with adequate sensitivity to determine 30 to 40 elements in a sample of atmospheric particulate material. Its nondestructive nature allows sample reanalysis by the same or a different analytical technique. In this paper as an example of the applicability of INAA to the study of atmospheric particulate material, a study of the emissions from municipal incinerators is described

Recent improvements concerning nondestructive testing

International Nuclear Information System (INIS)

Asty, M.

1984-12-01

Rare are the techniques of which development is not already touched by microelectronics and micro-data processing. Nondestructive testing and more particularly ultrasonic and Foucault current testing follow this general rule. With some examples, this paper focuses on the potential of numerical signal processing [fr

Nondestructive assay of plutonium in empty stainless steel boxes by apparent mass method

International Nuclear Information System (INIS)

Agarwal, C.; Chaudhury, S.; Nathaniel, T.N.; Goswami, A.

2012-01-01

Apparent mass method (Venkataraman and Croft, Nucl Instrum Methods Phys Res A 505:527, 2003), initially standardized for the assay of Pu (Agarwal et al., J Nucl Mater 651:386, 2007) has been used to get Pu amount in empty stainless steel boxes generally used for storing and transferring plutonium oxide powders. The results have been compared with the neutron coincidence counting results and have been found to match well. The advantage of the method is that it can be used for any sample with nonstandard geometry and with uncertain source distribution. (author)

Qualification and certification of nondestructive testing personnel. Vol. 1

Energy Technology Data Exchange (ETDEWEB)

Aly, E A [Quality Assurance Department, national Center for Nuclear Safety and Radiation Control, Atomic Energy Authority, Cairo, (Egypt)

1996-03-01

Nondestructive testing and inspection are functions in achieving the goals of quality and efficiency at an acceptable cost. All quality assurance systems necessitate that engineers, technicians and craftsmen are able to demonstrate that they have the required level of knowledge and skill. This applies particularly to nondestructive testing (NDT) and inspection. The paper presented highlights most important national and international standards and guidelines addressing training, qualification and certification of NDT personnel.

Qualification and certification of nondestructive testing personnel. Vol. 1

International Nuclear Information System (INIS)

Aly, E.A.

1996-01-01

Nondestructive testing and inspection are functions in achieving the goals of quality and efficiency at an acceptable cost. All quality assurance systems necessitate that engineers, technicians and craftsmen are able to demonstrate that they have the required level of knowledge and skill. This applies particularly to nondestructive testing (NDT) and inspection. The paper presented highlights most important national and international standards and guidelines addressing training, qualification and certification of NDT personnel

Neutron Generators for Spent Fuel Assay

International Nuclear Information System (INIS)

Ludewigt, Bernhard A.

2010-01-01

The Next Generation Safeguards Initiative (NGSI) of the U.S. DOE has initiated a multi-lab/university collaboration to quantify the plutonium (Pu) mass in, and detect the diversion of pins from, spent nuclear fuel (SNF) assemblies with non-destructive assay (NDA). The 14 NDA techniques being studied include several that require an external neutron source: Delayed Neutrons (DN), Differential Die-Away (DDA), Delayed Gammas (DG), and Lead Slowing-Down Spectroscopy (LSDS). This report provides a survey of currently available neutron sources and their underlying technology that may be suitable for NDA of SNF assemblies. The neutron sources considered here fall into two broad categories. The term 'neutron generator' is commonly used for sealed devices that operate at relatively low acceleration voltages of less than 150 kV. Systems that employ an acceleration structure to produce ion beam energies from hundreds of keV to several MeV, and that are pumped down to vacuum during operation, rather than being sealed units, are usually referred to as 'accelerator-driven neutron sources.' Currently available neutron sources and future options are evaluated within the parameter space of the neutron generator/source requirements as currently understood and summarized in section 2. Applicable neutron source technologies are described in section 3. Commercially available neutron generators and other source options that could be made available in the near future with some further development and customization are discussed in sections 4 and 5, respectively. The pros and cons of the various options and possible ways forward are discussed in section 6. Selection of the best approach must take a number of parameters into account including cost, size, lifetime, and power consumption, as well as neutron flux, neutron energy spectrum, and pulse structure that satisfy the requirements of the NDA instrument to be built.

Non-destructive microstructural analysis with depth resolution

Energy Technology Data Exchange (ETDEWEB)

Zolotoyabko, E. E-mail: zloto@tx.technion.ac.il; Quintana, J.P

2003-01-01

A depth-sensitive X-ray diffraction technique has been developed with the aim of studying microstructural modifications in inhomogeneous polycrystalline materials. In that method, diffraction profiles are measured at different X-ray energies varied by small steps. X-rays at higher energies probe deeper layers of material. Depth-resolved structural information is retrieved by comparing energy-dependent diffraction profiles. The method provides non-destructive depth profiling of the preferred orientation, grain size, microstrain fluctuations and residual strains. This technique is applied to the characterization of seashells. Similarly, energy-variable X-ray diffraction can be used for the non-destructive characterization of different laminated structures and composite materials.

Nondestructive inspection using neutron beams

International Nuclear Information System (INIS)

2013-01-01

Neutron-abased experimental techniques such as neutronography, diffraction, or composition and elemental analysis are well established. They have important advantages in the non-destructive analysis of materials, making them a suitable option for quality-control protocols in industrial production lines. In addition, they are highly complementary to other non-destructive techniques, particularly X-ray analysis. Examples of industrial use include studies of pipes and ducts, concrete, or aeronautical components. Notwithstanding the above, the high cost associated with the construction and operation of the requisite neutron facilities has been an important limiting factor for their widespread use by the industrial sector. In this brief contribution, we explore the emerging (and already demonstrated) possibility of using compact, proton-accelerator-based neutron sources. these novel sources can be built and ran at a cost as low as a few ME, making them a competitive option to the more intense spallation or fission-based facilities for industrial applications. (Author)

Fracture-mechanical results of non-destructive testing - function, goals, methods

International Nuclear Information System (INIS)

Herter, K.H.; Kockelmann, H.; Schuler, X.; Waidele, H.

2004-01-01

Non-destructive testing provides data for fracture-mechanical analyses, e.g. defect size and orientation. On the other hand, fracture-mechanical analyses may help to define criteria for non-destructive testing, e.g. sensitivity, inspection intervals and inspection sites. The criteria applied differ as a function of the safety relevance of a component. (orig.) [de

Proceedings of the Korean Society for Nondestructive Testing Fall Meeting 1993

International Nuclear Information System (INIS)

1993-11-01

This proceedings contains articles of the Korean Society for Nondestructive Testing Fall Meeting, 1993. It was held on Nov. 22, 1993 in Seoul, Korea and subject of the Korean Society for Nondestructive Testing Fall Meeting 1993. There are main session and technical session.

Proceedings of the Korean Society for Nondestructive Testing Spring Meeting 1992

International Nuclear Information System (INIS)

1992-05-01

This proceedings contains articles of the Korean Society for Nondestructive Testing Spring Meeting, 1992. It was held on May. 20, 1992 in Seoul, Korea and subject of the Korean Society for Nondestructive Testing Spring Meeting 1992. There are main session and technical session.

Proceedings of the Korean Society for Nondestructive Testing Spring Meeting 1993

International Nuclear Information System (INIS)

1993-05-01

This proceedings contains articles of the Korean Society for Nondestructive Testing Spring Meeting, 1993. It was held on May. 24, 1993 in Seoul, Korea and subject of the Korean Society for Nondestructive Testing Spring Meeting 1993. There are main session and technical session.

Proceedings of the Korean Society for Nondestructive Testing Fall Meeting 1999

International Nuclear Information System (INIS)

1999-11-01

This proceedings contains articles of the Korean Society for Nondestructive Testing Fall Meeting, 1999. It was held on Nov. 26, 1999 in Seoul, Korea and subject of the Korean Society for Nondestructive Testing Fall Meeting 1999. This proceedings is comprised of 4 sessions.

Artificial intelligence to maximise contributions of nondestructive evaluation to materials science and technology

International Nuclear Information System (INIS)

Baldev Raj; Rajagopalan, C.

1996-01-01

The paper reviews the current status of Nondestructive Testing and Evaluation (NDT and E), in relation to materials science and technology. It suggests a path of growth for Nondestructive Testing and Evaluation, taking into account the increase in data and knowledge. We recommend Artificial Intelligence (AI) concepts for maximising the contributions of and benefits from, Nondestructive Testing and Evaluation. (author)

ARIES NDA Robot operators' manual

International Nuclear Information System (INIS)

Scheer, N.L.; Nelson, D.C.

1998-05-01

The ARIES NDA Robot is an automation device for servicing the material movements for a suite of Non-destructive assay (NDA) instruments. This suite of instruments includes a calorimeter, a gamma isotopic system, a segmented gamma scanner (SGS), and a neutron coincidence counter (NCC). Objects moved by the robot include sample cans, standard cans, and instrument plugs. The robot computer has an RS-232 connection with the NDA Host computer, which coordinates robot movements and instrument measurements. The instruments are expected to perform measurements under the direction of the Host without operator intervention. This user's manual describes system startup, using the main menu, manual operation, and error recovery

Non-destructive testing and evaluation for structural integrity

International Nuclear Information System (INIS)

Baldev Raj; Jayakumar, T.; Rao, B.P.C.

1995-01-01

In this paper, a brief description of the physical concepts of non-destructive evaluation (NDE) methods and the physical/derived parameters that are used for assessing defects, stresses and microstructures are given. A few case studies highlighting the importance of non-destructive testing and evaluation for structural integrity assessment are also discussed based on the investigations carried out. Emerging concepts like intelligent processing of materials, expert systems, neural networks, use of multisensors with fusion of data and exploitation of signal analysis and imaging approaches are also addressed in this paper. (author). 92 refs., 1 tab

Some target assay uncertainties for passive neutron coincidence counting

International Nuclear Information System (INIS)

Ensslin, N.; Langner, D.G.; Menlove, H.O.; Miller, M.C.; Russo, P.A.

1990-01-01

This paper provides some target assay uncertainties for passive neutron coincidence counting of plutonium metal, oxide, mixed oxide, and scrap and waste. The target values are based in part on past user experience and in part on the estimated results from new coincidence counting techniques that are under development. The paper summarizes assay error sources and the new coincidence techniques, and recommends the technique that is likely to yield the lowest assay uncertainty for a given material type. These target assay uncertainties are intended to be useful for NDA instrument selection and assay variance propagation studies for both new and existing facilities. 14 refs., 3 tabs

Proceedings of the Korean Society for Nondestructive Testing Spring Meeting 2001

International Nuclear Information System (INIS)

2001-05-01

This proceedings contains articles of the Korean Society for Nondestructive Testing Spring Meeting, 2001. It was held on May. 11-12, 2001 in Seoul, Korea and subject of the Korean Society for Nondestructive Testing Spring Meeting 2001. This proceedings is comprised of 5 sessions.

Assaying Auxin Receptor Activity Using SPR Assays with F-Box Proteins and Aux/IAA Degrons.

Science.gov (United States)

Quareshy, Mussa; Uzunova, Veselina; Prusinska, Justyna M; Napier, Richard M

2017-01-01

The identification of TIR1 as an auxin receptor combined with advanced biophysical instrumentation has led to the development of real-time activity assays for auxins. Traditionally, molecules have been assessed for auxinic activity using bioassays, and agrochemical compound discovery continues to be based on "spray and pray" technologies. Here, we describe the methodology behind an SPR-based assay that uses TIR1 and related F-box proteins with surface plasmon resonance spectrometry for rapid compound screening. In addition, methods for collecting kinetic binding data and data processing are given so that they may support programs for rational design of novel auxin ligands.

Proceedings of the Korean Society for Nondestructive Testing Fall Meeting 1998

International Nuclear Information System (INIS)

1998-05-01

This proceedings contains articles of the Korean Society for Nondestructive Testing Spring Meeting, 1998. It was held on May.8-9, 1998 Yeungnam University in Daegu, Korea and subject of the Korean Society for Nondestructive Testing Spring Meeting 1998. This proceedings is comprised of 4 sessions.

Review of progress in quantitative nondestructive evaluation. Volume 8A and Volume 8B

International Nuclear Information System (INIS)

Thompson, D.O.; Chimenti, D.E.

1989-01-01

Volume 8 contains the edited papers presented at the 1988 Review of Progress in Quantitative Nondestructive Evaluation meeting. The 288 papers discuss such topics as fundamental techniques as acoustic testing, eddy current testing, and x-ray radiography; advanced techniques using x-ray computed tomography and laser ultrasonics; interpretive signal and image processing using expert systems and adaptive analysis; NDE probes and sensors and NDE systems and instrumentation; materials process control and inspection reliability including human factors. Materials discussed range from electronic circuit materials, coatings, adhesive bonds, smart structures, composite materials, welded joints, ferrous materials, and steels and alloys. Stress, texture, structural and fracture properties of materials are characterized using various NDE techniques. Applications to reactor, aircraft, and space vehicle components are investigated

Research of x-ray nondestructive detector for high-speed running conveyor belt with steel wire ropes

Science.gov (United States)

Wang, Junfeng; Miao, Changyun; Wang, Wei; Lu, Xiaocui

2008-03-01

An X-ray nondestructive detector for high-speed running conveyor belt with steel wire ropes is researched in the paper. The principle of X-ray nondestructive testing (NDT) is analyzed, the general scheme of the X-ray nondestructive testing system is proposed, and the nondestructive detector for high-speed running conveyor belt with steel wire ropes is developed. The hardware of system is designed with Xilinx's VIRTEX-4 FPGA that embeds PowerPC and MAC IP core, and its network communication software based on TCP/IP protocol is programmed by loading LwIP to PowerPC. The nondestructive testing of high-speed conveyor belt with steel wire ropes and network transfer function are implemented. It is a strong real-time system with rapid scanning speed, high reliability and remotely nondestructive testing function. The nondestructive detector can be applied to the detection of product line in industry.

Training Guidelines in Non-destructive Testing Techniques. 2013 Edition

International Nuclear Information System (INIS)

2014-12-01

The IAEA promotes industrial applications of radiation technology, including non-destructive testing (NDT), through activities such as Technical Cooperation Projects (national and regional) and Coordinated Research Projects. Through this cooperation, Member States have initiated national programmes for the training and certification of NDT personnel. National certifying bodies have also been established based on International Organization for Standardization (ISO) standards. As part of these efforts, the IAEA has been actively involved in developing training materials. Consequently, IAEA-TECDOC-407, Training Guidelines in Non-destructive Testing Techniques, was published in 1987, then revised and expanded as IAEA-TECDOC-628 in 1991. Revisions of IAEA-TECDOC-628 were considered essential to meet the demands of end-user industries in Member States, and revised and expanded versions were issued in 2002 and 2008. These latter versions included work conducted by the International Committee for Non-Destructive Testing (ICNDT) and many national NDT societies. It is one of the publications referred to in ISO 9712:2005, Non-destructive Testing: Qualification and Certification of Personnel, which in turn is an internationally accepted standard, revised as ISO 9712:2012, Non-destructive Testing: Qualification and Certification of NDT Personnel. This publication is an updated version of IAEA-TECDOC-628. The content of which has been revised following the changes of ISO 9712 converging with EN 473 and becoming EN ISO 9712:2012, based on the experience of experts and comments from end-user industries. The details of the topics on each subject have been expanded to include the latest developments in the respective methods. The incorporated changes will assist the end-user industries to update their NDT qualification and certification schemes and course materials. This publication, like the previous versions, will continue to play an important role in international harmonization

In-house validation study of the DuPont Qualicon BAX system Q7 instrument with the BAX system PCR Assay for Salmonella (modification of AOAC Official Method 2003.09 and AOAC Research Institute Performance-Tested Method 100201).

Science.gov (United States)

Tice, George; Andaloro, Bridget; White, H Kirk; Bolton, Lance; Wang, Siqun; Davis, Eugene; Wallace, Morgan

2009-01-01

In 2006, DuPont Qualicon introduced the BAX system Q7 instrument for use with its assays. To demonstrate the equivalence of the new and old instruments, a validation study was conducted using the BAX system PCR Assay for Salmonella, AOAC Official Method 2003.09, on three food types. The foods were simultaneously analyzed with the BAX system Q7 instrument and either the U.S. Food and Drug Administration Bacteriological Analytical Manual or the U.S. Department of Agriculture-Food Safety and Inspection Service Microbiology Laboratory Guidebook reference method for detecting Salmonella. Comparable performance between the BAX system and the reference methods was observed. Of the 75 paired samples analyzed, 39 samples were positive by both the BAX system and reference methods, and 36 samples were negative by both the BAX system and reference methods, demonstrating 100% correlation. Inclusivity and exclusivity for the BAX system Q7 instrument were also established by testing 50 Salmonella strains and 20 non-Salmonella isolates. All Salmonella strains returned positive results, and all non-Salmonella isolates returned a negative response.

Pattern recognition approach to nondestructive evaluation of materials

International Nuclear Information System (INIS)

Chen, C.H.

1987-01-01

In this paper, a pattern recognition approach to the ultrasonic nondestructive evaluation of materials is examined. Emphasis is placed on identifying effective features from time and frequency domains, correlation functions and impulse responses to classify aluminum plate specimens into three major defect geometry categories: flat, angular cut and circular hole defects. A multi-stage classification procedure is developed which can further determine the angles and sizes for defect characterization and classification. The research clearly demonstrates that the pattern recognition approach can significantly improve the nondestructive material evaluation capability of the ultrasonic methods without resorting to the solution of highly complex mathematical inverse problems

Advanced Instrumentation, Information, and Control System Technologies: Nondestructive Examination Technologies - FY11 Report

Energy Technology Data Exchange (ETDEWEB)

Meyer, Ryan M.; Coble, Jamie B.; Ramuhalli, Pradeep; Bond, Leonard J.

2011-08-30

Licensees of commercial nuclear power plants in the US are expected to submit license renewal applications for the period of operation of 60 to 80 years which has also been referred to as long term operation (LTO). The greatest challenges to LTO are associated with degradation of passive components as active components are routinely maintained and repaired or placed through maintenance programs. Some passive component degradation concerns include stress corrosion cracking (SCC) of metal components, radiation induced embrittlement of the reactor pressure vessel (RPV), degradation of buried piping, degradation of concrete containment structures, and degradation of cables. Proactive management of passive component aging employs three important elements including online monitoring of degradation, early detection of degradation at precursor stages, and application of prognostics for the prediction of remaining useful life (RUL). This document assesses several nondestructive examination (NDE) measurement technologies for integration into proactive aging management programs. The assessment is performed by discussing the three elements of proactive aging management identified above, considering the current state of the industry with respect to adopting these key elements, and analyzing measurement technologies for monitoring large cracks in metal components, monitoring early degradation at precursor stages, monitoring the degradation of concrete containment structures, and monitoring the degradation of cables. Specific and general needs have been identified through this assessment. General needs identified include the need for environmentally rugged sensors are needed that can operate reliably in an operating reactor environment, the need to identify parameters from precursor monitoring technologies that are unambiguously correlated with the level of pre-macro defect damage, and a methodology for identifying regions where precursor damage is most likely to initiate.

Advanced Instrumentation, Information, and Control System Technologies: Nondestructive Examination Technologies - FY11 Report

International Nuclear Information System (INIS)

Meyer, Ryan M.; Coble, Jamie B.; Ramuhalli, Pradeep; Bond, Leonard J.

2011-01-01

Licensees of commercial nuclear power plants in the US are expected to submit license renewal applications for the period of operation of 60 to 80 years which has also been referred to as long term operation (LTO). The greatest challenges to LTO are associated with degradation of passive components as active components are routinely maintained and repaired or placed through maintenance programs. Some passive component degradation concerns include stress corrosion cracking (SCC) of metal components, radiation induced embrittlement of the reactor pressure vessel (RPV), degradation of buried piping, degradation of concrete containment structures, and degradation of cables. Proactive management of passive component aging employs three important elements including online monitoring of degradation, early detection of degradation at precursor stages, and application of prognostics for the prediction of remaining useful life (RUL). This document assesses several nondestructive examination (NDE) measurement technologies for integration into proactive aging management programs. The assessment is performed by discussing the three elements of proactive aging management identified above, considering the current state of the industry with respect to adopting these key elements, and analyzing measurement technologies for monitoring large cracks in metal components, monitoring early degradation at precursor stages, monitoring the degradation of concrete containment structures, and monitoring the degradation of cables. Specific and general needs have been identified through this assessment. General needs identified include the need for environmentally rugged sensors are needed that can operate reliably in an operating reactor environment, the need to identify parameters from precursor monitoring technologies that are unambiguously correlated with the level of pre-macro defect damage, and a methodology for identifying regions where precursor damage is most likely to initiate.

Ultrasonic immersion probes characterization for use in nondestructive testing according to EN 12668-2:2001

International Nuclear Information System (INIS)

Silva, C E R; Alvarenga, A V; Costa-Felix, R P B

2011-01-01

Ultrasound is often used as a Non-Destructive Testing (NDT) technique to analyze components and structures to detect internal and surface flaws. To guarantee reliable measurements, it is necessary to calibrate instruments and properly assess related uncertainties. An important device of an ultrasonic instrument system is its probe, which characterization should be performed according to EN 12668-2. Concerning immersion probes beam profile, the parameters to be assessed are beam divergence, focal distance, width, and zone length. Such parameters are determined by scanning a reflector or a hydrophone throughout the transducer beam. Within the present work, a methodology developed at Inmetro's Laboratory of Ultrasound to evaluate relevant beam parameters is presented, based on hydrophone scan. Water bath and positioning system to move the hydrophone were used to perform the scan. Studied probes were excited by a signal generator, and the waterborne signals were detected by the hydrophone and acquired using an oscilloscope. A user-friendly virtual instrument was developed in LabVIEW to automate the system. The initial tests were performed using 1 and 2.25 MHz-ultrasonic unfocused probes (Oe 1.27 cm), and results were consistent with the manufacturer's specifications. Moreover, expanded uncertainties were lower than 6% for all parameters under consideration.

Ultrasonic immersion probes characterization for use in nondestructive testing according to EN 12668-2:2001

Science.gov (United States)

Silva, C. E. R.; Alvarenga, A. V.; Costa-Felix, R. P. B.

2011-02-01

Ultrasound is often used as a Non-Destructive Testing (NDT) technique to analyze components and structures to detect internal and surface flaws. To guarantee reliable measurements, it is necessary to calibrate instruments and properly assess related uncertainties. An important device of an ultrasonic instrument system is its probe, which characterization should be performed according to EN 12668-2. Concerning immersion probes beam profile, the parameters to be assessed are beam divergence, focal distance, width, and zone length. Such parameters are determined by scanning a reflector or a hydrophone throughout the transducer beam. Within the present work, a methodology developed at Inmetro's Laboratory of Ultrasound to evaluate relevant beam parameters is presented, based on hydrophone scan. Water bath and positioning system to move the hydrophone were used to perform the scan. Studied probes were excited by a signal generator, and the waterborne signals were detected by the hydrophone and acquired using an oscilloscope. A user-friendly virtual instrument was developed in LabVIEW to automate the system. The initial tests were performed using 1 and 2.25 MHz-ultrasonic unfocused probes (Ø 1.27 cm), and results were consistent with the manufacturer's specifications. Moreover, expanded uncertainties were lower than 6% for all parameters under consideration.

National seminar on non-destructive evaluation techniques: proceedings cum souvenir

International Nuclear Information System (INIS)

Dutta, N.G.; Kulkarni, P.G.; Purushotham, D.S.C.

1994-01-01

This volume contains selected papers presented at the National Seminar on Non-Destructive Evaluation Techniques held at Bhabha Atomic Research Centre, Mumbai during December 8-9, 1994. The papers covered a wide spectrum of non-destructive evaluation activities including that for quality assurance of various nuclear components and structures with the focal theme being computerization and robotics. The papers relevant to INIS are indexed separately

Summaries of the lectures of a conference on nondestructive testing

International Nuclear Information System (INIS)

1980-01-01

The present brochure contains summaries of the lectures that were held at the DGZfP-conference on non-destructive testing' in May 1980 in Goettingen. The greater part of the lectures dealt with ultrasonic methods, electromagnetic methods and applications of X-, γ- and neutron-rays in non-destructive testing. Besides, questions of quality ensurance, economics and problems of the training of testing personnel were treated. (RW) [de

Instrument for Real-Time Digital Nucleic Acid Amplification on Custom Microfluidic Devices.

Directory of Open Access Journals (Sweden)

David A Selck

Full Text Available Nucleic acid amplification tests that are coupled with a digital readout enable the absolute quantification of single molecules, even at ultralow concentrations. Digital methods are robust, versatile and compatible with many amplification chemistries including isothermal amplification, making them particularly invaluable to assays that require sensitive detection, such as the quantification of viral load in occult infections or detection of sparse amounts of DNA from forensic samples. A number of microfluidic platforms are being developed for carrying out digital amplification. However, the mechanistic investigation and optimization of digital assays has been limited by the lack of real-time kinetic information about which factors affect the digital efficiency and analytical sensitivity of a reaction. Commercially available instruments that are capable of tracking digital reactions in real-time are restricted to only a small number of device types and sample-preparation strategies. Thus, most researchers who wish to develop, study, or optimize digital assays rely on the rate of the amplification reaction when performed in a bulk experiment, which is now recognized as an unreliable predictor of digital efficiency. To expand our ability to study how digital reactions proceed in real-time and enable us to optimize both the digital efficiency and analytical sensitivity of digital assays, we built a custom large-format digital real-time amplification instrument that can accommodate a wide variety of devices, amplification chemistries and sample-handling conditions. Herein, we validate this instrument, we provide detailed schematics that will enable others to build their own custom instruments, and we include a complete custom software suite to collect and analyze the data retrieved from the instrument. We believe assay optimizations enabled by this instrument will improve the current limits of nucleic acid detection and quantification, improving our

49 CFR 193.2321 - Nondestructive tests.

Science.gov (United States)

2010-10-01

... ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE SAFETY LIQUEFIED NATURAL GAS FACILITIES... of storage tanks with internal design pressure above 15 psig must be nondestructively examined in... Vessel Code (Section VIII Division 1) (incorporated by reference, see § 193.2013). (b) For storage tanks...

Nondestructive testing: welding industry

International Nuclear Information System (INIS)

Raj, Baldev; Subramanian, C.V.

1992-01-01

This chapter highlights various conventional and advanced nondestructive testing (NDT) techniques that have been used for weld evaluation. Welding Codes and Standards of International and National organisations that have been followed in India for various weld evaluation purposes are also included. The chapter also emphasises the importance of NDT by way of a few case studies that have been carried out on important critical welded components. (author). 12 refs., 17 figs., 1 appendix

New technologies in electromagnetic non-destructive testing

CERN Document Server

Huang, Songling

2016-01-01

This book introduces novel developments in the field of electromagnetic non-destructive testing and evaluation (NDT/E). The topics include electromagnetic ultrasonic guided wave testing, pulsed eddy current testing, remote field eddy current testing, low frequency eddy current testing, metal magnetic memory testing, and magnetic flux leakage testing. Considering the increasing concern about the safety maintenance of critical structures in various industries and everyday life, these topics presented here will be of particular interest to the readers in the NDT/E field. This book covers both theoretical researches and the engineering applications of the electromagnetic NDT technology. It could serve as a valuable reference for college students and relevant NDT technicians. It is also a useful material for qualification training and higher learning for nondestructive testing professionals.

Nuclear materials safeguards. Volume 2. 1975--February 1977 (a bibliography with abstracts). Report for 1975--Feb 77

International Nuclear Information System (INIS)

Grooms, D.W.

1977-04-01

Citations cover the methods of safeguarding nuclear materials through effective management, accountability, nondestructive assays, instrumentation, and automated continuous inventory systems. Problem areas and recommendations for improving the management of nuclear materials are included. (This updated bibliography contains 143 abstracts, 56 of which are new entries to the previous edition.) See also, NTIS/PS-76/0200, Nuclear Materials Safeguards. Vol. 1. 1964-1974

Symmetry analyzer for nondestructive Bell-state detection using weak nonlinearities

International Nuclear Information System (INIS)

Barrett, S.D.; Kok, Pieter; Spiller, T.P.; Nemoto, Kae; Beausoleil, R.G.; Munro, W.J.

2005-01-01

We describe a method to project photonic two-qubit states onto the symmetric and antisymmetric subspaces of their Hilbert space. This device utilizes an ancillary coherent state, together with a weak cross-Kerr nonlinearity, generated, for example, by electromagnetically induced transparency. The symmetry analyzer is nondestructive, and works for small values of the cross-Kerr coupling. Furthermore, this device can be used to construct a nondestructive Bell-state detector

Vehicle for transporting instruments for testing against a wall

International Nuclear Information System (INIS)

Hyde, E.A.; Goldsmith, H.A.; Proudlove, M.J.

1981-01-01

This invention relates to a non-destructive testing apparatus and, in particular, to a vehicle that can be moved at will, for transporting instruments for testing against a surface remote from the operator. Under this invention a vehicle is intended, for instance, for testing the vessel of an installation containing a liquid metal cooled nuclear reactor of the pond type. Such an installation includes a nuclear reactor comprising an assembly containing a nuclear fuel immersed in a pond of liquid metal coolant, located in a vessel which is itself placed in a concrete containment vessel [fr

Nondestructive examination of irradiated fuel rods by pulsed eddy current techniques

International Nuclear Information System (INIS)

Francis, W.C.; Quapp, W.J.; Martin, M.R.; Gibson, G.W.

1976-02-01

A number of fuel rods and unfueled zircaloy cladding tubes which had been irradiated in the Saxton reactor have undergone extensive nondestructive and corroborative destructive examinations by Aerojet Nuclear Company as part of the Water Reactor Safety Research Program, Irradiation Effects Test Series. This report discusses the pulsed eddy current (PEC) nondestructive examinations on the fuel rods and tubing and the metallography results on two fuel rods and one irradiated zircaloy tube. The PEC equipment, designed jointly by Argonne National Laboratory and Aerojet, performed very satisfactorily the functions of diameter, profile, and wall thickness measurements and OD and ID surface defect detection. The destructive examination provided reasonably good confirmation of ''defects'' detected in the nondestructive examination

Analytical nondestructive evaluation for materials characterization

International Nuclear Information System (INIS)

Raj, Baldev

1993-01-01

Science and technology of nondestructive testing and evaluation has contributed immensely to the safety and productivity of industrial plants. In recent years, nondestructive evaluation (NDE) has emerged as a frontline research area of equal if not greater technological relevance, for materials characterization as well. A comprehensive range of techniques from qualitative nondestructive testing for quality control of engineering products and materials to quantitative NDE for materials characterization is being used by the engineering industry and materials researchers, for better understanding of the manufacturing practices and materials behaviour. Quantitative NDE is considered essential for ensuring fitness for purpose at the start of the life in case the component has been designed using fracture mechanics parameters. Quantitative NDE is also vital for assessing degradation of material during service. Moreover, quantitative NDE enables characterization of dynamics of certain phenomenon (not achievable by destructive test methodologies) leading to better understanding of the performance of materials in relation to unavoidable defects in the materials. As the next logical step, the need for an analytical approach to NDE is felt. The need and motivation for such an approach is addressed and the means to achieve this objective are identified. It is argued that analytical NDE is essential to meet the challenges of characterization, intelligent processing of materials and life prediction of components and plants. These requirements are of significant importance in the context of recent developments in materials engineering, and for enhancing the competitive advantage of Indian engineering industry in the international market. (author). 9 refs., 3 figs

Construction appraisal team inspection results on welding and nondestructive examination activities

International Nuclear Information System (INIS)

Wu, P.C.S.; Shaaban, H.I.

1987-09-01

This report summarizes data and findings on deficiencies and discrepancies in welding and nondestructive examination (NDE) activities identified by the US Nuclear Regulatory Commission Construction Appraisal Team (CAT) during its inspection of 11 plants. The CAT reviewed selected welds and NDE packages in its inspection of the following plant areas: piping and pipe supports and/or restraints; modification and installation of reactor internals; electrical installations and electrical supports; instrumentation tubing and supports; heating, ventilation, and air conditioning (HVAC) systems and supports; fabrication and erection of structural steel; fabrication of refueling cavity and spent fuel pool liner; containment liner and containment penetrations; and fire protection systems. The CAT inspected both structural welds and pressure-retaining welds and reviewed welder qualification test records and welding procedure documents for code compliance. The NDE activities that were evaluated included visual examination, magnetic particle examination, liquid penetrant examination, ultrasonic examination, and radiographic examination of welds. 4 refs., 14 figs., 15 tabs

Nondestructive examination development and demonstration plan

International Nuclear Information System (INIS)

Weber, J.R.

1991-01-01

Nondestructive examination (NDE) of waste matrices using penetrating radiation is by nature very subjective. Two candidate systems of examination have been identified for use in WRAP 1. This test plan describes a method for a comparative evaluation of different x-ray examination systems and techniques

Evaluation of a gamma-spectroscopy gauge for uranium-plutonium assay

International Nuclear Information System (INIS)

Notea, A.; Segal, Y.

1976-01-01

A procedure is presented for the characterization of a gamma passive method for non-destructive analysis of nuclear fuel. The approachh provides an organized and systematic way for optimizing the assay system. The key function is the relative resolving power defined as the smallest relative change in the quantity of radionuclide measured that may be detected within a certain confidence level. This function is derived for nuclear fuel employing a model based on empirical parameters. The ability to detect changes in fuels of binary and trinary compositions with a 50-cm 3 Ge(Li) at a 1-min counting period is discussed. As an example to a binary composition, an enriched uranium fuel was considered. The 185-keV and 1001-keV gamma lines are used for the assay of 235 U and 238 U, respectively. As a trinary composition a plutonium-containing fuel was examined. The plutonium was identified by the 414-keV gamma line. The interference of the high-energy lines is carefully analysed, and numerical results are presented. For both cases the range of measurement under specific accuracy demands is determined. The approac described is suitable also for evaluation of other passive as well as active assay methods. (author)

Nondestructive determination of residual fuel on leached hulls and dissolver sludges from LWR fuel reprocessing

International Nuclear Information System (INIS)

Wuerz, H.; Wagner, K.; Becker, H.J.

1990-01-01

In reprocessing plants leached hulls and dissolver sludges represent rather important intermediate level α-waste streams. A control of the Pu content of these waste streams is desirable. The nondestructive assay method to be preferred would be passive neutron counting. However, before any decision on passive neutron monitoring becomes possible, a characterization of hulls and sludges in terms of Pu content and neutron emission is necessary. For the direct determination of Plutonium on hulls and in sludges, as coming from reprocessing, an active neutron measurement is required. A simple, and sufficiently sensitive active neutron method which can easily be installed uses a stationary 252 Cf neutron source. This method was used for the characterization of hulls and sludges in terms of Plutonium content and total neutron emission in the Karlsruhe reprocessing plant WAK

Long-Range Nondestructive Testing System, Phase I

Data.gov (United States)

National Aeronautics and Space Administration — This proposal is for the development of a long range, multi-point non-destructive system for the detection of subsurface flaws in metallic and composite materials of...

Development of non-destructive Young's modulus measurement techniques in non-oriented CeF$_{3}$ crystals

CERN Document Server

Pietroni, P; Lebeau, M; Majni, G; Rinaldi, D

2005-01-01

For a reliable mechanical assembly of scintillating crystals for the application to radiographic systems such as Positron Emission Tomographer (PET) and high-energy physics calorimeters (e.g. in CMS at CERN LHC), the evaluation of the monocrystal elastic constant (Young's modulus) is needed. Its knowledge is also essential in the photoelastic analysis for the determination of residual stresses. In this work non-destructive techniques based on elastic wave propagation are tested. They differ in the mechanical excitation device: instrumented hammer, traditional ultrasonic probes and laser- generated ultrasound. We have analysed three non-oriented cerium fluoride crystal samples produced for scintillation applications. Finally, we have validated the experimental results comparing them with the elastic constant calculated by using the stiffness matrix.

Development of non-destructive Young's modulus measurement techniques in non-oriented CeF3 crystals

International Nuclear Information System (INIS)

Pietroni, P.; Paone, N.; Lebeau, M.; Majni, G.; Rinaldi, D.

2005-01-01

For a reliable mechanical assembly of scintillating crystals for the application to radiographic systems such as Positron Emission Tomographer (PET) and high-energy physics calorimeters (e.g. in CMS at CERN LHC), the evaluation of the monocrystal elastic constant (Young's modulus) is needed. Its knowledge is also essential in the photoelastic analysis for the determination of residual stresses. In this work non-destructive techniques based on elastic wave propagation are tested. They differ in the mechanical excitation device: instrumented hammer, traditional ultrasonic probes and laser-generated ultrasound. We have analysed three non-oriented cerium fluoride crystal samples produced for scintillation applications. Finally, we have validated the experimental results comparing them with the elastic constant calculated by using the stiffness matrix

Non-destructive in situ study of “Mad Meg” by Pieter Bruegel the Elder using mobile X-ray fluorescence, X-ray diffraction and Raman spectrometers

Energy Technology Data Exchange (ETDEWEB)

Van de Voorde, Lien, E-mail: lien.vandevoorde@ugent.be [Ghent University, Department of Analytical Chemistry, X-ray Microspectroscopy and Imaging Research Group, Krijgslaan 281 S12, B-9000 Gent (Belgium); Van Pevenage, Jolien [Ghent University, Department of Analytical Chemistry, Raman Spectroscopy Research Group, Krijgslaan 281 S12, B-9000 Gent (Belgium); De Langhe, Kaat [Ghent University, Department of Archaeology, Archaeometry Research Group, Sint-Pietersnieuwstraat 35, B-9000 Gent (Belgium); De Wolf, Robin; Vekemans, Bart; Vincze, Laszlo [Ghent University, Department of Analytical Chemistry, X-ray Microspectroscopy and Imaging Research Group, Krijgslaan 281 S12, B-9000 Gent (Belgium); Vandenabeele, Peter [Ghent University, Department of Archaeology, Archaeometry Research Group, Sint-Pietersnieuwstraat 35, B-9000 Gent (Belgium); Martens, Maximiliaan P.J. [Ghent University, Department of Art, Music and Theatre Sciences, Blandijnberg 2, B-9000 Gent (Belgium)

2014-07-01

“Mad Meg”, a figure of Flemish folklore, is the subject of a famous oil-on-panel painting by the Flemish renaissance artist Pieter Bruegel the Elder, exhibited in the Museum Mayer van den Bergh (Antwerp, Belgium). This article reports on the in situ chemical characterization of this masterpiece by using currently available state-of-the-art portable analytical instruments. The applied non-destructive analytical approach involved the use of a) handheld X-ray fluorescence instrumentation for retrieving elemental information and b) portable X-ray fluorescence/X-ray diffraction instrumentation and laser-based Raman spectrometers for obtaining structural/molecular information. Next to material characterization of the used pigments and of the different preparation layers of the painting, also the verification of two important historical iconographic hypotheses is performed concerning the economic way of painting by Brueghel, and whether or not he used blue smalt pigment for painting the boat that appears towards the top of the painting. The pigments identified are smalt pigment (65% SiO{sub 2} + 15% K{sub 2}O + 10% CoO + 5% Al{sub 2}O{sub 3}) for the blue color present in all blue areas of the painting, probably copper resinate for the green colors, vermillion (HgS) as red pigment and lead white is used to form different colors. The comparison of blue pigments used on different areas of the painting gives no differences in the elemental fingerprint which confirms the existing hypothesis concerning the economic painting method by Bruegel. - Highlights: • In situ, non-destructive investigation of a famous painting by Pieter Bruegel. • Use of a new, commercial available, portable XRF/XRD instrumentation. • Multi-methodological approach: make also use of a mobile Raman spectrometer. • Used pigments and different preparation layers of the painting are characterized. • The verification of two important historical iconographic hypotheses are performed.

Non-destructive in situ study of “Mad Meg” by Pieter Bruegel the Elder using mobile X-ray fluorescence, X-ray diffraction and Raman spectrometers

International Nuclear Information System (INIS)

Van de Voorde, Lien; Van Pevenage, Jolien; De Langhe, Kaat; De Wolf, Robin; Vekemans, Bart; Vincze, Laszlo; Vandenabeele, Peter; Martens, Maximiliaan P.J.

2014-01-01

“Mad Meg”, a figure of Flemish folklore, is the subject of a famous oil-on-panel painting by the Flemish renaissance artist Pieter Bruegel the Elder, exhibited in the Museum Mayer van den Bergh (Antwerp, Belgium). This article reports on the in situ chemical characterization of this masterpiece by using currently available state-of-the-art portable analytical instruments. The applied non-destructive analytical approach involved the use of a) handheld X-ray fluorescence instrumentation for retrieving elemental information and b) portable X-ray fluorescence/X-ray diffraction instrumentation and laser-based Raman spectrometers for obtaining structural/molecular information. Next to material characterization of the used pigments and of the different preparation layers of the painting, also the verification of two important historical iconographic hypotheses is performed concerning the economic way of painting by Brueghel, and whether or not he used blue smalt pigment for painting the boat that appears towards the top of the painting. The pigments identified are smalt pigment (65% SiO 2 + 15% K 2 O + 10% CoO + 5% Al 2 O 3 ) for the blue color present in all blue areas of the painting, probably copper resinate for the green colors, vermillion (HgS) as red pigment and lead white is used to form different colors. The comparison of blue pigments used on different areas of the painting gives no differences in the elemental fingerprint which confirms the existing hypothesis concerning the economic painting method by Bruegel. - Highlights: • In situ, non-destructive investigation of a famous painting by Pieter Bruegel. • Use of a new, commercial available, portable XRF/XRD instrumentation. • Multi-methodological approach: make also use of a mobile Raman spectrometer. • Used pigments and different preparation layers of the painting are characterized. • The verification of two important historical iconographic hypotheses are performed

Non-destructive examination system of vitreous body

Science.gov (United States)

Shibata, Takuma; Gong, Jin; Watanabe, Yosuke; Kabir, M. Hasnat; Masato, Makino; Furukawa, Hidemitsu; Nishitsuka, Koichi

2014-04-01

Eyeball plays a quite important role in acquiring the vision. Vitreous body occupies the largest part of the eyeball and consists of biological, elastic, transparent, gel materials. In the present medical examination, the non-destructive examination method of the vitreous body has not been well established. Here, we focus on an application of dynamic light scattering to this topic. We tried to apply our lab-made apparatus, scanning microscopic light scattering (SMILS), which was specially designed for observing the nanometer-scale network structure in gel materials. In order to examine the vitreous body using SMILS method, a commercial apparatus, nano Partica (Horiba Co. Ltd.) was also customized. We analyzed vitreous body using both the SMILS and the customized nano Partica. We successfully examined the vitreous bodies of healthy pigs in non-destructive way.

First nondestructive measurements of power MOSFET single event burnout cross sections

International Nuclear Information System (INIS)

Oberg, D.L.; Wert, J.L.

1987-01-01

A new technique to nondestructively measure single event burnout cross sections for N-channel power MOSFETs is presented. Previous measurements of power MOSFET burnout susceptibility have been destructive and thus not conducive to providing statistically meaningful burnout probabilities. The nondestructive technique and data for various device types taken at several accelerators, including the LBL Bevalac, are documented. Several new phenomena are observed

Colorimetric Assay Of Naproxen Tablets by Derivatization Using 4 ...

African Journals Online (AJOL)

Department of Pharmaceutical Chemistry, Faculty of Pharmacy, University of Ibadan, Orita UI, ... The assay methods employed ..... Instrumental Methods of Analysis, 7th ... Binding in: Physical Pharmacy: Physical. Chemical. Principles in the.

Using Nondestructive Portable X-ray Fluorescence Spectrometers on Stone, Ceramics, Metals, and Other Materials in Museums: Advantages and Limitations.

Science.gov (United States)

Tykot, Robert H

2016-01-01

Elemental analysis is a fundamental method of analysis on archaeological materials to address their overall composition or identify the source of their geological components, yet having access to instrumentation, its often destructive nature, and the time and cost of analyses have limited the number and/or size of archaeological artifacts tested. The development of portable X-ray fluorescence (pXRF) instruments over the past decade, however, has allowed nondestructive analyses to be conducted in museums around the world, on virtually any size artifact, producing data for up to several hundred samples per day. Major issues have been raised, however, about the sensitivity, precision, and accuracy of these devices, and the limitation of performing surface analysis on potentially heterogeneous objects. The advantages and limitations of pXRF are discussed here regarding archaeological studies of obsidian, ceramics, metals, bone, and painted materials. © The Author(s) 2015.

Non-destructive techniques in the conservation field in the USA

Directory of Open Access Journals (Sweden)

Berta de Miguel

2015-12-01

Full Text Available Nondestructive evaluation techniques are extensively used in the field of architectural heritage conservation in the United States. This paper outlines the most used techniques, classifying them in visual assessment techniques, and techniques based on wave propagation. Depending on the type of wave, the latter group is subdivided in electromagnetic and acoustic techniques. The final section includes a two nondestructive techniques facilitators: unmanned aerial vehicles and Tablet PC Annotation System.

Accumulation and preparation of nondestructive inspection data for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

In recent years, flaws due to stress corrosion cracking (SCC) in stainless steel piping and nickel based alloy welds were detected at nuclear power plants in Japan. Weld Overlay (WOL) has been developed as a repairing method for piping items without removing flaws. Since the inspection techniques for WOL pipes and nickel based alloy welds are not verified enough in Japan, Japan Nuclear Energy Safety Organization (JNES) has been carrying out a six year research project entitled 'Accumulation and Preparation of Nondestructive Inspection Data for Nuclear Power Plants' regarding nondestructive inspection since FY2007. In this research project, detection and sizing capability of SCC by Ultrasonic Testing (UT) are evaluated using mockup tests. In addition, the results of this project and past nondestructive inspection data performed by JNES projects are gathered, and inputted into the database of NDT information. In FY2012, followings were conducted. 1) Analysis for UT measurement results of nickel based alloy weld simulating safe end of reactor vessel outlet nozzle. 2) Analysis for UT measurement results of cast stainless steel piping. 3) Development of interface of UT simulation. 4) Development of nondestructive testing guideline. (author)

Advanced Laser-Compton Gamma-Ray Sources for Nuclear Materials Detection, Assay and Imaging

Science.gov (United States)

Barty, C. P. J.

2015-10-01

Highly-collimated, polarized, mono-energetic beams of tunable gamma-rays may be created via the optimized Compton scattering of pulsed lasers off of ultra-bright, relativistic electron beams. Above 2 MeV, the peak brilliance of such sources can exceed that of the world's largest synchrotrons by more than 15 orders of magnitude and can enable for the first time the efficient pursuit of nuclear science and applications with photon beams, i.e. Nuclear Photonics. Potential applications are numerous and include isotope-specific nuclear materials management, element-specific medical radiography and radiology, non-destructive, isotope-specific, material assay and imaging, precision spectroscopy of nuclear resonances and photon-induced fission. This review covers activities at the Lawrence Livermore National Laboratory related to the design and optimization of mono-energetic, laser-Compton gamma-ray systems and introduces isotope-specific nuclear materials detection and assay applications enabled by them.

CMB-8 material balance system

International Nuclear Information System (INIS)

Langner, D.; Canada, T.; Ensslin, N.; Atwell, T.; Baxman, H.; Cowder, L.; Speir, L.; Lyssel, T.V.; Sampson, T.

1980-08-01

We describe the automated nondestructive assay (NDA) system installed at the Los Alamos Scientific Laboratory (LASL) Group CMB-8 uranium recovery facility. A random driver (RD) is used to measure the 235 U content of various solids while a uranium solution assay system (USAS) measures the 235 U or total uranium content of solutions over a concentration range of a few ppM to 400 g/l. Both instruments are interfaced to and controlled by a single minicomputer. The measurement principles, mechanical specifications, system software description, and operational instructions are described

Nondestructive testing for manufacture and maintenance work. Abstracts

International Nuclear Information System (INIS)

1985-01-01

The opening lecture of the meeting put special emphasis on the economic impact of nuclear energy utilization, whereas the principal lecture discussed the role of nondestructive testing methods in manufacture and maintenance work. A motion picture shown to the audience explained thermoshock experiments in a superheated steam reactor. All in all 32 papers were presented, dealing with nondestructive testing methods using ultrasounds, X-rays, eddy currents, ultrasound imaging, broad-band holography, radiator assemblies, magnet powders, pulse and eddy current signals, and computed tomography. Aircraft testing - in particular welds testing - was a main topic. The papers were supplemented by poster sessions including 60 posters on ultrasound testing, electric and magnetic testing methods, and radiographic testing. (HP) [de

New tasks for non-destructive testing

International Nuclear Information System (INIS)

1990-01-01

The proceedings contain 29 lectures and 43 posters which were presented in Trier at the annual meeting of the DGZfP in May 1990. The contributions report on further development of non-destructive testing methods towards more reliability, both of inspections and with regard to interpretation of the results. (MM) [de

Magnetic Non-destructive Testing of Plastically Deformed Mild Steel

Directory of Open Access Journals (Sweden)

Jozef Pala

2004-01-01

Full Text Available The Barkhausen noise analysis and coercive field measurement have been used as magnetic non-destructive testing methods for plastically deformed high quality carbon steel specimens. The strain dependence of root mean square value and power spectrum of the Barkhausen noise and the coercive field are explained in terms of the dislocation density. The specimens have been subjected to different magnetizing frequencies to show the overlapping nature of the Barkhausen noise. The results are discussed in the context of usage of magnetic non-destructive testing to evaluate the plastic deformation of high quality carbon steel products.

Nondestructive examination techniques on Candu fuel elements

International Nuclear Information System (INIS)

Gheorghe, G.; Man, I.

2013-01-01

During irradiation in nuclear reactor, fuel elements undergo dimensional and structural changes, and changes of surface conditions sheath as well, which can lead to damages and even loss of integrity. Visual examination and photography of Candu fuel elements are among the non-destructive examination techniques, next to dimensional measurements that include profiling (diameter, bending, camber) and length, sheath integrity control with eddy currents, measurement of the oxide layer thickness by eddy current techniques. Unirradiated Zircaloy-4 tubes were used for calibration purposes, whereas irradiated Zircaloy-4 tubes were actually subjected to visual inspection and dimensional measurements. We present results of measurements done by eddy current techniques on Zircaloy- 4 tubes, unirradiated, but oxidized in an autoclave prior to examinations. The purpose of these nondestructive examination techniques is to determine those parameters that characterize the behavior and performance of nuclear fuel operation. (authors)

Emerging nondestructive inspection methods for aging aircraft

Energy Technology Data Exchange (ETDEWEB)

Beattie, A; Dahlke, L; Gieske, J [and others

1994-01-01

This report identifies and describes emerging nondestructive inspection (NDI) methods that can potentially be used to inspect commercial transport and commuter aircraft for structural damage. The nine categories of emerging NDI techniques are: acoustic emission, x-ray computed tomography, backscatter radiation, reverse geometry x-ray, advanced electromagnetics, including magnetooptic imaging and advanced eddy current techniques, coherent optics, advanced ultrasonics, advanced visual, and infrared thermography. The physical principles, generalized performance characteristics, and typical applications associated with each method are described. In addition, aircraft inspection applications are discussed along with the associated technical considerations. Finally, the status of each technique is presented, with a discussion on when it may be available for use in actual aircraft maintenance programs. It should be noted that this is a companion document to DOT/FAA/CT-91/5, Current Nondestructive Inspection Methods for Aging Aircraft.

Use of a Gantry robot in the assay of radioactive materials

International Nuclear Information System (INIS)

Phelan, P.F.; Beugelsdijk, T.J.; Powell, W.D.; Schneider, D.N.; Staley, H.C.; Blankenship, R.

1989-01-01

A large industrial robot has been installed in our plutonium processing facility to speed the assay of materials in process. The robot routinely transports radioactive items weighing 20 lbs or more between an automated inventory system and the analytical instruments. Because the system operates unattended under computer control, assays are now performed around-the-clock instead of just 8 hrs per day, thereby greatly increasing the utilization of our instruments. (When the system becomes fully operational, we except a four-fold increase in productivity.) In addition, recordkeeping has improved, the plutonium is better protected from theft, and our personnel are exposed to less radiation than before. 4 figs

Study on a new calibration methods of in-situ HPGe γ spectrometers used for non-destructive analyzing radioactivity in nuclear facilities decommissioning

International Nuclear Information System (INIS)

Xiao Xuefu; Song Lijun; Wang Yulai; Wen Fuping; Liao Haitao; Ban Ying; Xia Yihua; Li Ruixiang; Li Hang; Tu Xingmin

2007-06-01

A new calibration technique, which is the Monte Carlo modeling technique, of in-situ HPGe γ spectrometers used for non-destructive analyzing radioactivity in nuclear facilities decommissioning, is presented. A series of assay for some stainless steel pipes and tanks in some nuclear facilities/laboratories of CIAE are taken on site with the in-situ HPGe γ spectrometer. At the same time, some examples are taken and analyzed in laboratories. The relative bias/variation between the values of activity measured by in-situ HPGe γ spectrometers on site and that analyzed in laboratory is less than ±45.0%. (authors)

Application of ICT in the non-destructive inspection of explosive device

International Nuclear Information System (INIS)

Wang Zhe; Li Tiantuo; Liu Zhiqiang; Pei Zhihua; Wang Zhiping

2003-01-01

The inspection of explosive device is an important task in the store of the weapons. The technique of non-destructive examination with radial, especially the ICT, is an effective method. The paper mainly introduces the design and the theories on the inspection system and software system of the application of industrial ICT in the non-destructive examination of explosive device, and gives a reference to the work in such fields

Optical generation,detection and non-destructive testing applications of terahertz waves

Institute of Scientific and Technical Information of China (English)

ZHANG; Weili; LIANG; Dachuan; TIAN; Zhen; HAN; Jiaguang; GU; Jianqiang; HE; Mingxia; OUYANG; Chunmei

2016-01-01

Optoelectronic terahertz generation and detection play a key role in the applications of non-destructive testing,which involves different areas such as physics,biological,material science,imaging,explosions detection,astronomy applications,semiconductor technology and superconductiong electronics. In this article,we present a reviewof the principle and performance of typical terahertz sources,detectors and non-destructive testing applications. On this basis,the newdevelopment and trends of terahertz radiation detectors are also discussed.

The assay of encapsulated alpha-bearing waste: feasibility study

International Nuclear Information System (INIS)

Curry, R.G.

1983-09-01

This report contains a review of potentially applicable techniques for the determination of actinide isotopes in radioactive waste and a summary of results obtained with various prototype instruments. A schematic design of a complete assay station is derived with consideration given to practical aspects like remote handling, maintenance etc. and recommendations for further work are made. The place of waste assay in the overall quality assurance of packaged waste is also considered. (author)

Calcium Concentration in Culture Medium as a Nondestructive and Rapid Marker of Osteogenesis.

Science.gov (United States)

Tanikake, Yohei; Akahane, Manabu; Furukawa, Akira; Tohma, Yasuaki; Inagaki, Yusuke; Kira, Tsutomu; Tanaka, Yasuhito

2017-06-09

Artificial bones made of β-tricalcium phosphate (β-TCP) combined with bone marrow-derived mesenchymal stromal cells (BM-MSCs) are used for effective reconstruction of bone defects caused by genetic defects, traumatic injury, or surgical resection of bone tumors. However, the selection of constructs with high osteogenic potential before implantation is challenging. The purpose of this study was to determine whether the calcium concentration in BM-MSC culture medium can be used as a nondestructive and simple osteogenic marker for selecting tissue-engineered grafts constructed using β-TCP and BM-MSCs. We prepared three cell passages of BM-MSCs derived from three 7-week-old, male Fischer 344 rats; the cells were cultured in osteoinductive medium in the presence of β-TCP for 15 days. The medium was replaced with fresh medium on day 1 in culture and subsequently changed every 48 h; it was collected for measurement of osteocalcin secretion and calcium concentration by enzyme-linked immunosorbent assay and X-ray fluorescence spectrometry, respectively. After cultivation, the constructs were implanted subcutaneously into the backs of recipient rats. Four weeks after implantation, the alkaline phosphatase (ALP) activity and osteocalcin content of the constructs were measured. A strong inverse correlation was observed between the calcium concentration in the medium and the ALP activity and osteocalcin content of the constructs, with Pearson's correlation coefficients of 0.92 and 0.90, respectively. These results indicate that tissue-engineered bone with high osteogenic ability can be selected before implantation based on low calcium content of the culture medium, resulting in successful bone formation after implantation. This nondestructive, simple method shows great promise for assessing the osteogenic ability of tissue-engineered bone.

Non-destructive ripeness sensing by using proton NMR [Nuclear Magnetic Resonance

International Nuclear Information System (INIS)

Cho, Seong In; Krutz, G.W.; Stroshine, R.L.

1990-01-01

More than 80 kinds of fruits and vegetables are available in the United States. But only about 6 of them have their quality standards (Dull, 1986). In the 1990 Fresh Trends survey (Zind, 1990), consumers were asked to rate 16 characteristics important to their decision to purchase fresh produce. The four top ranking factors were ripeness/freshness, taste/flavor, appearance/condition and nutritional value. Of these surveyed, 96% rated ripeness/freshness as extremely important or very important. Therefore, the development of reliable grading or sorting techniques for fresh commodities is essential. Determination of fruit quality often involves cutting and tasting. Non-destructive quality control in fruit and vegetables is a goal of growers and distributors, as well as the food processing industry. Many nondestructive techniques have been evaluated including soft x-ray, optical transmission, near infrared radiation, and machine vision. However, there are few reports of successful non-destructive measurement of sugar content directly in fruit. Higher quality fruit could be harvested and available to consumers if a nondestructive sensor that detects ripeness level directly by measuring sugar content were available. Using proton Nuclear Magnetic Resonance (NMR) principle is the possibility. A nondestructive ripeness (or sweetness) sensor for fruit quality control can be developed with the proton NMR principle (Cho, 1989). Several feasibility studies were necessary for the ripeness sensor development. Main objectives in this paper was to investigate the feasibilities (1) to detect ripeness (or sweetness level) of raw fruit tissue with an high resolution proton NMR spectroscopy (200 MHz) and (2) to measure sugar content of intact fruit with a low resolution proton NMR spectroscopy (10 MHz). 7 refs., 4 figs

Non-destructive Ripeness Sensing by Using Proton NMR [Nuclear Magnetic Resonance

Science.gov (United States)

Cho, Seong In; Krutz, G. W.; Stroshine, R. L.; Bellon, V.

1990-01-01

More than 80 kinds of fruits and vegetables are available in the United States. But only about 6 of them have their quality standards (Dull, 1986). In the 1990 Fresh Trends survey (Zind, 1990), consumers were asked to rate 16 characteristics important to their decision to purchase fresh produce. The four top ranking factors were ripeness/freshness, taste/flavor, appearance/condition and nutritional value. Of these surveyed, 96% rated ripeness/freshness as extremely important or very important. Therefore, the development of reliable grading or sorting techniques for fresh commodities is essential. Determination of fruit quality often involves cutting and tasting. Non-destructive quality control in fruit and vegetables is a goal of growers and distributors, as well as the food processing industry. Many nondestructive techniques have been evaluated including soft x-ray, optical transmission, near infrared radiation, and machine vision. However, there are few reports of successful non-destructive measurement of sugar content directly in fruit. Higher quality fruit could be harvested and available to consumers if a nondestructive sensor that detects ripeness level directly by measuring sugar content were available. Using proton Nuclear Magnetic Resonance (NMR) principle is the possibility. A nondestructive ripeness (or sweetness) sensor for fruit quality control can be developed with the proton NMR principle (Cho, 1989). Several feasibility studies were necessary for the ripeness sensor development. Main objectives in this paper was to investigate the feasibilities (1) to detect ripeness (or sweetness level) of raw fruit tissue with an high resolution proton NMR spectroscopy (200 MHz) and (2) to measure sugar content of intact fruit with a low resolution proton NMR spectroscopy (10 MHz).

Acoustic sensors for fission gas characterization: R and D skills devoted to innovative instrumentation in MTR, non-destructive devices in hot lab facilities and specific transducers for measurements of LWR rods in nuclear plants

Energy Technology Data Exchange (ETDEWEB)

Ferrandis, J.Y.; Leveque, G.; Rosenkrantz, E.; Augereau, F.; Combette, P. [University Montpellier, IES, UMR 5214, F-34000, Montpellier (France); CNRS, IES, UMR 5214, F-34000, Montpellier (France)

2015-07-01

irradiation. The instrumented fuel rod incorporating the ultrasonic gas composition sensor was finally irradiated during 2 weeks in nominal conditions. Neutronics calculation will be performed in order to calculate the thermal and fast neutron fluence and the gamma dose absorbed by acoustic sensor. A first evaluation gives a thermal fluence about 4,5.10{sup 19} n/cm{sup 2}, a fast neutrons fluence about 4,5.1018 n/cm{sup 2} and a total gamma dose up to 0,25 MGy The maximal temperature during the irradiation test was about 150 C. Although the ultrasonic sensor appears to be damaged, the optimization of the electrical attack parameters and the development of a new signal processing maintain the measurement feasibility up the end of the irradiation campaign. It was the first time that the composition of fission gas has been monitored all along an irradiation experiment in a MTR, giving access to the gas release kinetics. New researches involve thick film transducers produced by screen-printing process in order to propose piezoelectric structures for harsh temperature and irradiation measurements. The second project consists in the development of a non-destructive device that can be directly applied on a LWR fuel rod. The problem to be solved relates to the measurement of the fission gas pressure and composition in a fuel rod using a non-destructive method. Fuel rod internal pressure is one of the safety criteria applied in nuclear power analyses. This criterion must be verified in order to avoid any fuel-cladding gap reopening risk and therefore any local clad ballooning. Apart from the safety implications, this parameter is also a fuel behaviour indicator and reflects the overall fuel performance in operation, but also during shipping and long-term storage. Rod internal pressure is one criterion amongst others, like cladding corrosion, against which the acceptable fuel burn-up limit is set. A sensor has been achieved in 2007. A full-scale hot cell test of the internal gas

Qualification of a select one-stage activated partial thromboplastin time-based clotting assay and two chromogenic assays for the post-administration monitoring of nonacog beta pegol.

Science.gov (United States)

Tiefenbacher, S; Bohra, R; Amiral, J; Bowyer, A; Kitchen, S; Lochu, A; Rosén, S; Ezban, M

2017-10-01

Essentials Nonacog beta pegol (N9-GP) is an extended half-life, recombinant human factor IX (FIX). One-stage clotting (OSC) and chromogenic FIX activity assays were assessed for N9-GP recovery. OSC STA ® -Cephascreen ® , ROX FIX and BIOPHEN FIX chromogenic assays were qualified for N9-GP. Other extended half-life factor products should be assessed in a similar way prior to approval. Background Nonacog beta pegol (N9-GP) is an extended half-life, glycoPEGylated recombinant human factor IX that is under development for the prophylaxis and treatment of bleeding episodes in hemophilia B patients. Considerable reagent-dependent variability has been observed when one-stage clotting assays are used to measure the recovery of recombinant FIX products, including N9-GP. Objective To qualify select one-stage clotting and chromogenic FIX activity assays for measuring N9-GP recovery. Methods The accuracy and precision of the one-stage clotting assay (with the STA-Cephascreen activated partial thromboplastin [APTT] reagent) and the ROX Factor IX and BIOPHEN Factor IX chromogenic assays for measuring N9-GP recovery were assessed in N9-GP-spiked hemophilia B plasma samples in a systematic manner at three independent sites, with manufacturer-recommended protocols and/or site-specific assay setups, including different instruments. Results For each of the three FIX activity assays qualified on five different reagent-instrument systems, acceptable intra-assay and interassay accuracy and precision, dilution integrity, reagent robustness and freeze-thaw and short-term sample stabilities were demonstrated. The STA-Cephascreen assay showed a limited reportable range at one of the three qualification sites, and the BIOPHEN Factor IX assay showed suspect low-end sensitivity at one of the three qualification sites. An individual laboratory would account for these limitations by adjusting the assay's reportable range; thus, these findings are not considered to impact the respective

Computer-determined assay time based on preset precision

International Nuclear Information System (INIS)

Foster, L.A.; Hagan, R.; Martin, E.R.; Wachter, J.R.; Bonner, C.A.; Malcom, J.E.

1994-01-01

Most current assay systems for special nuclear materials (SNM) operate on the principle of a fixed assay time which provides acceptable measurement precision without sacrificing the required throughput of the instrument. Waste items to be assayed for SNM content can contain a wide range of nuclear material. Counting all items for the same preset assay time results in a wide range of measurement precision and wastes time at the upper end of the calibration range. A short time sample taken at the beginning of the assay could optimize the analysis time on the basis of the required measurement precision. To illustrate the technique of automatically determining the assay time, measurements were made with a segmented gamma scanner at the Plutonium Facility of Los Alamos National Laboratory with the assay time for each segment determined by counting statistics in that segment. Segments with very little SNM were quickly determined to be below the lower limit of the measurement range and the measurement was stopped. Segments with significant SNM were optimally assays to the preset precision. With this method the total assay time for each item is determined by the desired preset precision. This report describes the precision-based algorithm and presents the results of measurements made to test its validity

Plan for the testing of radiation measurement instrumentation intended for use at an excavation site

International Nuclear Information System (INIS)

Gehrke, R.J.

1994-11-01

This plan describes performance tests to be made with ionizing radiation measurement instrumentation designed and built for in-field assay at an excavation site. One instrument measures gross gamma-ray and neutron fields and the other identifies gamma-ray emitting radionuclides and also is capable of assaying for selected hazardous materials. These instruments will be operationally tested to verify that original specifications have been met and performance tested to establish and verify that they have the potential to function as intended at an excavation site

Improvement of the reliability on nondestructive inspection

International Nuclear Information System (INIS)

Song, Sung Jin; Kim, Young H.; Lee, Hyang Beom; Shin, Young Kil; Jung, Hyun Jo; Park, Ik Keun; Park, Eun Soo

2002-03-01

Retaining reliabilities of nondestructive testing is essential for the life-time maintenance of Nuclear Power Plant. The nondestructive testing methods which are frequently used in the Nuclear Power Plant are eddy current testing for the inspection of steam generator tubes and ultrasonic testing for the inspection of weldments. In order to improve reliabilities of ultrasonic testing and eddy current testing, the subjects carried out in this study are as follows : development of BEM analysis technique for ECT of SG tube, development of neural network technique for the intelligent analysis of ECT flaw signals of SG tubes, development of RFECT technology for the inspection of SG tube, FEM analysis of ultrasonic scattering field, evaluation of statistical reliability of PD-RR test of ultrasonic testing and development of multi-Gaussian beam modeling technique to predict accurate signal of signal beam ultrasonic testing with the efficiency in calculation time

Improvement of the reliability on nondestructive inspection

Energy Technology Data Exchange (ETDEWEB)

Song, Sung Jin; Kim, Young H. [Sungkyunkwan Univ., Suwon (Korea, Republic of); Lee, Hyang Beom [Soongsil Univ., Seoul (Korea, Republic of); Shin, Young Kil [Kunsan National Univ., Gunsan (Korea, Republic of); Jung, Hyun Jo [Wonkwang Univ., Iksan (Korea, Republic of); Park, Ik Keun; Park, Eun Soo [Seoul Nationl Univ., Seoul (Korea, Republic of)

2002-03-15

Retaining reliabilities of nondestructive testing is essential for the life-time maintenance of Nuclear Power Plant. The nondestructive testing methods which are frequently used in the Nuclear Power Plant are eddy current testing for the inspection of steam generator tubes and ultrasonic testing for the inspection of weldments. In order to improve reliabilities of ultrasonic testing and eddy current testing, the subjects carried out in this study are as follows : development of BEM analysis technique for ECT of SG tube, development of neural network technique for the intelligent analysis of ECT flaw signals of SG tubes, development of RFECT technology for the inspection of SG tube, FEM analysis of ultrasonic scattering field, evaluation of statistical reliability of PD-RR test of ultrasonic testing and development of multi-Gaussian beam modeling technique to predict accurate signal of signal beam ultrasonic testing with the efficiency in calculation time.

DYMAC digital electronic balance

International Nuclear Information System (INIS)

Stephens, M.M.

1980-06-01

The Dynamic Materials Accountability (DYMAC) System at LASL integrates nondestructive assay (NDA) instruments with interactive data-processing equipment to provide near-real-time accountability of the nuclear material in the LASL Plutonium Processing Facility. The most widely used NDA instrument in the system is the DYMAC digital electronic balance. The DYMAC balance is a commercial instrument that has been modified at LASL for weighing material in gloveboxes and for transmitting the weight data directly to a central computer. This manual describes the balance components, details the LASL modifications, reviews a DYMAC measurement control program that monitors balance performance, and provides instructions for balance operation and maintenance

Nondestructive evaluation of creep-fatigue damage: an interim report

International Nuclear Information System (INIS)

Nickell, R.E.

1977-02-01

In view of the uncertainties involved in designing against creep-fatigue failure and the consequences of such failures in Class 1 nuclear components that operate at elevated temperature, the possibility of intermittent or even continuous non-destructive examination of these components has been considered. In this interim report some preliminary results on magnetic force and ultrasonic evaluation of creep-fatigue damage in an LMFBR steam generator material are presented. These results indicate that the non-destructive evaluation of pure creep damage will be extremely difficult. A set of biaxial creep-fatigue tests that are designed to discriminate between various failure theories is also described

First 25-hydroxyvitamin D assay for general chemistry analyzers.

Science.gov (United States)

Saida, Fakhri B; Chen, Xiaoru; Tran, Kiet; Dou, Chao; Yuan, Chong

2015-03-01

25-Hydroxyvitamin D [25(OH)D], the predominant circulating form of vitamin D, is an accurate indicator of the general vitamin D status of an individual. Because vitamin D deficiencies have been linked to several pathologies (including osteoporosis and rickets), accurate monitoring of 25(OH)D levels is becoming increasingly important in clinical settings. Current 25(OH)D assays are either chromatographic or immunoassay-based assays. These assays include HPLC, liquid chromatography-tandem mass spectrometry (LC-MS/MS), enzyme-immunosorbent, immunochemiluminescence, immunofluorescence and radioimmunoassay. All these assays use heterogeneous formats that require phase separation and special instrumentations. In this article, we present an overview of these assays and introduce the first homogeneous assay of 25(OH)D for use on general chemistry analyzers. A special emphasis is put on the unique challenges posed by the 25(OH)D analyte. These challenges include a low detection limit, the dissociation of the analyte from its serum transporter and the inactivation of various binding proteins without phase separation steps.

The impact of gate width setting and gate utilization factors on plutonium assay in passive correlated neutron counting

International Nuclear Information System (INIS)

Henzlova, D.; Menlove, H.O.; Croft, S.; Favalli, A.; Santi, P.

2015-01-01

In the field of nuclear safeguards, passive neutron multiplicity counting (PNMC) is a method typically employed in non-destructive assay (NDA) of special nuclear material (SNM) for nonproliferation, verification and accountability purposes. PNMC is generally performed using a well-type thermal neutron counter and relies on the detection of correlated pairs or higher order multiplets of neutrons emitted by an assayed item. To assay SNM, a set of parameters for a given well-counter is required to link the measured multiplicity rates to the assayed item properties. Detection efficiency, die-away time, gate utilization factors (tightly connected to die-away time) as well as optimum gate width setting are among the key parameters. These parameters along with the underlying model assumptions directly affect the accuracy of the SNM assay. In this paper we examine the role of gate utilization factors and the single exponential die-away time assumption and their impact on the measurements for a range of plutonium materials. In addition, we examine the importance of item-optimized coincidence gate width setting as opposed to using a universal gate width value. Finally, the traditional PNMC based on multiplicity shift register electronics is extended to Feynman-type analysis and application of this approach to Pu mass assay is demonstrated

The impact of gate width setting and gate utilization factors on plutonium assay in passive correlated neutron counting

Energy Technology Data Exchange (ETDEWEB)

Henzlova, D., E-mail: henzlova@lanl.gov [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Menlove, H.O. [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Croft, S. [Oak Ridge National Laboratory, Oak Ridge, TN 37831 (United States); Favalli, A.; Santi, P. [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)

2015-10-11

In the field of nuclear safeguards, passive neutron multiplicity counting (PNMC) is a method typically employed in non-destructive assay (NDA) of special nuclear material (SNM) for nonproliferation, verification and accountability purposes. PNMC is generally performed using a well-type thermal neutron counter and relies on the detection of correlated pairs or higher order multiplets of neutrons emitted by an assayed item. To assay SNM, a set of parameters for a given well-counter is required to link the measured multiplicity rates to the assayed item properties. Detection efficiency, die-away time, gate utilization factors (tightly connected to die-away time) as well as optimum gate width setting are among the key parameters. These parameters along with the underlying model assumptions directly affect the accuracy of the SNM assay. In this paper we examine the role of gate utilization factors and the single exponential die-away time assumption and their impact on the measurements for a range of plutonium materials. In addition, we examine the importance of item-optimized coincidence gate width setting as opposed to using a universal gate width value. Finally, the traditional PNMC based on multiplicity shift register electronics is extended to Feynman-type analysis and application of this approach to Pu mass assay is demonstrated.

Safeguards instrumentation for continuous unattended monitoring in plutonium fuel fabrication plants

International Nuclear Information System (INIS)

Menlove, H.O.; Miller, M.C.; Ohtani, T.; Seya, M.; Takahashi, S.

1993-01-01

Nondestructive assay (NDA) systems have been developed for use in an automated mixed oxide fabrication facility. Unique features have been developed for the NDA systems to accommodate robotic sample handling and remote operation. In addition, the systems have been designed to obtain International Atomic Energy Agency inspection data without the need for an inspector at the facility at the time of the measurements. The equipment is being designed to operate continuously in an unattended mode with data storage for periods of up to one month. The design, performance characteristics, and authentication of the NDA systems are described. The data related to reliability, precision, and accuracy are presented

Status of LSDS Development for Isotopic Fissile Assay in Used Fuel

International Nuclear Information System (INIS)

Lee, Y.D.; Ahn, S.; Kim, H.-D.; Song, K.C.; Park, C.J.

2015-01-01

Because of the large amount accumulation of spent fuel, a research to solve the spent fuel problem is actively performed in Korea. One option is to develop the SFR linked with the pyro process to reuse the existing fissile materials in spent fuel. Therefore, an accurate isotopic fissile content assay becomes a key factor in the reuse of fissile material for safety and safeguards purpose. There are several commercial non-destructive technologies for nuclear material assay. However, technology for direct isotopic fissile content assay in spent fuel is not developed yet. Internationally, a verification of special nuclear material in spent fuel, mainly U-235, Pu239, Pu241, is very important for the safeguards objective. These fissile materials can be misused for nuclear weapon purpose, not for peaceful use. As a future nuclear system is developed,, improved safeguards technology must be developed for an approval of fissile materials. A direct measurement of fissile materials is very important to provide a continuous of knowledge on nuclear materials. LSDS (Lead Slowing Down Spectrometer) has an advantage to assay an isotopic fissile content directly, without any help of burnup code and history. LSDS system is under development in KAERI (Korea Atomic Energy Research Institute) for spent fuel and recycled fuel. A linear assay model was setup for U235, Pu239 and Pu241. The dominant individual fission characteristic is appeared between 0.1 eV and 1 keV range. An electron linear accelerator for compact and low cost is under development to produce high source neutron effectively and efficiently. The LSDS is also applicable for optimum design of spent fuel storage and management. The advanced fissile assay technology will contribute to increase the transparency and credibility internationally on a reuse of fissile materials in future nuclear energy system development. (author)

Development of a Radioactive Waste Assay System

Energy Technology Data Exchange (ETDEWEB)

Kang, Duck Won; Song, Myung Jae; Shin, Sang Woon; Sung, Kee Bang; Ko, Dae Hach [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Kim, Kil Jeong; Park, Jong Mook; Jee, Kwang Yoong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-12-31

Nuclear Act of Korea requires the manifest of low and intermediate level radioactive waste generated at nuclear power plants prior to disposal sites.Individual history records of the radioactive waste should be contained the information about the activity of nuclides in the drum, total activity, weight, the type of waste. A fully automated nuclide analysis assay system, non-destructive analysis and evaluation system of the radioactive waste, was developed through this research project. For the nuclides that could not be analysis directly by MCA, the activities of the representative {gamma}-emitters(Cs-137, Co-60) contained in the drum were measured by using that system. Then scaling factors were used to calculate the activities of {alpha}, {beta}-emitters. Furthermore, this system can automatically mark the analysis results onto the drum surface. An automated drum handling system developed through this research project can reduce the radiation exposure to workers. (author). 41 refs., figs.

Non-destructive testing of electronic component packages

International Nuclear Information System (INIS)

Anderle, C.

1975-01-01

A non-destructive method of investigating packaged parts of semiconductor components by X radiation is described and the relevant theoretical relations limiting this technique are derived. The application of the technique is demonstrated in testing several components. The described method is iNsimple and quick. (author)

A blind test of nondestructive underground void detection by ground penetrating radar (GPR)

Science.gov (United States)

Lai, Wallace W. L.; Chang, Ray K. W.; Sham, Janet F. C.

2018-02-01

Blind test/experiment is widely adopted in various scientific disciplines like medicine drug testing/clinical trials/psychology, but not popular in nondestructive testing and evaluation (NDTE) nor near-surface geophysics (NSG). This paper introduces a blind test of nondestructive underground void detection in highway/pavement using ground penetrating radar (GPR). Purpose of which is to help the Highways Department (HyD) of the Hong Kong Government to evaluate the feasibility of large-scale and nationwide application, and examine the ability of appropriate service providers to carry out such works. In the past failure case of such NDTE/NSG based on lowest bid price, it is not easy to know which part(s) in SWIMS (S - service provider, i.e. people; W - work procedure; I - instrumentation; M - materials in the complex underground; S - specifications by client) fails, and how it/they fail(s). This work attempts to carry out the blind test by burying fit balls (as voids) under a site with reinforced concrete road and paving block by PolyU team A. The blind test about the void centroid, spread and cover depth was then carried out by PolyU team B without prior information given. Then with this baseline, a marking scheme, acceptance criteria and passing mark were set to test six local commercial service providers, determine their scores and evaluate the performance. A pass is a prerequisite of the award of a service contract of similar nature. In this first attempt of the blind test, results were not satisfactory and it is concluded that 'S-service provider' and 'W-work procedure' amongst SWIMS contributed to most part of the unsatisfactory performance.+

Magnetite Core-Shell Nanoparticles in Nondestructive Flaw Detection of Polymeric Materials.

Science.gov (United States)

Hetti, Mimi; Wei, Qiang; Pohl, Rainer; Casperson, Ralf; Bartusch, Matthias; Neu, Volker; Pospiech, Doris; Voit, Brigitte

2016-10-04

Nondestructive flaw detection in polymeric materials is important but difficult to achieve. In this research, the application of magnetite nanoparticles (MNPs) in nondestructive flaw detection is studied and realized, to the best of our knowledge, for the first time. Superparamagnetic and highly magnetic (up to 63 emu/g) magnetite core-shell nanoparticles are prepared by grafting bromo-end-group-functionalized poly(glycidyl methacrylate) (Br-PGMA) onto surface-modified Fe 3 O 4 NPs. These Fe 3 O 4 -PGMA NPs are blended into bisphenol A diglycidylether (BADGE)-based epoxy to form homogeneously distributed magnetic epoxy nanocomposites (MENCs) after curing. The core Fe 3 O 4 of the Fe 3 O 4 -PGMA NPs endows the MENCs with magnetic property, which is crucial for nondestructive flaw detection of the materials, while the shell PGMA promotes colloidal stability and prevents NP aggregation during curing. The eddy current testing (ET) technique is first applied to detect flaws in the MENCs. Through the brightness contrast of the ET image, surficial and subsurficial flaws in MENCs can be detected, even for MENCs with low content of Fe 3 O 4 -PGMA NPs (1 wt %). The incorporation of Fe 3 O 4 -PGMA NPs can be easily extended to other polymer and polymer-based composite systems and opens a new and very promising pathway toward MNP-based nondestructive flaw detection in polymeric materials.

A strategy for the unrestricted release of metallic scrap from decommissioned nuclear facilities, integrating quality planning with the effective use of non-destructive assay instrumentation

International Nuclear Information System (INIS)

Gunn, R.; Troughten, N.; Warran, C.

2000-01-01

The key component of any release operation is its quality plan. This plan is a step by step procedure which describes all the actions which are required during the entire process and also the information required at every stage of the process. Once drafted the quality plan will enable operators to determine at what stages it is necessary to measure the parameters required to allow the process to progress. The objective of the radiometric system is to provide the auditable proof that material has been surveyed, the record of the survey and the evidence that the system was operating within its design parameters during the survey. Typical radiometric instruments which have been deployed to provide the information requirements of the quality plan are described in this paper. These include the IonSens TM Conveyor, conveyorized survey monitor used to provide high throughout clearance surveys of removed metallic scrap. The IonSens TM Pipe, cut pipe monitor is used to survey interiors and exteriors of long lengths of removed pipe-work. The IonSens TM 208 large Item monitor is used to survey removed pieces of vessels and ductwork which may have convoluted shapes and finally the DrumScan TM system is used to survey 200 litre drums containing cut up pieces of metal. (author)

Nondestructive mechanical characterization of developing biological tissues using inflation testing.

Science.gov (United States)

Oomen, P J A; van Kelle, M A J; Oomens, C W J; Bouten, C V C; Loerakker, S

2017-10-01

One of the hallmarks of biological soft tissues is their capacity to grow and remodel in response to changes in their environment. Although it is well-accepted that these processes occur at least partly to maintain a mechanical homeostasis, it remains unclear which mechanical constituent(s) determine(s) mechanical homeostasis. In the current study a nondestructive mechanical test and a two-step inverse analysis method were developed and validated to nondestructively estimate the mechanical properties of biological tissue during tissue culture. Nondestructive mechanical testing was achieved by performing an inflation test on tissues that were cultured inside a bioreactor, while the tissue displacement and thickness were nondestructively measured using ultrasound. The material parameters were estimated by an inverse finite element scheme, which was preceded by an analytical estimation step to rapidly obtain an initial estimate that already approximated the final solution. The efficiency and accuracy of the two-step inverse method was demonstrated on virtual experiments of several material types with known parameters. PDMS samples were used to demonstrate the method's feasibility, where it was shown that the proposed method yielded similar results to tensile testing. Finally, the method was applied to estimate the material properties of tissue-engineered constructs. Via this method, the evolution of mechanical properties during tissue growth and remodeling can now be monitored in a well-controlled system. The outcomes can be used to determine various mechanical constituents and to assess their contribution to mechanical homeostasis. Copyright © 2017 Elsevier Ltd. All rights reserved.

Wavelet modeling of signals for non-destructive testing of concretes

International Nuclear Information System (INIS)

Shao, Zhixue; Shi, Lihua; Cai, Jian

2011-01-01

In a non-destructive test of concrete structures, ultrasonic pulses are commonly used to detect damage or embedded objects from their reflections. A wavelet modeling method is proposed here to identify the main reflections and to remove the interferences in the detected ultrasonic waves. This method assumes that if the structure is stimulated by a wavelet function with good time–frequency localization ability, the detected signal is a combination of time-delayed and amplitude-attenuated wavelets. Therefore, modeling of the detected signal by wavelets can give a straightforward and simple model of the original signal. The central time and amplitude of each wavelet represent the position and amplitude of the reflections in the detected structure. A signal processing method is also proposed to estimate the structure response to wavelet excitation from its response to a high-voltage pulse with a sharp leading edge. A signal generation card with a compact peripheral component interconnect extension for instrumentation interface is designed to produce this high-voltage pulse. The proposed method is applied to synthesized aperture focusing technology of concrete specimens and the image results are provided

High-resolution non-destructive three-dimensional imaging of integrated circuits.

Science.gov (United States)

Holler, Mirko; Guizar-Sicairos, Manuel; Tsai, Esther H R; Dinapoli, Roberto; Müller, Elisabeth; Bunk, Oliver; Raabe, Jörg; Aeppli, Gabriel

2017-03-15

Modern nanoelectronics has advanced to a point at which it is impossible to image entire devices and their interconnections non-destructively because of their small feature sizes and the complex three-dimensional structures resulting from their integration on a chip. This metrology gap implies a lack of direct feedback between design and manufacturing processes, and hampers quality control during production, shipment and use. Here we demonstrate that X-ray ptychography-a high-resolution coherent diffractive imaging technique-can create three-dimensional images of integrated circuits of known and unknown designs with a lateral resolution in all directions down to 14.6 nanometres. We obtained detailed device geometries and corresponding elemental maps, and show how the devices are integrated with each other to form the chip. Our experiments represent a major advance in chip inspection and reverse engineering over the traditional destructive electron microscopy and ion milling techniques. Foreseeable developments in X-ray sources, optics and detectors, as well as adoption of an instrument geometry optimized for planar rather than cylindrical samples, could lead to a thousand-fold increase in efficiency, with concomitant reductions in scan times and voxel sizes.

High-resolution non-destructive three-dimensional imaging of integrated circuits

Science.gov (United States)

Holler, Mirko; Guizar-Sicairos, Manuel; Tsai, Esther H. R.; Dinapoli, Roberto; Müller, Elisabeth; Bunk, Oliver; Raabe, Jörg; Aeppli, Gabriel

2017-03-01

Modern nanoelectronics has advanced to a point at which it is impossible to image entire devices and their interconnections non-destructively because of their small feature sizes and the complex three-dimensional structures resulting from their integration on a chip. This metrology gap implies a lack of direct feedback between design and manufacturing processes, and hampers quality control during production, shipment and use. Here we demonstrate that X-ray ptychography—a high-resolution coherent diffractive imaging technique—can create three-dimensional images of integrated circuits of known and unknown designs with a lateral resolution in all directions down to 14.6 nanometres. We obtained detailed device geometries and corresponding elemental maps, and show how the devices are integrated with each other to form the chip. Our experiments represent a major advance in chip inspection and reverse engineering over the traditional destructive electron microscopy and ion milling techniques. Foreseeable developments in X-ray sources, optics and detectors, as well as adoption of an instrument geometry optimized for planar rather than cylindrical samples, could lead to a thousand-fold increase in efficiency, with concomitant reductions in scan times and voxel sizes.

Alternative Methods for the Detection of Emerging Marine Toxins: Biosensors, Biochemical Assays and Cell-Based Assays

Directory of Open Access Journals (Sweden)

Laia Reverté

2014-11-01

Full Text Available The emergence of marine toxins in water and seafood may have a considerable impact on public health. Although the tendency in Europe is to consolidate, when possible, official reference methods based on instrumental analysis, the development of alternative or complementary methods providing functional or toxicological information may provide advantages in terms of risk identification, but also low cost, simplicity, ease of use and high-throughput analysis. This article gives an overview of the immunoassays, cell-based assays, receptor-binding assays and biosensors that have been developed for the screening and quantification of emerging marine toxins: palytoxins, ciguatoxins, cyclic imines and tetrodotoxins. Their advantages and limitations are discussed, as well as their possible integration in research and monitoring programs.

Alternative Methods for the Detection of Emerging Marine Toxins: Biosensors, Biochemical Assays and Cell-Based Assays

Science.gov (United States)

Reverté, Laia; Soliño, Lucía; Carnicer, Olga; Diogène, Jorge; Campàs, Mònica

2014-01-01

The emergence of marine toxins in water and seafood may have a considerable impact on public health. Although the tendency in Europe is to consolidate, when possible, official reference methods based on instrumental analysis, the development of alternative or complementary methods providing functional or toxicological information may provide advantages in terms of risk identification, but also low cost, simplicity, ease of use and high-throughput analysis. This article gives an overview of the immunoassays, cell-based assays, receptor-binding assays and biosensors that have been developed for the screening and quantification of emerging marine toxins: palytoxins, ciguatoxins, cyclic imines and tetrodotoxins. Their advantages and limitations are discussed, as well as their possible integration in research and monitoring programs. PMID:25431968

R and D non-destructive damage monitoring and diagnosing system for civil infrastructures

International Nuclear Information System (INIS)

Ren Weixin; Abu Bakar Mohamad Diah; Cheng Hao

1998-01-01

Since civil infrastructures serve as the underpinnings of our highly industrialized society, and much of them are now decaying, it is the time to consider how to maintain these widely spread infrastructures in order to prevent potential catastrophic events. Changes in use and the need to maintain an ageing system require improvements in instrumentation for sensing and recording, data acquisition for diagnosing the possible damage, and algorithm for identifying and monitoring the changes in structural characteristics. Researching and developing a real-time, in-serve health detection and monitoring system has drawn a worldwide attention recently for various types of structures. The paper conceives an integrated non-destructive damage monitoring and diagnosing system for civil infrastructures. The system is a high technology and high-commercialised industrial integrated product involved in research and development. The research activities of the system cover three core parts: structural modelling, structural system identification and damage criterion establishment. The development activities of the system include experimental measurements, data acquisition and processing, instrumentation set-up, computer visualisation, and software development. The state-of -the art theories and practices are systematically merged and integrated in the development of the system, and the system will be verified through the real world application for civil infrastructures. Our research results on the damage criterion based on the changes in structural dynamic properties are also reported in the paper. (Author)

Problems and progress in the preparation of sources for the alpha spectrometry of plutonium

International Nuclear Information System (INIS)

Miguel, M.; Deron, S.; Swietly, H.; Heinonen, O.J.

1981-01-01

The interpretation of non-destructive measurements of plutonium materials require more accurate determinations of the isotopic abundance of Pu-238 than conventional chemical assays. The requirements of calorimetry, passive neutron and conventional chemical assays are presented and compared. When Pu-238 is measured by alpha spectrometry, these requirements define how well the plutonium must be separated from americium, and what should be the accuracy of the spectrometry. The latter can strongly depend upon the resolution of the alpha spectrum. The authors describe a procedure to produce sources by drop deposition which ensure a resolution of 17 keV with commercial instrumentation

Nondestructive Evaluation Program: Progress in 1986

International Nuclear Information System (INIS)

1987-07-01

The increasing cost of equipment for power generating plants and the potential increases in productivity and safety available through rapidly developing Nondestructive Evaluation (NDE) technology led EPRI to initiate a Nondestructive Evaluation Program in 1974. To date, the major focus has been on light water reactor inspection problems; however, increased application to other systems is now under way. This report presents a comprehensive review of the EPRI effort in the NDE area. Most of the report consists of contractor-supplied progress reports on each current project. An organizational plan of the program is presented in overview. In addition, organization from several viewpoints is presented, e.g., in-service inspection operators, R and D personnel, and utility representatives. The report summarizes significant progress made since the previous EPRI Special Report NP-4315-SR was issued in May 1986. Section 1 contains information about the program organization, and the sections that follow contain contractor-supplied progress reports of each current project. The progress reports are grouped by plant components - pipe, pressure vessel, steam generator and boiler tubes, and turbine. In addition, Part 6 is devoted to discussions of technology transfer

Lead Slowing-Down Spectrometry Time Spectral Analysis for Spent Fuel Assay: FY12 Status Report

Energy Technology Data Exchange (ETDEWEB)

Kulisek, Jonathan A.; Anderson, Kevin K.; Casella, Andrew M.; Siciliano, Edward R.; Warren, Glen A.

2012-09-28

Executive Summary Developing a method for the accurate, direct, and independent assay of the fissile isotopes in bulk materials (such as used fuel) from next-generation domestic nuclear fuel cycles is a goal of the Office of Nuclear Energy, Fuel Cycle R&D, Material Protection and Control Technology (MPACT) Campaign. To meet this goal, MPACT supports a multi-institutional collaboration, of which PNNL is a part, to study the feasibility of Lead Slowing Down Spectroscopy (LSDS). This technique is an active nondestructive assay method that has the potential to provide independent, direct measurement of Pu and U isotopic masses in used fuel with an uncertainty considerably lower than the approximately 10% typical of today’s confirmatory methods. This document is a progress report for FY2012 PNNL analysis and algorithm development. Progress made by PNNL in FY2012 continues to indicate the promise of LSDS analysis and algorithms applied to used fuel assemblies. PNNL further refined the semi-empirical model developed in FY2011 based on singular value decomposition (SVD) to numerically account for the effects of self-shielding. The average uncertainty in the Pu mass across the NGSI-64 fuel assemblies was shown to be less than 3% using only six calibration assemblies with a 2% uncertainty in the isotopic masses. When calibrated against the six NGSI-64 fuel assemblies, the algorithm was able to determine the total Pu mass within <2% uncertainty for the 27 diversion cases also developed under NGSI. Two purely empirical algorithms were developed that do not require the use of Pu isotopic fission chambers. The semi-empirical and purely empirical algorithms were successfully tested using MCNPX simulations as well applied to experimental data measured by RPI using their LSDS. The algorithms were able to describe the 235U masses of the RPI measurements with an average uncertainty of 2.3%. Analyses were conducted that provided valuable insight with regard to design requirements (e

Nuclear Technology. Course 26: Nondestructive Examination (NDE) Techniques I. Module 26-6, Radiography Inspection.

Science.gov (United States)

Pelton, Rick; Espy, John

This sixth in a series of seven modules for a course titled Nondestructive Examination (NDE) Techniques I explains radiographic inspection as a means of nondestructively examining components, assemblies, structures, and fabricated piping. The module follows a typical format that includes the following sections: (1) introduction, (2) module…

Nondestructive methods for quality evaluation of livestock products.

Science.gov (United States)

Narsaiah, K; Jha, Shyam N

2012-06-01

The muscles derived from livestock are highly perishable. Rapid and nondestructive methods are essential for quality assurance of such products. Potential nondestructive methods, which can supplement or replace many of traditional time consuming destructive methods, include colour and computer image analysis, NIR spectroscopy, NMRI, electronic nose, ultrasound, X-ray imaging and biosensors. These methods are briefly described and the research work involving them for products derived from livestock is reviewed. These methods will be helpful in rapid screening of large number of samples, monitoring distribution networks, quick product recall and enhance traceability in the value chain of livestock products. With new developments in the areas of basic science related to these methods, colour, image processing, NIR spectroscopy, biosensors and ultrasonic analysis are expected to be widespread and cost effective for large scale meat quality evaluation in near future.

Advanced uses of radiation in non-destructive evaluation

International Nuclear Information System (INIS)

Baldev Raj; Viswanathan, B.; Venkataraman, B.

1998-01-01

The increasing demand for newer materials and stringency of specifications, have expanded the scope of advanced uses of radiation in non-destructive evaluation of materials and industrial components. This paper highlights the application of some of the advanced techniques of radiography and residual stress measurements, using x-ray diffraction, for materials characterisation and testing, based on the results obtained at the author's laboratory. The application of positron annihilation techniques based on the use of radioisotopes and high resolution gamma ray spectroscopy, is introduced as non-destructive tools for materials characterisation. Selective examples of significant results obtained using this technique, on the radiation damage and early stages of fatigue damage in technologically important steels are reviewed from recent works at the author's laboratory and elsewhere. The scope of application of charge particle based thin layer activation method is briefly outlined. (author)

Innovative technology transfer of nondestructive evaluation research

Science.gov (United States)

Brian Brashaw; Robert J. Ross; Xiping Wang

2008-01-01

Technology transfer is often an afterthought for many nondestructive evaluation (NDE) researchers. Effective technology transfer should be considered during the planning and execution of research projects. This paper outlines strategies for using technology transfer in NDE research and presents a wide variety of technology transfer methods used by a cooperative...

NonDestructive Evaluation for Industrial & Development Applications

Energy Technology Data Exchange (ETDEWEB)

Hunter, James F. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-10-12

Provide overview of weld inspection for Non-Destructive Testing at LANL. This includes radiography (RT/DR/CR/CT for x-ray & neutron sources), ultrasonic testing (UT/PAUT), dye penetrant inspection (PT), eddy current inspection (ET) and magnetic particle testing (MT). Facilities and capabilities for weld inspection will be summarized with examples.

Improved Nondestructive Disassembly Process using Augmented Reality and RFID Product/Part Tracking

Directory of Open Access Journals (Sweden)

Ile Mircheski

2017-11-01

Full Text Available The waste from electric and electronic equipment and discarded automobiles in the past grew rapidly and resulted with waste in billions of tones. The aim of this paper is to present an improved non-destructive disassembly process of electromechanical products using augmented reality based devices, such as glasses, tablets or mobile phones, and RFID technology for valuable product/part tracking. The proposed method includes tagging of components of interest in the product assembly by using a RFID tag. The valuable product is marked with specific ID number written in the RFID tag, in order to declare the product. The relevant data such as material and weight of components, guidelines for non-destructive disassembly for the valuable product and removing of component of interest will be obtained with the assistance of RFID tag and a centralized database. This modular system offers guidelines for the non-destructive disassembly process for obtaining valuable component of interest intended for easy repairs, remanufacture, reuse or recycling. The guidelines are in video presentation format using augmented reality for easy visualization of non-destructive disassembly process. The benefits of proposed modular system includes biggest percentage of reuse of the valuable components, easy maintaining, improved material recycling, environmental protection and greater total return form end of life products.

Evaluation of international and local magnetic rope testing instrument defect detection capabilities and resolution, particularly in respect of low rotation, multi-layer rope constructions.

CSIR Research Space (South Africa)

Dohm, M

1999-05-01

Full Text Available testing machine and pre-tensioned to 9,6 tons, which is 10% of the ultimate breaking strength of a new rope. The reason for tensioning the rope is to simulate rope conditions in-service. Each contractor was required to fit his instrument to the rope...-of-strength estimate.14. The above literature indicates that instruments are commercially available which exhibit high resolution which result in acceptable non-destructive rope inspection results. At the Mine Hoisting 93 Conference in London the following...

Monitoring of plutonium contaminated solid waste streams. Chapter IV: Passive neutron assay

International Nuclear Information System (INIS)

Birkhoff, G.; Bondar, L.

1978-01-01

The fundamentals of the passive neutron technique for the non destructive assay of plutonium bearing materials are summarized. A reference monitor for the passive neutron assay of Pu contaminated solids is described in terms of instrumental design principles and performances. The theoretical model of this reference monitor with pertinent nuclear data and functions for the interpretation of experimental data is given

Non-destructive assay of fissile materials by detection and multiplicity analysis of spontaneous neutrons

International Nuclear Information System (INIS)

Prosdocimi, A.

1979-01-01

A method for determining the absolute reaction rate of nuclear events giving rise to neutron emission, according to their neutron multiplicity, is proposed. A typical application is the measurement of the (α, n) and spontaneous fission rates in a fissile material sample, particularly of Pu oxide composition. An analysis of random and correlated neutron pulses is carried out on the basis of sequential order without requiring any time interval analysis, then the primary nuclear events are sorted versus their neutron multiplicity. Suitable theoretical relationships enable to derive the absolute (α, n) and SF reaction rates when the physical parameters of the neutron detector and the multiplicity spectrumm of pulses are known. A typical device is described and the results of experiments leading to Pu-239 and Pu-240 assay are given

Portable instrumentation for quantitatively measuring radioactive surface contaminations, including 90Sr

International Nuclear Information System (INIS)

Brodzinski, R.L.

1983-10-01

In order to measure the effectiveness of decontamination efforts, a quantitative analysis of the radiocontamination is necessary, both before and after decontamination. Since it is desirable to release the decontaminated material for unrestricted use or disposal, the assay equipment must provide adequate sensitivity to measure the radioactivity at or below the release limit. In addition, the instrumentation must be capable of measuring all kinds of radiocontaminants including fission products, activation products, and transuranic materials. Finally, the survey instrumentation must be extremely versatile in order to assay the wide variety of contaminated surfaces in many environments, some of which may be extremely hostile or remote. This communication describes the development and application of portable instrumentation capable of quantitatively measuring most transuranics, activation products, and fission products, including 90 Sr, on almost any contaminated surface in nearly any location

Human neuron-astrocyte 3D co-culture-based assay for evaluation of neuroprotective compounds.

Science.gov (United States)

Terrasso, Ana Paula; Silva, Ana Carina; Filipe, Augusto; Pedroso, Pedro; Ferreira, Ana Lúcia; Alves, Paula Marques; Brito, Catarina

Central nervous system drug development has registered high attrition rates, mainly due to the lack of efficacy of drug candidates, highlighting the low reliability of the models used in early-stage drug development and the need for new in vitro human cell-based models and assays to accurately identify and validate drug candidates. 3D human cell models can include different tissue cell types and represent the spatiotemporal context of the original tissue (co-cultures), allowing the establishment of biologically-relevant cell-cell and cell-extracellular matrix interactions. Nevertheless, exploitation of these 3D models for neuroprotection assessment has been limited due to the lack of data to validate such 3D co-culture approaches. In this work we combined a 3D human neuron-astrocyte co-culture with a cell viability endpoint for the implementation of a novel in vitro neuroprotection assay, over an oxidative insult. Neuroprotection assay robustness and specificity, and the applicability of Presto Blue, MTT and CytoTox-Glo viability assays to the 3D co-culture were evaluated. Presto Blue was the adequate endpoint as it is non-destructive and is a simpler and reliable assay. Semi-automation of the cell viability endpoint was performed, indicating that the assay setup is amenable to be transferred to automated screening platforms. Finally, the neuroprotection assay setup was applied to a series of 36 test compounds and several candidates with higher neuroprotective effect than the positive control, Idebenone, were identified. The robustness and simplicity of the implemented neuroprotection assay with the cell viability endpoint enables the use of more complex and reliable 3D in vitro cell models to identify and validate drug candidates. Copyright © 2016 Elsevier Inc. All rights reserved.

Non-destructive control: technologies, applications and markets

International Nuclear Information System (INIS)

Anon.

1995-01-01

A description of NDC - nondestructive controls - (acoustic emission, Eddy currents, infrared and thermal, liquid penetrants, magnetic particles, radiographic, ultrasonic, visual and optical techniques) is given with various industrial applications and market trends. Some research projects, contacts and a list of NDC systems main manufacturers are given. (A.B.). 37 figs. and tabs

Nondestructive techniques for the control of conditioned radioactive wastes

International Nuclear Information System (INIS)

Delprato, U.

1987-01-01

The final product of the radwaste conditioning process must satisfy certain requirments and physico-chemical properties in order to assure its safe long-term behaviour. Of course, the foreseen quality assurance and quality control should be conducted by means of non-destructive techniques. This work presents an over-view of various applicable non-destructive methods of analysis, showing their fields of investigation in testing waste packages, together with some arising practical problems. The most promising methods, such as eddy current testing, ultrasonic testing, γ-scanning, γ-spectroscopy, neutron counting and computerized tomography, are treated more deeply and some applications are presented. Particular attention is devoted to the development of a device based on computerized tomography; its essential components are reported and some design problems are also discussed

Computerized low-level waste assay system operation manual

International Nuclear Information System (INIS)

Jones, D.F.; Cowder, L.R.; Martin, E.R.

1976-01-01

An operation and maintenance manual for the computerized low-level waste box counter is presented, which describes routine assay techniques as well as theory of operation treated in sufficient depth so that an experienced assayist can make nonroutine assays. In addition, complete system schematics are included, along with a complete circuit description to facilitate not only maintenance and troubleshooting, but also reproduction of the instrument if desired. Complete software system descriptions are included so far as calculational algorithms are concerned, although detailed instruction listings would have to be obtained from Group R-1 at LASL in order to make machine-language code changes

Development of a micro-X-ray fluorescence system based on polycapillary X-ray optics for non-destructive analysis of archaeological objects

Science.gov (United States)

Cheng, Lin; Ding, Xunliang; Liu, Zhiguo; Pan, Qiuli; Chu, Xuelian

2007-08-01

A new micro-X-ray fluorescence (micro-XRF) system based on rotating anode X-ray generator and polycapillary X-ray optics has been set up in XOL Lab, BNU, China, in order to be used for analysis of archaeological objects. The polycapillary X-ray optics used here can focus the primary X-ray beam down to tens of micrometers in diameter that allows for non-destructive and local analysis of sub-mm samples with minor/trace level sensitivity. The analytical characteristics and potential of this micro-XRF system in archaeological research are discussed. Some described uses of this instrument include studying Chinese ancient porcelain.

Development of a micro-X-ray fluorescence system based on polycapillary X-ray optics for non-destructive analysis of archaeological objects

Energy Technology Data Exchange (ETDEWEB)

Cheng Lin [Key Laboratory of Beam Technology and Material Modification of Ministry of Education, Institute of Low Energy Nuclear Physics, Beijing Normal University, Beijing Radiation Center, Beijing, 100875 (China)], E-mail: chenglin@bnu.edu.cn; Ding Xunliang; Liu Zhiguo; Pan Qiuli; Chu Xuelian [Key Laboratory of Beam Technology and Material Modification of Ministry of Education, Institute of Low Energy Nuclear Physics, Beijing Normal University, Beijing Radiation Center, Beijing, 100875 (China)

2007-08-15

A new micro-X-ray fluorescence (micro-XRF) system based on rotating anode X-ray generator and polycapillary X-ray optics has been set up in XOL Lab, BNU, China, in order to be used for analysis of archaeological objects. The polycapillary X-ray optics used here can focus the primary X-ray beam down to tens of micrometers in diameter that allows for non-destructive and local analysis of sub-mm samples with minor/trace level sensitivity. The analytical characteristics and potential of this micro-XRF system in archaeological research are discussed. Some described uses of this instrument include studying Chinese ancient porcelain.

Easy instrumental analysis

International Nuclear Information System (INIS)

Ko, Myeong Su; Kim, Tae Hwa; Park, Gyu Hyeon; Yang, Jong Beom; Oh, Chang Hwan; Lee, Kyoung Hye

2010-04-01

This textbook describes instrument analysis in easy way with twelve chapters. The contents of the book are pH measurement on principle, pH meter, pH measurement, examples of the experiments, centrifugation, Absorptiometry, Fluorescent method, Atomic absorption analysis, Gas-chromatography, Gas chromatography-mass spectrometry, High performance liquid chromatography liquid chromatograph-mass spectrometry, Electrophoresis on practical case and analysis of the result and examples, PCR on principle, device, application and examples and Enzyme-linked immunosorbent assay with indirect ELISA, sandwich ELISA and ELISA reader.

Easy instrumental analysis

Energy Technology Data Exchange (ETDEWEB)

Ko, Myeong Su; Kim, Tae Hwa; Park, Gyu Hyeon; Yang, Jong Beom; Oh, Chang Hwan; Lee, Kyoung Hye

2010-04-15

This textbook describes instrument analysis in easy way with twelve chapters. The contents of the book are pH measurement on principle, pH meter, pH measurement, examples of the experiments, centrifugation, Absorptiometry, Fluorescent method, Atomic absorption analysis, Gas-chromatography, Gas chromatography-mass spectrometry, High performance liquid chromatography liquid chromatograph-mass spectrometry, Electrophoresis on practical case and analysis of the result and examples, PCR on principle, device, application and examples and Enzyme-linked immunosorbent assay with indirect ELISA, sandwich ELISA and ELISA reader.

Near instrument-free, simple molecular device for rapid detection of herpes simplex viruses.

Science.gov (United States)

Lemieux, Bertrand; Li, Ying; Kong, Huimin; Tang, Yi-Wei

2012-06-01

The first near instrument-free, inexpensive and simple molecular diagnostic device (IsoAmp HSV, BioHelix Corp., MA, USA) recently received US FDA clearance for use in the detection of herpes simplex viruses (HSV) in genital and oral lesion specimens. The IsoAmp HSV assay uses isothermal helicase-dependent amplification in combination with a disposable, hermetically-sealed, vertical-flow strip identification. The IsoAmp HSV assay has a total test-to-result time of less than 1.5 h by omitting the time-consuming nucleic acid extraction. The diagnostic sensitivity and specificity are comparable to PCR and are superior to culture-based methods. The near instrument-free, rapid and simple characteristics of the IsoAmp HSV assay make it potentially suitable for point-of-care testing.

Dissolvable fluidic time delays for programming multi-step assays in instrument-free paper diagnostics.

Science.gov (United States)

Lutz, Barry; Liang, Tinny; Fu, Elain; Ramachandran, Sujatha; Kauffman, Peter; Yager, Paul

2013-07-21

Lateral flow tests (LFTs) are an ingenious format for rapid and easy-to-use diagnostics, but they are fundamentally limited to assay chemistries that can be reduced to a single chemical step. In contrast, most laboratory diagnostic assays rely on multiple timed steps carried out by a human or a machine. Here, we use dissolvable sugar applied to paper to create programmable flow delays and present a paper network topology that uses these time delays to program automated multi-step fluidic protocols. Solutions of sucrose at different concentrations (10-70% of saturation) were added to paper strips and dried to create fluidic time delays spanning minutes to nearly an hour. A simple folding card format employing sugar delays was shown to automate a four-step fluidic process initiated by a single user activation step (folding the card); this device was used to perform a signal-amplified sandwich immunoassay for a diagnostic biomarker for malaria. The cards are capable of automating multi-step assay protocols normally used in laboratories, but in a rapid, low-cost, and easy-to-use format.

Radioisotopes in non-destructive testing

International Nuclear Information System (INIS)

Domanus, J.C.

1976-12-01

After defining nondestructive testing (NDT) and comparing this concept with destructive testing, a short description is given of NDT methods other than radiologic. The basic concepts of radiologic methods are discussed and the principles of radiography are explained. Radiation sources and gamma radiography machines are next reviewed and radiographic inspection of weldings and castings is described. A brief description is given of the radiographic darkroom and accessories. Other radioisotope methods, such as neutron radiography, are shortly reviewed. Cost estimations for radioisotopic equipment conclude the report. (author)

Recent developments at French atomic energy commission relating to non destructive nuclear waste assay by using electron accelerator

International Nuclear Information System (INIS)

Lvoussi, A.; Romeyer-Dhebey, J.; Jallu, F.; Passard, C.; Mariani, A.; Recroix, H.; Payan, E.; Denis, C.; Loridon, J.; Buisson, A.; Nurdin, G.; Allano, J.; Jaureguy, J.C.

2000-01-01

An important program is currently in progress at several laboratories over the world for the development of sensitive, practical non-destructive assay techniques for the quantification of low level transuranics (TRU) in solid wastes. The wide variety of materials and contaminants, the low concentrations and large volumes involve, all make this kind of assay a complicated affair. Over the last few years, considerable progress has been made in the field of assay techniques for low level contaminated wastes. This report describes the methods being developed at French Atomic Energy Commission (C.E.A.) in Cadarache to assay high density TRU waste packages by using photon, neutron or both photon and neutron as interrogating particles. All of these particles are produced by using a pulsed electron linear accelerator from which the photons are produced following Bremsstrahlung phenomena on a heavy metallic converter and the neutrons are generated in appropriate low level photoneutron threshold target (e.g. Beryllium). The dynamic of photonuclear interactions and photoneutron production, use of an electron linear accelerator as a particle source, experimental and electronics details, experimental results, simulation to experiment performances and future experimental and theoretical studies are discussed. (authors)

Nondestructive examination requirements for PWR vessel internals

International Nuclear Information System (INIS)

Spanner, J.

2015-01-01

This paper describes the requirements for the nondestructive examination of pressurized water reactor (PWR) vessel internals in accordance with the requirements of the EPRI Material Reliability Program (MRP) inspection standard for PWR internals (MRP-228) and the American Society of Mechanical Engineers Section XI In-service Inspection. The MRP vessel internals examinations have been performed at nuclear plants in the USA since 2009. The objective of the inspection standard is to provide the requirements for the nondestructive examination (NDE) methods implemented to support the inspection and evaluation of the internals. The inspection standard contains requirements specific to the inspection methodologies involved as well as requirements for qualification of the NDE procedures, equipment and personnel used to perform the vessel internals inspections. The qualification requirements for the NDE systems will be summarized. Six PWR plants in the USA have completed inspections of their internals using the Inspection and Evaluation Guideline (MRP-227) and the Inspection Standard (MRP-228). Examination results show few instances of service-induced degradation flaws, as expected. The few instances of degradation have mostly occurred in bolting

English-Japanese terms in nondestructive testing specifications

International Nuclear Information System (INIS)

1991-01-01

For technical development, it is the prerequisite to clarify the terms to be used in various fields and their definition, therefore, in various foreign countries, there are some standards on terms in respective fields, and also as international standards, ISO/TC 135 (Non-destructive testing) organized the SC on terms from the beginning of foundation. In JIS, there is the column for corresponding English (for reference), but there is the problem of English and American English. The English used in ISO, BS or EN and ASTM standards in relation to nondestructive testing were collected in every technical field and put in order, and the corresponding English terms were selected. Moreover at this opportunity, the terms having the definition in these international, national and semi-national standards were classified into eight fields, that is, common (approval, quality assurance, defects and others), radiography, ultrasonic flaw detection, acoustic emission, eddy current flaw detection, magnetic flaw detection, liquid penetrant testing and leak test, and the Japanese translation was stipulated. The draft of this standard was approved by the standardization committee on January 17, 1991. (K.I.)

Reduction of bias in neutron multiplicity assay using a weighted point model

Energy Technology Data Exchange (ETDEWEB)

Geist, W. H. (William H.); Krick, M. S. (Merlyn S.); Mayo, D. R. (Douglas R.)

2004-01-01

Accurate assay of most common plutonium samples was the development goal for the nondestructive assay technique of neutron multiplicity counting. Over the past 20 years the technique has been proven for relatively pure oxides and small metal items. Unfortunately, the technique results in large biases when assaying large metal items. Limiting assumptions, such as unifoh multiplication, in the point model used to derive the multiplicity equations causes these biases for large dense items. A weighted point model has been developed to overcome some of the limitations in the standard point model. Weighting factors are detemiined from Monte Carlo calculations using the MCNPX code. Monte Carlo calculations give the dependence of the weighting factors on sample mass and geometry, and simulated assays using Monte Carlo give the theoretical accuracy of the weighted-point-model assay. Measured multiplicity data evaluated with both the standard and weighted point models are compared to reference values to give the experimental accuracy of the assay. Initial results show significant promise for the weighted point model in reducing or eliminating biases in the neutron multiplicity assay of metal items. The negative biases observed in the assay of plutonium metal samples are caused by variations in the neutron multiplication for neutrons originating in various locations in the sample. The bias depends on the mass and shape of the sample and depends on the amount and energy distribution of the ({alpha},n) neutrons in the sample. When the standard point model is used, this variable-multiplication bias overestimates the multiplication and alpha values of the sample, and underestimates the plutonium mass. The weighted point model potentially can provide assay accuracy of {approx}2% (1 {sigma}) for cylindrical plutonium metal samples < 4 kg with {alpha} < 1 without knowing the exact shape of the samples, provided that the ({alpha},n) source is uniformly distributed throughout the

[Investigation of reference intervals of blood gas and acid-base analysis assays in China].

Science.gov (United States)

Zhang, Lu; Wang, Wei; Wang, Zhiguo

2015-10-01

To investigate and analyze the upper and lower limits and their sources of reference intervals in blood gas and acid-base analysis assays. The data of reference intervals were collected, which come from the first run of 2014 External Quality Assessment (EQA) program in blood gas and acid-base analysis assays performed by National Center for Clinical Laboratories (NCCL). All the abnormal values and errors were eliminated. Data statistics was performed by SPSS 13.0 and Excel 2007 referring to upper and lower limits of reference intervals and sources of 7 blood gas and acid-base analysis assays, i.e. pH value, partial pressure of carbon dioxide (PCO2), partial pressure of oxygen (PO2), Na+, K+, Ca2+ and Cl-. Values were further grouped based on instrument system and the difference between each group were analyzed. There were 225 laboratories submitting the information on the reference intervals they had been using. The three main sources of reference intervals were National Guide to Clinical Laboratory Procedures [37.07% (400/1 079)], instructions of instrument manufactures [31.23% (337/1 079)] and instructions of reagent manufactures [23.26% (251/1 079)]. Approximately 35.1% (79/225) of the laboratories had validated the reference intervals they used. The difference of upper and lower limits in most assays among 7 laboratories was moderate, both minimum and maximum (i.e. the upper limits of pH value was 7.00-7.45, the lower limits of Na+ was 130.00-156.00 mmol/L), and mean and median (i.e. the upper limits of K+ was 5.04 mmol/L and 5.10 mmol/L, the upper limits of PCO2 was 45.65 mmHg and 45.00 mmHg, 1 mmHg = 0.133 kPa), as well as the difference in P2.5 and P97.5 between each instrument system group. It was shown by Kruskal-Wallis method that the P values of upper and lower limits of all the parameters were lower than 0.001, expecting the lower limits of Na+ with P value 0.029. It was shown by Mann-Whitney that the statistic differences were found among instrument

Non-destructive test of lock actuator component using neutron radiography technique

International Nuclear Information System (INIS)

Juliyanti; Setiawan; Sutiarso

2012-01-01

Non-destructive test of lock actuator using neutron radiography technique has been done. The lock actuator is a mechanical system which is controlled by central lock module consisting of electronic circuit which drives the lock actuator works accordingly to open and lock the vehicle door. The non-destructive test using neutron radiography is carried out to identify the type of defect is presence by comparing between the broken and the brand new one. The method used to test the lock actuator component is film method (direct method). The result show that the radiography procedure has complied with the ASTM standard for neutron radiography with background density of 2.2, 7 lines and 3 holes was seen in the sensitivity indicator (SI) and the quite good image quality was obtained. In the brand new actuator is seen that isolator part which separated the coils has melted. By this non-destructive test using neutron radiography technique is able to detect in early stage the type of component's defect inside the lock actuator without to dismantle it. (author)

Feasibility Study of Non-Destructive Techniques to Measure Corrosion in SAVY Containers

Energy Technology Data Exchange (ETDEWEB)

Davenport, Matthew Nicholas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-07-15

Stainless Steel SAVY containers are used to transport and store nuclear material. They are prone to interior corrosion in the presence of certain chemicals and a low-oxygen environment. SAVY containers also have relatively thin walls to reduce their weight, making their structural integrity more vulnerable to the effects of corrosion. A nondestructive evaluation system that finds and monitors corrosion within containers in use would improve safety conditions and preclude hazards. Non-destructive testing can determine whether oxidation or corrosion is occurring inside the SAVY containers, and there are a variety of non-destructive testing methods that may be viable. The feasibility study described will objectively decide which method best fits the requirements of the facility and the problem. To improve efficiency, the containers cannot be opened during the non-destructive examination. The chosen technique should also be user-friendly and relatively quick to apply. It must also meet facility requirements regarding wireless technology and maintenance. A feasibility study is an objective search for a new technology or product to solve a particular problem. First, the design, technical, and facility feasibility requirements are chosen and ranked in order of importance. Then each technology considered is given a score based upon a standard ranking system. The technology with the highest total score is deemed the best fit for a certain application.

Training manuals for nondestructive testing using magnetic particles

Science.gov (United States)

1968-01-01

Training manuals containing the fundamentals of nondestructive testing using magnetic particle as detection media are used by metal parts inspectors and quality assurance specialists. Magnetic particle testing involves magnetization of the test specimen, application of the magnetic particle and interpretation of the patterns formed.

Nondestructive Investigation of Wet Building Material: Multimethodical Approach

Czech Academy of Sciences Publication Activity Database

Válek, Jan; Kruschwitz, S.; Wöstmann, J.; Kind, T.; Valach, Jaroslav; Köpp, Ch.; Lesák, Jaroslav

2010-01-01

Roč. 24, č. 5 (2010), s. 462-472 ISSN 0887-3828 Grant - others:evropská komise(XE) CHEF- SSPI-044251 Institutional research plan: CEZ:AV0Z20710524 Keywords : nondestructive tests * moisture * masonry Subject RIV: JN - Civil Engineering Impact factor: 0.293, year: 2010

A semiquantitative PCR assay for assessing Perkinsus marinus infections in the eastern oyster, Crassostrea virginica.

Science.gov (United States)

Marsh, A G; Gauthier, J D; Vasta, G R

1995-08-01

A 3.2-kb fragment of Perkinsus marinus DNA was cloned and sequenced. A noncoding domain was identified and targeted for the development of a semiquantitative polymerase chain reaction (PCR) assay for the presence of P. marinus in eastern oyster tissues. The assay involves extracting total DNA from oyster hemolymph and using 1 microgram of that DNA as template in a stringent PCR amplification with oligonucleotide primers that are specific for the P. marinus 3.2-kb fragment. With this assay, we can detect 10 pg of total P. marinus DNA per 1 microgram of oyster hemocyte DNA with ethidium bromide (EtBr) staining of agarose gels, 100 fg total P. marinus DNA with Southern blot autoradiography, and 10 fg of total P. marinus DNA with dot-blot hybridizations. We have used the sensitivity of the PCR assay to develop a method for estimating the level of P. marinus DNA in oyster hemolymph and have successfully applied this technique to gill tissues. Our semiquantitative assay uses a dilution series to essentially titrate the point at which a P. marinus DNA target is no longer amplified in a sample. We refer to this technique as "dilution endpoint" PCR. Using hemocytes obtained by withdrawing a 1-ml sample of hemolymph, this assay provides a nondestructive methodology for rapidly screening large numbers of adult oysters for the presence and quantification of P. marinus infection levels. This technique is applicable to other tissues (gills) and could potentially be applied to DNA extracts of whole larvae or spat.

Mathematical modelling of ultrasonic non-destructive evaluation

Directory of Open Access Journals (Sweden)

Larissa Ju Fradkin

2001-01-01

Full Text Available High-frequency asymptotics have been used at our Centre to develop codes for modelling pulse propagation and scattering in the near-field of the ultrasonic transducers used in NDE (Non-Destructive Evaluation, particularly of walls of nuclear reactors. The codes are hundreds of times faster than the direct numerical codes but no less accurate.

Non-destructive controls in the mechanical industry

Energy Technology Data Exchange (ETDEWEB)

Jarlan, L

1978-12-01

The sequence of operations implicating the mechanical industries from the suppliers to their customers is briefly recalled; a description of the field of application of non-destructive control methods in these industries is given. Follows a description of some recent typical applications of the principal methods: radiography, ultrasonic waves, magnetism, acoustic emission, sonic control, tracer techniques.

Non-destructive testing; Examenes no destructivos

Energy Technology Data Exchange (ETDEWEB)

Calva, Mauricio; Loske, Achim [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1988-12-31

The application of non-destructive testing (NDT) in several technical and industrial fields is pointed out, standing out its utilization in the detection of future failures without affecting the examined element. Likewise, the different types of NDTs and their processes, such as x-rays, ultrasoud, magnetic particles, induced currents, penetrating fluids, and optical means, are described. The Non-Destructive Tests Laboratory of the Instituto de Investigaciones Electricas (IIE), plans to create new and more reliable systems independent from the operator`s capacity, to contribute to fulfill the inspection and quality control needs of the generating Mexican power plants. [Espanol] Se senala la aplicacion de los examenes no destructivos (END) a diversos campos tecnicos e industriales, destacando su utilizacion en la deteccion de futuras fallas sin afectar el elemento examinado. Asimismo, se describen los diferentes tipos de END y sus procesos, tales como radiografia, ultrasonido, particulas magneticas, corrientes inducidas, liquidos penetrantes y metodos opticos. El Laboratorio de Pruebas no Destructivas, del Instituto de Investigaciones Electricas (IIE), planea crear sistemas novedosos mas confiables, que no dependan de la capacidad del operador, para contribuir a satisfacer las necesidades de inspeccion y control de calidad que se presentan en las plantas generadoras de energia mexicanas.

Non-destructive testing; Examenes no destructivos

Energy Technology Data Exchange (ETDEWEB)

Calva, Mauricio; Loske, Achim [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1987-12-31

The application of non-destructive testing (NDT) in several technical and industrial fields is pointed out, standing out its utilization in the detection of future failures without affecting the examined element. Likewise, the different types of NDTs and their processes, such as x-rays, ultrasoud, magnetic particles, induced currents, penetrating fluids, and optical means, are described. The Non-Destructive Tests Laboratory of the Instituto de Investigaciones Electricas (IIE), plans to create new and more reliable systems independent from the operator`s capacity, to contribute to fulfill the inspection and quality control needs of the generating Mexican power plants. [Espanol] Se senala la aplicacion de los examenes no destructivos (END) a diversos campos tecnicos e industriales, destacando su utilizacion en la deteccion de futuras fallas sin afectar el elemento examinado. Asimismo, se describen los diferentes tipos de END y sus procesos, tales como radiografia, ultrasonido, particulas magneticas, corrientes inducidas, liquidos penetrantes y metodos opticos. El Laboratorio de Pruebas no Destructivas, del Instituto de Investigaciones Electricas (IIE), planea crear sistemas novedosos mas confiables, que no dependan de la capacidad del operador, para contribuir a satisfacer las necesidades de inspeccion y control de calidad que se presentan en las plantas generadoras de energia mexicanas.

Collaborative, Nondestructive Analysis of Contaminated Soil

Energy Technology Data Exchange (ETDEWEB)

Knight, K. B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dai, Z. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Davidson, L. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Eppich, G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Lindvall, R. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Parsons-Davis, T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Ramon, C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Roberts, S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Sharp, M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Turin, H. J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); LaMont, S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Zidi, T. [Commissariat a l' Energie Atomique (COMENA), Gif-sur-Yvette (France); Belamri, M. [Commissariat a l' Energie Atomique (COMENA), Gif-sur-Yvette (France); Bounatiro, S. [Commissariat a l' Energie Atomique (COMENA), Gif-sur-Yvette (France); Benbouzid, S. [Commissariat a l' Energie Atomique (COMENA), Gif-sur-Yvette (France); Fellouh, A. S. [Commissariat a l' Energie Atomique (COMENA), Gif-sur-Yvette (France); Idir, T. [Commissariat a l' Energie Atomique (COMENA), Gif-sur-Yvette (France); Larbah, Y. [Commissariat a l' Energie Atomique (COMENA), Gif-sur-Yvette (France); Moulay, M. [Commissariat a l' Energie Atomique (COMENA), Gif-sur-Yvette (France); Noureddine, A. [Commissariat a l' Energie Atomique (COMENA), Gif-sur-Yvette (France); Rahal, B. [Commissariat a l' Energie Atomique (COMENA), Gif-sur-Yvette (France)

2017-12-14

This report summarizes a joint nondestructive analysis exercise that LLNL, LANL, and COMENA discussed through a collaborative meeting in July 2017. This work was performed as one part of a collaboration with Algeria under Action Sheet 7: “Technical Cooperation and Assistance in Nuclear Forensics”. The primary intent of this exercise was for US and Algerian participants to jointly share results of nondestructive analyses (NDA) of a contaminated soil sample provided by the Algerians and to discuss key observations and analytical approaches. While the two samples were analyzed blind at LLNL and LANL, the soil samples were revealed after the exercise to have a common origin, and to have originated as an IAEA soil sample (IAEA-326, Bojanowski et al., 2001) provided to COMENA as part of a previous exercise. Comparative analysis revealed common findings between the laboratories, and also emphasized the need for standardized operating procedures to improve inter-comparability and confidence in conclusions. Recommended handling practices in the presence of sample heterogeneities were also discussed. This exercise provided an opportunity to demonstrate nuclear forensics analytical capabilities at COMENA, LANL, and LLNL, and identified areas that could benefit from future technical exchanges. Plans were made for a follow-on joint exercise in 2018, involving destructive analyses of the CUP-2 uranium ore concentrate standard.

Nondestructive testing for bridge diagnosis

International Nuclear Information System (INIS)

Oshima, Toshiyuki; Mikami, Shuichi; Yamazaki, Tomoyuki

1997-01-01

There are many motivations for bridge diagnosis using Nondestructive testing (NDT) to monitor its integrity. The measured frequency and damping on real bridge are compared in one figure as a function of span length and general aspects are explained. These date were measured in every construction of bridges and applied to design new bridges. Ultrasonic testing is also well used for concrete and steel members mainly to detect internal damages or delaminations. Detail analysis on reflected waves gives us more accurate information about the defect. Experimental results are shown as examples in this paper.

DYMAC demonstration program: Phase I experience

International Nuclear Information System (INIS)

Augustson, R.H.

1978-02-01

The DYnamic MAterials Control (DYMAC) project tested a prototype system at the DP Site LASL plutonium facility, which consisted of a computerized accounting system based on material balancing by unit process. Transactions were written to describe the movement of material from one unit process to another. In the DYMAC prototype a specially designed computer program handled transactions that operators entered into the system via a terminal in the processing area. The transactions contained the same information that is used in the present LASL paper accounting system to create an inventory. During a 6-week period the DYMAC system operated in parallel with the paper system. At the end of the period results showed the DYMAC system was able to keep an accurate and timely inventory. Concurrent with testing the transaction-handling program, the project operated several nondestructive assay instruments in a glovebox environment, specifically the electronic balance, solution assay instrument, and thermal-neutron coincidence counter. From the instrument operation logs, project personnel were able to identify operational problems and incorporate design changes in the instrumentation for the new facility

Experimental electro-thermal method for nondestructively testing welds in stainless steel pipes

International Nuclear Information System (INIS)

Green, D.R.

1979-01-01

Welds in austenitic stainless steel pipes are notoriously difficult to nondestructively examine using conventional ultrasonic and eddy current methods. Survace irregularities and microscopic variations in magnetic permeability cause false eddy current signal variations. Ultrasonic methods have been developed which use computer processing of the data to overcome some of the problems. Electro-thermal nondestructive testing shows promise for detecting flaws that are difficult to detect using other NDT methods. Results of a project completed to develop and demonstrate the potential of an electro-thermal method for nondestructively testing stainless steel pipe welds are presented. Electro-thermal NDT uses a brief pulse of electrical current injected into the pipe. Defects at any depth within the weld cause small differences in surface electrical current distribution. These cause short-lived transient temperature differences on the pipe's surface that are mapped using an infrared scanning camera. Localized microstructural differences and normal surface roughness in the welds have little effect on the surface temperatures

Non-destructive control in nuclear construction

International Nuclear Information System (INIS)

Banus; Barbier; Launay

1978-01-01

Having recalled the characteristics of the fundamental components of the main primary circuit of nuclear boilers (900 MW) and the means appropriated for their control, it is recalled that the 'French Electricity Board's specifications and control rules' often prescribe more severe criteria than those existing in the U.S.A. Then practical examples of non-destructive controls concerning the steam generator end plates, vessel stainless steel linings, pump attachements, steam generator pipes are given [fr

The real defect and its nondestructive characterization

International Nuclear Information System (INIS)

Licht, H.

1982-01-01

Nondestructive test techniques to evaluate defect severity and component degradation are typically based on transmission of energy into the material to be inspected. The capabilities of such techniques are controlled by physical phenomena which generally do not coincide with inspection requirements. This paper reviews several recent developments (mainly in ultrasonic and eddy current testing) which highlight the state of the art

Non-Destructive Testing for Control of Radioactive Waste Package

Science.gov (United States)

Plumeri, S.; Carrel, F.

2015-10-01

Characterization and control of radioactive waste packages are important issues in the management of a radioactive waste repository. Therefore, Andra performs quality control inspection on radwaste package before disposal to ensure the compliance of the radwast characteristics with Andra waste disposal specifications and to check the consistency between Andra measurements results and producer declared properties. Objectives of this quality control are: assessment and improvement of producer radwaste packages quality mastery, guarantee of the radwaste disposal safety, maintain of the public confidence. To control radiological characteristics of radwaste package, non-destructive passive methods (gamma spectrometry and neutrons counting) are commonly used. These passive methods may not be sufficient, for instance to control the mass of fissile material contained inside radwaste package. This is particularly true for large concrete hull of heterogeneous radwaste containing several actinides mixed with fission products like 137Cs. Non-destructive active methods, like measurement of photofission delayed neutrons, allow to quantify the global mass of actinides and is a promising method to quantify mass of fissile material. Andra has performed different non-destructive measurements on concrete intermediate-level short lived nuclear waste (ILW-SL) package to control its nuclear material content. These tests have allowed Andra to have a first evaluation of the performance of photofission delayed neutron measurement and to identify development needed to have a reliable method, especially for fissile material mass control in intermediate-level long lived waste package.

Non-destructive assay of radioactive waste

International Nuclear Information System (INIS)

Eid, C.; Bernard, P.

1990-01-01

The nuclear fuel cycle generates a large variety of waste containing Pu. After treatment and conditioning the final destination of this waste is either to be disposed by shallow land burial or in underground geological repositories. The method of disposal is determined by the quantity of Pu contained in the waste to be disposed of. For this reason and taking into account the rigorous requirements of the safety authorities concerning the protection of people and the environment, it is most important to determine accurately the Pu contents in the waste. Separate abstracts were prepared for 28 papers in this book

The non-destructive control, a major constituent of quality

International Nuclear Information System (INIS)

Anon.

1998-01-01

The number of continuous research and development works about non-destructive control in all sectors of activity is justified by the increasing need for high quality materials without anomalies. This paper gives a overview of the state of the art and of the recent trends in non-destructive testing researches in different sectors: aeronautics, nuclear industry, automotive industry. New studies and techniques are presented: ultrasonic testing of welds on large diameter pipes, automated applications of ultrasonic testing, ultrasound/computer-aided design coupling, pressure vessels inspection using acoustic emission testing (leaks detection, application to composite materials), numerical radiography (image visualisation and processing), magnetic testing (steel damage detection using Barkhausen noise testing), 'shearography' (detection of the loss of thickness in pipes due to corrosion), X-ray tomography (density measurement of sintered steels, fluid flow calculations in automobile parts). (J.S.)

Holographic nondestructive testing in bone biomechanics

Science.gov (United States)

Silvennoinen, Raimo V. J.; Nygren, Kaarlo; Karna, Markku