Materials of the Second Sumy-Cracow-Muenster Symposium on Nuclear Analytical Methods

International Nuclear Information System (INIS)

2001-01-01

The applications of nuclear analytical methods in physico-chemical, biological and medical studies have been presented in large number of applications. Environmental, geological and biological materials have been analysed by means of neutron activation analysis, proton microprobe, x-ray diffraction, synchrotron radiation X-ray spectrum analysis, ESR and others

Nuclear analytical methods in teaching and research at the university of Illinois

International Nuclear Information System (INIS)

Landsberger, S.

1994-01-01

An overview of the nuclear analytical methods opportunities at the University of Illinois at Urbana-Champaign are given. Undergraduate and graduate level teaching and research are highlighted. The TRIGA reactor and neutron activation analysis facilities are described in the context of this role within an inter-disciplinary environment. (author)

Analytical method for reconstruction pin to pin of the nuclear power density distribution

International Nuclear Information System (INIS)

Pessoa, Paulo O.; Silva, Fernando C.; Martinez, Aquilino S.

2013-01-01

An accurate and efficient method for reconstructing pin to pin of the nuclear power density distribution, involving the analytical solution of the diffusion equation for two-dimensional neutron energy groups in homogeneous nodes, is presented. The boundary conditions used for analytic as solution are the four currents or fluxes on the surface of the node, which are obtained by Nodal Expansion Method (known as NEM) and four fluxes at the vertices of a node calculated using the finite difference method. The analytical solution found is the homogeneous distribution of neutron flux. Detailed distributions pin to pin inside a fuel assembly are estimated by the product of homogeneous flux distribution by local heterogeneous form function. Furthermore, the form functions of flux and power are used. The results obtained with this method have a good accuracy when compared with reference values. (author)

Analytical method for reconstruction pin to pin of the nuclear power density distribution

Energy Technology Data Exchange (ETDEWEB)

Pessoa, Paulo O.; Silva, Fernando C.; Martinez, Aquilino S., E-mail: ppessoa@con.ufrj.br, E-mail: fernando@con.ufrj.br, E-mail: aquilino@imp.ufrj.br [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil)

2013-07-01

An accurate and efficient method for reconstructing pin to pin of the nuclear power density distribution, involving the analytical solution of the diffusion equation for two-dimensional neutron energy groups in homogeneous nodes, is presented. The boundary conditions used for analytic as solution are the four currents or fluxes on the surface of the node, which are obtained by Nodal Expansion Method (known as NEM) and four fluxes at the vertices of a node calculated using the finite difference method. The analytical solution found is the homogeneous distribution of neutron flux. Detailed distributions pin to pin inside a fuel assembly are estimated by the product of homogeneous flux distribution by local heterogeneous form function. Furthermore, the form functions of flux and power are used. The results obtained with this method have a good accuracy when compared with reference values. (author)

Analytical chemistry of nuclear materials

International Nuclear Information System (INIS)

1963-01-01

The last two decades have witnessed an enormous development in chemical analysis. The rapid progress of nuclear energy, of solid-state physics and of other fields of modern industry has extended the concept of purity to limits previously unthought of, and to reach the new dimensions of these extreme demands, entirely new techniques have been invented and applied and old ones have been refined. Recognizing these facts, the International Atomic Energy Agency convened a Panel on Analytical Chemistry of Nuclear Materials to discuss the general problems facing the analytical chemist engaged in nuclear energy development, particularly in newly developing centre and countries, to analyse the represent situation and to advise as to the directions in which research and development appear to be most necessary. The Panel also discussed the analytical programme of the Agency's laboratory at Seibersdorf, where the Agency has already started a programme of international comparison of analytical methods which may lead to the establishment of international standards for many materials of interest. Refs and tabs

Use of decision analytic methods in nuclear safety. An international survey

International Nuclear Information System (INIS)

Holmberg, J.; Pulkkinen, U.

1996-12-01

This report reviews applications of formal decision analysis methods in resolving nuclear safety related issues. The review is based on selected published reports and a questionnaire sent to the members of the Principal Working Group 5 on risk analysis (PWG5) of OECD/NEA/CSNI. In the report, decision analysis methodology is shortly described. The applications discussed in this review are related to probabilistic safety goals of safety criteria, operational safety management, nuclear waste management and emergency management. The experiences from the application decision analysis methodology have been mainly positive. The advantages provided by the decision analytical thinking are the structured view over the problem under consideration and the explicit statements on uncertainties, values and preferences. The decision analysis methodology is rather mature to be applied in solution of nuclear safety issues. Although the applications have been mainly research oriented, it can be expected that the practical use of the methodology shall be more common in future. (orig.) (27 refs.)

Use of decision analytic methods in nuclear safety. An international survey

Energy Technology Data Exchange (ETDEWEB)

Holmberg, J.; Pulkkinen, U. [VTT Automation, Espoo (Finland). Industrial Automation

1996-12-01

This report reviews applications of formal decision analysis methods in resolving nuclear safety related issues. The review is based on selected published reports and a questionnaire sent to the members of the Principal Working Group 5 on risk analysis (PWG5) of OECD/NEA/CSNI. In the report, decision analysis methodology is shortly described. The applications discussed in this review are related to probabilistic safety goals of safety criteria, operational safety management, nuclear waste management and emergency management. The experiences from the application decision analysis methodology have been mainly positive. The advantages provided by the decision analytical thinking are the structured view over the problem under consideration and the explicit statements on uncertainties, values and preferences. The decision analysis methodology is rather mature to be applied in solution of nuclear safety issues. Although the applications have been mainly research oriented, it can be expected that the practical use of the methodology shall be more common in future. (orig.) (27 refs.).

Nuclear forensics and nuclear analytical chemistry - iridium determination in a referred forensic sample

International Nuclear Information System (INIS)

Basu, A.K.; Bhadkambekar, C.A.; Tripathi, A.B.R.; Chattopadhyay, N.; Ghosh, P.

2010-01-01

Nuclear approaches for compositional characterization has bright application prospect in forensic perspective towards assessment of nature and origin of seized material. The macro and micro physical properties of nuclear materials can be specifically associated with a process or type of nuclear activity. Under the jurisdiction of nuclear analytical chemistry as well as nuclear forensics, thrust areas of scientific endeavor like determination of radioisotopes, isotopic and mass ratios, analysis for impurity contents, arriving at chemical forms/species and physical parameters play supporting evidence in forensic investigations. The analytical methods developed for this purposes can be used in international safeguards as well for nuclear forensics. Nuclear material seized in nuclear trafficking can be identified and a profile of the nuclear material can be created

HTGR analytical methods and design verification

International Nuclear Information System (INIS)

Neylan, A.J.; Northup, T.E.

1982-05-01

Analytical methods for the high-temperature gas-cooled reactor (HTGR) include development, update, verification, documentation, and maintenance of all computer codes for HTGR design and analysis. This paper presents selected nuclear, structural mechanics, seismic, and systems analytical methods related to the HTGR core. This paper also reviews design verification tests in the reactor core, reactor internals, steam generator, and thermal barrier

Atomic and nuclear analytical methods. XRF, Moessbauer, XPS, NAA and ion-beam spectroscopic techniques

International Nuclear Information System (INIS)

Verma, H.R.

2007-01-01

This book is a blend of analytical methods based on the phenomenon of atomic and nuclear physics. It comprises comprehensive presentations about X-ray Fluorescence (XRF), Moessbauer Spectroscopy (MS), X-ray Photoelectron Spectroscopy (XPS), Neutron- Activation Analysis (NAA), Particle Induced X-ray Emission Analysis (PIXE), Rutherford Backscattering Analysis (RBS), Elastic Recoil Detection (ERD), Nuclear Reaction Analysis (NRA), Particle Induced Gamma-ray Emission Analysis (PIGE), and Accelerator Mass Spectrometry (AMS). These techniques are commonly applied in the fields of medicine, biology, environmental studies, archaeology or geology et al. and pursued in major international research laboratories. (orig.)

Chemical characterization of materials relevant to nuclear technology using neutron and proton based nuclear analytical methods

International Nuclear Information System (INIS)

Acharya, R.

2014-01-01

Nuclear analytical techniques (NATs), utilizing neutron and proton based nuclear reactions and subsequent measurement of gamma rays, are capable of chemical characterization of various materials at major to trace concentration levels. The present article deals with the recent developments and applications of conventional and k0-based internal monostandard (i) neutron activation analysis (NAA) and (ii) prompt gamma ray NAA (PGNAA) methods as well as (iii) in situ current normalized particle induced gamma ray emission (PIGE). The materials that have been analyzed by NAA and PGNAA include (i) nuclear reactor structural materials like zircaloys, stainless steels, Ni alloys, high purity aluminium and graphite and (ii) uranium oxide, U-Th mixed oxides, uranium ores and minerals. Internal monostandard NAA (IM-NAA) method with in situ detection efficiency was used to analyze large and non-standard geometry samples and standard-less compositional characterization was carried out for zircaloys and stainless steels. PIGE methods using proton beams were standardized for quantification of low Z elements (Li to Ti) and applied for compositional analysis of borosilicate glass and lithium titanate (Li 2 TiO 3 ) samples and quantification of total B and its isotopic composition of B ( 10 B/ 11 B) in boron based neutron absorbers like B 4 C. (author)

Laser-based analytical monitoring in nuclear-fuel processing plants

International Nuclear Information System (INIS)

Hohimer, J.P.

1978-09-01

The use of laser-based analytical methods in nuclear-fuel processing plants is considered. The species and locations for accountability, process control, and effluent control measurements in the Coprocessing, Thorex, and reference Purex fuel processing operations are identified and the conventional analytical methods used for these measurements are summarized. The laser analytical methods based upon Raman, absorption, fluorescence, and nonlinear spectroscopy are reviewed and evaluated for their use in fuel processing plants. After a comparison of the capabilities of the laser-based and conventional analytical methods, the promising areas of application of the laser-based methods in fuel processing plants are identified

Manual of selected physico-chemical analytical methods. IV

International Nuclear Information System (INIS)

Beran, M.; Klosova, E.; Krtil, J.; Sus, F.; Kuvik, V.; Vrbova, L.; Hamplova, M.; Lengyel, J.; Kelnar, L.; Zakouril, K.

1990-11-01

The Central Testing Laboratory of the Nuclear Research Institute at Rez has for a decade been participating in the development of analytical procedures and has been providing analyses of samples of different types and origin. The analytical procedures developed have been published in special journals and a number of them in the Manuals of analytical methods, in three parts. The 4th part of the Manual contains selected physico-chemical methods developed or modified by the Laboratory in the years 1986-1990 within the project ''Development of physico-chemical analytical methods''. In most cases, techniques are involved for non-nuclear applications. Some can find wider applications, especially in analyses of environmental samples. Others have been developed for specific cases of sample analyses or require special instrumentation (mass spectrometer), which partly restricts their applicability by other institutions. (author)

Atomic and Nuclear Analytical Methods XRF, Mössbauer, XPS, NAA and Ion-Beam Spectroscopic Techniques

CERN Document Server

Verma, H R

2007-01-01

This book is a blend of analytical methods based on the phenomenon of atomic and nuclear physics. It comprises comprehensive presentations about X-ray Fluorescence (XRF), Mössbauer Spectroscopy (MS), X-ray Photoelectron Spectroscopy (XPS), Neutron- Activation Analysis (NAA), Particle Induced X-ray Emission Analysis (PIXE), Rutherford Backscattering Analysis (RBS), Elastic Recoil Detection (ERD), Nuclear Reaction Analysis (NRA), Particle Induced Gamma-ray Emission Analysis (PIGE), and Accelerator Mass Spectrometry (AMS). These techniques are commonly applied in the fields of medicine, biology, environmental studies, archaeology or geology et al. and pursued in major international research laboratories.

The use of nuclear analytical methods in the investigation of objects of art and historical monuments

International Nuclear Information System (INIS)

Janovsky, I.

2006-01-01

Special nuclear analytical methods contribute significantly to the identification of the origin, manufacturing technology and/or authenticity of objects of art and historical monuments, Such methods primarily include variants of X-ray fluorescence analysis and activation analysis. The former enables non/destructive testing of materials, the latter features a high sensitivity. The article presents numerous examples of use of such methods especially in the Czech Republic (or former Czechoslovakia). (author)

Quantifying uncertainty in nuclear analytical measurements

International Nuclear Information System (INIS)

2004-07-01

Laboratories to quantify the uncertainty of measurement results, and the fact that this standard is used as a basis for the development and implementation of quality management systems in many laboratories performing nuclear analytical measurements, triggered the demand for specific guidance to cover uncertainty issues of nuclear analytical methods. The demand was recognized by the IAEA and a series of examples was worked out by a group of consultants in 1998. The diversity and complexity of the topics addressed delayed the publication of a technical guidance report, but the exchange of views among the experts was also beneficial and led to numerous improvements and additions with respect to the initial version. This publication is intended to assist scientists using nuclear analytical methods in assessing and quantifying the sources of uncertainty of their measurements. The numerous examples provide a tool for applying the principles elaborated in the GUM and EURACHEM/CITAC publications to their specific fields of interest and for complying with the requirements of current quality management standards for testing and calibration laboratories. It also provides a means for the worldwide harmonization of approaches to uncertainty quantification and thereby contributes to enhanced comparability and competitiveness of nuclear analytical measurements

Nuclear analytical methods for trace element studies in calcified tissues

International Nuclear Information System (INIS)

Chaudhry, M.A.; Chaudhry, M.N.

2001-01-01

Full text: Various nuclear analytical methods have been developed and applied to determine the elemental composition of calcified tissues (teeth and bones). Fluorine was determined by prompt gamma activation analysis through the 19 F(p,ag) 16 O reaction. Carbon was measured by activation analysis with He-3 ions, and the technique of Proton-Induced X-ray Emission (PIXE) was applied to simultaneously determine Ca, P, and trace elements in well-documented teeth. Dental hard tissues, enamel, dentine, cement, and their junctions, as well as different parts of the same tissue, were examined separately. Furthermore, using a Proton Microprobe, we measured the surface distribution of F and other elements on and around carious lesions on the enamel. The depth profiles of F, and other elements, were also measured right up to the amelodentin junction

Nuclear analytical chemistry 5. Tables, nomograms and schemes

Energy Technology Data Exchange (ETDEWEB)

Tolgyessy, J; Varga, S; Dillinger, P; Kyrs, M

1976-01-01

Tables, graphs and nomograms are given on aspects of nuclear analytical chemistry. The tables contain data on physical and chemical units and their conversion, exponential functions, the characteristics of radioactive nuclides, data on the interaction of nuclear radiation with matter, data useful in measuring nuclear radiation, in scintillation and semiconductor spectrometry, activation analysis, data on masking reactions of ions in chemical separation, on extraction, ion exchange, accuracy in applying the method of isotope dilution, on radiochemical analysis.

Nuclear analytical methods in quality control of microanalysis

International Nuclear Information System (INIS)

Tian Weizhi

2004-01-01

Quantitative calibration and quality control have been a major bottleneck in microanalysis due to the lack of natural-matrix CRMs certified at sample sizes compatible with those of unknown samples. A solution is described to characterize sampling behavior for individual elements, so as to identify elements homogeneous enough at stated sample size levels in given CRMs/RMs. By using a combination of several nuclear analytical techniques, INAA-EDXRF-μPIXE, sampling behavior for individual elements can be characterized at sample size levels from grams down to pg. Natural-matrix CRMs specifically for QC of microanalysis may thus be created. Additional information in certificates of these new generation CRMs is imagined. (author)

Nuclear Analytical Techniques for Commercial Applications in China

International Nuclear Information System (INIS)

Chai, Z.; Zhang, Z.; Feng, S.; Yang, J.; Ouyang, H.; Feng, X.; Mao, X.

2013-01-01

Since the establishment of the first Chinese nuclear reactor and accelerator in 1958, the nuclear analytical techniques (NATs) in China have dramatically developed in past half century. Nowadays 10 research nuclear reactors and over 100 small accelerators are available in China. Roughly, about 50 % of the machine time is applied for commercial purpose at the moment. The versatile nuclear analytical methods, mainly NAA, PIXE, XRF, etc., in China have been and are being applied widely and extensively in the following three fields: scientific, training, and commercial. This paper will briefly describe the past experience and present status about NATs for commercial applications. Some practical examples to demonstrate the role of NATs in this aspect will be given as well. Basically, the NATs used for the commercial applications in China can be divided into two types, i.e. off-line and on-line. The former mainly includes instrumental neutron activation analysis (INAA) for compositional determination, particle induced X-ray emission (PIXE) also for compositional analysis, accelerator-based mass-spectrometry (AMS) for analysis of C-14, Be-7, Cl-36 and other long-lived radioactive nuclides, solid state nuclear track detector

Detection of sensor failures in nuclear plants using analytic redundancy

International Nuclear Information System (INIS)

Kitamura, M.

1980-01-01

A method for on-line, nonperturbative detection and identification of sensor failures in nuclear power plants was studied to determine its feasibility. This method is called analytic redundancy, or functional redundancy. Sensor failure has traditionally been detected by comparing multiple signals from redundant sensors, such as in two-out-of-three logic. In analytic redundancy, with the help of an assumed model of the physical system, the signals from a set of sensors are processed to reproduce the signals from all system sensors

Hairs, criminals, moonrocks, metals, diseases, polluters[ Where next for nuclear analytical chemistry

International Nuclear Information System (INIS)

Jervis, R.E.

1992-01-01

Nuclear methods of analysis have advanced dramatically in recent years, and in many ways, techniques that once were viewed as a scientific curiosity and the toys of a few scientists working in large nuclear research establishments, are now semi-routine and can be applied even by young students. Large amount of good analytical data are outputted from instruments having sophisticated embedded software. It is interesting to speculate on the directions that nuclear analytical techniques may take next: whether more multielement; more automation for vastly larger sample suites; extension to minor and major components of samples as well as trace components; coupling of nuclear methods to hyphenated methods. However, in some respects the resources needed to continue to develop and apply radioanalytical methods are on the wane: reactors and accelerators are being closed and fewer radiochemical specialists are being trained. The open question is whether instrumental analysis techniques will offer more and better results with less effort, or be less equipment intensive? In this paper some personal reflections on nuclear activation methods and their trends are presented and discussed. Some mileposts in the development of the field and some unique and interesting applicaions (as implied by the paper title) are cited and discussed. (author) 13 refs

Analytical methodology for nuclear safeguards

International Nuclear Information System (INIS)

Ramakumar, K.L.

2011-01-01

This paper attempts to briefly describe the analytical methodologies available and also highlight some of the challenges, expectations from nuclear material accounting and control (NUMAC) point of view

Nuclear analytical techniques in medicine

International Nuclear Information System (INIS)

Cesareo, R.

1988-01-01

This book acquaints one with the fundamental principles and the instrumentation relevant to analytical technique based on atomic and nuclear physics, as well as present and future biomedical applications. Besides providing a theoretical description of the physical phenomena, a large part of the book is devoted to applications in the medical and biological field, particularly in hematology, forensic medicine and environmental science. This volume reviews methods such as the possibility of carrying out rapid multi-element analysis of trace elements on biomedical samples, in vitro and in vivo, by XRF-analysis; the ability of the PIXE-microprobe to analyze in detail and to map trace elements in fragments of biomedical samples or inside the cells; the potentiality of in vivo nuclear activation analysis for diagnostic purposes. Finally, techniques are described such as radiation scattering (elastic and inelastic scattering) and attenuation measurements which will undoubtedly see great development in the immediate future

Nuclear analytical techniques in medicine

Energy Technology Data Exchange (ETDEWEB)

Cesareo, R.

1988-01-01

This book acquaints one with the fundamental principles and the instrumentation relevant to analytical technique based on atomic and nuclear physics, as well as present and future biomedical applications. Besides providing a theoretical description of the physical phenomena, a large part of the book is devoted to applications in the medical and biological field, particularly in hematology, forensic medicine and environmental science. This volume reviews methods such as the possibility of carrying out rapid multi-element analysis of trace elements on biomedical samples, in vitro and in vivo, by XRF-analysis; the ability of the PIXE-microprobe to analyze in detail and to map trace elements in fragments of biomedical samples or inside the cells; the potentiality of in vivo nuclear activation analysis for diagnostic purposes. Finally, techniques are described such as radiation scattering (elastic and inelastic scattering) and attenuation measurements which will undoubtedly see great development in the immediate future.

Analytical study in 1D nuclear waste migration

International Nuclear Information System (INIS)

Perez Guerrero, Jesus S.; Heilbron Filho, Paulo L.; Romani, Zrinka V.

1999-01-01

The simulation of the nuclear waste migration phenomena are governed mainly by diffusive-convective equation that includes the effects of hydrodynamic dispersion (mechanical dispersion and molecular diffusion), radioactive decay and chemical interaction. For some special problems (depending on the boundary conditions and when the domain is considered infinite or semi-infinite) an analytical solution may be obtained using classical analytical methods such as Laplace Transform or variable separation. The hybrid Generalized Integral Transform Technique (GITT) is a powerful tool that can be applied to solve diffusive-convective linear problems to obtain formal analytical solutions. The aim of this work is to illustrate that the GITT may be used to obtain an analytical formal solution for the study of migration of radioactive waste in saturated flow porous media. A case test considering 241 Am radionuclide is presented. (author)

Radiochemistry and nuclear methods of analysis

International Nuclear Information System (INIS)

Ehmann, W.D.; Vance, D.

1991-01-01

This book provides both the fundamentals of radiochemistry as well as specific applications of nuclear techniques to analytical chemistry. It includes such areas of application as radioimmunoassay and activation techniques using very short-lined indicator radionuclides. It emphasizes the current nuclear methods of analysis such as neutron activation PIXE, nuclear reaction analysis, Rutherford backscattering, isotope dilution analysis and others

Analytical methods for fissionable materials in the nuclear fuel cycle. Covering June 1974--June 1975

International Nuclear Information System (INIS)

Waterbury, G.R.

1975-10-01

Research progress is reported on method development for the dissolution of difficult-to-dissolve materials, the automated analysis of plutonium and uranium, the preparation of plutonium materials for the Safeguard Analytical Laboratory Evaluation (SALE) Program, and the analysis of HTGR fuel and SALE uranium materials. The previously developed Teflon-container, metal-shell apparatus was applied to the dissolution of various nuclear materials. Gas--solid reactions, mainly using chlorine at elevated temperatures, are promising for separating uranium from refractory compounds. An automated spectrophotometer designed for determining plutonium and uranium was tested successfully. Procedures were developed for this instrument to analyze uranium--plutonium mixtures and the effects of diverse ions upon the analysis of plutonium and uranium were further established. A versatile apparatus was assembled to develop electrotitrimetric methods that will serve as the basis for precise automated determinations of plutonium. Plutonium materials prepared for the Safeguard Analytical Laboratory Evaluation (SALE) Program were plutonium oxide, uranium--plutonium mixed oxide, and plutonium metal. Improvements were made in the methods used for determining uranium in HTGR fuel materials and SALE uranium materials. Plutonium metal samples were prepared, characterized, and distributed, and half-life measurements were in progress as part of an inter-ERDA-laboratory program to measure accurately the half-lives of long-lived plutonium isotopes

Decision analytic methods in RODOS

International Nuclear Information System (INIS)

Borzenko, V.; French, S.

1996-01-01

In the event of a nuclear accident, RODOS seeks to provide decision support at all levels ranging from the largely descriptive to providing a detailed evaluation of the benefits and disadvantages of various countermeasure strategies and ranking them according to the societal preferences as perceived by the decision makers. To achieve this, it must draw upon several decision analytic methods and bring them together in a coherent manner so that the guidance offered to decision makers is consistent from one stage of an accident to the next. The methods used draw upon multi-attribute value and utility theories

An analytical method for the calculation of static characteristics of linear step motors for control rod drives in nuclear reactors

International Nuclear Information System (INIS)

Khan, S.H.; Ivanov, A.A.

1995-01-01

An analytical method for calculating static characteristics of linear dc step motors (LSM) is described. These multiphase passive-armature motors are now being developed for control rod drives (CRD) in large nuclear reactors. The static characteristics of such LSM is defined by the variation of electromagnetic force with armature displacement and it determines motor performance in its standing and dynamic modes of operation. The proposed analytical technique for calculating this characteristic is based on the permeance analysis method applied to phase magnetic circuits of LSM. Reluctances of various parts of phase magnetic circuit is calculated analytically by assuming probable flux paths and by taking into account complex nature of magnetic field distribution in it. For given armature positions stator and armature iron saturations are taken into account by an efficient iterative algorithm which gives fast convergence. The method is validated by comparing theoretical results with experimental ones which shows satisfactory agreement for small stator currents and weak iron saturation

International conference on isotopic and nuclear analytical techniques for health and environment. Book of abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

Decision makers and stakeholders are becoming increasingly dependent on reliable chemical measurements that serve as a basis for decisions related to health, consumer safety, commerce, environment protection and compliance to regulations. Several millions of analytical results are produced annually, thus consuming appreciable amounts of resources. Reliability of these data is of major concern if cost-benefit figures are applied. Nuclear and isotopic analytical techniques (NATs) have been supported by the IAEA as part of their mandate to foster the peaceful use of nuclear energy for many years. Nuclear analytical laboratories have been installed and upgraded through Technical Co-operation assistance in many Member State laboratories. These techniques, including INAA, XRF, PIXE, stable and radioisotopes, spectrometroscopy, etc. have been applied to a wide range of subjects with varying success. Nuclear analytical techniques, featuring some intrinsic quality control aspects, such as multi-nuclide analysis, frequently serve as 'reference methods' to cross-check critical results. As nuclear properties of elements are targeted, matrix problems seem to be negligible to a great extent. The International Conference on Isotopic and Nuclear Analytical Techniques for Health and Environment was held 10-13 June 2003 in Vienna, Austria. The main purpose of this Conference was to bring together scientists, technologists, representatives of industry and regulatory authorities to exchange information and review the status of current developments and applications of isotopic and nuclear analytical techniques, and to discuss future trends and developments. A further objective is to identify potential opportunities for developing countries for applying isotopic and nuclear analytical techniques in health and environmental studies, and to consider the promotion and transfer of such technology. International developments and trends in health care, nutrition, and environmental monitoring

Optimal design of nuclear mechanical dampers with analytical hierarchy process

International Nuclear Information System (INIS)

Zou Yuehua; Wen Bo; Xu Hongxiang; Qin Yonglie

2000-01-01

An optimal design with analytical hierarchy process on nuclear mechanical dampers manufactured by authors' university was described. By using fuzzy judgement matrix the coincidence was automatically satisfied without the need of coincidence test. The results obtained by this method have been put into the production practices

Accelerator based nuclear analytical methods for trace element studies in materials- calcified tissues

International Nuclear Information System (INIS)

Chaudhri, M. Anwar

2006-01-01

Full text: Various nuclear analytical methods have been developed and applied to determine the elemental composition of calcified tissues (teeth and bones). Fluorine was determined by prompt gamma activation analysis through the 19 F(p,αγ) 16 O reaction. Carbon was measured by activation analysis with He-3 ions, and the technique of Proton-Induced X-ray Emission (PIXE) was applied to simultaneously determine Ca, P, and trace elements in well-documented teeth. Dental hard tissues: enamel, dentine, cementum, and their junctions, as well as different parts of the same tissue, were examined separately. Furthermore, using a Proton Microprobe, we measured the surface distribution of F and other elements on and around carious lesions on the enamel. The depth profiles of F, and other elements, were also measured right up to the amelodentin junction. (author)

Use of nuclear and related analytical techniques in environmental research as exemplified by selected air pollution studies

International Nuclear Information System (INIS)

Smodis, B.; Jacimovic, R.; Jeran, Z.; Stropnik, B.; Svetina, M.

2000-01-01

Among nuclear and nuclear related analytical techniques, neutron activation analysis and X-ray fluorescence spectrometry proved to be particularly useful for environmental studies owing to their nondestructive character and multi element capability. This paper emphasizes their importance among other multielement analytical methods by discussing their specific role due to specific physics basis, quite different to other destructive non-nuclear methods, and by summarizing results obtained in several studies related to air pollution research, including analyses of airborne particulate matter, water samples, lichens and mosses. (author)

Study On Analytical Methods Of Tellurium Content In Natriiodide (Na131I) Radiopharmaceutical Solution Produced In The Dalat Nuclear Reactor

International Nuclear Information System (INIS)

Vo Thi Cam Hoa; Duong Van Dong; Nguyen Thi Thu; Chu Van Khoa

2007-01-01

This report describes the practical methods for analyzing of Tellurium content in Na 131 I solution produced at the Dalat Nuclear Research Institute. We studied analytical methods to control Tellurium content in final Na 131 I solution product used in medical purposes by three methods such as: spot test, gamma spectrometric and spectrophotometric methods. These investigation results are shown that the spot test method is suitable for controlling Tellurium trace in the final product. This spot test can be determinate Tellurium trace less than 10 ppm and are used to quality control of Na 131 I solution using in medical application. (author)

Two-dimensional analytical solution for nodal calculation of nuclear reactors

International Nuclear Information System (INIS)

Silva, Adilson C.; Pessoa, Paulo O.; Silva, Fernando C.; Martinez, Aquilino S.

2017-01-01

Highlights: • A proposal for a coarse mesh nodal method is presented. • The proposal uses the analytical solution of the two-dimensional neutrons diffusion equation. • The solution is performed homogeneous nodes with dimensions of the fuel assembly. • The solution uses four average fluxes on the node surfaces as boundary conditions. • The results show good accuracy and efficiency. - Abstract: In this paper, the two-dimensional (2D) neutron diffusion equation is analytically solved for two energy groups (2G). The spatial domain of reactor core is divided into a set of nodes with uniform nuclear parameters. To determine iteratively the multiplication factor and the neutron flux in the reactor we combine the analytical solution of the neutron diffusion equation with an iterative method known as power method. The analytical solution for different types of regions that compose the reactor is obtained, such as fuel and reflector regions. Four average fluxes in the node surfaces are used as boundary conditions for analytical solution. Discontinuity factors on the node surfaces derived from the homogenization process are applied to maintain averages reaction rates and the net current in the fuel assembly (FA). To validate the results obtained by the analytical solution a relative power density distribution in the FAs is determined from the neutron flux distribution and compared with the reference values. The results show good accuracy and efficiency.

Analytic function expansion nodal method for nuclear reactor core design

International Nuclear Information System (INIS)

Noh, Hae Man

1995-02-01

In most advanced nodal methods the transverse integration is commonly used to reduce the multi-dimensional diffusion equation into equivalent one- dimensional diffusion equations when derving the nodal coupling equations. But the use of the transverse integration results in some limitations. The first limitation is that the transverse leakage term which appears in the transverse integration procedure must be appropriately approximated. The second limitation is that the one-dimensional flux shapes in each spatial direction resulted from the nodal calculation are not accurate enough to be directly used in reconstructing the pinwise flux distributions. Finally the transverse leakage defined for a non-rectangular node such as a hexagonal node or a triangular node is too complicated to be easily handled and may contain non-physical singular terms of step-function and delta-function types. In this thesis, the Analytic Function Expansion Nodal (AFEN) method and its two variations : the Polynomial Expansion Nodal (PEN) method and the hybrid of the AFEN and PEN methods, have been developed to overcome the limitations of the transverse integration procedure. All of the methods solve the multidimensional diffusion equation without the transverse integration. The AFEN method which we believe is the major contribution of this study to the reactor core analysis expands the homogeneous flux distributions within a node in non-separable analytic basis functions satisfying the neutron diffusion equations at any point of the node and expresses the coefficients of the flux expansion in terms of the nodal unknowns which comprise a node-average flux, node-interface fluxes, and corner-point fluxes. Then, the nodal coupling equations composed of the neutron balance equations, the interface current continuity equations, and the corner-point leakage balance equations are solved iteratively to determine all the nodal unknowns. Since the AFEN method does not use the transverse integration in

Analytical and Radiochemistry for Nuclear Forensics

Energy Technology Data Exchange (ETDEWEB)

Steiner, Robert Ernest [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Dry, Donald E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Kinman, William Scott [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Podlesak, David [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Tandon, Lav [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-05-26

Information about nonproliferation nuclear forensics, activities in forensics at Los Alamos National Laboratory, radio analytical work at LANL, radiochemical characterization capabilities, bulk chemical and materials analysis capabilities, and future interests in forensics interactions.

Description of JNC's analytical method and its performance for FBR cores

International Nuclear Information System (INIS)

Ishikawa, M.

2000-01-01

The description of JNC's analytical method and its performance for FBR cores includes: an outline of JNC's Analytical System Compared with ERANOS; a standard data base for FBR Nuclear Design in JNC; JUPITER Critical Experiment; details of Analytical Method and Its Effects on JUPITER; performance of JNC Analytical System (effective multiplication factor k eff , control rod worth, and sodium void reactivity); design accuracy of a 600 MWe-class FBR Core. JNC developed a consistent analytical system for FBR core evaluation, based on JENDL library, f-table method, and three dimensional diffusion/transport theory, which includes comprehensive sensitivity tools to improve the prediction accuracy of core parameters. JNC system was verified by analysis of JUPITER critical experiment, and other facilities. Its performance can be judged quite satisfactory for FBR-core design work, though there is room for further improvement, such as more detailed treatment of cross-section resonance regions

Analytic study for physical protection system (PPS) in nuclear power plants (NPPs)

Energy Technology Data Exchange (ETDEWEB)

Woo, Tae Ho, E-mail: thw@snu.ac.kr

2013-12-15

Highlights: • The physical protection system (PPS) is investigated. • General NPPs are modeled in the study. • Possible terror cases, likelihood, and consequence are studied. • PPS is constructed by analytical methods. - Abstract: The nuclear safeguard is analyzed in the aspect of the physical protection system (PPS) in nuclear power plants (NPPs). The PPS is reviewed and its related terror scenarios are investigated. The PPS is developed using analytical methods. In the terror scenarios, there are 8 possible cases for the terror attacks to the NPPs. Then, the likelihood of terror is classified by the general terror incidents. The consequence of terror is classified by Design Basis Threat (DBT) of the International Atomic Energy Agency (IAEA) scale. The physical protection method is suggested by defense-in-depth constraints and severe accident countermeasures. Finally, the advanced PPS is constructed, which could be used for the preparation for the possible terror attacks in the NPPs.

Analytic study for physical protection system (PPS) in nuclear power plants (NPPs)

International Nuclear Information System (INIS)

Woo, Tae Ho

2013-01-01

Highlights: • The physical protection system (PPS) is investigated. • General NPPs are modeled in the study. • Possible terror cases, likelihood, and consequence are studied. • PPS is constructed by analytical methods. - Abstract: The nuclear safeguard is analyzed in the aspect of the physical protection system (PPS) in nuclear power plants (NPPs). The PPS is reviewed and its related terror scenarios are investigated. The PPS is developed using analytical methods. In the terror scenarios, there are 8 possible cases for the terror attacks to the NPPs. Then, the likelihood of terror is classified by the general terror incidents. The consequence of terror is classified by Design Basis Threat (DBT) of the International Atomic Energy Agency (IAEA) scale. The physical protection method is suggested by defense-in-depth constraints and severe accident countermeasures. Finally, the advanced PPS is constructed, which could be used for the preparation for the possible terror attacks in the NPPs

Prioritizing the countries for BOT nuclear power project using Analytic Hierarchy Process

International Nuclear Information System (INIS)

Choi, Sun Woo; Roh, Myung Sub

2013-01-01

This paper proposes factors influencing the success of BOT nuclear power projects and their weighting method using Analytic Hierarchy Process (AHP) to find the optimal country which developer intends to develop. To summarize, this analytic method enable the developer to select and focus on the country which has preferable circumstance so that it enhances the efficiency of the project promotion by minimizing the opportunity cost. Also, it enables the developer to quantify the qualitative factors so that it diversifies the project success strategy and policy for the targeted country. Although the performance of this study is insufficient due to the limitation of time, small sampling and security of materials, it still has the possibility to improve the analytic model more systematically through further study with more data. Developing Build-Own(or Operate)-Transfer (BOT) nuclear power project carrying large capital in the long term requires initially well-made multi-decision which it prevents sorts of risks from unexpected situation of targeted countries. Moreover, the nuclear power project in most case is practically implemented by Government to Government cooperation, so the key concern for such nuclear power project would be naturally focused on the country situation rather than project viability at planning stage. In this regard, it requires the evaluation of targeted countries before involving the project, comprehensive and proper decision making for complex judgment factors, and efficient integration of expert's opinions, etc. Therefore, prioritizing and evaluating the feasibility of country for identification of optimal project region is very meaningful study

Analytical chemistry needs for nuclear safeguards in nuclear fuel reprocessing

International Nuclear Information System (INIS)

Hakkila, E.A.

1977-01-01

A fuel reprocessing plant designed to process 1500 tons of light water reactor fuel per year will recover 15 tons of Pu during that time, or approximately 40 to 50 kg of Pu per day. Conventional nuclear safeguards accountability has relied on batch accounting at the head and tail ends of the reprocessing plant with semi-annual plant cleanout to determine in-process holdup. An alternative proposed safeguards system relies on dynamic material accounting whereby in-line NDA and conventional analytical techniques provide indications on a daily basis of SNM transfers into the system and information of Pu holdup within the system. Some of the analytical requirements and problems for dynamic materials accounting in a nuclear fuel reprocessing plant are described. Some suggestions for further development will be proposed

Analytical Methods for Biomass Characterization during Pretreatment and Bioconversion

Energy Technology Data Exchange (ETDEWEB)

Pu, Yunqiao [ORNL; Meng, Xianzhi [University of Tennessee, Knoxville (UTK); Yoo, Chang Geun; Li, Mi; Ragauskas, Arthur J [ORNL

2016-01-01

Lignocellulosic biomass has been introduced as a promising resource for alternative fuels and chemicals because of its abundance and complement for petroleum resources. Biomass is a complex biopolymer and its compositional and structural characteristics largely vary depending on its species as well as growth environments. Because of complexity and variety of biomass, understanding its physicochemical characteristics is a key for effective biomass utilization. Characterization of biomass does not only provide critical information of biomass during pretreatment and bioconversion, but also give valuable insights on how to utilize the biomass. For better understanding biomass characteristics, good grasp and proper selection of analytical methods are necessary. This chapter introduces existing analytical approaches that are widely employed for biomass characterization during biomass pretreatment and conversion process. Diverse analytical methods using Fourier transform infrared (FTIR) spectroscopy, gel permeation chromatography (GPC), and nuclear magnetic resonance (NMR) spectroscopy for biomass characterization are reviewed. In addition, biomass accessibility methods by analyzing surface properties of biomass are also summarized in this chapter.

Nuclear analytical chemistry: recent developments and applications

International Nuclear Information System (INIS)

Acharya, R.

2013-01-01

Recent R and D studies on Nuclear Analytical Chemistry utilizing techniques like Neutron Activation Analysis (NAA), Prompt Gamma-ray NAA (PGNAA), Particle Induced Gamma Ray and X-Ray Emission (PICE/PIXE) for compositional analysis of materials have been summarized. The work includes developments and applications of (i) single comparator NAA, called as k 0 -NAA, (ii) k 0 -based internal monostandard NAA (IM-NAA), (iii) k 0 -based prompt gamma ray NAA (PGNAA) and (iv) instrumental NAA using thermal and epithermal neutrons and (v) PIGE and PIXE methods using proton beam for low Z and medium Z elements, respectively. (author)

New analytical methods for materials characterization using the techniques of nuclear activation reactions induced by thermal neutrons and accelerated ion beams, coupled to gamma-ray spectroscopy

International Nuclear Information System (INIS)

Cincu, Emanuela

1999-01-01

data from nuclear activation reactions. In the theoretical part of the thesis (Chapter 2) an explanation for the 'critical' phenomena discussed in the CPAA literature was advanced. In Chapters 3-4, new analytical formulae were derived, based on new nuclear parameters (z 0 , z), which are similar to the known (k 0 , k) parameters for the NAA field. A new, absolute standardization method, without any reference standard was also described. Chapter 5 presents new, original applications for determining the energy of the accelerated ion beams and thickness of thin materials, while the Chapter 6 describes two practical methods for optimizing the experiments: the Unitary (CPAA-NAA) analytical method based on the new parameters (z 0 , z), and the Optographic Method based on the specific evolution of each radionuclide. A new concept of the software for processing the experimental data from nuclear activation was developed for CPAA and NAA, and a database of the specific nuclear data was constructed (Chapter 7) by using the 'Fox-Pro' operating system. The experimental CPAA setup (Chapter 8) was a newly constructed reaction vacuum chamber based on the author's design, which allowed an accurate control of the electrical charge transferred to the target and reproducibility of irradiation; the analysis of the gamma-ray spectra from both types of irradiation was carried out by a spectrometer with a high resolution HPGe detector. In conclusion (Chapter 9) this thesis is significant for the field of analysis by nuclear activation (CPAA, and NAA) due to the original contributions to the theoretical, methodological, experimental and specific software and calculation methods. (author)

International conference on isotopic and nuclear analytical techniques for health and environment. Unedited papers

International Nuclear Information System (INIS)

2004-01-01

The IAEA has been supporting nuclear and isotopic analytical techniques as part of its mandate to foster the peaceful uses of nuclear energy for many years. Nuclear analytical laboratories have been installed and upgraded through technical co-operation assistance in many laboratories of Member States. These techniques, including INAA, CRF, PIXE, stable isotopes and radioisotopes, α, β, γ spectrometry, Moessbauer spectrometry, etc., have been applied to a wide range of subjects with varying success. Nuclear analytical techniques, featuring some intrinsic quality control aspects, such as multi-nuclide analysis, frequently serve as 'reference methods' to crosscheck critical results. As nuclear properties of elements are targeted, matrix problems seem to be negligible. In light of its continued commitment and support, the IAEA organized the International Conference on Isotopic and Nuclear Analytical Techniques for Health and Environment. Out of 220 from 61 countries who applied for participation, 155 official participants and five observers from 47 countries were in attendance, with 67 from 32 developing countries and 21 from international organizations, including the World Health Organization. Eleven plenary sessions were held. Also conducted was a panel discussion on Human Capacity Development Needs in the Areas of Analytical Quality Control Services (AQCS), Radiochemistry and Nutrition. The scientific sessions were divided into several topics, which reflect some of the important activities of the IAEA's Department of Nuclear Sciences and Applications (NA): - Isotopic and nuclear techniques (general); - Metrology and quality assurance in nuclear measurements; - Nuclear analytical techniques for environmental monitoring; - Radioecology; - Environmental monitoring; - Radiological safety of food and water; - Methodological aspects of stable isotope techniques in health and environment; - Applications of isotopic techniques in health and environment; - New

Applications of Nuclear Analytical Methods for High Tech Industry

International Nuclear Information System (INIS)

Hossain, T.

2013-01-01

Silicon based semiconductor chip manufacturing is a worldwide high technology industry with numerous measurement issues. One of the major concerns in the semiconductor manufacturing is contamination such as the trace metal impurities. This concern is vividly illustrated by the fact that the manufacturing in this industry is done in ultra clean environment where the entire manufacturing facility or “Fab” is a clean room facility or each and every manufacturing tool is enclosed in a mini-environment Although semiconductor devices are fabricated on the surface of the Si wafers contamination in the bulk material is a major concern. Nuclear methods of analysis are uniquely suited for the contamination analysis in such a matrix. Many opportunities in the semiconductor manufacturing field exist for the nuclear methods to provide support services. Contamination analysis by NAA, depth profiles by NDP and prompt gamma analysis of H in thin films are a few examples. These needs are on-going and require commitment from the lab so that a manufacturing operation can rely on the delivery of these services when required

Studies on analytical method and nondestructive measuring method on the sensitization of austenitic stainless steels

International Nuclear Information System (INIS)

Onimura, Kichiro; Arioka, Koji; Horai, Manabu; Noguchi, Shigeru.

1982-03-01

Austenitic stainless steels are widely used as structural materials for the machine and equipment of various kinds of plants, such as thermal power, nuclear power, and chemical plants. The machines and equipment using this kind of material, however, have the possibility of suffering corrosion damage while in service, and these damages are considered to be largely due to the sensitization of the material in sometimes. So, it is necessary to develop an analytical method for grasping the sensitization of the material more in detail and a quantitative nondestructive measuring method which is applicable to various kinds of structures in order to prevent the corrosion damage. From the above viewpoint, studies have been made on the analytical method based on the theory of diffusion of chromium in austenitic stainless steels and on Electro-Potentiokinetics Reactivation Method (EPR Method) as a nondestructive measuring method, using 304 and 316 austenitic stainless steels having different carbon contents in base metals. This paper introduces the results of EPR test on the sensitization of austenitic stainless steels and the correlation between analytical and experimental results. (author)

Quality system implementation for nuclear analytical techniques

International Nuclear Information System (INIS)

2004-01-01

The international effort (UNIDO, ILAC, BIPM, etc.) to establish a functional infrastructure for metrology and accreditation in many developing countries needs to be complemented by assistance to implement high quality practices and high quality output by service providers and producers in the respective countries. Knowledge of how to approach QA systems that justify a formal accreditation is available in only a few countries and the dissemination of know how and development of skills is needed bottom up from the working level of laboratories and institutes. Awareness building, convincing of management, introduction of good management practices, technical expertise and good documentation will lead to the creation of a quality culture that assures a sustainability and inherent development of quality practices as a prerequisite of economic success. Quality assurance and quality control can be used as a valuable management tool and is a prerequisite for international trade and information exchange. This publication tries to assist quality managers, Laboratory Managers and staff involved in setting up a QA/QC system in a nuclear analytical laboratory to take appropriate action to start and complete the necessary steps for a successful quality system for ultimate national accreditation. This guidebook contributes to a better understanding of the basic ideas behind ISO/IEC 17025, the international standard for 'General requirements for the competence of testing and calibration laboratories'. It provides basic information and detailed explanation about the establishment of the QC system in analytical and nuclear analytical laboratories. It is a proper training material for training of trainers and makes managers with QC management and implementation familiar. This training material aims to facilitate the implementation of internationally accepted quality principles and to promote attempts by Member States' laboratories to obtain accreditation for nuclear analytical

Analytical chemistry of nuclear materials

International Nuclear Information System (INIS)

1966-01-01

The second panel on the Analytical Chemistry of Nuclear Materials was organized for two purposes: first, to advise the Seibersdorf Laboratory of the Agency on its future programme, and second, to review the results of the Second International Comparison of routine analysis of trace impurities in uranium and also the action taken as a result of the recommendations of the first panel in 1962. Refs, figs and tabs

Analytical solution of dispersion relations for the nuclear optical model

Energy Technology Data Exchange (ETDEWEB)

VanderKam, J.M. [Center for Communications Research, Thanet Road, Princeton, NJ 08540 (United States); Weisel, G.J. [Triangle Universities Nuclear Laboratory, and Duke University, Box 90308, Durham, NC 27708-0308 (United States); Penn State Altoona, 3000 Ivyside Park, Altoona, PA 16601-3760 (United States); Tornow, W. [Triangle Universities Nuclear Laboratory, and Duke University, Box 90308, Durham, NC 27708-0308 (United States)

2000-12-01

Analytical solutions of dispersion integral relations, linking the real and imaginary parts of the nuclear optical model, have been derived. These are displayed for some widely used forms of the volume- and surface-absorptive nuclear potentials. When the analytical solutions are incorporated into the optical-model search code GENOA, replacing a numerical integration, the code runs three and a half to seven times faster, greatly aiding the analysis of direct-reaction, elastic scattering data. (author)

Nuclear methods in national development

International Nuclear Information System (INIS)

1993-01-01

This volume of the proceedings of the First National Conference on Nuclear Methods held at Kongo Conference Hotel Zaria from 2-4 September 1993, contains the full text of about 30 technical papers and speeches of invited dignitaries presented at the conference. The technical papers are original or review articles containing results and experiences in nuclear and related analytical techniques. Topics treated include neutron generator operation and control, nuclear data, application of nuclear techniques in environment, geochemistry, medicine, biology, agriculture, material science and industries. General topics in nuclear laboratory organization and research experiences were also covered. The papers were fully discussed during the conference and authors were requested to make changes in the manuscripts where necessary. However, they were further edited. The organizing committee wishes to thank all authors for their presentation and cooperation in submitting their manuscripts promptly and the participants for their excellent contribution during the conference

Continuous Analytical Performances Monitoring at the On-Site Laboratory through Proficiency, Inter-Laboratory Testing and Inter-Comparison Analytical Methods

International Nuclear Information System (INIS)

Duhamel, G.; Decaillon, J.-G.; Dashdondog, S.; Kim, C.-K.; Toervenyi, A.; Hara, S.; Kato, S.; Kawaguchi, T.; Matsuzawa, K.

2015-01-01

Since 2008, as one measure to strengthen its quality management system, the On-Site Laboratory for nuclear safeguards at the Rokkasho Reprocessing Plant, has increased its participation in domestic and international proficiency and inter-laboratory testing for the purpose of determining analytical method accuracy, precision and robustness but also to support method development and improvement. This paper provides a description of the testing and its scheduling. It presents the way the testing was optimized to cover most of the analytical methods at the OSL. The paper presents the methodology used for the evaluation of the obtained results based on Analysis of variance (ANOVA). Results are discussed with respect to random, systematic and long term systematic error. (author)

Application of thermo-analytical techniques in nuclear waste management

International Nuclear Information System (INIS)

Raje, Naina; Ghonge, Darshana K.; Reddy, A.V.R.

2015-01-01

Sodium nitrate solution is the byproduct of nuclear fuel reprocessing plant. It is produced during the neutralization of nitric acid received through purex process and stored in tanks or immobilized in bitumen/cement at site as waste packets. In order to minimize the environmental impact due to these waste packets, it is desirable to reduce nitrate ion to harmless gases like nitrogen. Biodegradation, ion exchange, electrodialysis and chemical treatment are the methods for nitrate reduction in the case of non nuclear industrial waste. Chemical treatment seems to be the most viable process to treat the waste from nuclear reprocessing plant in comparison to the other methods used for the non nuclear industrial waste. During chemical treatment, the nitrate ions can be converted to nitrogen by using a suitable reductant in presence of a catalyst. Formaldehyde has been chosen as the reducing agent for the nitrate - nitrogen conversion and in the process, formaldehyde gets converted to formic acid. In order to optimize the reduction process, it is essential to determine the formaldehyde and formic acid content in the waste feed solution and no direct analytical methodology is available for the same. Present work describes the attempts made to apply evolved gas analysis for understanding the mechanism of conversion of formaldehyde to formic acid. The developed method can be applied for the qualitative/quantitative determination of formaldehyde and formic acid in the waste feed solution. Waste feed samples were received from PSDD, BARC

Applications of nuclear methods in the automotive industry

International Nuclear Information System (INIS)

Schneider, E.W.; Yusuf, S.O.

1996-01-01

Over the years nuclear methods have proved to be a valuable asset to industry in general and to the automotive industry in particular. This paper summarizes some of the most important recent contributions of nuclear technology to the development of vehicles having high quality and long-term durability. Radiotracer methods are used to measure engine oil consumption and the wear rates of inaccessible components. Radiographic and tomographic methods are used to image fluids and structures in engines and accessory components. Tracers are used to understand combustion chemistry and quantify fluid flow. Gauging methods are used for inspection and process control. Nuclear analytical methods are used routinely for materials characterization and problem solving. Although nuclear methods are usually considered as the means of last resort, they can often be applied more easily and quickly than conventional methods when those in industrial engineering and R and D are aware of their unique capabilities. (author). 51 refs., 5 figs

Nuclear legislation analytical study. Regulatory and institutional framework for nuclear activities

International Nuclear Information System (INIS)

1997-01-01

This study is the second update of the 1995 edition of a series of analytical studies on nuclear legislation in OECD member countries, prepared by the OECD Nuclear Energy Agency (NEA) with the co-operation of the countries concerned. It is organised on the basis of a standardised format for all countries, thus facilitating the comparison of information. This study deals with national legislations concerning nuclear third party liability and other aspects of nuclear laws (transport, radiation protection, trade, radioactive waste management, public and semi-public agencies...). The 1997 update consists of replacement chapters for Australia, France, Germany, Korea, Norway, Sweden, and the United Kingdom. In addition, there are completely new chapters for the Czech Republic, Hungary and Poland. (A.L.B.)

Application of nuclear analytical methods to heavy metal pollution studies of estuaries

International Nuclear Information System (INIS)

Anders, B.; Junge, W.; Knoth, J.; Michaelis, W.; Pepelnik, R.; Schwenke, H.

1984-01-01

Important objectives of heavy metal pollution studies of estuaries are the understanding of the transport phenomena in these complex ecosystems and the discovery of the pollution history and the geochemical background. Such studies require high precision and accuracy of the analytical methods. Moreover, pronounced spatial heterogeneities and temporal variabilities that are typical for estuaries necessitate the analysis of a great number of samples if relevant results are to be obtained. Both requirements can economically be fulfilled by a proper combination of analytical methods. Applications of energy-dispersive X-ray fluorescence analysis with total reflection of the exciting beam at the sample support and of neutron activation analysis with both thermal and fast neutrons are reported in the light of pollution studies performed in the Lower Elbe River. (orig.)

Karlsruhe international conference on analytical chemistry in nuclear technology

International Nuclear Information System (INIS)

1985-01-01

This volume presents 218 abstracts of contributions by researchers working in the analytical chemistry field of nuclear technology. The majority of the papers deal with analysis with respect to process control in fuel reprocessing plants, fission and corrosion product characterization throughout the fuel cycle as well as studies of the chemical composition of radioactive wastes. Great interest is taken in the development and optimization of methods and instrumentation especially for in-line process control. About 3/4 of the papers have been entered into the data base separately. (RB)

Prompt nuclear analytical techniques for material research in accelerator driven transmutation technologies: Prospects and quantitative analyses

International Nuclear Information System (INIS)

Vacik, J.; Hnatowicz, V.; Cervena, J.; Perina, V.; Mach, R.

1998-01-01

Accelerator driven transmutation technology (ADTT) is a promising way toward liquidation of spent nuclear fuel, nuclear wastes and weapon grade Pu. The ADTT facility comprises a high current (proton) accelerator supplying a sub-critical reactor assembly with spallation neutrons. The reactor part is supposed to be cooled by molten fluorides or metals which serve, at the same time, as a carrier of nuclear fuel. Assumed high working temperature (400-600 C) and high radiation load in the subcritical reactor and spallation neutron source put forward the problem of optimal choice of ADTT construction materials, especially from the point of their radiation and corrosion resistance when in contact with liquid working media. The use of prompt nuclear analytical techniques in ADTT related material research is considered and examples of preliminary analytical results obtained using neutron depth profiling method are shown for illustration. (orig.)

Survey of methods and measurements of nuclear reactor time and frequency responses

International Nuclear Information System (INIS)

Cummins, J.D.

1961-11-01

Methods of measuring reactivity effects in nuclear reactors are described and the main control engineering analytical problems in nuclear reactors are detailed. A description of the use of reactor models and adaptive control in improving the economy of power producing nuclear reactors is included. (author)

The combination of four analytical methods to explore skeletal muscle metabolomics: Better coverage of metabolic pathways or a marketing argument?

Science.gov (United States)

Bruno, C; Patin, F; Bocca, C; Nadal-Desbarats, L; Bonnier, F; Reynier, P; Emond, P; Vourc'h, P; Joseph-Delafont, K; Corcia, P; Andres, C R; Blasco, H

2018-01-30

Metabolomics is an emerging science based on diverse high throughput methods that are rapidly evolving to improve metabolic coverage of biological fluids and tissues. Technical progress has led researchers to combine several analytical methods without reporting the impact on metabolic coverage of such a strategy. The objective of our study was to develop and validate several analytical techniques (mass spectrometry coupled to gas or liquid chromatography and nuclear magnetic resonance) for the metabolomic analysis of small muscle samples and evaluate the impact of combining methods for more exhaustive metabolite covering. We evaluated the muscle metabolome from the same pool of mouse muscle samples after 2 metabolite extraction protocols. Four analytical methods were used: targeted flow injection analysis coupled with mass spectrometry (FIA-MS/MS), gas chromatography coupled with mass spectrometry (GC-MS), liquid chromatography coupled with high-resolution mass spectrometry (LC-HRMS), and nuclear magnetic resonance (NMR) analysis. We evaluated the global variability of each compound i.e., analytical (from quality controls) and extraction variability (from muscle extracts). We determined the best extraction method and we reported the common and distinct metabolites identified based on the number and identity of the compounds detected with low analytical variability (variation coefficient<30%) for each method. Finally, we assessed the coverage of muscle metabolic pathways obtained. Methanol/chloroform/water and water/methanol were the best extraction solvent for muscle metabolome analysis by NMR and MS, respectively. We identified 38 metabolites by nuclear magnetic resonance, 37 by FIA-MS/MS, 18 by GC-MS, and 80 by LC-HRMS. The combination led us to identify a total of 132 metabolites with low variability partitioned into 58 metabolic pathways, such as amino acid, nitrogen, purine, and pyrimidine metabolism, and the citric acid cycle. This combination also showed

Nuclear methods in coal research

International Nuclear Information System (INIS)

Lyon, W.S.

1980-01-01

Nuclear methods, particularly neutron activation analysis (NAA) provide useful information about elemental constituents in coal and fly ash, but often other techniques are required to supplement NAA data. Spark source mass spectrometry and atomic absorption have been studied as methods for determination of certain elements in coal that are not easily measured by NAA. In work concerned with the chemical speciation of elements in fly ash, a number of analytical techniques have been used; these include NAA, chemical etching and separation, optical and electron microscopy and x-ray diffraction

7 CFR 94.303 - Analytical methods.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Analytical methods. 94.303 Section 94.303 Agriculture... POULTRY AND EGG PRODUCTS Processed Poultry Products § 94.303 Analytical methods. The analytical methods... latest edition of the Official Methods of Analysis of AOAC INTERNATIONAL, Suite 500, 481 North Frederick...

Solution standards for quality control of nuclear-material analytical measurements

International Nuclear Information System (INIS)

Clark, J.P.

1981-01-01

Analytical chemistry measurement control depends upon reliable solution standards. At the Savannah River Plant Control Laboratory over a thousand analytical measurements are made daily for process control, product specification, accountability, and nuclear safety. Large quantities of solution standards are required for a measurement quality control program covering the many different analytical chemistry methods. Savannah River Plant produced uranium, plutonium, neptunium, and americium metals or oxides are dissolved to prepare stock solutions for working or Quality Control Standards (QCS). Because extensive analytical effort is required to characterize or confirm these solutions, they are prepared in large quantities. These stock solutions are diluted and blended with different chemicals and/or each other to synthesize QCS that match the matrices of different process streams. The target uncertainty of a standard's reference value is 10% of the limit of error of the methods used for routine measurements. Standard Reference Materials from NBS are used according to special procedures to calibrate the methods used in measuring the uranium and plutonium standards so traceability can be established. Special precautions are required to minimize the effects of temperature, radiolysis, and evaporation. Standard reference values are periodically corrected to eliminate systematic errors caused by evaporation or decay products. Measurement control is achieved by requiring analysts to analyze a blind QCS each shift a measurement system is used on plant samples. Computer evaluation determines whether or not a measurement is within the +- 3 sigma control limits. Monthly evaluations of the QCS measurements are made to determine current bias correction factors for accountability measurements and detect significant changes in the bias and precision statistics. The evaluations are also used to plan activities for improving the reliability of the analytical chemistry measurements

7 CFR 98.4 - Analytical methods.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Analytical methods. 98.4 Section 98.4 Agriculture....4 Analytical methods. (a) The majority of analytical methods used by the USDA laboratories to perform analyses of meat, meat food products and MRE's are listed as follows: (1) Official Methods of...

Dynamical nuclear safeguard investigations in nuclear materials using Analytic Pair Values

International Nuclear Information System (INIS)

Woo, Tae-Ho

2011-01-01

Highlights: → The quantification of the safeguard is performed to enhance operation safety. → Newly introduced maximum pair values with multiplications are obtained by the AHP method. → The dynamical simulations are performed based on the energy policy aspect. → The comparisons using NSP are possible. → A better operation skill is developed. - Abstract: The operation of nuclear power plants (NPPs) has been investigated from the view point of safeguard assessment. The risk of terrorist attack on NPPs is one of the critical points in the secure plant operations. The basic event of the related incidents is quantified by the random sampling using a Monte-Carlo method. The Analytic Hierarchy Process (AHP) is developed leading to the maximum pair values with multiplications which are decided by reactor characteristics. The matrix form analysis is compared with five NPP types of interest. Using a life cycle of 60 years, the range of the secure operation is between 0.020628 and 0.0212986, as relative numbers. This means the highest value in the range of secure power operation is about 1.043 times larger than the lowest one in this study. The consistency has the highest consistent values in the 24th and 54th years, as represented by C.I. (Consistency Index) and C.R. (Consistency Ratio). Finally, a nuclear safeguard protocol (NSP) is successfully constructed for the safe operation.

7 CFR 93.4 - Analytical methods.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Analytical methods. 93.4 Section 93.4 Agriculture... PROCESSED FRUITS AND VEGETABLES Citrus Juices and Certain Citrus Products § 93.4 Analytical methods. (a) The majority of analytical methods for citrus products are found in the Official Methods of Analysis of AOAC...

Analytical model for relativistic corrections to the nuclear magnetic shielding constant in atoms

International Nuclear Information System (INIS)

Romero, Rodolfo H.; Gomez, Sergio S.

2006-01-01

We present a simple analytical model for calculating and rationalizing the main relativistic corrections to the nuclear magnetic shielding constant in atoms. It provides good estimates for those corrections and their trends, in reasonable agreement with accurate four-component calculations and perturbation methods. The origin of the effects in deep core atomic orbitals is manifestly shown

Analytical model for relativistic corrections to the nuclear magnetic shielding constant in atoms

Energy Technology Data Exchange (ETDEWEB)

Romero, Rodolfo H. [Facultad de Ciencias Exactas, Universidad Nacional del Nordeste, Avenida Libertad 5500 (3400), Corrientes (Argentina)]. E-mail: rhromero@exa.unne.edu.ar; Gomez, Sergio S. [Facultad de Ciencias Exactas, Universidad Nacional del Nordeste, Avenida Libertad 5500 (3400), Corrientes (Argentina)

2006-04-24

We present a simple analytical model for calculating and rationalizing the main relativistic corrections to the nuclear magnetic shielding constant in atoms. It provides good estimates for those corrections and their trends, in reasonable agreement with accurate four-component calculations and perturbation methods. The origin of the effects in deep core atomic orbitals is manifestly shown.

Application of nuclear analytical methods to heavy metal pollution studies of estuaries

International Nuclear Information System (INIS)

Anders, B.; Junge, W.; Knoth, J.; Michaelis, W.; Pepelnik, R.; Schwenke, H.

1984-01-01

Important objectives of heavy metal pollution studies of estuaries are the understanding of the transport phenomena in these complex ecosystems and the discovery of the pollution history and the geochemical background. Such studies require high precision and accuracy of the analytical methods. Moreover, pronounced spatial heterogeneities and temporal variabilities that are typical for estuaries necessitate the analysis of a great number of samples if relevant results are to be obtained. Both requirements can economically be fulfilled by a proper combination of analytical methods. Applications of energy-dispersive X-ray fluorescence analysis with total reflection of the exciting beam at the sample support and of neutron activation analysis with both thermal and fast neutrons are reported in the light of pollution studies performed in the Lower Elbe River. Profiles are presented for the total heavy metal content determined from particulate matter and sediment. They include V, Mn, Fe, Ni, Cu, Zn, As, Pb, and Cd. 16 references 10 figures, 1 table

7 CFR 94.103 - Analytical methods.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Analytical methods. 94.103 Section 94.103 Agriculture... POULTRY AND EGG PRODUCTS Voluntary Analyses of Egg Products § 94.103 Analytical methods. The analytical methods used by the Science and Technology Division laboratories to perform voluntary analyses for egg...

Conference on Nuclear and Conventional Analytical Techniques and their Applications

International Nuclear Information System (INIS)

2010-01-01

Full text : A panoply analytic techniques methods has emerged in recent decades due to the challenges of society in quality of products and the increasing demand of chemical analysis services. The industrial progress which came along with an instrumental perfection of devices with analytical use, led to the development of new techniques more and more advanced in this field. These come as well, to answer the disturbing effects of this industrialization and the wishes of a public increasingly conscious and requiring globally. The leaders in this field of analysis and material characterization are more than ever confronted with problems of identification and quantification of different chemical forms of a multitude of products in varied circles; Industrial pollutants, soil, water, air, food, medicines, ceramics, concrete, plants etc. It was from that perspective that the unifying theme ''geomaterials: characterization to applications '' of the conference on nuclear and conventional analytical techniques and their applications (TANCA 2010) was chosen. It contributes to the debate of these subjects and builds relationships between stakeholders in this field, both technically and practically [fr

7 CFR 94.4 - Analytical methods.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Analytical methods. 94.4 Section 94.4 Agriculture... POULTRY AND EGG PRODUCTS Mandatory Analyses of Egg Products § 94.4 Analytical methods. The majority of analytical methods used by the USDA laboratories to perform mandatory analyses for egg products are listed as...

Industrial and environmental applications of nuclear analytical techniques. Report of a workshop

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-11-01

The IAEA has programme the utilisation of nuclear analytical techniques (NATs), in particular for industrial and environmental applications. A major purpose is to help the developing Member States apply their analytical capabilities optimally for socio-economic progress and development. A large number of institutions in Europe, Africa, Latin America and Asia have established X ray fluorescence (XRF) and gamma ray measurement techniques and facilities for neutron activation analysis (NAA) have been initiated in institutions in these regions. Moreover, there is a growing interest among many institutes in applying more advanced analytical techniques, such as particle induced X ray emission (PIXE) and microanalytical techniques based on X ray emission induced by conventional sources or synchrotron radiation to the analysis of environmental and biological materials and industrial products. In order to define new areas of application of NATs and to extend the range of these techniques, a number of initiatives have recently been taken. It includes a workshop on industrial and environmental applications of nuclear analytical techniques, organized by the IAEA in Vienna, 7-11 September 1998. The main objectives of the workshop were as follows: (1) to review recent applications of NATs in industrial and environmental studies; (2) to identify emerging trends in methodologies and applications of NATs; (3) to demonstrate analytical capabilities of selected NATs. The following topics were reviewed during the workshop: (1) XRF and accelerator based analytical techniques; (2) portable XRF systems and their applications in industry, mineral prospecting and processing, (3) portable gamma ray spectrometers; and (4) NAA and its applications in industry and environmental studies. Micro-XRF and micro-PIXE methods and their applications in the above fields were also discussed, including aspects of synchrotron radiation induced X ray emission.

Industrial and environmental applications of nuclear analytical techniques. Report of a workshop

International Nuclear Information System (INIS)

1999-11-01

The IAEA has programme the utilisation of nuclear analytical techniques (NATs), in particular for industrial and environmental applications. A major purpose is to help the developing Member States apply their analytical capabilities optimally for socio-economic progress and development. A large number of institutions in Europe, Africa, Latin America and Asia have established X ray fluorescence (XRF) and gamma ray measurement techniques and facilities for neutron activation analysis (NAA) have been initiated in institutions in these regions. Moreover, there is a growing interest among many institutes in applying more advanced analytical techniques, such as particle induced X ray emission (PIXE) and microanalytical techniques based on X ray emission induced by conventional sources or synchrotron radiation to the analysis of environmental and biological materials and industrial products. In order to define new areas of application of NATs and to extend the range of these techniques, a number of initiatives have recently been taken. It includes a workshop on industrial and environmental applications of nuclear analytical techniques, organized by the IAEA in Vienna, 7-11 September 1998. The main objectives of the workshop were as follows: (1) to review recent applications of NATs in industrial and environmental studies; (2) to identify emerging trends in methodologies and applications of NATs; (3) to demonstrate analytical capabilities of selected NATs. The following topics were reviewed during the workshop: (1) XRF and accelerator based analytical techniques; (2) portable XRF systems and their applications in industry, mineral prospecting and processing, (3) portable gamma ray spectrometers; and (4) NAA and its applications in industry and environmental studies. Micro-XRF and micro-PIXE methods and their applications in the above fields were also discussed, including aspects of synchrotron radiation induced X ray emission

Role of analytical chemistry in the development of nuclear fuels

International Nuclear Information System (INIS)

Ramakumar, K.L.

2012-01-01

Analytical chemistry is indispensable and plays a pivotal role in the entire gamut of nuclear fuel cycle activities starting from ore refining, conversion, nuclear fuel fabrication, reactor operation, nuclear fuel reprocessing to waste management. As the fuel is the most critical component of the reactor where the fissions take place to produce power, extreme care should be taken to qualify the fuel. For example, in nuclear fuel fabrication, depending upon the reactor system, selection of nuclear fuel has to be made. The fuel for thermal reactors is normally uranium oxide either natural or slightly enriched. For research reactors it can be uranium metal or alloy. The fuel for FBR can be metal, alloy, oxide, carbide or nitride. India is planning an advanced heavy water reactor for utilization of vast resources of thorium in the country. Also research is going on to identify suitable metallic/alloy fuels for our future fast reactors and possible use in fast breeder test reactor. Other advanced fuel materials are also being investigated for thermal reactors for realizing increased performance levels. For example, advanced fuels made from UO 2 doped with Cr 2 O 3 and Al 2 O 3 are being suggested in LWR applications. These have shown to facilitate pellet densification during sintering and enlarge the pellet grain size. The chemistry of these materials has to be understood during the preparation to the stringent specification. A number of analytical parameters need to be determined as a part of chemical quality control of nuclear materials. Myriad of analytical techniques starting from the classical to sophisticated instrumentation techniques are available for this purpose. Insatiable urge of the analytical chemist enables to devise and adopt new superior methodologies in terms of reduction in the time of analysis, improvement in the measurement precision and accuracy, simplicity of the technique itself etc. Chemical quality control provides a means to ensure that the

Evaluation method for change of concentration of nuclear fuel material

International Nuclear Information System (INIS)

Kiyono, Takeshi; Ando, Ryohei.

1997-01-01

The present invention provides a method of evaluating the change of concentration of compositions of nuclear fuel element materials loaded to a reactor along with neutron irradiation based on analytic calculation not relying on integration with time. Namely, the method of evaluating the change of concentration of nuclear fuel materials comprises evaluating the changing concentration of nuclear fuel materials based on nuclear fission, capturing of neutrons and radioactive decaying along with neutron irradiation. In this case, an optional nuclide on a nuclear conversion chain is determined as a standard nuclide. When the main fuel material is Pu-239, it is determined as the standard nuclide. The ratio of the concentration of the standard nuclide to that of the nuclide as an object of the evaluation can be expressed by the ratio of the cross sectional area of neutron nuclear reaction of the standard nuclide to the cross sectional area of the neutron nuclear reaction of the nuclide as the object of the evaluation. Accordingly, the concentration of the nuclide as the object of the evaluation can be expressed by an analysis formula shown by an analysis function for the ratio of the concentration of the standard nuclide to the cross section of the neutron nuclear reaction. As a result, by giving an optional concentration of the standard nuclide to the analysis formula, the concentration of each of other nuclides can be determined analytically. (I.S.)

Application of an analytical method for the field calculation in superconducting magnets

International Nuclear Information System (INIS)

Martinelli, G.; Morini, A.

1983-01-01

Superconducting magnets are taking on ever-growing importance due to their increasing prospects of utilization in electrical machines, nuclear fusion, MHD conversion and high-energy physics. These magnets are generally composed of cylindrical or saddle coils, while a ferromagnetic shield is generally situated outside them. This paper uses an analytical method for calculating the magnetic field at every point in a superconducting magnet composed of cylindrical or saddle coils. The method takes into account the real lengths and finite thickness of the coils as well as their radial and axial ferromagnetic shields, if present. The values and distribution of the flux density for some superconducting magnets of high dimensions and high magnetic field, composed of cylindrical or saddle coils, are also given. The results obtained with analytical method are compared with those obtained using numerical methods

Evaluation method of nuclear nonproliferation credibility

International Nuclear Information System (INIS)

Kwon, Eun-ha; Ko, Won Il

2009-01-01

This paper presents an integrated multicriteria analysis method for the quantitative evaluation of a state's nuclear nonproliferation credibility level. Underscoring the implications of policy on the sources of political demand for nuclear weapons rather than focusing on efforts to restrict the supply of specific weapons technology from the 'haves' to the 'have-nots', the proposed methodology considers the political, social, and cultural dimensions of nuclear proliferation. This methodology comprises three steps: (1) identifying the factors that influence credibility formation and employing them to construct a criteria tree that will illustrate the relationships among these factors; (2) defining the weight coefficients of each criterion through pairwise comparisons of the Analytical Hierarchy Process (AHP); and (3) assigning numerical scores to a state under each criterion and combining them with the weight coefficients in order to provide an overall assessment of the state. The functionality of this methodology is examined by assessing the current level of nuclear nonproliferation credibility of four countries: Japan, North Korea, South Korea, and Switzerland.

Analytical methods for fissionable material determinations in the nuclear fuel cycle. Progress report, October 1, 1976--September 30, 1977

International Nuclear Information System (INIS)

Waterbury, G.R.

1978-01-01

Development of dissolution techniques for difficult-to-dissolve nuclear materials, development of methods and automated instruments for plutonium and uranium determinations, preparation of plutonium-containing materials for the Safeguards Analytical Laboratory Evaluation (SALE) program, analysis of SALE uranium materials, preparation of certified reference material plutonium metal, measurement of longer plutonium isotope half-lives, and study of ion exchange behavior of elements in various media continued. Gas-solid reaction of carbonyl chloride with uranium-bearing materials at elevated temperature is superior to reaction with chlorine for uranium volatilization and separation. Neither reaction with a variety of nonaqueous solvents nor reaction with molten selenium oxide provides practical dissolution of refractory materials characteristic of nuclear fuel cycle materials. The LASL automated spectrophotometer has been used to determine 0.1-mg amounts without instrumental or procedural changes. A microgram-sensitive spectrophotometric method for uranium has been developed, and the automated spectrophotometer is being modified to its use. A controlled-potential coulometric method has been developed for selective determination of plutonium. An automated analyzer to use this method is being built. Uranium-plutonium mixed oxide powder, for SALE samples, has not remained stable during storage, but high-density pellets have. In a DOE interlaboratory program, the half-life of 239 Pu has been measured, experiments on 241 Pu half-life measurement are in progress, and 240 Pu half-life measurement is planned. Ion exchange distributions for over 50 elements have been measured to determine cation exchange in nitric acid and anion exchange in both hydrobromic and hydriodic acids

Analytical methods for fissionable material determinations in the nuclear fuel cycle. Progress report, October 1, 1976--September 30, 1977

Energy Technology Data Exchange (ETDEWEB)

Waterbury, G.R. (comp.)

1978-01-01

Development of dissolution techniques for difficult-to-dissolve nuclear materials, development of methods and automated instruments for plutonium and uranium determinations, preparation of plutonium-containing materials for the Safeguards Analytical Laboratory Evaluation (SALE) program, analysis of SALE uranium materials, preparation of certified reference material plutonium metal, measurement of longer plutonium isotope half-lives, and study of ion exchange behavior of elements in various media continued. Gas-solid reaction of carbonyl chloride with uranium-bearing materials at elevated temperature is superior to reaction with chlorine for uranium volatilization and separation. Neither reaction with a variety of nonaqueous solvents nor reaction with molten selenium oxide provides practical dissolution of refractory materials characteristic of nuclear fuel cycle materials. The LASL automated spectrophotometer has been used to determine 0.1-mg amounts without instrumental or procedural changes. A microgram-sensitive spectrophotometric method for uranium has been developed, and the automated spectrophotometer is being modified to its use. A controlled-potential coulometric method has been developed for selective determination of plutonium. An automated analyzer to use this method is being built. Uranium-plutonium mixed oxide powder, for SALE samples, has not remained stable during storage, but high-density pellets have. In a DOE interlaboratory program, the half-life of /sup 239/Pu has been measured, experiments on /sup 241/Pu half-life measurement are in progress, and /sup 240/Pu half-life measurement is planned. Ion exchange distributions for over 50 elements have been measured to determine cation exchange in nitric acid and anion exchange in both hydrobromic and hydriodic acids.

An analytical method for estimating the 14N nuclear quadrupole resonance parameters of organic compounds with complex free induction decays for radiation effects studies

International Nuclear Information System (INIS)

Iselin, L.H.

1992-01-01

The use of 14 N nuclear quadrupole resonance (NQR) as a radiation dosimetry tool has only recently been explored. An analytical method for analyzing 14 N NQR complex free induction decays is presented with the background necessary to conduct pulsed NQR experiments. The 14 N NQR energy levels and possible transitions are derived in step-by-step detail. The components of a pulsed NQR spectrometer are discussed along with the experimental techniques for conducting radiation effects experiments using the spectrometer. Three data analysis techniques -- the power spectral density Fourier transform, state space singular value decomposition (HSVD), and nonlinear curve fitting (using the downhill simplex method of global optimization and the Levenberg-Marquart method) -- are explained. These three techniques are integrated into an analytical method which uses these numerical techniques in this order to determine the physical NQR parameters. Sample data sets of urea and guanidine sulfate data are used to demonstrate how these methods can be employed to analyze both simple and complex free induction decays. By determining baseline values for biologically significant organics, radiation effects on the NQR parameters can be studied to provide a link between current radiation dosimetry techniques and the biological effects of radiation

Life cycle management of analytical methods.

Science.gov (United States)

Parr, Maria Kristina; Schmidt, Alexander H

2018-01-05

In modern process management, the life cycle concept gains more and more importance. It focusses on the total costs of the process from invest to operation and finally retirement. Also for analytical procedures an increasing interest for this concept exists in the recent years. The life cycle of an analytical method consists of design, development, validation (including instrumental qualification, continuous method performance verification and method transfer) and finally retirement of the method. It appears, that also regulatory bodies have increased their awareness on life cycle management for analytical methods. Thus, the International Council for Harmonisation of Technical Requirements for Pharmaceuticals for Human Use (ICH), as well as the United States Pharmacopeial Forum discuss the enrollment of new guidelines that include life cycle management of analytical methods. The US Pharmacopeia (USP) Validation and Verification expert panel already proposed a new General Chapter 〈1220〉 "The Analytical Procedure Lifecycle" for integration into USP. Furthermore, also in the non-regulated environment a growing interest on life cycle management is seen. Quality-by-design based method development results in increased method robustness. Thereby a decreased effort is needed for method performance verification, and post-approval changes as well as minimized risk of method related out-of-specification results. This strongly contributes to reduced costs of the method during its life cycle. Copyright © 2017 Elsevier B.V. All rights reserved.

Nuclear analytical techniques and their application to environmental samples

International Nuclear Information System (INIS)

Lieser, K.H.

1986-01-01

A survey is given on nuclear analytical techniques and their application to environmental samples. Measurement of the inherent radioactivity of elements or radionuclides allows determination of natural radioelements (e.g. Ra), man-made radioelements (e.g. Pu) and radionuclides in the environment. Activation analysis, in particular instrumental neutron activation analysis, is a very reliable and sensitive method for determination of a great number of trace elements in environmental samples, because the most abundant main constituents are not activated. Tracer techniques are very useful for studies of the behaviour and of chemical reactions of trace elements and compounds in the environment. Radioactive sources are mainly applied for excitation of characteristic X-rays (X-ray fluorescence analysis). (author)

Quality assurance and quality control of nuclear analytical techniques

International Nuclear Information System (INIS)

Cincu, Emanuelathor

2001-01-01

Test and analytical laboratories in East and Central European countries need to prove the reliability and credibility of their economic, environmental, medical and legal decisions and their capacity of issuing reliable, verifiable reports. These demands imposed by the European Union aimed at avoiding a possible barrier to trade for the developing countries. In June 1999, in order to help Member States to develop according to EU objectives and the overall situation of the European market, IAEA launched a new co-operation programme designed to help the nuclear analytical laboratories in nuclear institutions and universities of Member States by training in the use of some Nuclear Analytical Techniques (NAT) that include: alpha, beta and gamma-ray spectrometry, radiochemical and neutron activation analysis, total reflection X-ray fluorescence. The Regional IAEA Project, named 'Quality Assurance/Quality Control of Nuclear Analytical Techniques' (NAT) aims at implementing the QA principles via a system of defined consecutive steps leading to a level on which the QA system is self-sustainable for formal accreditation or certification and satisfies the EU technical performance criteria; the requirements are in accordance with the new ISO/IEC 17025 Standard/Dec.1999 'General requirements for the competence of testing and calibration laboratories' - First edition. The Horia Hulubei National Institute for Nuclear Physics and Engineering, IFIN-HH, was admitted for participation in the IAEA Project in June 1999 account taken of its experience in the QA and metrology fields and its performance in the fields of beta and gamma-ray spectrometry, and radiochemical and neutron activation analysis, employed in both basic research and applications for external clients. Two working groups of specialists with the QA and Standardization and Metrology Departments and six analytical groups with the departments of Nuclear Applied Physics, Life Physics and Ionising Radiation Metrology are

AN ANALYTICAL FRAMEWORK FOR ASSESSING RELIABLE NUCLEAR FUEL SERVICE APPROACHES: ECONOMIC AND NON-PROLIFERATION MERITS OF NUCLEAR FUEL LEASING

International Nuclear Information System (INIS)

Kreyling, Sean J.; Brothers, Alan J.; Short, Steven M.; Phillips, Jon R.; Weimar, Mark R.

2010-01-01

The goal of international nuclear policy since the dawn of nuclear power has been the peaceful expansion of nuclear energy while controlling the spread of enrichment and reprocessing technology. Numerous initiatives undertaken in the intervening decades to develop international agreements on providing nuclear fuel supply assurances, or reliable nuclear fuel services (RNFS) attempted to control the spread of sensitive nuclear materials and technology. In order to inform the international debate and the development of government policy, PNNL has been developing an analytical framework to holistically evaluate the economics and non-proliferation merits of alternative approaches to managing the nuclear fuel cycle (i.e., cradle-to-grave). This paper provides an overview of the analytical framework and discusses preliminary results of an economic assessment of one RNFS approach: full-service nuclear fuel leasing. The specific focus of this paper is the metrics under development to systematically evaluate the non-proliferation merits of fuel-cycle management alternatives. Also discussed is the utility of an integrated assessment of the economics and non-proliferation merits of nuclear fuel leasing.

237 Np analytical method using 239 Np tracers and application to a contaminated nuclear disposal facility

Energy Technology Data Exchange (ETDEWEB)

Snow, Mathew S.; Morrison, Samuel S.; Clark, Sue B.; Olson, John E.; Watrous, Matthew G.

2017-06-01

Environmental 237Np analyses are challenged by low 237Np concentrations and lack of an available yield tracer; we report a rapid, inexpensive 237Np analytical approach employing the short lived 239Np (t1/2 = 2.3 days) as a chemical yield tracer followed by 237Np quantification using inductively coupled plasma-mass spectrometry. 239Np tracer is obtained via separation from a 243Am stock solution and standardized using gamma spectrometry immediately prior to sample processing. Rapid digestions using a commercial, 900 watt “Walmart” microwave and Parr microwave vessels result in 99.8 ± 0.1% digestion yields, while chromatographic separations enable Np/U separation factors on the order of 106 and total Np yields of 95 ± 4% (2σ). Application of this method to legacy soil samples surrounding a radioactive disposal facility (the Subsurface Disposal Area at Idaho National Laboratory) reveal the presence of low level 237Np contamination within 600 meters of this site, with maximum 237Np concentrations on the order of 103 times greater than nuclear weapons testing fallout levels.

Analytical methods for fissionable materials in the nuclear fuel cycle. Progress report, July 1, 1975--September 30, 1976

International Nuclear Information System (INIS)

Waterbury, G.R.

1976-12-01

Progress continued on development of dissolution techniques for difficult-to-dissolve nuclear materials, development of methods and automated instruments for determinations of plutonium and uranium, preparation of plutonium-containing materials for the Safeguards Analytical Laboratory Evaluation (SALE) program, analysis of SALE uranium materials, and measurement of plutonium isotope half-lives. Gas-solid reactions at elevated temperatures using reactive gases such as chlorine continue to show promise for separating uranium from refractory materials. An extensive study of nonaqueous solvents for the dissolution of refractory materials is in progress. An extraction-separation procedure, highly specific for microgram amounts of uranium, has been developed, and its adaptation to the Los Alamos Scientific Laboratory (LASL) automated spectrophotometer is being evaluated. Development of an electrometric analysis method for plutonium is nearing completion, and design of an automated instrument using the method has been started. Batches of plutonium oxide and mixed uranium--plutonium, intended for issue as Secondary Reference and Calibration Test Materials, are being recharacterized for assay and isotopic contents. The half-life of 239 Pu has been determined by isotope-dilution mass-spectrometric measurement of 235 U grow-in as a function of time

Analytical methods for fissionable materials in the nuclear fuel cycle. Progress report, July 1, 1975--September 30, 1976

Energy Technology Data Exchange (ETDEWEB)

Waterbury, G.R. (comp.)

1976-12-01

Progress continued on development of dissolution techniques for difficult-to-dissolve nuclear materials, development of methods and automated instruments for determinations of plutonium and uranium, preparation of plutonium-containing materials for the Safeguards Analytical Laboratory Evaluation (SALE) program, analysis of SALE uranium materials, and measurement of plutonium isotope half-lives. Gas-solid reactions at elevated temperatures using reactive gases such as chlorine continue to show promise for separating uranium from refractory materials. An extensive study of nonaqueous solvents for the dissolution of refractory materials is in progress. An extraction-separation procedure, highly specific for microgram amounts of uranium, has been developed, and its adaptation to the Los Alamos Scientific Laboratory (LASL) automated spectrophotometer is being evaluated. Development of an electrometric analysis method for plutonium is nearing completion, and design of an automated instrument using the method has been started. Batches of plutonium oxide and mixed uranium--plutonium, intended for issue as Secondary Reference and Calibration Test Materials, are being recharacterized for assay and isotopic contents. The half-life of /sup 239/Pu has been determined by isotope-dilution mass-spectrometric measurement of /sup 235/U grow-in as a function of time.

Solution of the isotopic depletion equation using decomposition method and analytical solution

Energy Technology Data Exchange (ETDEWEB)

Prata, Fabiano S.; Silva, Fernando C.; Martinez, Aquilino S., E-mail: fprata@con.ufrj.br, E-mail: fernando@con.ufrj.br, E-mail: aquilino@lmp.ufrj.br [Coordenacao dos Programas de Pos-Graduacao de Engenharia (PEN/COPPE/UFRJ), RJ (Brazil). Programa de Engenharia Nuclear

2011-07-01

In this paper an analytical calculation of the isotopic depletion equations is proposed, featuring a chain of major isotopes found in a typical PWR reactor. Part of this chain allows feedback reactions of (n,2n) type. The method is based on decoupling the equations describing feedback from the rest of the chain by using the decomposition method, with analytical solutions for the other isotopes present in the chain. The method was implemented in a PWR reactor simulation code, that makes use of the nodal expansion method (NEM) to solve the neutron diffusion equation, describing the spatial distribution of neutron flux inside the reactor core. Because isotopic depletion calculation module is the most computationally intensive process within simulation systems of nuclear reactor core, it is justified to look for a method that is both efficient and fast, with the objective of evaluating a larger number of core configurations in a short amount of time. (author)

Solution of the isotopic depletion equation using decomposition method and analytical solution

International Nuclear Information System (INIS)

Prata, Fabiano S.; Silva, Fernando C.; Martinez, Aquilino S.

2011-01-01

In this paper an analytical calculation of the isotopic depletion equations is proposed, featuring a chain of major isotopes found in a typical PWR reactor. Part of this chain allows feedback reactions of (n,2n) type. The method is based on decoupling the equations describing feedback from the rest of the chain by using the decomposition method, with analytical solutions for the other isotopes present in the chain. The method was implemented in a PWR reactor simulation code, that makes use of the nodal expansion method (NEM) to solve the neutron diffusion equation, describing the spatial distribution of neutron flux inside the reactor core. Because isotopic depletion calculation module is the most computationally intensive process within simulation systems of nuclear reactor core, it is justified to look for a method that is both efficient and fast, with the objective of evaluating a larger number of core configurations in a short amount of time. (author)

Development of analytical methods for the separation of plutonium, americium, curium and neptunium from environmental samples

Energy Technology Data Exchange (ETDEWEB)

Salminen, S.

2009-07-01

In this work, separation methods have been developed for the analysis of anthropogenic transuranium elements plutonium, americium, curium and neptunium from environmental samples contaminated by global nuclear weapons testing and the Chernobyl accident. The analytical methods utilized in this study are based on extraction chromatography. Highly varying atmospheric plutonium isotope concentrations and activity ratios were found at both Kurchatov (Kazakhstan), near the former Semipalatinsk test site, and Sodankylae (Finland). The origin of plutonium is almost impossible to identify at Kurchatov, since hundreds of nuclear tests were performed at the Semipalatinsk test site. In Sodankylae, plutonium in the surface air originated from nuclear weapons testing, conducted mostly by USSR and USA before the sampling year 1963. The variation in americium, curium and neptunium concentrations was great as well in peat samples collected in southern and central Finland in 1986 immediately after the Chernobyl accident. The main source of transuranium contamination in peats was from global nuclear test fallout, although there are wide regional differences in the fraction of Chernobyl-originated activity (of the total activity) for americium, curium and neptunium. The separation methods developed in this study yielded good chemical recovery for the elements investigated and adequately pure fractions for radiometric activity determination. The extraction chromatographic methods were faster compared to older methods based on ion exchange chromatography. In addition, extraction chromatography is a more environmentally friendly separation method than ion exchange, because less acidic waste solutions are produced during the analytical procedures. (orig.)

40 CFR 141.704 - Analytical methods.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 22 2010-07-01 2010-07-01 false Analytical methods. 141.704 Section... Monitoring Requirements § 141.704 Analytical methods. (a) Cryptosporidium. Systems must analyze for Cryptosporidium using Method 1623: Cryptosporidium and Giardia in Water by Filtration/IMS/FA, 2005, United States...

Contribution of CNESTEN to the developpement of analytical nuclear and conventional technic and their applications to the environment

International Nuclear Information System (INIS)

Bounakhla, M.

2008-01-01

Full text: In CNESTEN (National Center for Energy Sciences and Nuclear Techniques), the NAA is considered a main activity to be developed around the reactor Triga Mark 2 (2 MW) of CEN (Center for Nuclear Studies ) of Maamoura. This method allows determining 40 to 50 elements, many of them affect the environment (antimony, arsenic, cadmium, chromium, mercury, selenium, etc. ...). It also allows the determination of important elements such as sodium, chlorine and potassium, and many lanthanides. It presents many advantages and is applied in various areas, however, and as it is the case for any analysis method, it has analytical limits. To supplement this method and then allowing to cover a range analytical widest possible in various matrices, CNESTEN has already installed 4 analytical techniques: fluorescence-X Energy Dispersive (ED-XRF), fluorescence-X dispersion wavelength (WD-XRF), SAA and PCI-SEO. For the AAN, the AAN instrumental is already operational while the technique based on the Prompt Gammas is being developed with the IAEA (International Atomic Energy Agency). Using reactors of Pierre Sue Laboratories (Saclay) in France and Jozef Stefan Institute in Slovenia for the AAN and analytical techniques available in CNESTEN and in partner universities in France and Spain, many projects and studies research has been realized in the field of environment and geochemistry, that is in collaboration with national and/or foreign partners [fr

Dalhousie SLOWPOKE-2 reactor: A nuclear analytical chemistry facility

International Nuclear Information System (INIS)

Chatt, A.; Holzbecher, J.

1990-01-01

SLOWPOKE is an acronym for Safe Low POwer Kritical Experiment. The SOWPOKE-2 is a compact, inherently safe, swimming-pool-type reactor designed by the Atomic Energy of Canada Limited for neutron activation analysis (NAA) and isotope production. The Dalhousie University SLOWPOKE-2 reactor (DUSR) has been operating since 1976; a large beryllium reflector was added in 1986 to extend its lifetime by another 8 to 10 yr. The DUSR is generally operated at half-power with a maximum thermal flux of 1.1 x 10 12 n/cm 2 ·s in the inner pneumatic sites and that of 5.4 x 10 11 n/cm 2 ·s in the outer sites. Despite this comparatively low flux, SLOWPOKE-2 reactors have many beneficial features that are continuously being exploited at the DUSR facility for developing nuclear analytical methods for fundamental as well as applied studies. Although NAA is a well-established analytical technique, much of the activation analysis being performed in most facilities has been limited to methods using fairly long-lived nuclides. The approach at the DUSR facility has been to utilize the highly homogeneous, stable, and reproducible neutron flux to develop NAA methods based on short-lived nuclides. SLOWPOKE reactors have a fairly high epithermal neutron flux, which is being advantageously used for determining several trace elements in complex matrices. Radiochemical NAA (RNAA) methods using coprecipitation, distillation, and ion-exchange separations have been used for the determination of very low levels of several elements in biological materials

40 CFR 141.89 - Analytical methods.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 22 2010-07-01 2010-07-01 false Analytical methods. 141.89 Section 141...) NATIONAL PRIMARY DRINKING WATER REGULATIONS Control of Lead and Copper § 141.89 Analytical methods. (a... shall be conducted with the methods in § 141.23(k)(1). (1) Analyses for alkalinity, calcium...

Nuclear analytical techniques with neutron beams at the Univ. of Texas at Austin

International Nuclear Information System (INIS)

Uenlue, K.; Wehring, B.W.

1996-01-01

Neutron beams produced by nuclear research reactors can be used for analytical chemical analysis by measuring nuclear radiation produced by neutron capture. Prompt gamma activation analysis (PGAA) and neutron depth profiling (NDP) are two such analytical techniques. For the last three decades, these techniques have been applied at a number of research reactors around the world. Within the last 4 yr, we have developed NDP and PGAA facilities at The University of Texas at Austin research reactor, a 1-MW TRIGA Mark II reactor. Brief descriptions of the facilities and summaries of activities for these analytical techniques at the University of Texas at Austin are provided in this paper

Facility and application of nuclear and supplementary analytical techniques at Dalat Nuclear Research Institute

International Nuclear Information System (INIS)

Nguyen Mong Sinh; Ho Manh Dung; Nguyen Thanh Binh

2006-01-01

The main applications of the nuclear and supplementary analytical techniques (N and SATs) in the Dalat Nuclear Research Institute (DNRI) and the facilities for the techniques are presented. The NATs in DNRI include the neutron activation analysis (NAA) with instrumental, radiochemical and prompt gamma methods (INAA, RNAA, PGNAA), the X-ray fluorescence analysis (XRFA) and the low-level counting and spectrometry. The sample irradiation sites for NAA, the automatic and manual pneumatic transfer systems, were installed at channels 7-1 and 13-2 and rotary rack on the Dalat research reactor. An ORTEC automatic sample changer (model ASC2) for γ-ray counting was equipped. A computer software for NAA based on the k 0 -standardization method for calculation of elemental concentration was developed. The low-level counting and spectrometry techniques have been setup. The devices required for sampling, sample preparation and data processing have also been equipped. The applications of N and SATs for determination of elemental composition, particularly important in providing data so-called trace elements, radionuclides and multi-element have been enlarged for objects of geology, archaeology, bio-agriculture, health-nutrition and environment. The implementation a quality system for N and SATs has been planned and initiated. (author)

Analytical benchmarks for nuclear engineering applications. Case studies in neutron transport theory

International Nuclear Information System (INIS)

2008-01-01

The developers of computer codes involving neutron transport theory for nuclear engineering applications seldom apply analytical benchmarking strategies to ensure the quality of their programs. A major reason for this is the lack of analytical benchmarks and their documentation in the literature. The few such benchmarks that do exist are difficult to locate, as they are scattered throughout the neutron transport and radiative transfer literature. The motivation for this benchmark compendium, therefore, is to gather several analytical benchmarks appropriate for nuclear engineering applications under one cover. We consider the following three subject areas: neutron slowing down and thermalization without spatial dependence, one-dimensional neutron transport in infinite and finite media, and multidimensional neutron transport in a half-space and an infinite medium. Each benchmark is briefly described, followed by a detailed derivation of the analytical solution representation. Finally, a demonstration of the evaluation of the solution representation includes qualified numerical benchmark results. All accompanying computer codes are suitable for the PC computational environment and can serve as educational tools for courses in nuclear engineering. While this benchmark compilation does not contain all possible benchmarks, by any means, it does include some of the most prominent ones and should serve as a valuable reference. (author)

Real stabilization method for nuclear single-particle resonances

International Nuclear Information System (INIS)

Zhang Li; Zhou Shangui; Meng Jie; Zhao Enguang

2008-01-01

We develop the real stabilization method within the framework of the relativistic mean-field (RMF) model. With the self-consistent nuclear potentials from the RMF model, the real stabilization method is used to study single-particle resonant states in spherical nuclei. As examples, the energies, widths, and wave functions of low-lying neutron resonant states in 120 Sn are obtained. These results are compared with those from the scattering phase-shift method and the analytic continuation in the coupling constant approach and satisfactory agreements are found

Use of some nuclear methods for materials analysis

International Nuclear Information System (INIS)

Habbani, Farouk

1994-01-01

A review is given about the use of two nuclear-related analytical methods, namely: X-ray fluorescence (XRF) and neutron activation analysis (NAA), for the determination of elemental composition of various materials. Special emphasis is given to the use of XRF for the analysis of geological samples, and NAA for the analysis of food - stuffs for their protein content. (Author)

A report on recent progress of Central Analytical Laboratory (NRI Rez plc.) for upgrading capabilities for identification of illicit nuclear materials

International Nuclear Information System (INIS)

Malek, Z.; Sus, F.

2002-01-01

Full text: In the first half of the 90's, the State Office for Nuclear Safety (SONS) -- in close co-operation with other state organizations and following the IAEA's extended safeguards system - strengthened its attention to the development of procedures for the characterization of unknown nuclear materials. This problem become important in the context of increasing danger of illicit trafficking of nuclear material which emerged with the political changes in former 'Comecon' countries during late 80's and 90's. Particular attention has been drawn to the upgrade of the counter-potential in possible transit countries situated in Central Europe. The Central Analytical Laboratory as the main Czech institution working in the field of nuclear material analytical chemistry participated in the development and upgrading of analytical procedures for detailed identification and characterization of nuclear material samples. The special methods for the determination of uranium content, isotopic composition, swipe sample analysis, determination of age and long-lived radioisotopes were developed. In second half of the 90's within the IAEA Project entitled 'Special Analytical Methods for Determination of Traces Radioactivity and Detection of Undeclared Nuclear Activities' basic procedures were prepared for the determination of: - selected isotopes of the natural disintegration series in the samples of water, sediments and technological waste solutions after termination of the uranium ores mining, - age of uranium and plutonium materials based on the 230 Th/ 234 Th, 226 Ra/ 234 U and 241 Am/ 241 Pu pairs, studies on the application of the 231 Pa/ 235 U pair were started. In 1998 PHARE PH5.01/95 project, 'Assistance in setting up special analytical services including a data bank for analysis of radioactive substances and nuclear materials of unknown origin' was started. The project was funded from the European Commission's PHARE Programme. The activities were performed at the

Cyber security in nuclear industry – Analytic study from the terror incident in nuclear power plants (NPPs)

International Nuclear Information System (INIS)

Cho, Hyo Sung; Woo, Tae Ho

2017-01-01

Highlights: • The cyber terrorism in NPPs of South Korea shows the study motivations. • Analyses of the cyber terrorism in NPPs are investigated. • Designed solutions for the cyber terrorism in NPPs are discussed. • South Korean case is considered as the cyber terrorism in NPPs. - Abstract: The cyber terrorism for nuclear power plants (NPPs) is investigated for the analytic study following the South Korean case on December 2014. There are several possible cyber terror attacks in which the twelve cases are studied for the nuclear terror cases including the computer hacking and data stealing. The defense-in-depth concept is compared for cyber terrorism, which was imported from the physical terror analysis. The conventional three conditions of the physical protection system (PPS) are modified as prevention, detection, and response. The six cases are introduced for the solutions of the facility against the possible cyber terrorism in NPPs. The computer hacking methods and related solutions are analyzed for the applications in the nuclear industry. The nuclear security in the NPPs could be an extremely serious condition and the remedies are very important in the safe plant operations. In addition, the quantitative modeling study is performed.

Survey and analysis of deep water mineral deposits using nuclear methods

International Nuclear Information System (INIS)

Staehle, C.M.; Noakes, J.E.; Spaulding, J.

1991-01-01

Present knowledge of the location, quality, quantity and recoverability of sea floor minerals is severely limited, particularly in the abyssal depths and deep water within the 200 mile Exclusion Economic Zone (EEZ) surrounding the U.S. Pacific Islands. To improve this understanding and permit exploitation of these mineral reserves much additional data is needed. This paper will discuss a sponsored program for extending existing proven nuclear survey methods currently used on the shallow continental margins of the Atlantic and Gulf of Mexico into the deeper waters of the Pacific. This nuclear technology can be readily integrated and extended to depths of 2000 m using the existing RCV-150 remotely operated vehicle (ROV) and the PISCESE V manned deep submersible vehicle (DSV) operated by The University of Hawaii's, Hawaii Underseas Research Laboratory (HURL). Previous papers by the authors have also proposed incorporating these nuclear analytical methods for survey of the deep ocean through the use of Autonomous Underwater Vehicle (AUX). Such a vehicle could extend the use of passive nuclear instrument operation, in addition to conventional analytical methods, into the abyssal depths and do so with speed and economy not otherwise possible. The natural radioactivity associated with manganese nodules and crustal deposits is sufficiently above normal background levels to allow discrimination and quantification in near real time

Contribution to the development of new analytical methods by the coupling between capillary electrophoresis and mass spectrometry (ICP-MS and ESI-MS): applications to the nuclear and biological fields

International Nuclear Information System (INIS)

Pitois, A.

2006-04-01

The coupling between chromatographic and electrophoretic separation techniques and mass spectrometry is used to combine the efficiency of the separation technique to the selectivity and sensitivity of the detectors. In this work, the number of applications of the CE-MS couplings has been increased. New analytical methods have been set up in the nuclear and biological fields. New analytical methods for the determination of fission products (cesium and lanthanides) have been developed by CE-ICP-MS. They enable to determine both concentration and isotopic composition of the fission products for very low detection limits (ng/mL by CE-Q-ICPMS, pg/mL by CE-HR-ICP-MS), since all the isobaric interferences are resolved. Moreover, only some nano-liters of sample are necessary to perform the analysis. These method have been applied with success to a simulated sample of spent fuel, to a nuclear sample from PUREX process and to a leaching of MOX fuel. Then, lanthanides have been analysed by CE-ESI-MS and the capability of ESI-MS to provide structural information has been studied. Elementary information has been obtained for strong potentials. Structural information has been obtained for low potentials. Finally, a new analytical method by CE-ESI-MS for the determination of 10B-boronophenylalanine (10B-BPA) has been developed for Boron Neutron Capture Therapy (BNCT). It has been applied to the cellular lines F98 and HUVEC. This CE-ESI-MS method has been validated by HR-ICP-MS. It enables a direct quantification of the chemical form 10B-BPA in samples of limited size (some nano-liters) and for low concentrations (ng/mL). As a consequence, this CE-ESI-MS method has enabled the study of the kinetics of 10B-BPA release and uptake for the F98 cells. (author)

Reactor Section standard analytical methods. Part 1

Energy Technology Data Exchange (ETDEWEB)

Sowden, D.

1954-07-01

the Standard Analytical Methods manual was prepared for the purpose of consolidating and standardizing all current analytical methods and procedures used in the Reactor Section for routine chemical analyses. All procedures are established in accordance with accepted practice and the general analytical methods specified by the Engineering Department. These procedures are specifically adapted to the requirements of the water treatment process and related operations. The methods included in this manual are organized alphabetically within the following five sections which correspond to the various phases of the analytical control program in which these analyses are to be used: water analyses, essential material analyses, cotton plug analyses boiler water analyses, and miscellaneous control analyses.

237Np analytical method using 239Np tracers and application to a contaminated nuclear disposal facility.

Science.gov (United States)

Snow, Mathew S; Morrison, Samuel S; Clark, Sue B; Olson, John E; Watrous, Matthew G

2017-06-01

Environmental 237 Np analyses are challenged by low 237 Np concentrations and lack of an available yield tracer; we report a rapid, inexpensive 237 Np analytical approach employing the short lived 239 Np (t 1/2  = 2.3 days) as a chemical yield tracer followed by 237 Np quantification using inductively coupled plasma-mass spectrometry. 239 Np tracer is obtained via separation from a 243 Am stock solution and standardized using gamma spectrometry immediately prior to sample processing. Rapid digestions using a commercial, 900 W "Walmart" microwave and Parr microwave vessels result in 99.8 ± 0.1% digestion yields, while chromatographic separations enable Np/U separation factors on the order of 10 6 and total Np yields of 95 ± 4% (2σ). Application of this method to legacy soil samples surrounding a radioactive disposal facility (the Subsurface Disposal Area at Idaho National Laboratory) reveal the presence of low level 237 Np contamination within 600 m of this site, with maximum 237 Np concentrations on the order of 10 3 times greater than nuclear weapons testing fallout levels. Copyright © 2017 Elsevier Ltd. All rights reserved.

Supercritical fluid analytical methods

International Nuclear Information System (INIS)

Smith, R.D.; Kalinoski, H.T.; Wright, B.W.; Udseth, H.R.

1988-01-01

Supercritical fluids are providing the basis for new and improved methods across a range of analytical technologies. New methods are being developed to allow the detection and measurement of compounds that are incompatible with conventional analytical methodologies. Characterization of process and effluent streams for synfuel plants requires instruments capable of detecting and measuring high-molecular-weight compounds, polar compounds, or other materials that are generally difficult to analyze. The purpose of this program is to develop and apply new supercritical fluid techniques for extraction, separation, and analysis. These new technologies will be applied to previously intractable synfuel process materials and to complex mixtures resulting from their interaction with environmental and biological systems

Waste minimization in analytical methods

International Nuclear Information System (INIS)

Green, D.W.; Smith, L.L.; Crain, J.S.; Boparai, A.S.; Kiely, J.T.; Yaeger, J.S. Schilling, J.B.

1995-01-01

The US Department of Energy (DOE) will require a large number of waste characterizations over a multi-year period to accomplish the Department's goals in environmental restoration and waste management. Estimates vary, but two million analyses annually are expected. The waste generated by the analytical procedures used for characterizations is a significant source of new DOE waste. Success in reducing the volume of secondary waste and the costs of handling this waste would significantly decrease the overall cost of this DOE program. Selection of appropriate analytical methods depends on the intended use of the resultant data. It is not always necessary to use a high-powered analytical method, typically at higher cost, to obtain data needed to make decisions about waste management. Indeed, for samples taken from some heterogeneous systems, the meaning of high accuracy becomes clouded if the data generated are intended to measure a property of this system. Among the factors to be considered in selecting the analytical method are the lower limit of detection, accuracy, turnaround time, cost, reproducibility (precision), interferences, and simplicity. Occasionally, there must be tradeoffs among these factors to achieve the multiple goals of a characterization program. The purpose of the work described here is to add waste minimization to the list of characteristics to be considered. In this paper the authors present results of modifying analytical methods for waste characterization to reduce both the cost of analysis and volume of secondary wastes. Although tradeoffs may be required to minimize waste while still generating data of acceptable quality for the decision-making process, they have data demonstrating that wastes can be reduced in some cases without sacrificing accuracy or precision

Nuclear analytical techniques for on-line elemental analysis in industry

International Nuclear Information System (INIS)

1988-06-01

This report is the result of an advisory group meeting held in Espoo, Finland, 1-5 June, 1987. The purpose of the meeting was to assess the present status and development of nuclear analytical techniques used for industrial process control. The report gives an overview of the different nuclear techniques used for process control and the most important applications. A separate abstract was prepared for each of the 7 papers presented at the meeting. Refs, figs and tabs

Revisit of analytical methods for the process and plant control analyses during reprocessing of fast reactor fuels

International Nuclear Information System (INIS)

Subba Rao, R.V.

2016-01-01

CORAL (COmpact facility for Reprocessing of Advanced fuels in Lead cell) is an experimental facility for demonstrating the reprocessing of irradiated fast reactor fuels discharged from the Fast Breeder Test Reactor (FBTR). The objective of the reprocessing plant is to achieve nuclear grade plutonium and uranium oxides with minimum process waste volumes. The process flow sheet for the reprocessing of spent Fast Reactor Fuel consists of Transport of spent fuel, Chopping, Dissolution, Feed conditioning, Solvent Extraction cycle, Partitioning Cycle and Re-conversion of Plutonium nitrate and uranium nitrate to respective oxides. The efficiency and performance of the plant to achieve desired objective depends on the analyses of various species in the different steps adopted during reprocessing of fuels. The analytical requirements in the plant can be broadly classified as 1. Process control Analyses (Analyses which effect the performance of the plant- PCA); 2. Plant control Analyses (Analyses which indicates efficiency of the plant-PLCA); 3. Nuclear Material Accounting samples (Analyses which has bearing on nuclear material accounting in the plant - NUMAC) and Quality control Analyses (Quality of the input bulk chemicals as well as products - QCA). The analytical methods selected are based on the duration of analyses, precision and accuracies required for each type analytical requirement classified earlier. The process and plant control analyses requires lower precision and accuracies as compared to NUMAC analyses, which requires very high precision accuracy. The time taken for analyses should be as lower as possible for process and plant control analyses as compared to NUMAC analyses. The analytical methods required for determining U and Pu in process and plant samples from FRFR will be different as compared to samples from TRFR (Thermal Reactor Fuel Reprocessing) due to higher Pu to U ratio in FRFR as compared TRFR and they should be such that they can be easily

Technical meeting on commercial applications of nuclear analytical techniques. Meeting report

International Nuclear Information System (INIS)

2004-01-01

This report summarizes the findings of the Technical Meeting on the Commercial Applications of Nuclear Analytical Techniques held in Vienna on 23-26 November 2004, where an assessment was initiated of the world capacity and market potentials for neutron activation analysis and nuclear spectroscopy, including an estimation of economic revenues. Industry and governmental agencies were identified as stakeholders for these laboratories. Examples are given of potential benefits of these techniques to the stakeholders. The potentials for commercial applications of neutron activation analysis and nuclear spectroscopy (measurement of alpha, beta and gamma ray emitting radionuclides) are addressed. First estimates are given of the worldwide capacity of these laboratories, suggestions and examples are given for potential markets and the typical organizational and technical constraints are discussed. Two case studies of commercial neutron activation analysis laboratories at a small and a medium-size reactor are given in the 'individual contributions' section of this document. An assessment of other nuclear analytical techniques such as X ray Fluorescence Spectrometry, Particle Induced X ray Emission Spectrometry or Ion Beam Analysis Spectrometry has been completed after a comprehensive collection of background information

Technical meeting on commercial applications of nuclear analytical techniques. Meeting report

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

This report summarizes the findings of the Technical Meeting on the Commercial Applications of Nuclear Analytical Techniques held in Vienna on 23-26 November 2004, where an assessment was initiated of the world capacity and market potentials for neutron activation analysis and nuclear spectroscopy, including an estimation of economic revenues. Industry and governmental agencies were identified as stakeholders for these laboratories. Examples are given of potential benefits of these techniques to the stakeholders. The potentials for commercial applications of neutron activation analysis and nuclear spectroscopy (measurement of alpha, beta and gamma ray emitting radionuclides) are addressed. First estimates are given of the worldwide capacity of these laboratories, suggestions and examples are given for potential markets and the typical organizational and technical constraints are discussed. Two case studies of commercial neutron activation analysis laboratories at a small and a medium-size reactor are given in the 'individual contributions' section of this document. An assessment of other nuclear analytical techniques such as X ray Fluorescence Spectrometry, Particle Induced X ray Emission Spectrometry or Ion Beam Analysis Spectrometry has been completed after a comprehensive collection of background information.

Research on fuzzy comprehensive assessment method of nuclear power plant safety culture

International Nuclear Information System (INIS)

Xiang Yuanyuan; Chen Xukun; Xu Rongbin

2012-01-01

Considering the traits of safety culture in nuclear plant, 38 safety culture assessment indexes are established from 4 aspects such as safety values, safety institution, safety behavior and safety sub- stances. Based on it, a comprehensive assessment method for nuclear power plant safety culture is constructed by using AHP (Analytic Hierarchy Process) approach and fuzzy mathematics. The comprehensive assessment method has the quality of high precision and high operability, which can support the decision making of safety culture development. (authors)

Role of nuclear analytical probe techniques in biological trace element research

International Nuclear Information System (INIS)

Jones, K.W.; Pounds, J.G.

1985-01-01

Many biomedical experiments require the qualitative and quantitative localization of trace elements with high sensitivity and good spatial resolution. The feasibility of measuring the chemical form of the elements, the time course of trace elements metabolism, and of conducting experiments in living biological systems are also important requirements for biological trace element research. Nuclear analytical techniques that employ ion or photon beams have grown in importance in the past decade and have led to several new experimental approaches. Some of the important features of these methods are reviewed here along with their role in trace element research, and examples of their use are given to illustrate potential for new research directions. It is emphasized that the effective application of these methods necessitates a closely integrated multidisciplinary scientific team. 21 refs., 4 figs., 1 tab

The analytic nodal method in cylindrical geometry

International Nuclear Information System (INIS)

Prinsloo, Rian H.; Tomasevic, Djordje I.

2008-01-01

Nodal diffusion methods have been used extensively in nuclear reactor calculations, specifically for their performance advantage, but also for their superior accuracy. More specifically, the Analytic Nodal Method (ANM), utilising the transverse integration principle, has been applied to numerous reactor problems with much success. In this work, a nodal diffusion method is developed for cylindrical geometry. Application of this method to three-dimensional (3D) cylindrical geometry has never been satisfactorily addressed and we propose a solution which entails the use of conformal mapping. A set of 1D-equations with an adjusted, geometrically dependent, inhomogeneous source, is obtained. This work describes the development of the method and associated test code, as well as its application to realistic reactor problems. Numerical results are given for the PBMR-400 MW benchmark problem, as well as for a 'cylindrisized' version of the well-known 3D LWR IAEA benchmark. Results highlight the improved accuracy and performance over finite-difference core solutions and investigate the applicability of nodal methods to 3D PBMR type problems. Results indicate that cylindrical nodal methods definitely have a place within PBMR applications, yielding performance advantage factors of 10 and 20 for 2D and 3D calculations, respectively, and advantage factors of the order of 1000 in the case of the LWR problem

Nuclear Materials Characterization in the Materials and Fuels Complex Analytical Hot Cells

International Nuclear Information System (INIS)

Rodriquez, Michael

2009-01-01

As energy prices skyrocket and interest in alternative, clean energy sources builds, interest in nuclear energy has increased. This increased interest in nuclear energy has been termed the 'Nuclear Renaissance'. The performance of nuclear fuels, fuels and reactor materials and waste products are becoming a more important issue as the potential for designing new nuclear reactors is more immediate. The Idaho National Laboratory (INL) Materials and Fuels Complex (MFC) Analytical Laboratory Hot Cells (ALHC) are rising to the challenge of characterizing new reactor materials, byproducts and performance. The ALHC is a facility located near Idaho Falls, Idaho at the INL Site. It was built in 1958 as part of the former Argonne National Laboratory West Complex to support the operation of the second Experimental Breeder Reactor (EBR-II). It is part of a larger analytical laboratory structure that includes wet chemistry, instrumentation and radiochemistry laboratories. The purpose of the ALHC is to perform analytical chemistry work on highly radioactive materials. The primary work in the ALHC has traditionally been dissolution of nuclear materials so that less radioactive subsamples (aliquots) could be transferred to other sections of the laboratory for analysis. Over the last 50 years though, the capabilities within the ALHC have also become independent of other laboratory sections in a number of ways. While dissolution, digestion and subdividing samples are still a vitally important role, the ALHC has stand alone capabilities in the area of immersion density, gamma scanning and combustion gas analysis. Recent use of the ALHC for immersion density shows that extremely fine and delicate operations can be performed with the master-slave manipulators by qualified operators. Twenty milligram samples were tested for immersion density to determine the expansion of uranium dioxide after irradiation in a nuclear reactor. The data collected confirmed modeling analysis with very tight

Analytic solutions of QCD evolution equations for parton cascades inside nuclear matter at small x

International Nuclear Information System (INIS)

Geiger, K.

1994-01-01

An analytical method is presented to solve generalized QCD evolution equations for the time development of parton cascades in a nuclear environment. In addition to the usual parton branching processes in vacuum, these evolution equations provide a consistent description of interactions with the nuclear medium by accounting for stimulated branching processes, fusion, and scattering processes that are specific to QCD in a medium. Closed solutions for the spectra of produced partons with respect to the variables time, longitudinal momentum, and virtuality are obtained under some idealizing assumptions about the composition of the nuclear medium. Several characteristic features of the resulting parton distributions are discussed. One of the main conclusions is that the evolution of a parton shower in a medium is dilated as compared to free space and is accompanied by an enhancement of particle production. These effects become stronger with increasing nuclear density

Experimental and analytical studies for a BWR nuclear reactor building. Evaluation of soil-structure interaction behaviour

International Nuclear Information System (INIS)

Mizuno, N.; Tsushima, Y.

1975-01-01

This paper evaluates the spatial characteristics of dynamic properties, especially soil-structure interaction behaviour, of the BWR nuclear building by experimental and analytical studies. It is well known that the damping effects in soil-structure interaction are remarkable on the building with short periods by the dissipation of vibrational energy to the soil. The authors have previously reported an analytical method for estimating the damping effects the properties of which are characterized as follows: 1) The complex damping is used, because the so-called structural damping may be more suitable for estimating the damping effects of an elastic structure. 2) H. Tajimi's theory is used for estimating the dynamical soil-foundation stiffness with the dissipation of vibrational energy on the elastic half-space soil. In this paper, an approximate explanation is presented in regard to the more developmental mathematical method for estimating the damping effects than the above-mentioned previous method, which is 'Modes Superposition Method for Multi-Degrees of Freedom System' with the constant complex stiffness showing the structural damping effects and the dynamical soil-foundation stiffness approximated by the linear or quadratic functions of the eigenvalues. An approximate explanation is presented in regard to the experimental results of the No. 1 reactor building (BWR) of Hamaoka Nuclear Power Station, The Chubu Electric Power Co., Ltd. (Auth.)

Analytical chemistry in nuclear science and technology: a scientometric mapping

International Nuclear Information System (INIS)

Kademani, B.S.; Kumar, Anil; Kumar, Vijai

2007-01-01

This paper attempts to analyse quantitatively the growth and development of Analytical Chemistry research in Nuclear Science and Technology in terms of publication output as reflected in International Nuclear Information System (INIS) database (1970-2005). During 1970-2005 a total of 8224 papers were published. There were only seven papers published in 1970. Thereafter, a tremendous explosion of literature was observed in this area. The highest number of papers (636) were published in 1985. The average number of publications published per year was 228.44. United States topped the list with 1811 publications followed by USSR with 1688 publications, Germany with 777 publications, India with 730 publications and Hungary with 519 publications. Authorship and collaboration trend was towards multi-authored papers as 80.3 percent of the papers were collaborative is indicative of the multidisciplinary nature of research activity. The most prolific authors were: B. F. Myasoedov, AN SSSR Moscow Inst. Geokhimii I Analitisheskoi Khimii, Russian Federation with 84 publications, M. Sudersanan, Bhabha Atomic Research Centre, Mumbai, India with 67 publications, P.Vanura and V. Jedinakova Krizova both from Institute of Chemical Technology, Prague, Czech Republic with 54 publications each, S. Gangadharan, Bhabha Atomic Research Centre, Mumbai, India with 47 publications, V.M. Ivanova , M.V. Lomonosov Moscow State University, Russian Federation with 45 publications and Yu. A Zolotov Lomonosov Moscow State University, Russian Federation with 40 publications. The journals most preferred by the scientists for publication of papers were : Zhurnal Analiticheskoj Khimii with 713 papers, Journal of Radioanalytical and Nuclear Chemistry with 409 papers, Analytical Chemistry Washington with 364 papers, Fresenius' Journal of Analytical Chemistry with 324 papers, Indian Journal of Chemistry, Section A with 251 papers, and Journal of Analytical Chemistry of the USSR with 145 papers. The high

Nuclear legislation analytical study. Regulatory and institutional framework for nuclear activities in OECD member countries. Volume II

International Nuclear Information System (INIS)

1984-01-01

This study is part of a series of analytical studies of the major aspects of nuclear legislation in OECD Member countries and is published in two volumes. This volume II of the study is a revision and an expansion of a 1969 study concerning the organisation and general regime governing nuclear activities. The national studies were prepared, to the extent possible, following a standard plan for all countries to facilitate information retrieval and comparison. This volume also contains tables of international conventions of relevance to the nuclear field. (NEA) [fr

Applied research on air pollution using nuclear-related analytical techniques

International Nuclear Information System (INIS)

1994-01-01

A co-ordinated research programme (CRP) on applied research on air pollution using nuclear-related techniques is a global CRP which will run from 1992-1996, and will build upon the experience gained by the Agency from the laboratory support that it has been providing for several years to BAPMoN - the Background Air Pollution Monitoring Network programme organized under the auspices of the World Meterological Organization. The purpose of this CRP is to promote the use of nuclear analytical techniques in air pollution studies, e.g. NAA, XFR, and PIXE for the analysis of toxic and other trace elements in suspended particulate matter (including air filter samples), rainwater and fog-water samples, and in biological indicators of air pollution (e.g. lichens and mosses). The main purposes of the core programme are i) to support the use of nuclear and nuclear-related analytical techniques for practically-oriented research and monitoring studies on air pollution ii) to identify major sources of air pollution affecting each of the participating countries with particular reference to toxic heavy metals, and iii) to obtain comparative data on pollution levels in areas of high pollution (e.g. a city centre or a populated area downwind of a large pollution source) and low pollution (e.g. rural areas). This document reports the discussions held during the first Research Co-ordination Meeting (RCM) for the CRP which took place at the IAEA Headquarters in Vienna. Refs, figs and tabs

Analytical methods for fissionable material determinations in the nuclear fuel cycle. Progress report, October 1, 1977--September 30, 1978

International Nuclear Information System (INIS)

Waterbury, G.R.

1979-01-01

Work has continued on the development of dissolution techniques for difficult-to-dissolve nuclear materials, development of methods and automated instruments for plutonium and uranium determinations, preparation of plutonium-containing materials for the Safeguards Analytical Laboratory Evaluation (SALE) program, preparation of plutonium materials for distribution by the National Bureau of Standards (NBS) as standard reference materials (SRMs), measurement of longer plutonium isotope half-lives, and analysis of SALE uranium materials. New tasks include the development of methods and automated instruments for the determination of thorium and uranium, and an evaluation of the ion-exchange-bead technique for the mass spectrometric measurement of uranium and plutonium isotope distributions. Completed tasks include the measurements of ion exchange distributions of over 50 elements on cation exchange resins from nitric acid media and anion exchange resins from hydrobromic and hydriodic acid media. Using a newly developed procedure, the LASL automated spectrophotometer was modified to determine microgram levels of uranium and to determine milligram levels of uranium and plutonium. Construction of an automated controlled-potential analyzer for the determination of plutonium is nearing completion. Apparatus and procedures for the separation and complexometric titration of thorium and uranium are being developed

Analytical methods for fissionable material determinations in the nuclear fuel cycle. Progress report, October 1, 1978-September 30, 1979

Energy Technology Data Exchange (ETDEWEB)

Waterbury, G.R. (comp.)

1980-03-01

Work continues on the development of dissolution techniques for difficult-to-dissolve nuclear materials, the development of methods and automated instruments for plutonium, uranium, and thorium determinations, and the preparation of plutonium materials for the Safeguards Analytical Laboratory Evaluation (SALE) program and distribution by the National Bureau of Standards (NBS) as standard reference materials (SRMs). We are measuring the loner plutonium isotope half-lives, evaluating the isotope correlation techniques and the chemistry involved in the mass-spectrometric ion-bead techniques, and analyzing the SALE uranium materials. Completed subtasks include evaluations of various Teflon materials to recommend those acceptable for the dissolution apparatus developed at LASL, investigations of laser-enhanced dissolution of refractory materials, determinations of diverse ion effects on the microgram-sensitive method for determining uranium, fabrication of the first automated controlled-potential coulometric analyzer for determining plutonium, preparation of a /sup 244/Pu material for distribution by NBS as a SRM, and determination of the half-life of /sup 239/Pu. Work has been started on a spectrophotometric method for determining microgram quantities of plutonium, a microcomplexometric titration method for determining uranium, the use of new reagents for separations of plutonium, the preparation and packaging of a new lot of high-purity plutonium metal for distribution by NBS as a plutonium chemical SRM, and determination of half-lives of other plutonium isotopes.

Analytical methods for fissionable material determinations in the nuclear fuel cycle. Progress report, October 1, 1978-September 30, 1979

International Nuclear Information System (INIS)

Waterbury, G.R.

1980-03-01

Work continues on the development of dissolution techniques for difficult-to-dissolve nuclear materials, the development of methods and automated instruments for plutonium, uranium, and thorium determinations, and the preparation of plutonium materials for the Safeguards Analytical Laboratory Evaluation (SALE) program and distribution by the National Bureau of Standards (NBS) as standard reference materials (SRMs). We are measuring the loner plutonium isotope half-lives, evaluating the isotope correlation techniques and the chemistry involved in the mass-spectrometric ion-bead techniques, and analyzing the SALE uranium materials. Completed subtasks include evaluations of various Teflon materials to recommend those acceptable for the dissolution apparatus developed at LASL, investigations of laser-enhanced dissolution of refractory materials, determinations of diverse ion effects on the microgram-sensitive method for determining uranium, fabrication of the first automated controlled-potential coulometric analyzer for determining plutonium, preparation of a 244 Pu material for distribution by NBS as a SRM, and determination of the half-life of 239 Pu. Work has been started on a spectrophotometric method for determining microgram quantities of plutonium, a microcomplexometric titration method for determining uranium, the use of new reagents for separations of plutonium, the preparation and packaging of a new lot of high-purity plutonium metal for distribution by NBS as a plutonium chemical SRM, and determination of half-lives of other plutonium isotopes

An analytical method for estimating the ¹⁴N nuclear quadrupole resonance parameters of organic compounds with complex free induction decays for radiation effects studies

Energy Technology Data Exchange (ETDEWEB)

Iselin, Louis Henry [Univ. of Florida, Gainesville, FL (United States)

1992-01-01

The use of ¹⁴N nuclear quadrupole resonance (NQR) as a radiation dosimetry tool has only recently been explored. An analytical method for analyzing ¹⁴N NQR complex free induction decays is presented with the background necessary to conduct pulsed NQR experiments. The ¹⁴N NQR energy levels and possible transitions are derived in step-by-step detail. The components of a pulsed NQR spectrometer are discussed along with the experimental techniques for conducting radiation effects experiments using the spectrometer. Three data analysis techniques -- the power spectral density Fourier transform, state space singular value decomposition (HSVD), and nonlinear curve fitting (using the downhill simplex method of global optimization and the Levenberg-Marquart method) -- are explained. These three techniques are integrated into an analytical method which uses these numerical techniques in this order to determine the physical NQR parameters. Sample data sets of urea and guanidine sulfate data are used to demonstrate how these methods can be employed to analyze both simple and complex free induction decays. By determining baseline values for biologically significant organics, radiation effects on the NQR parameters can be studied to provide a link between current radiation dosimetry techniques and the biological effects of radiation.

Analytical chemistry instrumentation

International Nuclear Information System (INIS)

Laing, W.R.

1986-01-01

In nine sections, 48 chapters cover 1) analytical chemistry and the environment 2) environmental radiochemistry 3) automated instrumentation 4) advances in analytical mass spectrometry 5) fourier transform spectroscopy 6) analytical chemistry of plutonium 7) nuclear analytical chemistry 8) chemometrics and 9) nuclear fuel technology

Proceedings of the 4. National Meeting on Analytical Chemistry - Abstracts

International Nuclear Information System (INIS)

1987-01-01

The 4. National Meeting on Analytical Chemistry includes analysis of nuclear interest elements with nuclear and non nuclear methods and the elements not interest of nuclear energy with nuclear methods. The materials analysed are rocks, ores, metals alloys, waters, plants and biological materials. (C.G.C.)

Method for effective usage of Google Analytics tools

Directory of Open Access Journals (Sweden)

Ирина Николаевна Егорова

2016-01-01

Full Text Available Modern Google Analytics tools have been investigated against effective attraction channels for users and bottlenecks detection. Conducted investigation allowed to suggest modern method for effective usage of Google Analytics tools. The method is based on main traffic indicators analysis, as well as deep analysis of goals and their consecutive tweaking. Method allows to increase website conversion and might be useful for SEO and Web analytics specialists

Actual methods of nuclear physics in the analysis of the elemental composition of rocks and minerals

International Nuclear Information System (INIS)

Leonard, M.; Tsipenyuk, Yu. M.

1981-01-01

In this paper two methods are described for the Nuclear Physical analysis of the elementary composition of ores, mineral rocks and principles, elementary particles and radiation sources. Some examples are given showing their applications, high sensibility, selectivity, quichness and economy in comparison with other analytical methods. They are classified by their sensibilities among other analytical techniques in the determination of a large quantity of elements. (author)

Application of model-based and knowledge-based measuring methods as analytical redundancy

International Nuclear Information System (INIS)

Hampel, R.; Kaestner, W.; Chaker, N.; Vandreier, B.

1997-01-01

The safe operation of nuclear power plants requires the application of modern and intelligent methods of signal processing for the normal operation as well as for the management of accident conditions. Such modern and intelligent methods are model-based and knowledge-based ones being founded on analytical knowledge (mathematical models) as well as experiences (fuzzy information). In addition to the existing hardware redundancies analytical redundancies will be established with the help of these modern methods. These analytical redundancies support the operating staff during the decision-making. The design of a hybrid model-based and knowledge-based measuring method will be demonstrated by the example of a fuzzy-supported observer. Within the fuzzy-supported observer a classical linear observer is connected with a fuzzy-supported adaptation of the model matrices of the observer model. This application is realized for the estimation of the non-measurable variables as steam content and mixture level within pressure vessels with water-steam mixture during accidental depressurizations. For this example the existing non-linearities will be classified and the verification of the model will be explained. The advantages of the hybrid method in comparison to the classical model-based measuring methods will be demonstrated by the results of estimation. The consideration of the parameters which have an important influence on the non-linearities requires the inclusion of high-dimensional structures of fuzzy logic within the model-based measuring methods. Therefore methods will be presented which allow the conversion of these high-dimensional structures to two-dimensional structures of fuzzy logic. As an efficient solution of this problem a method based on cascaded fuzzy controllers will be presented. (author). 2 refs, 12 figs, 5 tabs

Development of Nuclear Analytical Technology

International Nuclear Information System (INIS)

Park, Yong Joon; Kim, J. Y.; Sohn, S. C.

2007-06-01

The pre-treatment and handling techniques for the micro-particles in swipe samples were developed for the safeguards purpose. The development of screening technique for the swipe samples has been established using the nuclear fission track method as well as the alpha track method. The laser ablation system to take a nuclear particle present in swipe was designed and constructed for the determination of the enrichment factors for uranium or plutonium, and its performance was tested in atmosphere as well as in vacuum. The optimum conditions for the synthesis of silica based micro-particles were obtained for mass production. The optimum ion exchange resin was selected and the optimum conditions for the uranium adsorption in resin bead technique were established for the development of the enrichment factor for nuclear particles in swipe. The established technique was applied to the swipe taken directly from the nuclear facility and also to the archive samples of IAEA's environmental swipes. The evaluation of dose rate of neutron and secondary gamma-ray for the radiation shields were carried out to design the NIPS system, as well as the evaluation of the thermal neutron concentration effect by the various reflectors. D-D neutron generator was introduced as a neutron source for the NIPS system to have more advantages such as easier control and moderation capability than the 252 Cf source. Simulated samples for explosive and chemical warfare were prepared to construct a prompt gamma-ray database. Based on the constructed database, a computer program for the detection of illicit chemical and nuclear materials was developed using the MATLAB software

SRL online Analytical Development

International Nuclear Information System (INIS)

Jenkins, C.W.

1991-01-01

The Savannah River Site is operated by the Westinghouse Savannah River Co. for the Department of Energy to produce special nuclear materials for defense. R ampersand D support for site programs is provided by the Savannah River Laboratory, which I represent. The site is known primarily for its nuclear reactors, but actually three fourths of the efforts at the site are devoted to fuel/target fabrication, fuel/target reprocessing, and waste management. All of these operations rely heavily on chemical processes. The site is therefore a large chemical plant. There are then many potential applications for process analytical chemistry at SRS. The Savannah River Laboratory (SRL) has an Analytical Development Section of roughly 65 personnel that perform analyses for R ampersand D efforts at the lab, act as backup to the site Analytical Laboratories Department and develop analytical methods and instruments. I manage a subgroup of the Analytical Development Section called the Process Control ampersand Analyzer Development Group. The Prime mission of this group is to develop online/at-line analytical systems for site applications

Application of system reliability analytical method, GO-FLOW

International Nuclear Information System (INIS)

Matsuoka, Takeshi; Fukuto, Junji; Mitomo, Nobuo; Miyazaki, Keiko; Matsukura, Hiroshi; Kobayashi, Michiyuki

1999-01-01

The Ship Research Institute proceed a developmental study on GO-FLOW method with various advancing functionalities for the system reliability analysis method occupying main parts of PSA (Probabilistic Safety Assessment). Here was attempted to intend to upgrade functionality of the GO-FLOW method, to develop an analytical function integrated with dynamic behavior analytical function, physical behavior and probable subject transfer, and to prepare a main accident sequence picking-out function. In 1997 fiscal year, in dynamic event-tree analytical system, an analytical function was developed by adding dependency between headings. In simulation analytical function of the accident sequence, main accident sequence of MRX for improved ship propulsion reactor became possible to be covered perfectly. And, input data for analysis was prepared with a function capable easily to set by an analysis operator. (G.K.)

Development of Nuclear Analytical Technology

Energy Technology Data Exchange (ETDEWEB)

Park, Yong Joon; Kim, J. Y.; Sohn, S. C. (and others)

2007-06-15

The pre-treatment and handling techniques for the micro-particles in swipe samples were developed for the safeguards purpose. The development of screening technique for the swipe samples has been established using the nuclear fission track method as well as the alpha track method. The laser ablation system to take a nuclear particle present in swipe was designed and constructed for the determination of the enrichment factors for uranium or plutonium, and its performance was tested in atmosphere as well as in vacuum. The optimum conditions for the synthesis of silica based micro-particles were obtained for mass production. The optimum ion exchange resin was selected and the optimum conditions for the uranium adsorption in resin bead technique were established for the development of the enrichment factor for nuclear particles in swipe. The established technique was applied to the swipe taken directly from the nuclear facility and also to the archive samples of IAEA's environmental swipes. The evaluation of dose rate of neutron and secondary gamma-ray for the radiation shields were carried out to design the NIPS system, as well as the evaluation of the thermal neutron concentration effect by the various reflectors. D-D neutron generator was introduced as a neutron source for the NIPS system to have more advantages such as easier control and moderation capability than the {sup 252}Cf source. Simulated samples for explosive and chemical warfare were prepared to construct a prompt gamma-ray database. Based on the constructed database, a computer program for the detection of illicit chemical and nuclear materials was developed using the MATLAB software.

Nuclear legislation. Analytical study. Regulatory and Institutional framework for nuclear activities in OECD Member countries. Volume I

International Nuclear Information System (INIS)

1983-01-01

This study is part of a series of analytical studies of the major aspects of nuclear legislation in OECD Member countries and is published in two volumes. This Volume I of the study is a revision and an expansion of a 1969 study concerning the organisation and general regime governing nuclear activities. The national studies were prepared, to the extent possible, following a standard plan for all countries to facilitate information retrieval and comparison. (NEA) [fr

Nonlinear ordinary differential equations analytical approximation and numerical methods

CERN Document Server

Hermann, Martin

2016-01-01

The book discusses the solutions to nonlinear ordinary differential equations (ODEs) using analytical and numerical approximation methods. Recently, analytical approximation methods have been largely used in solving linear and nonlinear lower-order ODEs. It also discusses using these methods to solve some strong nonlinear ODEs. There are two chapters devoted to solving nonlinear ODEs using numerical methods, as in practice high-dimensional systems of nonlinear ODEs that cannot be solved by analytical approximate methods are common. Moreover, it studies analytical and numerical techniques for the treatment of parameter-depending ODEs. The book explains various methods for solving nonlinear-oscillator and structural-system problems, including the energy balance method, harmonic balance method, amplitude frequency formulation, variational iteration method, homotopy perturbation method, iteration perturbation method, homotopy analysis method, simple and multiple shooting method, and the nonlinear stabilized march...

Workshop on Analytical Methods in Statistics

CERN Document Server

Jurečková, Jana; Maciak, Matúš; Pešta, Michal

2017-01-01

This volume collects authoritative contributions on analytical methods and mathematical statistics. The methods presented include resampling techniques; the minimization of divergence; estimation theory and regression, eventually under shape or other constraints or long memory; and iterative approximations when the optimal solution is difficult to achieve. It also investigates probability distributions with respect to their stability, heavy-tailness, Fisher information and other aspects, both asymptotically and non-asymptotically. The book not only presents the latest mathematical and statistical methods and their extensions, but also offers solutions to real-world problems including option pricing. The selected, peer-reviewed contributions were originally presented at the workshop on Analytical Methods in Statistics, AMISTAT 2015, held in Prague, Czech Republic, November 10-13, 2015.

Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium nitrate solutions

CERN Document Server

American Society for Testing and Materials. Philadelphia

2010-01-01

1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium nitrate solutions to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Plutonium by Controlled-Potential Coulometry Plutonium by Amperometric Titration with Iron(II) Plutonium by Diode Array Spectrophotometry Free Acid by Titration in an Oxalate Solution 8 to 15 Free Acid by Iodate Precipitation-Potentiometric Titration Test Method 16 to 22 Uranium by Arsenazo I Spectrophotometric Test Method 23 to 33 Thorium by Thorin Spectrophotometric Test Method 34 to 42 Iron by 1,10-Phenanthroline Spectrophotometric Test Method 43 to 50 Impurities by ICP-AES Chloride by Thiocyanate Spectrophotometric Test Method 51 to 58 Fluoride by Distillation-Spectrophotometric Test Method 59 to 66 Sulfate by Barium Sulfate Turbidimetric Test Method 67 to 74 Isotopic Composition by Mass Spectrom...

40 CFR 141.25 - Analytical methods for radioactivity.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 22 2010-07-01 2010-07-01 false Analytical methods for radioactivity... § 141.25 Analytical methods for radioactivity. (a) Analysis for the following contaminants shall be conducted to determine compliance with § 141.66 (radioactivity) in accordance with the methods in the...

Proceedings of BARC golden jubilee year DAE-BRNS topical symposium on role of analytical chemistry in nuclear technology

International Nuclear Information System (INIS)

Swain, K.K.; Venkataramani, B.

2007-01-01

Among the various disciplines in Chemistry, Analytical Chemistry is unique, because it is an integral part of every aspect of technology- product and process development and deployment. In Nuclear Industry, the quality assurance criteria are very stringent. And truly, Analytical Chemistry has continued to play a pivotal role in the entire nuclear fuel cycle, since the beginning of the Indian Atomic Energy Programme. The conference covers invited talk, nuclear materials, reactor systems, thorium technology, alternate energy sources, biology, agriculture and environment, water technology, isotope, radiation and laser technology, development of analytical instruments, and reference materials and inter-comparison exercises. Papers relevant to INIS are indexed separately. (author)

Analytical methods in sphingolipidomics: Quantitative and profiling approaches in food analysis.

Science.gov (United States)

Canela, Núria; Herrero, Pol; Mariné, Sílvia; Nadal, Pedro; Ras, Maria Rosa; Rodríguez, Miguel Ángel; Arola, Lluís

2016-01-08

In recent years, sphingolipidomics has emerged as an interesting omic science that encompasses the study of the full sphingolipidome characterization, content, structure and activity in cells, tissues or organisms. Like other omics, it has the potential to impact biomarker discovery, drug development and systems biology knowledge. Concretely, dietary food sphingolipids have gained considerable importance due to their extensively reported bioactivity. Because of the complexity of this lipid family and their diversity among foods, powerful analytical methodologies are needed for their study. The analytical tools developed in the past have been improved with the enormous advances made in recent years in mass spectrometry (MS) and chromatography, which allow the convenient and sensitive identification and quantitation of sphingolipid classes and form the basis of current sphingolipidomics methodologies. In addition, novel hyphenated nuclear magnetic resonance (NMR) strategies, new ionization strategies, and MS imaging are outlined as promising technologies to shape the future of sphingolipid analyses. This review traces the analytical methods of sphingolipidomics in food analysis concerning sample extraction, chromatographic separation, the identification and quantification of sphingolipids by MS and their structural elucidation by NMR. Copyright © 2015 Elsevier B.V. All rights reserved.

Analytical methods used at model facility

International Nuclear Information System (INIS)

Wing, N.S.

1984-01-01

A description of analytical methods used at the model LEU Fuel Fabrication Facility is presented. The methods include gravimetric uranium analysis, isotopic analysis, fluorimetric analysis, and emission spectroscopy

Analytical methods for heat transfer and fluid flow problems

CERN Document Server

Weigand, Bernhard

2015-01-01

This book describes useful analytical methods by applying them to real-world problems rather than solving the usual over-simplified classroom problems. The book demonstrates the applicability of analytical methods even for complex problems and guides the reader to a more intuitive understanding of approaches and solutions. Although the solution of Partial Differential Equations by numerical methods is the standard practice in industries, analytical methods are still important for the critical assessment of results derived from advanced computer simulations and the improvement of the underlying numerical techniques. Literature devoted to analytical methods, however, often focuses on theoretical and mathematical aspects and is therefore useless to most engineers. Analytical Methods for Heat Transfer and Fluid Flow Problems addresses engineers and engineering students. The second edition has been updated, the chapters on non-linear problems and on axial heat conduction problems were extended. And worked out exam...

Nuclear analytical techniques in Cuban Sugar Industry

International Nuclear Information System (INIS)

Diaz Riso, O.; Griffith Martinez, J.

1996-01-01

This paper is a review concerning the applications of Nuclear Analytical Techniques in the Cuban sugar industry. The most complete elemental composition of final molasses (34 elements ) and natural zeolites (38) this last one employed as an auxiliary agent in sugar technological processes has been performed by means of Instrumental Neutron Activation Analysis (INAA) and X-Ray Fluorescence Analysis (XRFA). The trace elements sugar cane soil plant relationship and elemental composition of different types of Cuban sugar (rawr, blanco directo and refine) were also studied. As a result, valuable information referred to the possibilities of using these products in animal and human foodstuff so as in other applications are given

Fatigue analysis for analytically overloaded piping components and valves in nuclear power plants

International Nuclear Information System (INIS)

Charalambus, B.

1992-01-01

Lately, in connection with life extension aspects of power plants, an increasingly accurate determination of the lifetime of components in nuclear stations is being required. In order to assess reliably current fatigue levels in piping systems, variables such as pressure, temperature, and resultant force and moment transients as well as analytical methods which take into account the real operational history must be considered. This paper presents a method for analyzing the transient heat transfer between fluid and pipe wall in order to investigate effects which until now have been assumed conservatively to be caused by a sudden jump in temperature. Further, an example is given showing that the K e factor approach in current design codes for performing simplified elastic-plastic fatigue analyses is conservative. (orig.)

Information and analytical data system on radioecological impact of the Russian nuclear complex

International Nuclear Information System (INIS)

Iskra, A. A.; Serezhnikov, D. A.

2006-01-01

The information and analytical system contains data on enterprises of the Russian nuclear complex, beginning from mining and processing of uranium ores and ending by processing of spent nuclear fuel (SNF) and ionizing radiation sources (IRS). Radioecological information is presented about radiation hazardous objects of civil mission of the Federal Agency for Atomic Energy (Rosatom): underground leaching sites, radioactive waste (RW) storage facilities, tailing dumps, burials, reactors and critical facilities, etc. Radioecological impact is examined and information and regulatory-methodical documents of Federal Agency on Hydro meteorology and Environmental Monitoring, Federal Agency for Atomic Energy, Federal Agency on ecological, technological and atomic control, Federal Agency on Geodesy and Cartography is used concerning: -radionuclide discharges from the enterprises; -radionuclide releases from the enterprises under routine and accidental conditions; -contaminated lands; -radioecological consequences of RW dumped in the Arctic and Far-East seas. The report is accompanied by the operating sophisticated database demonstration

FAPIG's activities for public acceptance of nuclear energy. Analytical results of questionnaire executed at organized visits to nuclear power stations

International Nuclear Information System (INIS)

Yoneda, Masaaki

2010-01-01

The First Atomic Power Industry Group (FAPIG) organized eighteenth visit of woman employees to nuclear power stations. They would have few chance of such a visit and to unfamiliar with mechanism of nuclear power generation as well as radiation and radioactivity. Participants were required to have a lecture on energy in general and basic understanding of nuclear energy and then had a visit to nuclear power stations to learn nuclear energy as correct knowledge. They also filled out the same questionnaire before the lecture and after the visit to express their ideas or comments on nuclear energy. This paper described analytical results of the questionnaire and significance of the organized visit for public acceptance of nuclear energy. (T. Tanaka)

Hair elemental analysis for forensic science using nuclear and related analytical methods

Czech Academy of Sciences Publication Activity Database

Kučera, Jan; Kameník, Jan; Havránek, Vladimír

2018-01-01

Roč. 7, č. 3 (2018), s. 65-74 ISSN 2468-1709 R&D Projects: GA ČR(CZ) GBP108/12/G108; GA MŠk LM2015056 Institutional support: RVO:61389005 Keywords : hair * forensic analysis * neutron activation analysis * particle induced X-ray emission Subject RIV: CB - Analytical Chemistry, Separation OBOR OECD: Analytical chemistry

Application of advanced nuclear and instrumental analytical techniques for characterisation of environmental materials

International Nuclear Information System (INIS)

Sudersanan, M.; Pawaskar, P.B.; Kayasth, S.R.; Kumar, S.C.

2002-01-01

Full text: Increasing realisation about the toxic effects of metal ions in environmental materials has given an impetus to research on analytical techniques for their characterization. The large number of analytes present at very low levels has necessitated the use of sensitive, selective and element specific techniques for their characterization. The concern about precision and accuracy on such analysis, which have socio-economic bearing, has emphasized the use of Certified Reference Materials and the use of multi-technique approach for the unambiguous characterization of analytes. The recent work carried out at Analytical Chemistry Division, BARC on these aspects is presented in this paper. Increasing use of fossil fuels has led to the generation of large quantities of fly ash which pose problems of safe disposal. The utilization of these materials for land filling is an attractive option but the presence of trace amounts of toxic metals like mercury, arsenic, lead etc may cause environmental problems. In view of the inhomogeneous nature of the material, efficient sample processing is an important factor, in addition to the validation of the results by the use of proper standards. Analysis was carried out on flyash samples received as reference materials and also as samples from commercial sources using a combination of both nuclear techniques like INAA and RNAA as well as other techniques like AAS, ICPAES, cold vapour AAS for mercury and hydride generation technique for arsenic. Similar analysis using nuclear techniques was employed for the characterization of air particulates. Biological materials often serve as sensitive indicator materials for pollution measurements. They are also employed for studies on the uptake of toxic metals like U, Th, Cd, Pb, Hg etc. The presence of large amounts of organic materials in them necessitate an appropriate sample dissolution procedure. In view of the possibility of loss of certain analytes like Cd, Hg, As, by high

Prioritizing pesticide compounds for analytical methods development

Science.gov (United States)

Norman, Julia E.; Kuivila, Kathryn; Nowell, Lisa H.

2012-01-01

The U.S. Geological Survey (USGS) has a periodic need to re-evaluate pesticide compounds in terms of priorities for inclusion in monitoring and studies and, thus, must also assess the current analytical capabilities for pesticide detection. To meet this need, a strategy has been developed to prioritize pesticides and degradates for analytical methods development. Screening procedures were developed to separately prioritize pesticide compounds in water and sediment. The procedures evaluate pesticide compounds in existing USGS analytical methods for water and sediment and compounds for which recent agricultural-use information was available. Measured occurrence (detection frequency and concentrations) in water and sediment, predicted concentrations in water and predicted likelihood of occurrence in sediment, potential toxicity to aquatic life or humans, and priorities of other agencies or organizations, regulatory or otherwise, were considered. Several existing strategies for prioritizing chemicals for various purposes were reviewed, including those that identify and prioritize persistent, bioaccumulative, and toxic compounds, and those that determine candidates for future regulation of drinking-water contaminants. The systematic procedures developed and used in this study rely on concepts common to many previously established strategies. The evaluation of pesticide compounds resulted in the classification of compounds into three groups: Tier 1 for high priority compounds, Tier 2 for moderate priority compounds, and Tier 3 for low priority compounds. For water, a total of 247 pesticide compounds were classified as Tier 1 and, thus, are high priority for inclusion in analytical methods for monitoring and studies. Of these, about three-quarters are included in some USGS analytical method; however, many of these compounds are included on research methods that are expensive and for which there are few data on environmental samples. The remaining quarter of Tier 1

Foreword of the Fifth Symposium on Nuclear Analytical Chemistry (NAC-V)

International Nuclear Information System (INIS)

Acharya, R.; Goswami, A.; Reddy, A.V.R.

2014-01-01

The Fifth Symposium on Nuclear Analytical Chemistry (NAC-V) was organized at BARC, Mumbai during January 20-24, 2014 with more than 300 participants. It was sponsored by the Board of Research in Nuclear Sciences, Department of Atomic Energy (DAE), India and organized in cooperation with the IAEA and coorganized by the IANCAS. A total of 240 contributed abstracts along with 27 invited talks and 10 invited short talks were presented in 15 technical sessions. Selected 54 full papers of NAC-V have been accepted after review for publication in special issue of JRNC. (author)

Regional technical cooperation model project, IAEA - RER/2/2004 ''quality control and quality assurance for nuclear analytical techniques'

International Nuclear Information System (INIS)

Arikan, P.

2002-01-01

assistance of 3 external and 5 agency staff auditors. This very demanding project required the submission of 6 monthly progress reports, two external audit inspections and participation in two proficiency tests rounds. Nuclear Analytical Laboratories (NALs) (gamma, x-rays and alpha/beta) of Ankara Nuclear Research and Training Center were selected by IAEA to participate fully with appropriate staff and facilities in the model project. The NALs made reasonable progress in the implementation of its Quality Assurance (QA) system during the two-year span of the RER project. Besides the increase in the number of QA related documents and SOPs, significant progress and benefits were noted in the following areas: Critical technical variables, control charts, performance checks, track ability, traceability, sample custody and coding, method validation, qualification of personnel and quality manual

Analytical quality control in environmental analysis - Recent results and future trends of the IAEA's analytical quality control programme

Energy Technology Data Exchange (ETDEWEB)

Suschny, O; Heinonen, J

1973-12-01

The significance of analytical results depends critically on the degree of their reliability, an assessment of this reliability is indispensable if the results are to have any meaning at all. Environmental radionuclide analysis is a relatively new analytical field in which new methods are continuously being developed and into which many new laboratories have entered during the last ten to fifteen years. The scarcity of routine methods and the lack of experience of the new laboratories have made the need for the assessment of the reliability of results particularly urgent in this field. The IAEA, since 1962, has provided assistance to its member states by making available to their laboratories analytical quality control services in the form of standard samples, reference materials and the organization of analytical intercomparisons. The scope of this programme has increased over the years and now includes, in addition to environmental radionuclides, non-radioactive environmental contaminants which may be analysed by nuclear methods, materials for forensic neutron activation analysis, bioassay materials and nuclear fuel. The results obtained in recent intercomparisons demonstrate the continued need for these services. (author)

Analytical detection methods for irradiated foods

International Nuclear Information System (INIS)

1991-03-01

The present publication is a review of scientific literature on the analytical identification of foods treated with ionizing radiation and the quantitative determination of absorbed dose of radiation. Because of the extremely low level of chemical changes resulting from irradiation or because of the lack of specificity to irradiation of any chemical changes, a few methods of quantitative determination of absorbed dose have shown promise until now. On the other hand, the present review has identified several possible methods, which could be used, following further research and testing, for the identification of irradiated foods. An IAEA Co-ordinated Research Programme on Analytical Detection Methods for Irradiation Treatment of Food ('ADMIT'), established in 1990, is currently investigating many of the methods cited in the present document. Refs and tab

Experimental and analytical studies for a BWR nuclear reactor building evaluation of soil-structure interaction behavior

International Nuclear Information System (INIS)

Mizuno, N.; Tsushima, Y.

1975-01-01

The purpose of this paper is to evaluate the spatial characteristics of dynamic properties, especially soil-structure interaction behavior, or the BWR nuclear reactor building by experimental and analytical studies. An analytical method (SMIRT-1 Paper K 2/4) for estimating the damping effects is reported. The complex damping is used, because the so-called structural damping may be more suitable for estimating the damping effects of an elastic structure. H. Tajimi's theory is used for estimating the dynamical soil-foundation stiffness with the dissipation of vibrational energy on the elastic half-space soil. An approximate explanation is presented in regard to the more developmental mathematical method for estimating the damping effects than the above-mentioned previous method, which is 'Modes Superposition Method for Multi-Degrees of Freedom System' with the constant complex stiffness showing the structural damping effects and the dynamical soil-foundation stiffness approximated by the linear or quadratic functions of the eigenvalues. Next, an approximate explanation is presented in regard to the experimental results of the No.1 reactor building (BWR) of Hamaoka Nuclear Power Station, The Chubu Electric Power Co., Ltd. The regression analyses of the experimental resonance curves by one degree system show that the critical damping ratio is larger than the 0.10 used in the design for the fundamental natural period. It is attempted to simulate the experimental results by the above-mentioned method. The simulated model is a fourty-eight degrees of freedom spring mass system because of the eight masses for the eight floors including the base foundation and the six degrees of freedom for a mass

Concepts of analytical user interface evaluation method for continuous work in NPP main control room

International Nuclear Information System (INIS)

Lee, S. J.; Heo, G. Y.; Jang, S. H.

2003-01-01

This paper describes a conceptual study of analytical evaluation method for computer-based user interface in the main control room of advanced nuclear power plant. User interfaces can classify them into two groups as static interface and dynamic interface. Existing evaluation and design methods of user interface have been mainly performed for the static user interface. But, it is useful for the dynamic user interface to control the complex system, and proper evaluation method for this is seldom. Therefore an evaluation method for dynamic user interface is proper for continuous works by standards of the load of cognition and the similarity of an interface

Analytical solution of point kinetics equations for linear reactivity variation during the start-up of a nuclear reactor

International Nuclear Information System (INIS)

Palma, Daniel A.P.; Martinez, Aquilino S.; Goncalves, Alessandro C.

2009-01-01

The analytical solution of point kinetics equations with a group of delayed neutrons is useful in predicting the variation of neutron density during the start-up of a nuclear reactor. In the practical case of an increase of nuclear reactor power resulting from the linear insertion of reactivity, the exact analytical solution cannot be obtained. Approximate solutions have been obtained in previous articles, based on considerations that need to be verifiable in practice. In the present article, an alternative analytic solution is presented for point kinetics equations in which the only approximation consists of disregarding the term of the second derivative for neutron density in relation to time. The results proved satisfactory when applied to practical situations in the start-up of a nuclear reactor through the control rods withdraw.

Analytical solution of point kinetics equations for linear reactivity variation during the start-up of a nuclear reactor

Energy Technology Data Exchange (ETDEWEB)

Palma, Daniel A.P. [CEFET QUIMICA de Nilopolis/RJ, 21941-914 Rio de Janeiro (Brazil)], E-mail: agoncalves@con.ufrj.br; Martinez, Aquilino S.; Goncalves, Alessandro C. [COPPE/UFRJ - Programa de Engenharia Nuclear, Rio de Janeiro (Brazil)

2009-09-15

The analytical solution of point kinetics equations with a group of delayed neutrons is useful in predicting the variation of neutron density during the start-up of a nuclear reactor. In the practical case of an increase of nuclear reactor power resulting from the linear insertion of reactivity, the exact analytical solution cannot be obtained. Approximate solutions have been obtained in previous articles, based on considerations that need to be verifiable in practice. In the present article, an alternative analytic solution is presented for point kinetics equations in which the only approximation consists of disregarding the term of the second derivative for neutron density in relation to time. The results proved satisfactory when applied to practical situations in the start-up of a nuclear reactor through the control rods withdraw.

Analytical methods under emergency conditions

International Nuclear Information System (INIS)

Sedlet, J.

1983-01-01

This lecture discusses methods for the radiochemical determination of internal contamination of the body under emergency conditions, here defined as a situation in which results on internal radioactive contamination are needed quickly. The purpose of speed is to determine the necessity for medical treatment to increase the natural elimination rate. Analytical methods discussed include whole-body counting, organ counting, wound monitoring, and excreta analysis. 12 references

Nuclear analytical techniques in Cuban sugar industry

International Nuclear Information System (INIS)

Diaz R, O.; Griffith M, J.

1997-01-01

This paper is a review concerning the application of Nuclear Analytical Techniques in the Cuban sugar industry. The most complete elemental composition of final molasses (34 elements) and natural zeolites (38) this last one employed as an auxiliary agent in sugar technological processe4s has been performed by means of instrumental Neutron Activation Analysis (INAA) and X-Ray Fluorescence Analysis (XRFA). The trace elemental sugar cane soill-plant relationship and elemental composition of different types of Cuban sugar (raw, blanco-directo and refine) were also studied. As a result, valuable information referred to the possibilities of using these products in animal and human foodstuff so as in the other applications are given. (author). 34 refs., 6 figs., 1 tab

Analytical methodology for optimization of waste management scenarios in nuclear installation decommissioning process - 16148

International Nuclear Information System (INIS)

Zachar, Matej; Necas, Vladimir; Daniska, Vladimir; Rehak, Ivan; Vasko, Marek

2009-01-01

The nuclear installation decommissioning process is characterized by production of large amount of various radioactive and non-radioactive waste that has to be managed, taking into account its physical, chemical, toxic and radiological properties. Waste management is considered to be one of the key issues within the frame of the decommissioning process. During the decommissioning planning period, the scenarios covering possible routes of materials release into the environment and radioactive waste disposal, should be discussed and evaluated. Unconditional and conditional release to the environment, long-term storage at the nuclear site, near surface or deep geological disposal and relevant material management techniques for achieving the final status should be taken into account in the analysed scenarios. At the level of the final decommissioning plan, it is desirable to have the waste management scenario optimized for local specific facility conditions taking into account a national decommissioning background. The analytical methodology for the evaluation of decommissioning waste management scenarios, presented in the paper, is based on the materials and radioactivity flow modelling, which starts from waste generation activities like pre-dismantling decontamination, selected methods of dismantling, waste treatment and conditioning, up to materials release or conditioned radioactive waste disposal. The necessary input data for scenarios, e.g. nuclear installation inventory database (physical and radiological data), waste processing technologies parameters or material release and waste disposal limits, have to be considered. The analytical methodology principles are implemented into the standardised decommissioning parameters calculation code OMEGA, developed in the DECOM company. In the paper the examples of the methodology implementation for the scenarios optimization are presented and discussed. (authors)

Nuclear Analytical Applications within the IAEA Nuclear Data Section

International Nuclear Information System (INIS)

Kellett, Mark A.

2011-01-01

The Nuclear Data Section, International Atomic Energy Agency, supports Member States development of nuclear techniques through a number of targeted actions and projects. The Section fulfills this role by organizing Coordinated Research Projects, or through less formal Data Development Projects and/or Technical Meetings. Training workshops are also regularly organized in conjunction with the International Centre for Theoretical Physics (ICTP), Trieste, Italy. A number of projects relating to materials analysis techniques have been recently undertaken, e.g. neutron activation analysis, ion beam analysis, and proton induced X- or γ-ray emission. In particular, details of the Coordinated Research Project focusing on the nuclear data requirements for the k 0 method of neutron activation analysis are given. The paper illustrates how the IAEA strives to bring together relevant partners and provides a unique and structured basis for international collaboration.

Is a Nuclear Deal with Iran Possible? An Analytical Framework for the Iran Nuclear Negotiations

OpenAIRE

Sebenius, James Kimble; Singh, Michael K.

2012-01-01

Varied diplomatic approaches by multiple negotiators over several years have failed to conclude a nuclear deal with Iran. Mutual hostility, misperception, and flawed diplomacy may be responsible. Yet, more fundamentally, no mutually acceptable deal may exist. To assess this possibility, a "negotiation analytic" framework conceptually disentangles two issues: 1) whether a feasible deal exists and 2) how to design the most promising process to achieve one. Focusing on whether a "zone of possibl...

Analytical framework for the analysis/assessment of transition scenarios to sustainable nuclear energy systems and its applications

International Nuclear Information System (INIS)

Kuznetsov, V.

2013-01-01

IAEA/INPRO (in cooperation with the IAEA's Planning and Economic Studies Section) have developed an internationally verified analytical framework to assist Member States in Nuclear energy development modelling, including material flow analysis, economic assessment and least cost model optimization (IAEA Nuclear Energy Series No. NP-T-1.14 in print). The INPRO Group (in cooperation with the IAEA's Planning and Economic Studies Section) provides training to Member States on mastering and application of this analytical framework to particular problems of national/ collaborative nuclear energy development. For small programmes of the fast reactors/closed nuclear fuel cycle deployment the economic benefits from their introduction would be substantially lower than the amount of investments needed for RD&D, licensing and deployment. Only a few countries in the world with large nuclear energy programmes (30 GW(e) for fast reactors) can bear the burden of the technology development for fast reactors/closed nuclear fuel cycle. Therefore, global nuclear energy system would follow a heterogeneous world model, at least, within the present century

Development of nuclear analytical technology

International Nuclear Information System (INIS)

Jee, Kwang Yong; Kim, W. H.; Park, Yeong J.; Park, Yong J.; Sohn, S. C.; Song, B. C.; Jeon, Y. S.; Pyo, H. Y.; Ha, Y. K.

2004-04-01

The objectives of this study are to develop the technology for the determination of isotopic ratios of nuclear particles detected from swipe samples and to develop the NIPS system. The R and D contents and results of this study are firstly the production of nuclear micro particle(1 ∼ 20 μm) and standardization, the examination of variation in fission track characteristic according to nuclear particle size and enrichment( 235 U: 1-50%), the construction of database and the application of this technique to swipe samples. If this technique is verified its superiority by various field tests and inter-laboratory comparison program with other institutes in developed countries, it can be possible to join NWAL supervised under IAEA and to export our technology abroad. Secondly, characteristics of alpha track by boron (n, α) nuclear reaction were studied to measure both total boron concentration and 10B enrichment. The correlation of number of alpha tracks and various 10B concentration was studied to evaluate the reliability of this method. Especially, cadmium shielding technique was introduced to reduce the background of alpha tracks by covering the solid track detector and the multi-dot detector plate was developed to increase the reproducibility of measurement by making boron solution dried evenly in the plate. The results of the alpha track method were found to be well agreed with those of mass spectroscopy within less than 10 % deviation. Finally, the NIPS system using 252 Cf neutron source was developed and prompt gamma spectrum and its background were obtained. Monte Carlo method using MCNP-4B code was utilized for the interpretation of neutron and gamma-ray shielding condition as well as the moderation of a fast neutron. Gamma-gamma coincidence was introduced to reduce the prompt gamma background. The counting efficiency of the HPGe detector was calibrated in the energy range from 50 keV to 10 MeV using radio isotope standards and prompt gamma rays of Cl for the

Study of the analytic quality in the determinations of Cr, Fe, Mn, Cu, Zn, Pb and Hg through conventional and nuclear analytical techniques in mosses of the MATV

International Nuclear Information System (INIS)

Caballero S, B.

2013-01-01

To evaluate the environmental risks of air pollution and to facilitate the decision-making for control, is necessary to have the capacity to generate data with analytical quality. A comparison between nuclear (Neutron activation analysis and total reflection X-ray fluorescence spectrometry) and no nuclear analytical techniques (atomic absorption spectrometry and inductively coupled plasma optical emission spectrometry) for simultaneous determination of metal content (Cr, Cu, Fe, Hg, Mn, Pb and Zn) in mosses from Metropolitan Area of the Toluca Valley (MATV) was performed. Epiphytic mosses (Fabriona ciliaris and Leskea angustata) were sampled in two campaigns, 16 sites (urban, transition and natural) and were prepared for each technique. The biological certified reference materials were used for the quality control and to evaluate accuracy, precision, linearity, detection and quantification limits. Results show that nuclear analytical techniques and no nuclear applied in chemical analysis of Cr, Cu, Fe, Hg, Mn, Pb and Zn in moss from MATV are comparable and therefore all of these can potentially be used for this purpose. However, if its considered both, the performance parameters and economic/operational characteristics is widely recommended inductively coupled plasma optical emission spectrometry, conventional analytical technique, which showed the highest analytical grade quality. Also were observed spatial and temporal variations in the concentrations of Cr, Cu, Fe, Hg, Mn, Pb and Zn in mosses from MATV and was discussed its potential origin. The urban sites had the highest concentration of anthropogenic elements as Cr, Cu, Fe, Hg, Pb and Zn because are strongly impacted by roads with high vehicle traffic. (Author)

Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of uranium hexafluoride

CERN Document Server

American Society for Testing and Materials. Philadelphia

2011-01-01

1.1 These test methods cover procedures for subsampling and for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of uranium hexafluoride UF6. Most of these test methods are in routine use to determine conformance to UF6 specifications in the Enrichment and Conversion Facilities. 1.2 The analytical procedures in this document appear in the following order: Note 1—Subcommittee C26.05 will confer with C26.02 concerning the renumbered section in Test Methods C761 to determine how concerns with renumbering these sections, as analytical methods are replaced with stand-alone analytical methods, are best addressed in subsequent publications. Sections Subsampling of Uranium Hexafluoride 7 - 10 Gravimetric Determination of Uranium 11 - 19 Titrimetric Determination of Uranium 20 Preparation of High-Purity U3O 8 21 Isotopic Analysis 22 Isotopic Analysis by Double-Standard Mass-Spectrometer Method 23 - 29 Determination of Hydrocarbons, Chlorocarbons, and Partially Substitut...

Statistically qualified neuro-analytic failure detection method and system

Science.gov (United States)

Vilim, Richard B.; Garcia, Humberto E.; Chen, Frederick W.

2002-03-02

An apparatus and method for monitoring a process involve development and application of a statistically qualified neuro-analytic (SQNA) model to accurately and reliably identify process change. The development of the SQNA model is accomplished in two stages: deterministic model adaption and stochastic model modification of the deterministic model adaptation. Deterministic model adaption involves formulating an analytic model of the process representing known process characteristics, augmenting the analytic model with a neural network that captures unknown process characteristics, and training the resulting neuro-analytic model by adjusting the neural network weights according to a unique scaled equation error minimization technique. Stochastic model modification involves qualifying any remaining uncertainty in the trained neuro-analytic model by formulating a likelihood function, given an error propagation equation, for computing the probability that the neuro-analytic model generates measured process output. Preferably, the developed SQNA model is validated using known sequential probability ratio tests and applied to the process as an on-line monitoring system. Illustrative of the method and apparatus, the method is applied to a peristaltic pump system.

Development of rapid analytical methods for Sr-89/90, Pu-239/40 and Pu-238 activity concentrations in fallout, surface water, plants and aerosol filters based on modified routine used analytical procedures

International Nuclear Information System (INIS)

Siebert, H.-U.; Thiele, J.; Loennig, M.; Kunert, M.; Kranl, H.

1995-01-01

In accordance with the tasks of the National Board for Atomic Safety and Radiation Protection in the system of nuclear, environmental surveillance for many years there has existed a traditional spectrum of methods for the determination of radionuclides in environmental media. Due to the existing environmental monitoring programmes: surveillance of GDR territory with respect to the impact of global radioactive fallout; surveillance of the environment of nuclear facilities and nuclear power plants; surveillance of the environment of mining facilities, and the involved necessity of analyzing a great number of samples, the following demands were made on the radionuclide determination methods: as few as possible, simple and safe steps of analysis; use of effective nuclide selective activity measuring methods; parallel processing of several samples; possible determination of several individual nuclides by one analytic approach; selective separation methods to produce pure element-specific measuring samples, due to the necessary use of gross activity measurements; using of same principal schemes of analysis for different sample media excluding methods of decomposition

Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solutions

CERN Document Server

American Society for Testing and Materials. Philadelphia

1999-01-01

1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solution to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Determination of Uranium 7 Specific Gravity by Pycnometry 15-20 Free Acid by Oxalate Complexation 21-27 Determination of Thorium 28 Determination of Chromium 29 Determination of Molybdenum 30 Halogens Separation by Steam Distillation 31-35 Fluoride by Specific Ion Electrode 36-42 Halogen Distillate Analysis: Chloride, Bromide, and Iodide by Amperometric Microtitrimetry 43 Determination of Chloride and Bromide 44 Determination of Sulfur by X-Ray Fluorescence 45 Sulfate Sulfur by (Photometric) Turbidimetry 46 Phosphorus by the Molybdenum Blue (Photometric) Method 54-61 Silicon by the Molybdenum Blue (Photometric) Method 62-69 Carbon by Persulfate Oxidation-Acid Titrimetry 70 Conversion to U3O8 71-74 Boron by ...

Use of nuclear and nuclear-related analytical techniques in studies of trace and minor elements in air pollution

International Nuclear Information System (INIS)

Smodis, Borut; Stropnik, Boris

1994-01-01

Among nuclear and nuclear-related analytical techniques, neutron activation and X-ray fluorescence analysis are particularly useful for environmental studies owing to their non-destructive character and multi-element capability. In this work, procedures for k o -standardized instrumental neutron activation analysis (INAA) and energy-dispersive X-ray fluorescence (EDXRF) spectrometry for trace and minor elements in air pollution studies were investigated. The methods applied were validated by the analysis of suitable reference materials. Using INAA, 20 experimentally obtained elemental values out of 21 certified and all 29 experimentally obtained values compared with 'consensus' values (for the elements where no certified numbers are available) in two SRMs were statistically indistinguishable. Also, the contents of 28 elements in candidate NIST SRM 1573a Tomato Leaves are reported. The EDXRF results were statistically indistinguishable from certified values for eight out of nine elements in NIST SRM 3087. The detection limit for this method is around at 0.1 μg cm -2 per element, so in BCR CRM No. 128, which is intended for ambient air pollution data, only Fe and Zn out of 14 elements reported in the certificate were detected with acceptable precision (i.e., 10%) owing to the very low air particulate matter loading, lying in the region of only 250 μg cm -2 . (Author)

Comparative research of finite element methods for perforated structures of nuclear power plant primary equipment

International Nuclear Information System (INIS)

Xiong Guangming; Deng Xiaoyun; Jin Ting

2013-01-01

Many perforated structures are used for nuclear power plant primary equipment, and they are complex, and have various forms. In order to explore the analysis and evaluation method, this paper used finite element method and equivalent analytic method to do the comparative analysis of perforated structures. The paper considered the main influence factors (including perforated forms, arrangements, and etc.), obtaining the systematic analysis methods of perforated structures. (authors)

Thermal fatigue crack growth in mixing tees nuclear piping - An analytical approach

International Nuclear Information System (INIS)

Radu, V.

2009-01-01

The assessment of fatigue crack growth due to cyclic thermal loads arising from turbulent mixing presents significant challenges, principally due to the difficulty of establishing the actual loading spectrum. So-called sinusoidal methods represent a simplified approach in which the entire spectrum is replaced by a sine-wave variation of the temperature at the inner pipe surface. The need for multiple calculations in this process has lead to the development of analytical solutions for thermal stresses in a pipe subject to sinusoidal thermal loading, described in previous work performed at JRC IE Petten, The Netherlands, during the author's stage as seconded national expert. Based on these stress distributions solutions, the paper presents a methodology for assessment of thermal fatigue crack growth life in mixing tees nuclear piping. (author)

Europe needs to take clear, analytical approach in considering future of nuclear energy

Energy Technology Data Exchange (ETDEWEB)

Shepherd, John [nuclear 24, Redditch (United Kingdom)

2016-11-15

Europe's political leaders have been accused of failing to offer a clear and comprehensive approach to the future of nuclear power in Europe. The criticism came in an opinion adopted recently by the European Economic and Social Committee (EESC). According to the EESC, the European Commission should propose ''a clear analytical process and methodology which can offer a consistent, voluntary framework for national decision-making about the role - if any - of nuclear power in the energy mix''.

Europe needs to take clear, analytical approach in considering future of nuclear energy

International Nuclear Information System (INIS)

Shepherd, John

2016-01-01

Europe's political leaders have been accused of failing to offer a clear and comprehensive approach to the future of nuclear power in Europe. The criticism came in an opinion adopted recently by the European Economic and Social Committee (EESC). According to the EESC, the European Commission should propose ''a clear analytical process and methodology which can offer a consistent, voluntary framework for national decision-making about the role - if any - of nuclear power in the energy mix''.

Fundamentals of nuclear chemistry

International Nuclear Information System (INIS)

Majer, K.

1982-01-01

The textbook is a Czech-to-German translation of the second revised edition and covers the subject under the headings: general nuclear chemistry, methods of nuclear chemistry, preparative nuclear chemistry, analytical nuclear chemistry, and applied chemistry. The book is especially directed to students

NUMERICAL AND ANALYTIC METHODS OF ESTIMATION BRIDGES’ CONSTRUCTIONS

Directory of Open Access Journals (Sweden)

Y. Y. Luchko

2010-03-01

Full Text Available In this article the numerical and analytical methods of calculation of the stressed-and-strained state of bridge constructions are considered. The task on increasing of reliability and accuracy of the numerical method and its solution by means of calculations in two bases are formulated. The analytical solution of the differential equation of deformation of a ferro-concrete plate under the action of local loads is also obtained.

Analytical measurements of fission products during a severe nuclear accident

Science.gov (United States)

Doizi, D.; Reymond la Ruinaz, S.; Haykal, I.; Manceron, L.; Perrin, A.; Boudon, V.; Vander Auwera, J.; tchana, F. Kwabia; Faye, M.

2018-01-01

The Fukushima accident emphasized the fact that ways to monitor in real time the evolution of a nuclear reactor during a severe accident remain to be developed. No fission products were monitored during twelve days; only dose rates were measured, which is not sufficient to carry out an online diagnosis of the event. The first measurements were announced with little reliability for low volatile fission products. In order to improve the safety of nuclear plants and minimize the industrial, ecological and health consequences of a severe accident, it is necessary to develop new reliable measurement systems, operating at the earliest and closest to the emission source of fission products. Through the French program ANR « Projet d'Investissement d'Avenir », the aim of the DECA-PF project (diagnosis of core degradation from fission products measurements) is to monitor in real time the release of the major fission products (krypton, xenon, gaseous forms of iodine and ruthenium) outside the nuclear reactor containment. These products are released at different times during a nuclear accident and at different states of the nuclear core degradation. Thus, monitoring these fission products gives information on the situation inside the containment and helps to apply the Severe Accident Management procedures. Analytical techniques have been proposed and evaluated. The results are discussed here.

Analytical measurements of fission products during a severe nuclear accident

Directory of Open Access Journals (Sweden)

Doizi D.

2018-01-01

Full Text Available The Fukushima accident emphasized the fact that ways to monitor in real time the evolution of a nuclear reactor during a severe accident remain to be developed. No fission products were monitored during twelve days; only dose rates were measured, which is not sufficient to carry out an online diagnosis of the event. The first measurements were announced with little reliability for low volatile fission products. In order to improve the safety of nuclear plants and minimize the industrial, ecological and health consequences of a severe accident, it is necessary to develop new reliable measurement systems, operating at the earliest and closest to the emission source of fission products. Through the French program ANR « Projet d’Investissement d’Avenir », the aim of the DECA-PF project (diagnosis of core degradation from fission products measurements is to monitor in real time the release of the major fission products (krypton, xenon, gaseous forms of iodine and ruthenium outside the nuclear reactor containment. These products are released at different times during a nuclear accident and at different states of the nuclear core degradation. Thus, monitoring these fission products gives information on the situation inside the containment and helps to apply the Severe Accident Management procedures. Analytical techniques have been proposed and evaluated. The results are discussed here.

Propulsion and launching analysis of variable-mass rockets by analytical methods

OpenAIRE

D.D. Ganji; M. Gorji; M. Hatami; A. Hasanpour; N. Khademzadeh

2013-01-01

In this study, applications of some analytical methods on nonlinear equation of the launching of a rocket with variable mass are investigated. Differential transformation method (DTM), homotopy perturbation method (HPM) and least square method (LSM) were applied and their results are compared with numerical solution. An excellent agreement with analytical methods and numerical ones is observed in the results and this reveals that analytical methods are effective and convenient. Also a paramet...

Maintenance planning support method for nuclear power plants based on collective decision making

International Nuclear Information System (INIS)

Shimizu, Shunichi; Sakurai, Shoji; Takaoka, Kazushi; Kanemoto, Shigeru; Fukutomi, Shigeki

1992-01-01

Inspection and maintenance planning in nuclear power plants is conducted by decision making based on experts' collective consensus. However, since a great deal of time and effort is required to reach a consensus among expert judgments, the establishment of effective decision making methods is necessary. Therefore, the authors developed a method for supporting collective decision making, based on a combination of three types of decision making methods; the Characteristic Diagram method, Interpretative Structural Modeling method, and the Analytic Hierarchy Process method. The proposed method enables us to determine the evaluation criteria systematically for collective decision making, and also allows extracting collective decisions using simplified questionnaires. The proposed method can support reaching a consensus of groups effectively through the evaluation of collective decision structural models and their characteristics. In this paper, the effectiveness of the proposed method was demonstrated through its application to the decision making problem concerning whether or not the improved ultrasonic testing equipment should be adopted at nuclear power plants. (author)

Rigid inclusions-Comparison between analytical and numerical methods

International Nuclear Information System (INIS)

Gomez Perez, R.; Melentijevic, S.

2014-01-01

This paper compares different analytical methods for analysis of rigid inclusions with finite element modeling. First of all, the load transfer in the distribution layer is analyzed for its different thicknesses and different inclusion grids to define the range between results obtained by analytical and numerical methods. The interaction between the soft soil and the inclusion in the estimation of settlements is studied as well. Considering different stiffness of the soft soil, settlements obtained analytical and numerically are compared. The influence of the soft soil modulus of elasticity on the neutral point depth was also performed by finite elements. This depth has a great importance for the definition of the total length of rigid inclusion. (Author)

Nuclear activation analysis work at Analytical Chemistry Division: an overview

International Nuclear Information System (INIS)

Verma, R.; Swain, K.K.; Remya Devi, P.S.; Dalvi, Aditi A.; Ajith, Nicy; Ghosh, M.; Chowdhury, D.P.; Datta, J.; Dasgupta, S.

2016-04-01

Nuclear activation analysis using neutron and charged particles is used routinely for analysis and research at Analytical Chemistry Division (ACD), Bhabha Atomic Research Centre (BARC). Neutron activation analysis at ACD, BARC, Mumbai, India has been pursued since late fifties using Apsara, CIRUS, Dhruva and Critical facility Research reactors, 239 Pu-Be neutron source and neutron generator. Instrumental, Radiochemical, Chemical and Derivative neutron activation analysis approaches are adopted depending on the analyte and the matrix. Large sample neutron activation analysis as well as k 0 -based internal monostandard neutron activation analysis is also used. Charged particle activation analysis at ACD, Variable Energy Cyclotron Centre (VECC), Kolkata started in late eighties and is being used for industrial applications and research. Proton, alpha, deuteron and heavy ion beams from 224 cm room temperature Variable Energy Cyclotron are used for determination of trace elements, measurement of excitation function, thin layer activation and preparation of endohedral fullerenes encapsulated with radioactive isotopes. Analytical Chemistry Division regularly participates in Inter and Intra laboratory comparison exercises conducted by various organizations including International Atomic Energy Agency (IAEA) and the results invariably include values obtained by neutron activation analysis. (author)

The role of nuclear analytical techniques in the study of aqueous corrosion of glasses

International Nuclear Information System (INIS)

Trocellier, P.

1984-01-01

Direct observation of resonant nuclear reactions, backscattering spectrometry and X ray microanalysis with a nuclear microprobe were used to determine elementary depth profiles in the near surface region of leached glasses. Some computing programs required to interpretate the analytical information detected were built. Experimental conditions to characterize glass samples without secondary effects were defined; and the influence of some leaching parameters was studied to describe the first stages of aqueous corrosion of borosilicate glasses [fr

Jet substructure with analytical methods

Energy Technology Data Exchange (ETDEWEB)

Dasgupta, Mrinal [University of Manchester, Consortium for Fundamental Physics, School of Physics and Astronomy, Manchester (United Kingdom); Fregoso, Alessandro; Powling, Alexander [University of Manchester, School of Physics and Astronomy, Manchester (United Kingdom); Marzani, Simone [Durham University, Institute for Particle Physics Phenomenology, Durham (United Kingdom)

2013-11-15

We consider the mass distribution of QCD jets after the application of jet-substructure methods, specifically the mass-drop tagger, pruning, trimming and their variants. In contrast to most current studies employing Monte Carlo methods, we carry out analytical calculations at the next-to-leading order level, which are sufficient to extract the dominant logarithmic behaviour for each technique, and compare our findings to exact fixed-order results. Our results should ultimately lead to a better understanding of these jet-substructure methods which in turn will influence the development of future substructure tools for LHC phenomenology. (orig.)

Experimental and analytical studies on soil-structure interaction behavior of nuclear reactor building

International Nuclear Information System (INIS)

Tsushima, Y.

1978-01-01

The purpose of this study is to estimate damping effects due to soil-structure interaction by the dissipation of vibrational energy to the ground through the foundation in a building with a short fundamental period such as a nuclear reactor building. The author performed experimental and analytical studies on the vibrational characteristics of model steel structures ranging from one to four stories high erected on the rigid base and located on soil, which are simulated from the vibrational characteristics of a prototype reactor building: the former study is to obtain damping effects due to inner friction of steel frames and the latter to obtain radiation damping effects due to soil-structure interaction. The author also touches upon the results of experiments performed on a BWR-type reactor building in 1974, which showed damping ratios higher than 20% of those in fundamental modes. Then the author attempts to estimate the damping effects of the reactor building by his own method proposed in the report. Through these studies the author finally concludes that the experimental damping effects are remarkable in the lower modes by the energy dissipation and the analytical results show a fairly good fit to the experimental ones

Investigation of potential analytical methods for redox control of the vitrification process

International Nuclear Information System (INIS)

Goldman, D.S.

1985-11-01

An investigation was conducted to evaluate several analytical techniques to measure ferrous/ferric ratios in simulated and radioactive nuclear waste glasses for eventual redox control of the vitrification process. Redox control will minimize the melt foaming that occurs under highly oxidizing conditions and the metal precipitation that occurs under highly reducing conditions. The analytical method selected must have a rapid response for production problems with minimal complexity and analyst involvement. The wet-chemistry, Moessbauer spectroscopy, glass color analysis, and ion chromatography techniques were explored, with particular emphasis being placed on the Moessbauer technique. In general, all of these methods can be used for nonradioactive samples. The Moessbauer method can readily analyze glasses containing uranium and thorium. A shielded container was designed and built to analyze fully radioactive glasses with the Moessbauer spectrometer in a hot cell environment. However, analyses conducted with radioactive waste glasses containing 90 Sr and 137 Cs were unsuccessful, presumably due to background radiation problems caused by the samples. The color of glass powder can be used to analyze the ferrous/ferric ratio for low chromium glasses, but this method may not be as precise as the others. Ion chromatography was only tested on nonradioactive glasses, but this technique appears to have the required precision due to its analysis of both Fe +2 and Fe +3 and its anticipated adaptability for radioactivity samples. This development would be similar to procedures already in use for shielded inductively coupled plasma emission (ICP) spectrometry. Development of the ion chromatography method is therefore recommended; conventional wet-chemistry is recommended as a backup procedure

Quality assurance of analytical, scientific, and design computer programs for nuclear power plants

International Nuclear Information System (INIS)

1994-06-01

This Standard applies to the design and development, modification, documentation, execution, and configuration management of computer programs used to perform analytical, scientific, and design computations during the design and analysis of safety-related nuclear power plant equipment, systems, structures, and components as identified by the owner. 2 figs

Quality assurance of analytical, scientific, and design computer programs for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-06-01

This Standard applies to the design and development, modification, documentation, execution, and configuration management of computer programs used to perform analytical, scientific, and design computations during the design and analysis of safety-related nuclear power plant equipment, systems, structures, and components as identified by the owner. 2 figs.

Analytical Methods INAA and PIXE Applied to Characterization of Airborne Particulate Matter in Bandung, Indonesia

Directory of Open Access Journals (Sweden)

D.D. Lestiani

2011-08-01

Full Text Available Urbanization and industrial growth have deteriorated air quality and are major cause to air pollution. Air pollution through fine and ultra-fine particles is a serious threat to human health. The source of air pollution must be known quantitatively by elemental characterization, in order to design the appropriate air quality management. The suitable methods for analysis the airborne particulate matter such as nuclear analytical techniques are hardly needed to solve the air pollution problem. The objectives of this study are to apply the nuclear analytical techniques to airborne particulate samples collected in Bandung, to assess the accuracy and to ensure the reliable of analytical results through the comparison of instrumental neutron activation analysis (INAA and particles induced X-ray emission (PIXE. Particle samples in the PM2.5 and PM2.5-10 ranges have been collected in Bandung twice a week for 24 hours using a Gent stacked filter unit. The result showed that generally there was a systematic difference between INAA and PIXE results, which the values obtained by PIXE were lower than values determined by INAA. INAA is generally more sensitive and reliable than PIXE for Na, Al, Cl, V, Mn, Fe, Br and I, therefore INAA data are preffered, while PIXE usually gives better precision than INAA for Mg, K, Ca, Ti and Zn. Nevertheless, both techniques provide reliable results and complement to each other. INAA is still a prospective method, while PIXE with the special capabilities is a promising tool that could contribute and complement the lack of NAA in determination of lead, sulphur and silicon. The combination of INAA and PIXE can advantageously be used in air pollution studies to extend the number of important elements measured as key elements in source apportionment.

Analytical Methods INAA and PIXE Applied to Characterization of Airborne Particulate Matter in Bandung, Indonesia

International Nuclear Information System (INIS)

Lestiani, D.D.; Santoso, M.

2011-01-01

Urbanization and industrial growth have deteriorated air quality and are major cause to air pollution. Air pollution through fine and ultra-fine particles is a serious threat to human health. The source of air pollution must be known quantitatively by elemental characterization, in order to design the appropriate air quality management. The suitable methods for analysis the airborne particulate matter such as nuclear analytical techniques are hardly needed to solve the air pollution problem. The objectives of this study are to apply the nuclear analytical techniques to airborne particulate samples collected in Bandung, to assess the accuracy and to ensure the reliable of analytical results through the comparison of instrumental neutron activation analysis (INAA) and particles induced X-ray emission (PIXE). Particle samples in the PM 2.5 and PM 2.5-10 ranges have been collected in Bandung twice a week for 24 hours using a Gent stacked filter unit. The result showed that generally there was a systematic difference between INAA and PIXE results, which the values obtained by PIXE were lower than values determined by INAA. INAA is generally more sensitive and reliable than PIXE for Na, Al, Cl, V, Mn, Fe, Br and I, therefore INAA data are preferred, while PIXE usually gives better precision than INAA for Mg, K, Ca, Ti and Zn. Nevertheless, both techniques provide reliable results and complement to each other. INAA is still a prospective method, while PIXE with the special capabilities is a promising tool that could contribute and complement the lack of NAA in determination of lead, sulphur and silicon. The combination of INAA and PIXE can advantageously be used in air pollution studies to extend the number of important elements measured as key elements in source apportionment. (author)

Modern analytic methods applied to the art and archaeology

International Nuclear Information System (INIS)

Tenorio C, M. D.; Longoria G, L. C.

2010-01-01

The interaction of diverse areas as the analytic chemistry, the history of the art and the archaeology has allowed the development of a variety of techniques used in archaeology, in conservation and restoration. These methods have been used to date objects, to determine the origin of the old materials and to reconstruct their use and to identify the degradation processes that affect the integrity of the art works. The objective of this chapter is to offer a general vision on the researches that have been realized in the Instituto Nacional de Investigaciones Nucleares (ININ) in the field of cultural goods. A series of researches carried out in collaboration with national investigators and of the foreigner is described shortly, as well as with the great support of degree students and master in archaeology of the National School of Anthropology and History, since one of the goals that have is to diffuse the knowledge of the existence of these techniques among the young archaeologists, so that they have a wider vision of what they could use in an in mediate future and they can check hypothesis with scientific methods. (Author)

Development of 3D CFD simulation method in nuclear reactor safety analysis

International Nuclear Information System (INIS)

Rosli Darmawan; Mariah Adam

2012-01-01

One of the most prevailing issues in the operation of nuclear reactor is the safety of the system. Worldwide publicity on a few nuclear accidents as well as the notorious Hiroshima and Nagasaki bombing have always brought about public fear on anything related to nuclear. Most findings on the nuclear reactor accidents are closely related to the reactor cooling system. Thus, the understanding of the behaviour of reactor cooling system is very important to ensure the development and improvement on safety can be continuously done. Throughout the development of nuclear reactor technology, investigation and analysis on reactor safety have gone through several phases. In the early days, analytical and experimental methods were employed. For the last three decades 1D system level codes were widely used. The continuous development of nuclear reactor technology has brought about more complex system and processes of nuclear reactor operation. More detailed dimensional simulation codes are needed to assess these new reactors. This paper discusses the development of 3D CFD usage in nuclear reactor safety analysis worldwide. A brief review on the usage of CFD at Malaysia's Reactor TRIGA PUSPATI is also presented. (author)

An Analytical Method to Measure Free-Water Tritium in Foods using Azeotropic Distillation.

Science.gov (United States)

Soga, Keisuke; Kamei, Toshiyuki; Hachisuka, Akiko; Nishimaki-Mogami, Tomoko

2016-01-01

A series of accidents at the Fukushima Dai-ichi Nuclear Power Plant has raised concerns about the discharge of contaminated water containing tritium ((3)H) from the nuclear power plant into the environment and into foods. In this study, we explored convenient analytical methods to measure free-water (3)H in foods using a liquid scintillation counting and azeotropic distillation method. The detection limit was 10 Bq/L, corresponding to about 0.01% of 1 mSv/year. The (3)H recoveries were 85-90% in fruits, vegetables, meats and fishes, 75-85% in rice and cereal crops, and less than 50% in sweets containing little water. We found that, in the case of sweets, adding water to the sample before the azeotropic distillation increased the recovery and precision. Then, the recoveries reached more than 75% and RSD was less than 10% in all food categories (13 kinds). Considering its sensitivity, precision and simplicity, this method is practical and useful for (3)H analysis in various foods, and should be suitable for the safety assessment of foods. In addition, we examined the level of (3)H in foods on the Japanese market. No (3)H radioactivity was detected in any of 42 analyzed foods.

Nuclear methods in environmental and energy research

Energy Technology Data Exchange (ETDEWEB)

Vogt, J. R. [ed.

1977-01-01

The topics considered in the seven sessions were nuclear methods in atmospheric research; nuclear and atomic methodology; nuclear methods in tracer applications; energy exploration, production, and utilization; nuclear methods in environmental monitoring; nuclear methods in water research; and nuclear methods in biological research. Individual abstracts were prepared for each paper. (JSR)

Analytical methods in untargeted metabolomics: state of the art in 2015

Directory of Open Access Journals (Sweden)

Arnald eAlonso

2015-03-01

Full Text Available Metabolomics comprises the methods and techniques that are used to measure the small molecule composition of biofluids and tissues, and is actually one of the most rapidly evolving research fields. The determination of the metabolomic profile –the metabolome- has multiple applications in many biological sciences, including the developing of new diagnostic tools in medicine. Recent technological advances in nuclear magnetic resonance (NMR and mass spectrometry (MS are significantly improving our capacity to obtain more data from each biological sample. Consequently, there is a need for fast and accurate statistical and bioinformatic tools that can deal with the complexity and volume of the data generated in metabolomic studies. In this review we provide an update of the most commonly used analytical methods in metabolomics, starting from raw data processing and ending with pathway analysis and biomarker identification. Finally, the integration of metabolomic profiles with molecular data from other high throughput biotechnologies is also reviewed.

Approaches to characterization of nuclear material for establishment of nuclear forensics

International Nuclear Information System (INIS)

Okazaki, Hiro; Sumi, Mika; Sato, Mitsuhiro; Kayano, Masashi; Kageyama, Tomio; Shinohara, Nobuo; Martinez, Patrick; Xu, Ning; Thomas, Mariam; Porterfield, Donivan; Colletti, Lisa; Schwartz, Dan; Tandon, Lav

2014-01-01

The Plutonium Fuel Development Center (PFDC) of Japan Atomic Energy Agency has been analyzing isotopic compositions and contents of plutonium and uranium as well as trace impurities and physics in the nuclear fuel from MOX fuel fabrication process for accountancy and process control purpose. These analytical techniques are also effective for nuclear forensics to identify such as source, history, and route of the material by determining a composition and characterization of nuclear material. Therefore, PFDC cooperates with Los Alamos National Laboratory which has broad experience and established measurement skill for nuclear forensics, and evaluates the each method, procedure and analytical data toward R and D of characterizing a nuclear material for forensic purposes. This paper describes the approaches to develop characterization techniques of nuclear material for nuclear forensics purposes at PFDC. (author)

Modelling dynamic processes in a nuclear reactor by state change modal method

Science.gov (United States)

Avvakumov, A. V.; Strizhov, V. F.; Vabishchevich, P. N.; Vasilev, A. O.

2017-12-01

Modelling of dynamic processes in nuclear reactors is carried out, mainly, using the multigroup neutron diffusion approximation. The basic model includes a multidimensional set of coupled parabolic equations and ordinary differential equations. Dynamic processes are modelled by a successive change of the reactor states. It is considered that the transition from one state to another occurs promptly. In the modal method the approximate solution is represented as eigenfunction expansion. The numerical-analytical method is based on the use of dominant time-eigenvalues of a group diffusion model taking into account delayed neutrons.

Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013

International Nuclear Information System (INIS)

2013-01-01

The Mathematics and Computation Division of the American Nuclear (ANS) and the Idaho Section of the ANS hosted the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M and C 2013). This proceedings contains over 250 full papers with topics ranging from reactor physics; radiation transport; materials science; nuclear fuels; core performance and optimization; reactor systems and safety; fluid dynamics; medical applications; analytical and numerical methods; algorithms for advanced architectures; and validation verification, and uncertainty quantification

Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-07-01

The Mathematics and Computation Division of the American Nuclear (ANS) and the Idaho Section of the ANS hosted the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M and C 2013). This proceedings contains over 250 full papers with topics ranging from reactor physics; radiation transport; materials science; nuclear fuels; core performance and optimization; reactor systems and safety; fluid dynamics; medical applications; analytical and numerical methods; algorithms for advanced architectures; and validation verification, and uncertainty quantification.

Comparative aseismic response study of different analytical models of nuclear power plant

International Nuclear Information System (INIS)

Takemori, T.; Ogiwara, Y.; Kawakatsu, T.; Abe, Y.; Kitade, K.

1977-01-01

This study consists of two major sections; one is comparison of magnification factor of input acceleration between finite model and spring-mass model, the other is evaluation of modified spring-mass models for aseismic design of nuclear power plant. The structure model used in this study is a P.W.R. reactor containment building composed of the outer shield wall, the steel containment and the internal structure. The rigidity of the foundation rock is represented by shear wave velocity Vs. The magnification of bedrock acceleration at the structure foundation, main floors and free surface of foundation rock are calculated using axisymmetric finite element analytical model with various rock rigidities. The outer shield wall and the steel containment are represented by shell elements, and the internal structure and foundation rock are represented by quadrilateral elements. Each nodal point has four degrees of freedom, in shell element, and three in quadrilateral element. The total degrees of this analytical model are large, so the eigenvalue is calculated by the subspace iterative method. The responses are calculated by time history of acceleration and response spectrum based on the mode superposition method. The spring-mass model is most used in aseismic design for its simplicity. But, if the foundation rock spring is calculated assuming the semi-infinite elastic solid, the analyses of the magnification of acceleration in foundation rock are limited. From the calculated results of the F.E.M. model, the modification of the spring-mass model is estimated, considering the magnification ratio of foundation rock beneath the structure

Analytical N beam position monitor method

Directory of Open Access Journals (Sweden)

A. Wegscheider

2017-11-01

Full Text Available Measurement and correction of focusing errors is of great importance for performance and machine protection of circular accelerators. Furthermore LHC needs to provide equal luminosities to the experiments ATLAS and CMS. High demands are also set on the speed of the optics commissioning, as the foreseen operation with β^{*}-leveling on luminosity will require many operational optics. A fast measurement of the β-function around a storage ring is usually done by using the measured phase advance between three consecutive beam position monitors (BPMs. A recent extension of this established technique, called the N-BPM method, was successfully applied for optics measurements at CERN, ALBA, and ESRF. We present here an improved algorithm that uses analytical calculations for both random and systematic errors and takes into account the presence of quadrupole, sextupole, and BPM misalignments, in addition to quadrupolar field errors. This new scheme, called the analytical N-BPM method, is much faster, further improves the measurement accuracy, and is applicable to very pushed beam optics where the existing numerical N-BPM method tends to fail.

Analytical N beam position monitor method

Science.gov (United States)

Wegscheider, A.; Langner, A.; Tomás, R.; Franchi, A.

2017-11-01

Measurement and correction of focusing errors is of great importance for performance and machine protection of circular accelerators. Furthermore LHC needs to provide equal luminosities to the experiments ATLAS and CMS. High demands are also set on the speed of the optics commissioning, as the foreseen operation with β*-leveling on luminosity will require many operational optics. A fast measurement of the β -function around a storage ring is usually done by using the measured phase advance between three consecutive beam position monitors (BPMs). A recent extension of this established technique, called the N-BPM method, was successfully applied for optics measurements at CERN, ALBA, and ESRF. We present here an improved algorithm that uses analytical calculations for both random and systematic errors and takes into account the presence of quadrupole, sextupole, and BPM misalignments, in addition to quadrupolar field errors. This new scheme, called the analytical N-BPM method, is much faster, further improves the measurement accuracy, and is applicable to very pushed beam optics where the existing numerical N-BPM method tends to fail.

Systems and Methods for Composable Analytics

Science.gov (United States)

2014-04-29

simplistic module that performs a mathematical operation on two numbers. The most important method is the Execute() method. This will get called when it is...addition, an input control is also specified in the example below. In this example, the mathematical operator can only be chosen from a preconfigured...approaches. Some of the industries that could benefit from Composable Analytics include pharmaceuticals, health care, insurance, actuaries , and

Nuclear analytical techniques applied to forensic chemistry

International Nuclear Information System (INIS)

Nicolau, Veronica; Montoro, Silvia; Pratta, Nora; Giandomenico, Angel Di

1999-01-01

Gun shot residues produced by firing guns are mainly composed by visible particles. The individual characterization of these particles allows distinguishing those ones containing heavy metals, from gun shot residues, from those having a different origin or history. In this work, the results obtained from the study of gun shot residues particles collected from hands are presented. The aim of the analysis is to establish whether a person has shot a firing gun has been in contact with one after the shot has been produced. As reference samples, particles collected hands of persons affected to different activities were studied to make comparisons. The complete study was based on the application of nuclear analytical techniques such as Scanning Electron Microscopy, Energy Dispersive X Ray Electron Probe Microanalysis and Graphite Furnace Atomic Absorption Spectrometry. The essays allow to be completed within time compatible with the forensic requirements. (author)

7 CFR 93.13 - Analytical methods.

Science.gov (United States)

2010-01-01

... No. 1, USDA, Agricultural Marketing Service, Science and Technology, 3521 South Agriculture Building... 7 Agriculture 3 2010-01-01 2010-01-01 false Analytical methods. 93.13 Section 93.13 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Standards...

Secondary waste minimization in analytical methods

International Nuclear Information System (INIS)

Green, D.W.; Smith, L.L.; Crain, J.S.; Boparai, A.S.; Kiely, J.T.; Yaeger, J.S.; Schilling, J.B.

1995-01-01

The characterization phase of site remediation is an important and costly part of the process. Because toxic solvents and other hazardous materials are used in common analytical methods, characterization is also a source of new waste, including mixed waste. Alternative analytical methods can reduce the volume or form of hazardous waste produced either in the sample preparation step or in the measurement step. The authors are examining alternative methods in the areas of inorganic, radiological, and organic analysis. For determining inorganic constituents, alternative methods were studied for sample introduction into inductively coupled plasma spectrometers. Figures of merit for the alternative methods, as well as their associated waste volumes, were compared with the conventional approaches. In the radiological area, the authors are comparing conventional methods for gross α/β measurements of soil samples to an alternative method that uses high-pressure microwave dissolution. For determination of organic constituents, microwave-assisted extraction was studied for RCRA regulated semivolatile organics in a variety of solid matrices, including spiked samples in blank soil; polynuclear aromatic hydrocarbons in soils, sludges, and sediments; and semivolatile organics in soil. Extraction efficiencies were determined under varying conditions of time, temperature, microwave power, moisture content, and extraction solvent. Solvent usage was cut from the 300 mL used in conventional extraction methods to about 30 mL. Extraction results varied from one matrix to another. In most cases, the microwave-assisted extraction technique was as efficient as the more common Soxhlet or sonication extraction techniques

Nuclear methods in environmental and energy research

Energy Technology Data Exchange (ETDEWEB)

Vogt, J R [ed.

1980-01-01

A total of 75 papers were presented on nuclear methods for analysis of environmental and biological samples. Sessions were devoted to software and mathematical methods; nuclear methods in atmospheric and water research; nuclear and atomic methodology; nuclear methods in biology and medicine; and nuclear methods in energy research.

Nuclear methods in environmental and energy research

International Nuclear Information System (INIS)

Vogt, J.R.

1980-01-01

A total of 75 papers were presented on nuclear methods for analysis of environmental and biological samples. Sessions were devoted to software and mathematical methods; nuclear methods in atmospheric and water research; nuclear and atomic methodology; nuclear methods in biology and medicine; and nuclear methods in energy research

Impurities determination on nuclear fuel element components for the IEA-R1 research reactor by analytical methods based on ED-XRF and ICP-OES

International Nuclear Information System (INIS)

Reis, Edson Luis Tocaia dos; Scapin, Marcos; Cotrim, Marycel Elena Barboza; Salvador, Vera Lucia; Pires, Maria Aparecida Faustino

2009-01-01

The production of nuclear fuel used in the research reactor at Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP) requires a series of chemical and metallurgical processes. The quality of the end product depends on the control over all the stages of the manufacturing process and over the quality of raw materials employed. In fact, spectrometric methods are increasingly used as quantitative analytical techniques applicable to uranium compounds because of simultaneous determination of several elements with minimum amounts of sample. However, the main obstacle of uranium compounds analysis by spectrometric techniques such as optical emission spectrometry with inductively coupled plasma (ICP-OES) is the complex emission spectrum of uranium. The ICP-OES is not appropriately capable of determining the major elements of interest without initial chemical separation of uranium. In this sense, the use of X-ray fluorescence spectrometry (XRF) has been considered for quantitative determination of main elements with the advantage of not being destructive and not requiring a prior preparation of samples for analysis. Due to the simplicity of this technique, its applicability includes research and quality control in universities, research institutions, petrochemical industries, metallurgy, mining, etc. In this work, some components considered impurities in nuclear fuel element samples used in the IEA-R1 research reactor of IPEN/CNEN-SP were chemically characterized by ICP-OES analysis after chromatography extraction separation by using TBP/XAD-14 system and compared to results obtained by energy dispersive X-ray fluorescence spectrometry (EDXRF) and wavelength dispersive X-ray fluorescence (WDXRF). (author)

Analytical method for solving radioactive transformations

International Nuclear Information System (INIS)

Vudakin, Z.

1999-01-01

Analytical method for solving radioactive transformations is presented in this paper. High accuracy series expansion of the depletion function and nonsingular Bateman coefficients are used to overcome numerical difficulties when applying well-known Bateman solution of a simple radioactive decay. Generality and simplicity of the method are found to be useful in evaluating nuclide chains with one hundred or more nuclides in the chain. Method enables evaluation of complete chain, without elimination of short-lives nuclides. It is efficient and accurate

Analytical methods and problems for the diamides type of extractants

International Nuclear Information System (INIS)

Cuillerdier, C.; Nigond, L.; Musikas, C.; Vitart, H.; Hoel, P.

1989-01-01

Diamides of carboxylic acids and especially malonamides are able to extract alpha emitters (including trivalent ions such as Am and Cm) contained in the wastes solutions of the nuclear industry. As they are completely incinerable and easy to purify, they could be an alternative to the mixture CMPO-TBP which is used in the TRUEX process. A large oxyalkyl radical enhances the distribution coefficients of americium in nitric acid sufficiently to permit the decontamination of wastes solutions in a classical mixers-settlers battery. Now researches are pursued with the aim of optimizing the formula of extractant, the influence of the structure of the extractant on its basicity and stability under radiolysis and hydrolysis is investigated. Analytical methods (potentiometry and NMR of C 13 ) have been developed for solvent titration and to evaluate the percentage of degradation and to identify some of the degradation products

A New Method to Study Analytic Inequalities

Directory of Open Access Journals (Sweden)

Xiao-Ming Zhang

2010-01-01

Full Text Available We present a new method to study analytic inequalities involving n variables. Regarding its applications, we proved some well-known inequalities and improved Carleman's inequality.

Application of nuclear-physical methods for studies in the solid state physics area

International Nuclear Information System (INIS)

Gorlachrv, I.D.; Knyazev, B.B.; Platov, A.B.

2004-01-01

The set of nuclear-physical methods developed on the heavy ion accelerator at the Institute of Nuclear Physics of the National Nuclear Center of the Republic of Kazakhstan allows to conduct an examination of elementary content as well as to obtain the elements distribution in a sample in their depth and surface. This information could be very important for study of samples wide range integral parameters and the characteristics of sputtered layers and implanted films. The beam analysis methods, as well as Rutherford backscattering methods (RBS), nuclear reaction analysis (NRA), proton-induced X-ray emission analysis (PIXE) are included in the complex structure. Besides for expand an analyzed elements range and precision increase for quantitative characteristics of elementarily content of samples the X-ray florescent analysis method with isotope excitation (RFA) is using in the capacity complementary PIXE method. Modernization of proton beam transportation system at the heavy ion accelerator allows to develop a new analytical trend - combination of the proton micro-probe with PIXE analysis. In this case the information about examined sample elementary content is within size field ∼10 μm. The beam scanning by the surface is allowing to obtain the elements distribution by the two spatial coordinates connected with the surface. This information may be useful in the case of an existence of a micro-inclusions in the sample

2. Scientific meeting of Chilean Nuclear Energy Commission. Abstracts; Segundas jornadas cientificas de la Comision Chilena de Energia Nuclear. Resumenes

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-10-01

This publication includes 33 papers in the fields on analytical methods nuclear and conventional, atomic and molecular physics, ionizing radiations, nuclear and non nuclear materials, radiological protection and nuclear safety.

Calculations of hydrogen detonations in nuclear containments by the random choice method

International Nuclear Information System (INIS)

Delichatsios, M.A.; Genadry, M.B.

1983-01-01

Computer codes were developed for the prediction of pressure histories at different points of a nuclear containment wall due to postulated internal hydrogen detonations. These pressure histories are required to assess the structural response of a nuclear containment to hydrogen detonations. The compressible flow equations including detonation, which was treated as a sharp fluid discontinuity, were solved by the random choice method which reproduces maximum pressures and discontinuities sharply. The computer codes were validated by calculating pressure profiles and maximum wall pressures for plane and spherical geometries and comparing the results with exact analytic solutions. The two-dimensional axisymmetric program was used to calculate wall pressure histories in an actual nuclear containment. The numerical results for wall pressures are presented in a dimensionless form, which allows their use for different combinations of hydrogen concentration, and initial conditions. (orig.)

Study on the analytical methods to evaluate the interaction effects of embedded nuclear power plants

International Nuclear Information System (INIS)

Fukuzawa, R.; Chiba, O.; Tohdo, M.; Hatori, T.

1987-01-01

For the seismic response analyses of nuclear power plants which are more or less embedded into soil medium, it is very important to evaluate the interactive effects on the interface between soil and foundation wall, such as wave propagation to infinity radiated from the side wall. The methods generally used in these analyses can be classified into the two basic procedures. One is the direct procedure in which a structure and soil are medeled together into finite elements or beam elements having the quiet boundary; transmitting boundary, non-reflecting boundary. The other is the substructure procedure in which the computational procedure is divided into two steps. In the first step the behavior of massless foundation due to an external force and seismic motion under the assumption as rigid foundation is analyzed, and the results are represented by impedance functions and foundation input motions. Using the results, the structural response analyses are performed. Taking the substructure procedure for seismic response analyses of embedded nuclear power plants, it is the purpose of this paper to present the features of solutions on impedance functions and foundation input motions obtained by various methods such as 3- or 2-dimensional approach, and their influences on structural responses

Xenon spatial oscillation in nuclear power reactors:an analytical approach through non linear modal analysis

International Nuclear Information System (INIS)

Suarez Antola, R.

2005-01-01

It was proponed recently to apply an extension of Lyapunov's first method to the non-linear regime, known as non-linear modal analysis (NMA), to the study of space-time problems in nuclear reactor kinetics, nuclear power plant dynamics and nuclear power plant instrumentation and control(1). The present communication shows how to apply NMA to the study of Xenon spatial oscillations in large nuclear reactors. The set of non-linear modal equations derived by J. Lewins(2) for neutron flux, Xenon concentration and Iodine concentration are discussed, and a modified version of these equations is taken as a starting point. Using the methods of singular perturbation theory a slow manifold is constructed in the space of mode amplitudes. This allows the reduction of the original high dimensional dynamics to a low dimensional one. It is shown how the amplitudes of the first mode for neutron flux field, temperature field and concentrations of Xenon and Iodine fields can have a stable steady state value while the corresponding amplitudes of the second mode oscillates in a stable limit cycle. The extrapolated dimensions of the reactor's core are used as bifurcation parameters. Approximate analytical formulae are obtained for the critical values of this parameters( below which the onset of oscillations is produced), for the period and for the amplitudes of the above mentioned oscillations. These results are applied to the discussion of neutron flux and temperature excursions in critical locations of the reactor's core. The results of NMA can be validated from the results obtained applying suitable computer codes, using homogenization theory(3) to link the complex heterogeneous model of the codes with the simplified mathematical model used for NMA

Analytical mass formula and nuclear surface properties in the ETF approximation. Part II: asymmetric nuclei

Science.gov (United States)

Aymard, François; Gulminelli, Francesca; Margueron, Jérôme

2016-08-01

We have recently addressed the problem of the determination of the nuclear surface energy for symmetric nuclei in the framework of the extended Thomas-Fermi (ETF) approximation using Skyrme functionals. We presently extend this formalism to the case of asymmetric nuclei and the question of the surface symmetry energy. We propose an approximate expression for the diffuseness and the surface energy. These quantities are analytically related to the parameters of the energy functional. In particular, the influence of the different equation of state parameters can be explicitly quantified. Detailed analyses of the different energy components (local/non-local, isoscalar/isovector, surface/curvature and higher order) are also performed. Our analytical solution of the ETF integral improves previous models and leads to a precision of better than 200 keV per nucleon in the determination of the nuclear binding energy for dripline nuclei.

Nuclear methods for tribology

International Nuclear Information System (INIS)

Racolta, P.M.

1994-01-01

The tribological field of activity is mainly concerned with the relative movement of different machine components, friction and wear phenomena and their dependence upon lubrication. Tribological studies on friction and wear processes are important because they lead to significant parameter-improvements of engineering tools and machinery components. A review of fundamental aspects of both friction and wear phenomena is presented. A number of radioindicator-based methods have been known for almost four decades, differing mainly with respect to the mode of introducing the radio-indicators into the machine part to be studied. All these methods briefly presented in this paper are based on the measurement of the activity of wear products and therefore require high activity levels of the part. For this reason, such determinations can be carried out only in special laboratories and under conditions which do not usually agree with the conditions of actual use. What is required is a sensitive, fast method allowing the determination of wear under any operating conditions, without the necessity of stopping and disassembling the machine. The above mentioned requirements are the features that have made the Thin Layer Activation technique (TLA) the most widely used method applied in wear and corrosion studies in the last two decades. The TLA principle, taking in account that wear and corrosion processes are characterised by a loss of material, consists in an ion beam irradiation of a well defined volume of a machine part subjected to wear. The radioactivity level changes can usually be measured by gamma-ray spectroscopy methods. A review of both main TLA fields of application in major laboratories abroad and of those performed at the U-120 cyclotron of I.P.N.E.-Bucharest together with the existing trends to extend other nuclear analytical methods to tribological studies is presented as well. (author). 25 refs., 6 figs., 2 tabs

Role of thermo-analytical techniques in compositional characterization of nuclear materials

International Nuclear Information System (INIS)

Raje, Naina

2015-01-01

The study of heat effects on different materials has a long history. Extraction of metals from the ores, pottery production, glasses making etc. are the examples, where the performance of products obtained from raw materials depends on the processing temperatures. Concrete, pottery, bricks etc., are severely damaged due to uncontrolled high temperatures. Therefore, the heating of raw materials in controlled manner is of pivotal importance to get products of the desired quality. Thermo-analytical techniques provide the information on the effect of heat under controlled heating conditions. In thermo-analytical techniques, physical properties of materials are measured as a function of temperature. Simultaneous thermo-analytical techniques are beneficial in comparison to any single thermo-analytical technique. Simultaneous techniques refer to the measurement of two or more signals on the same sample at the same time in the same instrument. Nowadays, simultaneous thermo-analytical technique are extensively in use for the analysis of materials. Ammonium diuranate (ADU) and magnesium diuranate (MDU), also known as yellowcake, are intermediate precursors in fuel fabrication process, with stringent specifications along with the need to understand its thermal behavior. In the processing of lowgrade ores, higher levels of impurities are being encountered in the leach solution that affects the properties of ADU/MDU. In order to meet the fuel specifications, quality assurance of these nuclear materials is essential. Current studies describe the application of simultaneous Thermogravimetry (TG) - differential thermal analysis (DTA) - evolved gas analysis (EGA) techniques for the compositional characterization of ADU/MDU with respect to the impurities present in the matrices

Surface analytical methods in nuclear technology

International Nuclear Information System (INIS)

Baumgaertner, F.

1985-06-01

Application of SEM-EDX, AES, XPS are exemplarily demonstrated for highly radioactive materials with ionizing dose rates of about 1 Sv near the surface. The samples studied are aerosols from the high level waste vitrification process, postprecipitation in a pretreated fuel solution and emulsifying sludge from a solvent extraction process. The results of the chemical composition differentiated down to microscopic level reveal much more information about the history of a sample than those available from the integral macro-methods analysing. Elucidication of chemical composition and body structure in micrometer level may give insight into the origin and generation processes of samples under investigation. (orig.)

Statistical methods for nuclear material management

International Nuclear Information System (INIS)

Bowen, W.M.; Bennett, C.A.

1988-12-01

This book is intended as a reference manual of statistical methodology for nuclear material management practitioners. It describes statistical methods currently or potentially important in nuclear material management, explains the choice of methods for specific applications, and provides examples of practical applications to nuclear material management problems. Together with the accompanying training manual, which contains fully worked out problems keyed to each chapter, this book can also be used as a textbook for courses in statistical methods for nuclear material management. It should provide increased understanding and guidance to help improve the application of statistical methods to nuclear material management problems

Statistical methods for nuclear material management

Energy Technology Data Exchange (ETDEWEB)

Bowen W.M.; Bennett, C.A. (eds.)

1988-12-01

This book is intended as a reference manual of statistical methodology for nuclear material management practitioners. It describes statistical methods currently or potentially important in nuclear material management, explains the choice of methods for specific applications, and provides examples of practical applications to nuclear material management problems. Together with the accompanying training manual, which contains fully worked out problems keyed to each chapter, this book can also be used as a textbook for courses in statistical methods for nuclear material management. It should provide increased understanding and guidance to help improve the application of statistical methods to nuclear material management problems.

Quantifying the measurement uncertainty of results from environmental analytical methods.

Science.gov (United States)

Moser, J; Wegscheider, W; Sperka-Gottlieb, C

2001-07-01

The Eurachem-CITAC Guide Quantifying Uncertainty in Analytical Measurement was put into practice in a public laboratory devoted to environmental analytical measurements. In doing so due regard was given to the provisions of ISO 17025 and an attempt was made to base the entire estimation of measurement uncertainty on available data from the literature or from previously performed validation studies. Most environmental analytical procedures laid down in national or international standards are the result of cooperative efforts and put into effect as part of a compromise between all parties involved, public and private, that also encompasses environmental standards and statutory limits. Central to many procedures is the focus on the measurement of environmental effects rather than on individual chemical species. In this situation it is particularly important to understand the measurement process well enough to produce a realistic uncertainty statement. Environmental analytical methods will be examined as far as necessary, but reference will also be made to analytical methods in general and to physical measurement methods where appropriate. This paper describes ways and means of quantifying uncertainty for frequently practised methods of environmental analysis. It will be shown that operationally defined measurands are no obstacle to the estimation process as described in the Eurachem/CITAC Guide if it is accepted that the dominating component of uncertainty comes from the actual practice of the method as a reproducibility standard deviation.

FAPIG's activities for public acceptance of nuclear energy. Analytical results of questionnaire executed at organized visits to nuclear power stations

International Nuclear Information System (INIS)

Mizoguchi, Tadao

1999-01-01

FAPIG organizes a visit to nuclear power station in every November. It is an object that visitors acquire the correct knowledge of nuclear power by looking at the various facilities in the nuclear power stations. The paper showed the analytical results of questionnaire executed at organized visits to the Kashiwazaki-Kariwa nuclear power station. The visitors were 18 women. The questionnaire was carried out by the same problems before and after seminar and a conducted tour. Their impressions and opinions and the changes are analyzed. The speakers used easy words, video, OHP, pamphlet and experimental equipment. These means showed very good results to visitors. The seminar had very large effect on just recognition of safety and need of it. The change of answer proved from 3 to 6 of need and from 0 to 7 of safety of it. Nine members indicated good understanding of seminar content. The interested items in the seminar were measurement of radiation, effects of radiation, reason of decreasing average life, Chernobyl accident, difference between nuclear power and atomic bomb and nuclear power dose not generate carbon dioxide and recycle plutonium after nuclear fission of uranium. (S.Y.)

Analytical one-dimensional frequency response and stability model for PWR nuclear power plants

International Nuclear Information System (INIS)

Hoeld, A.

1975-01-01

A dynamic model for PWR nuclear power plants is presented. The plant is assumed to consist of one-dimensional single-channel core, a counterflow once-through steam generator (represented by two nodes according to the nonboiling and boiling region) and the necessary connection coolant lines. The model describes analytically the frequency response behaviour of important parameters of such a plant with respect to perturbations in reactivity, subcooling or mass flow (both at the entrances to the reactor core and/or the secondary steam generator side), the perturbations in steam load or system pressure (on the secondary side of the steam generator). From corresponding 'open' loop considerations it can then be concluded - by applying the Nyquist criterion - upon the degree of the stability behaviour of the underlying system. Based on this theoretical model, a computer code named ADYPMO has been established. From the knowledge of the frequency response behaviour of such a system, the corresponding transient behaviour with respect to a stepwise or any other perturbation signal can also be calculated by applying an appropriate retransformation method, e.g. by using digital code FRETI. To demonstrate this procedure, a transient experimental curve measured during the pre-operational test period at the PWR nuclear power plant KKS Stade was recalculated using the combination ADYPMO-FRETI. Good agreement between theoretical calculations and experimental results give an insight into the validity and efficiency of the underlying theoretical model and the applied retransformation method. (Auth.)

Teaching Analytical Method Transfer through Developing and Validating Then Transferring Dissolution Testing Methods for Pharmaceuticals

Science.gov (United States)

Kimaru, Irene; Koether, Marina; Chichester, Kimberly; Eaton, Lafayette

2017-01-01

Analytical method transfer (AMT) and dissolution testing are important topics required in industry that should be taught in analytical chemistry courses. Undergraduate students in senior level analytical chemistry laboratory courses at Kennesaw State University (KSU) and St. John Fisher College (SJFC) participated in development, validation, and…

Nuclear analytical techniques for nanotoxicology studies

International Nuclear Information System (INIS)

Zhang, Z.Y.; Zhao, Y.L.; Chai, Z.F.

2011-01-01

With the rapid development of nanotechnology and its applications, a wide variety of nanomaterials are now used in commodities, pharmaceutics, cosmetics, biomedical products, and industries. The potential interactions of nanomaterials with living systems and the environment have attracted increasing attention from the public, as well as from manufacturers of nanomaterial-based products, academic researchers and policymakers. It is important to consider the environmental, health and safety aspects at an early stage of nanomaterial development and application in order to more effectively identify and manage potential human and environmental health impacts from nanomaterial exposure. This will require research in a range of areas, including detection and characterization, environmental fate and transport, ecotoxicology and toxicology. Nuclear analytical techniques (NATs) can play an important role in such studies due to their intrinsic merits such as high sensitivity, good accuracy, high space resolution, ability to distinguish the endogenous or exogenous sources of materials, and ability of in situ and in vivo analysis. In this paper, the applications of NATs in nanotoxicological and nano-ecotoxicological studies are outlined, and some recent results obtained in our laboratory are reported. (orig.)

Recent developments in analytical detection methods for radiation processed foods

International Nuclear Information System (INIS)

Wu Jilan

1993-01-01

A short summary of the programmes of 'ADMIT' (FAO/IAEA) and the developments in analytical detection methods for radiation processed foods has been given. It is suggested that for promoting the commercialization of radiation processed foods and controlling its quality, one must pay more attention to the study of analytical detection methods of irradiated food

Biomonitoring of air pollution in Jamaica through trace-element analysis of epiphytic plants using nuclear and related analytical techniques

International Nuclear Information System (INIS)

Vutchkov, Mitko

2001-01-01

The main goal of the Coordinated Research Project (No:9937/R0), entitled 'Biomonitoring of Air Pollution in Jamaica Through Trace-Element Analysis of Epiphytic Plants Using Nuclear and Related Analytical Techniques', is to identify and validate site specific epiphytic plants for biomonitoring the atmospheric pollution in Jamaica using nuclear analytical techniques at the International Centre for Environmental and Nuclear Sciences (ICENS). The specific objectives for the second year of the project were: Development of HOP for sampling epiphytic plants in Jamaica; Sampling design and sample collection; Sample preparation and analysis; Development of an in-house SRM and participation in the NAT-5 inter-laboratory study; Data analysis and interpretation of the results; Development of a work plan of the third year of the project

Annual Report of Institute of Nuclear Chemistry and Technology 2001

International Nuclear Information System (INIS)

2002-06-01

The INCT 2001 Annual Report is the review of scientific activities in all branches being developed in the Institute of Nuclear Chemistry and Technology in Warsaw. The studies are connected in general with the following fields: radiation chemistry and physics, radiation technologies, radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general, radiobiology, process engineering, material engineering, structural studies and diagnostics, nucleonic control systems and accelerators and nuclear analytical methods

Annual Report 2004 of Institute of Nuclear Chemistry and Technology

International Nuclear Information System (INIS)

Michalik, J.; Smulek, W.; Godlewska-Para, E.

2005-06-01

The INCT 2004 Annual Report is the review of scientific activities in all branches being developed in the Institute of Nuclear Chemistry and Technology Warsaw. The studies are connected in general with the following fields: radiation chemistry and physics, radiation technologies, radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general, radiobiology, process engineering, material engineering, structural studies and diagnostics, nucleonic control systems and accelerators, radiobiology and nuclear analytical methods

Annual Report 2004 of Institute of Nuclear Chemistry and Technology

Energy Technology Data Exchange (ETDEWEB)

Michalik, J; Smulek, W; Godlewska-Para, E [eds.

2005-06-01

The INCT 2004 Annual Report is the review of scientific activities in all branches being developed in the Institute of Nuclear Chemistry and Technology Warsaw. The studies are connected in general with the following fields: radiation chemistry and physics, radiation technologies, radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general, radiobiology, process engineering, material engineering, structural studies and diagnostics, nucleonic control systems and accelerators, radiobiology and nuclear analytical methods.

Annual Report of Institute of Nuclear Chemistry and Technology 2001

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-06-01

The INCT 2001 Annual Report is the review of scientific activities in all branches being developed in the Institute of Nuclear Chemistry and Technology in Warsaw. The studies are connected in general with the following fields: radiation chemistry and physics, radiation technologies, radiochemistry, stable isotopes, nuclear analytical methods, chemistry in general, radiobiology, process engineering, material engineering, structural studies and diagnostics, nucleonic control systems and accelerators and nuclear analytical methods.

Analytical method comparisons for the accurate determination of PCBs in sediments

Energy Technology Data Exchange (ETDEWEB)

Numata, M.; Yarita, T.; Aoyagi, Y.; Yamazaki, M.; Takatsu, A. [National Metrology Institute of Japan, Tsukuba (Japan)

2004-09-15

National Metrology Institute of Japan in National Institute of Advanced Industrial Science and Technology (NMIJ/AIST) has been developing several matrix reference materials, for example, sediments, water and biological tissues, for the determinations of heavy metals and organometallic compounds. The matrix compositions of those certified reference materials (CRMs) are similar to compositions of actual samples, and those are useful for validating analytical procedures. ''Primary methods of measurements'' are essential to obtain accurate and SI-traceable certified values in the reference materials, because the methods have the highest quality of measurement. However, inappropriate analytical operations, such as incomplete extraction of analytes or crosscontamination during analytical procedures, will cause error of analytical results, even if one of the primary methods, isotope-dilution, is utilized. To avoid possible procedural bias for the certification of reference materials, we employ more than two analytical methods which have been optimized beforehand. Because the accurate determination of trace POPs in the environment is important to evaluate their risk, reliable CRMs are required by environmental chemists. Therefore, we have also been preparing matrix CRMs for the determination of POPs. To establish accurate analytical procedures for the certification of POPs, extraction is one of the critical steps as described above. In general, conventional extraction techniques for the determination of POPs, such as Soxhlet extraction (SOX) and saponification (SAP), have been characterized well, and introduced as official methods for environmental analysis. On the other hand, emerging techniques, such as microwave-assisted extraction (MAE), pressurized fluid extraction (PFE) and supercritical fluid extraction (SFE), give higher recovery yields of analytes with relatively short extraction time and small amount of solvent, by reasons of the high

Extension of the analytic nodal method to four energy groups

International Nuclear Information System (INIS)

Parsons, D.K.; Nigg, D.W.

1985-01-01

The Analytic Nodal Method is one of several recently-developed coarse mesh numerical methods for efficiently and accurately solving the multidimensional static and transient neutron diffusion equations. This summary describes a mathematically rigorous extension of the Analytic Nodal Method to the frequently more physically realistic four-group case. A few general theoretical considerations are discussed, followed by some calculated results for a typical steady-state two-dimensional PWR quarter core application. 8 refs

Vertical equilibrium with sub-scale analytical methods for geological CO2 sequestration

KAUST Repository

Gasda, S. E.; Nordbotten, J. M.; Celia, M. A.

2009-01-01

equilibrium with sub-scale analytical method (VESA) combines the flexibility of a numerical method, allowing for heterogeneous and geologically complex systems, with the efficiency and accuracy of an analytical method, thereby eliminating expensive grid

Application of an analytical method for solution of thermal hydraulic conservation equations

Energy Technology Data Exchange (ETDEWEB)

Fakory, M.R. [Simulation, Systems & Services Technologies Company (S3 Technologies), Columbia, MD (United States)

1995-09-01

An analytical method has been developed and applied for solution of two-phase flow conservation equations. The test results for application of the model for simulation of BWR transients are presented and compared with the results obtained from application of the explicit method for integration of conservation equations. The test results show that with application of the analytical method for integration of conservation equations, the Courant limitation associated with explicit Euler method of integration was eliminated. The results obtained from application of the analytical method (with large time steps) agreed well with the results obtained from application of explicit method of integration (with time steps smaller than the size imposed by Courant limitation). The results demonstrate that application of the analytical approach significantly improves the numerical stability and computational efficiency.

Development and Validation of Analytical Method for Losartan ...

African Journals Online (AJOL)

Development and Validation of Analytical Method for Losartan-Copper Complex Using UV-Vis Spectrophotometry. ... Tropical Journal of Pharmaceutical Research ... Purpose: To develop a new spectrophotometric method for the analysis of losartan potassium in pharmaceutical formulations by making its complex with ...

Broyden's method in nuclear structure calculations

International Nuclear Information System (INIS)

Baran, Andrzej; Bulgac, Aurel; Forbes, Michael McNeil; Hagen, Gaute; Nazarewicz, Witold; Schunck, Nicolas; Stoitsov, Mario V.

2008-01-01

Broyden's method, widely used in quantum chemistry electronic-structure calculations for the numerical solution of nonlinear equations in many variables, is applied in the context of the nuclear many-body problem. Examples include the unitary gas problem, the nuclear density functional theory with Skyrme functionals, and the nuclear coupled-cluster theory. The stability of the method, its ease of use, and its rapid convergence rates make Broyden's method a tool of choice for large-scale nuclear structure calculations

2. Scientific meeting of Chilean Nuclear Energy Commission. Abstracts

International Nuclear Information System (INIS)

2000-10-01

This publication includes 33 papers in the fields on analytical methods nuclear and conventional, atomic and molecular physics, ionizing radiations, nuclear and non nuclear materials, radiological protection and nuclear safety

Mathematical methods for physical and analytical chemistry

CERN Document Server

Goodson, David Z

2011-01-01

Mathematical Methods for Physical and Analytical Chemistry presents mathematical and statistical methods to students of chemistry at the intermediate, post-calculus level. The content includes a review of general calculus; a review of numerical techniques often omitted from calculus courses, such as cubic splines and Newton's method; a detailed treatment of statistical methods for experimental data analysis; complex numbers; extrapolation; linear algebra; and differential equations. With numerous example problems and helpful anecdotes, this text gives chemistry students the mathematical

Recent advances in nuclear techniques for environmental radioactivity monitoring

International Nuclear Information System (INIS)

Kumar, Ajay; Tripathi, R.M.

2016-01-01

The environmental radioactivity monitoring was first started in the late 1950s following the global fallout from testing of nuclear weapons in the atmosphere. Nuclear analytical techniques are generally classified into two categories: destructive and non-destructive. Destructive techniques are carried out through several analytical methods such as α-spectrometry, liquid Scintillation counting system, solid state nuclear track detector, spectrophotometry, fluorimetry, atomic absorption spectrometry (AAS), inductively coupled plasma mass spectrometry (ICP-MS), inductively coupled plasma optical emission spectrometry (ICP-OES), chromatography techniques, electro-analytical techniques etc. However, nondestructive methods include gamma spectrometry, X-Ray fluorescence (XRF) spectrometry, neutron activation analysis (NAA) etc. The development of radiochemical methods and measurement techniques using alpha and gamma spectrometry have been described in brief

Application of Wielandt method in continuous-energy nuclear data sensitivity analysis with RMC code

International Nuclear Information System (INIS)

Qiu Yishu; Wang Kan; She Ding

2015-01-01

The Iterated Fission Probability (IFP) method, an accurate method to estimate adjoint-weighted quantities in the continuous-energy Monte Carlo criticality calculations, has been widely used for calculating kinetic parameters and nuclear data sensitivity coefficients. By using a strategy of waiting, however, this method faces the challenge of high memory usage to store the tallies of original contributions which size is proportional to the number of particle histories in each cycle. Recently, the Wielandt method, applied by Monte Carlo code McCARD to calculate kinetic parameters, estimates adjoint fluxes in a single particle history and thus can save memory usage. In this work, the Wielandt method has been applied in Rector Monte Carlo code RMC for nuclear data sensitivity analysis. The methodology and algorithm of applying Wielandt method in estimation of adjoint-based sensitivity coefficients are discussed. Verification is performed by comparing the sensitivity coefficients calculated by Wielandt method with analytical solutions, those computed by IFP method which is also implemented in RMC code for sensitivity analysis, and those from the multi-group TSUNAMI-3D module in SCALE code package. (author)

Hanford environmental analytical methods: Methods as of March 1990

International Nuclear Information System (INIS)

Goheen, S.C.; McCulloch, M.; Daniel, J.L.

1993-05-01

This paper from the analytical laboratories at Hanford describes the method used to measure pH of single-shell tank core samples. Sludge or solid samples are mixed with deionized water. The pH electrode used combines both a sensor and reference electrode in one unit. The meter amplifies the input signal from the electrode and displays the pH visually

Investigation of analytical and experimental behavior of nuclear facility ventilation systems

International Nuclear Information System (INIS)

Smith, P.R.; Ricketts, C.I.; Andrae, R.W.; Bolstad, J.W.; Horak, H.L.; Martin, R.A.; Tang, P.K.; Gregory, W.S.

1979-01-01

The behavior of nuclear facility ventilation systems subjected to both natural and man-caused accidents is being investigated. The purpose of the paper is to present a program overview and highlight recent results of the investigations. The program includes both analytical and experimental investigations. Computer codes for predicting accident-induced gas dynamics and test facilities to obtain supportive experimental data to define structural integrity and confinement effectiveness of ventilation system components are described. A unique test facility and recently obtained structural limits for high efficiency particulate air filters are reported

Analytical methods for determination of mycotoxins: a review.

Science.gov (United States)

Turner, Nicholas W; Subrahmanyam, Sreenath; Piletsky, Sergey A

2009-01-26

Mycotoxins are small (MW approximately 700), toxic chemical products formed as secondary metabolites by a few fungal species that readily colonise crops and contaminate them with toxins in the field or after harvest. Ochratoxins and Aflatoxins are mycotoxins of major significance and hence there has been significant research on broad range of analytical and detection techniques that could be useful and practical. Due to the variety of structures of these toxins, it is impossible to use one standard technique for analysis and/or detection. Practical requirements for high-sensitivity analysis and the need for a specialist laboratory setting create challenges for routine analysis. Several existing analytical techniques, which offer flexible and broad-based methods of analysis and in some cases detection, have been discussed in this manuscript. There are a number of methods used, of which many are lab-based, but to our knowledge there seems to be no single technique that stands out above the rest, although analytical liquid chromatography, commonly linked with mass spectroscopy is likely to be popular. This review manuscript discusses (a) sample pre-treatment methods such as liquid-liquid extraction (LLE), supercritical fluid extraction (SFE), solid phase extraction (SPE), (b) separation methods such as (TLC), high performance liquid chromatography (HPLC), gas chromatography (GC), and capillary electrophoresis (CE) and (c) others such as ELISA. Further currents trends, advantages and disadvantages and future prospects of these methods have been discussed.

A new unextracted-sample radioimmunoassay method for hepatic endogenous nuclear L-tri-iodothyronine content

International Nuclear Information System (INIS)

Yagura, T.; Walfish, P.G.

1982-01-01

Endogenous L-tri-iodothyronine content in an hepatic nuclear extract was measured by a new unextracted-sample radioimmunoassay method using 8-anilinonaphthalene-1-sulphonic acid to inhibit the L-[ 125 I]tri-iodothyronine binding to the nuclear L-tri-iodothyronine receptor within the extract. The amount of endogenous L-tri-iodothyronine was 10-40 pg/0.2 ml of hepatic nuclear extract from euthyroid rats, compared with less than 3.125 pg/0.2ml from thyroidectomized rats. The results obtained were compared with a Sephadex G-25 column extracted-sample radioimmunoassay method and showed a good agreement. The values for the endogenous L-tri-iodothyronine content were utilized to correct for the L-tri-iodothyronine concentration within the binding assay mixture in order to accurately determine by Scatchard analysis the binding characteristics of the nuclear L-tri-iodothyronine receptor. The validity of the correction for endogenous L-tri-iodothyronine was demonstrated by using a nuclear extract from a thyroidectomized rat which was preincubated with a small known amount of L-tri-iodothyronine before determining the nuclear L-tri-iodothyronine receptor binding characteristics. It is concluded that the necessity and validity of using endogenous L-tri-iodothyronine corrections in the Scatchard analytical computations of the nuclear L-tri-iodothyronine receptor binding characteristics has been demonstrated, being particularly more important for affinity constant than maximum binding capacity. (author)

Applied research on air pollution using nuclear-related analytical techniques. Report on the second research co-ordination meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

A co-ordinated research programme (CRP) on applied research on air pollution using nuclear-related techniques is a global CRP which started in 1992, and is scheduled to run until early 1997. The purpose of this CRP is to promote the use of nuclear analytical techniques in air pollution studies, e.g. NAA, XRF, and PIXE for the analysis of toxic and other trace elements in air particulate matter. The main purposes of the core programme are i) to support the use of nuclear and nuclear-related analytical techniques for research and monitoring studies on air pollution, ii) to identify major sources of air pollution affecting each of the participating countries with particular reference to toxic heavy metals, and iii) to obtain comparative data on pollution levels in areas of high pollution (e.g. a city centre or a populated area downwind of a large pollution source) and low pollution (e.g. rural area). This document reports the discussions held during the second Research Co-ordination Meeting (RCM) for the CRP which took place at ANSTO in Menai, Australia. (author)

Applied research on air pollution using nuclear-related analytical techniques. Report on the second research co-ordination meeting

International Nuclear Information System (INIS)

1995-01-01

A co-ordinated research programme (CRP) on applied research on air pollution using nuclear-related techniques is a global CRP which started in 1992, and is scheduled to run until early 1997. The purpose of this CRP is to promote the use of nuclear analytical techniques in air pollution studies, e.g. NAA, XRF, and PIXE for the analysis of toxic and other trace elements in air particulate matter. The main purposes of the core programme are i) to support the use of nuclear and nuclear-related analytical techniques for research and monitoring studies on air pollution, ii) to identify major sources of air pollution affecting each of the participating countries with particular reference to toxic heavy metals, and iii) to obtain comparative data on pollution levels in areas of high pollution (e.g. a city centre or a populated area downwind of a large pollution source) and low pollution (e.g. rural area). This document reports the discussions held during the second Research Co-ordination Meeting (RCM) for the CRP which took place at ANSTO in Menai, Australia. (author)

Characterization of Catalytic Fast Pyrolysis Oils: The Importance of Solvent Selection for Analytical Method Development

Energy Technology Data Exchange (ETDEWEB)

Ferrell, Jack R [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Ware, Anne E [National Renewable Energy Laboratory (NREL), Golden, CO (United States)

2018-02-25

Two catalytic fast pyrolysis (CFP) oils (bottom/heavy fraction) were analyzed in various solvents that are used in common analytical methods (nuclear magnetic resonance - NMR, gas chromatography - GC, gel permeation chromatography - GPC, thermogravimetric analysis - TGA) for oil characterization and speciation. A more accurate analysis of the CFP oils can be obtained by identification and exploitation of solvent miscibility characteristics. Acetone and tetrahydrofuran can be used to completely solubilize CFP oils for analysis by GC and tetrahydrofuran can be used for traditional organic GPC analysis of the oils. DMSO-d6 can be used to solubilize CFP oils for analysis by 13C NMR. The fractionation of oils into solvents that did not completely solubilize the whole oils showed that miscibility can be related to the oil properties. This allows for solvent selection based on physico-chemical properties of the oils. However, based on semi-quantitative comparisons of the GC chromatograms, the organic solvent fractionation schemes did not speciate the oils based on specific analyte type. On the other hand, chlorinated solvents did fractionate the oils based on analyte size to a certain degree. Unfortunately, like raw pyrolysis oil, the matrix of the CFP oils is complicated and is not amenable to simple liquid-liquid extraction (LLE) or solvent fractionation to separate the oils based on the chemical and/or physical properties of individual components. For reliable analyses, for each analytical method used, it is critical that the bio-oil sample is both completely soluble and also not likely to react with the chosen solvent. The adoption of the standardized solvent selection protocols presented here will allow for greater reproducibility of analysis across different users and facilities.

Methodologies for nuclear material accounting and control: challenges and expectations

International Nuclear Information System (INIS)

Ramakumar, K.L.

2007-01-01

Nuclear Material Accounting and Control (NUMAC) represents one of the most important and indispensable responsibilities of any nuclear installation. The emphasis is to ensure that the nuclear material being handled in the nuclear installation is properly accounted for with the expected accuracy and confidence levels. A number of analytical methods based on both destructive and non-destructive assay techniques are available at the disposal of the nuclear analytical scientists for this purpose and they have been enumerated extensively in literature. Instead of recounting the analytical methodologies available, an attempt has been made in this paper to highlight some of the challenges. (author)

Big data analytics methods and applications

CERN Document Server

Rao, BLS; Rao, SB

2016-01-01

This book has a collection of articles written by Big Data experts to describe some of the cutting-edge methods and applications from their respective areas of interest, and provides the reader with a detailed overview of the field of Big Data Analytics as it is practiced today. The chapters cover technical aspects of key areas that generate and use Big Data such as management and finance; medicine and healthcare; genome, cytome and microbiome; graphs and networks; Internet of Things; Big Data standards; bench-marking of systems; and others. In addition to different applications, key algorithmic approaches such as graph partitioning, clustering and finite mixture modelling of high-dimensional data are also covered. The varied collection of themes in this volume introduces the reader to the richness of the emerging field of Big Data Analytics.

An Investigation to Manufacturing Analytical Services Composition using the Analytical Target Cascading Method.

Science.gov (United States)

Tien, Kai-Wen; Kulvatunyou, Boonserm; Jung, Kiwook; Prabhu, Vittaldas

2017-01-01

As cloud computing is increasingly adopted, the trend is to offer software functions as modular services and compose them into larger, more meaningful ones. The trend is attractive to analytical problems in the manufacturing system design and performance improvement domain because 1) finding a global optimization for the system is a complex problem; and 2) sub-problems are typically compartmentalized by the organizational structure. However, solving sub-problems by independent services can result in a sub-optimal solution at the system level. This paper investigates the technique called Analytical Target Cascading (ATC) to coordinate the optimization of loosely-coupled sub-problems, each may be modularly formulated by differing departments and be solved by modular analytical services. The result demonstrates that ATC is a promising method in that it offers system-level optimal solutions that can scale up by exploiting distributed and modular executions while allowing easier management of the problem formulation.

Power systems with nuclear-electric generators - Modelling methods

International Nuclear Information System (INIS)

Valeca, Serban Constantin

2002-01-01

This is a vast analysis on the issue of sustainable nuclear power development with direct conclusions regarding the Nuclear Programme of Romania. The work is targeting specialists and decision making boards. Specific to the nuclear power development is its public implication, the public being most often misinformed by non-professional media. The following problems are debated thoroughly: - safety, nuclear risk, respectively, is treated in chapter 1 and 7 aiming at highlighting the quality of nuclear power and consequently paving the way to public acceptance; - the environment considered both as resource of raw materials and medium essential for life continuation, which should be appropriately protected to ensure healthy and sustainable development of human society; its analysis is also presented in chapter 1 and 7, where the problem of safe management of radioactive waste is addressed too; - investigation methods based on information science of nuclear systems, applied in carrying out the nuclear strategy and planning are widely analyzed in the chapter 2, 3 and 6; - optimizing the processes by following up the structure of investment and operation costs, and, generally, the management of nuclear units is treated in the chapter 5 and 7; - nuclear weapon proliferation as a possible consequence of nuclear power generation is treated as a legal issue. The development of Romanian NPP at Cernavoda, practically, the core of the National Nuclear Programme, is described in chapter 8. Actually, the originality of the present work consists in the selection and adaptation from a multitude of mathematical models applicable to the local and specific conditions of nuclear power plant at Cernavoda. The Romanian economy development and power development oriented towards reduction of fossil fuel consumption and protection of environment, most reliably ensured by the nuclear power, is discussed in the frame of the world trends of the energy production. Various scenarios are

Analytic continuation of scattering data as a method of obtaining characteristics of bound states

International Nuclear Information System (INIS)

Blokhintsev, L.; Savin, D.

2014-01-01

An asymptotic normalization coefficient (ANC) determines the asymptotics of a wave function of a nucleus a in a binary channel b + c. ANCs are proportional to nuclear vertex constants (NVCs), which are on-shell matrix elements of the virtual processes a ↔ b+c. The method of the analytic continuation of the effective range function is applied to obtain the asymptotic normalization coefficients for 6 Li nucleus in the α+ d channel. Several sets of scattering phases obtained from the phase-shift analyses as well as from Faddeev calculations are used as an input. Since the α+d system possesses the low-lying inelastic threshold due to the dissociation of a deuteron, the approach used is generalized to include inelastic channels. The sensitivity of the obtained values of asymptotic normalization coefficients to the elastic channels coupling and to account of the inelastic channel is investigated. In summary, we can say that employing the analytic continuation of the effective range expansion to determine the ANCs and NVCs for the 6 Li → α + d channel turns out to be successful

Multicriteria decision analysis based on analytic hierarchy process in GIS environment for siting nuclear power plant in Egypt

International Nuclear Information System (INIS)

Abudeif, A.M.; Abdel Moneim, A.A.; Farrag, A.F.

2015-01-01

Highlights: • The binary overlay method was used in Phase I through OR operator for selecting the candidate areas. • The WLC and AHP methods was used to screen and select the potential sites (phase II) in Arc GIS 10.1 software. • In phase III, four sites, all located on the North western coast and Red Sea, of highest scores were chosen as Candidate sites after eliminating the lowest score sites. • The AHP method was applied to select preferred candidate site and calculating the eigenvectors in Expert Choice Software Package. - Abstract: Due to increasing demand of electrical energy and freshwater in Egypt, it is safe to assume that the decision makers will turn to nuclear power as the feasible alternative for energy. However, as time goes by, fewer sites will be available and suitable for nuclear power plant development. Site selection is a key phase of the siting process of a nuclear plant and may significantly affect the safety and cost of the facility during its entire life cycle. The siting of nuclear power plants is one of multi-criteria problems, which makes it complex. Many interrelated factors affect the process. Six constraints and twenty-two factors corresponding to safety, environment and socio-economy were considered in the siting study presented in this paper. Multi-Criteria Decision Analysis was applied during the selection of nuclear power plants site using GIS software. Three spatial decision making models were applied in this paper during site selection stage. The binary overlay (Boolean logic) with Low Risk approach in which the logical OR operator is used to determine the candidate areas. All constraints were represented in binary maps, combined and a masking layer was created to eliminate the lands considered as constraints in Arc GIS Software. The 22 factors were represented in normalized maps after unifying all of them to 0–1 score scales based on the philosophy of suitability criteria (factors) using the Weighted Linear Combination

An analytic data analysis method for oscillatory slug tests.

Science.gov (United States)

Chen, Chia-Shyun

2006-01-01

An analytical data analysis method is developed for slug tests in partially penetrating wells in confined or unconfined aquifers of high hydraulic conductivity. As adapted from the van der Kamp method, the determination of the hydraulic conductivity is based on the occurrence times and the displacements of the extreme points measured from the oscillatory data and their theoretical counterparts available in the literature. This method is applied to two sets of slug test response data presented by Butler et al.: one set shows slow damping with seven discernable extremities, and the other shows rapid damping with three extreme points. The estimates of the hydraulic conductivity obtained by the analytic method are in good agreement with those determined by an available curve-matching technique.

A SIMPLE ANALYTICAL METHOD TO DETERMINE SOLAR ENERGETIC PARTICLES' MEAN FREE PATH

International Nuclear Information System (INIS)

He, H.-Q.; Qin, G.

2011-01-01

To obtain the mean free path of solar energetic particles (SEPs) for a solar event, one usually has to fit time profiles of both flux and anisotropy from spacecraft observations to numerical simulations of SEPs' transport processes. This method can be called a simulation method. But a reasonably good fitting needs a lot of simulations, which demand a large amount of calculation resources. Sometimes, it is necessary to find an easy way to obtain the mean free path of SEPs quickly, for example, in space weather practice. Recently, Shalchi et al. provided an approximate analytical formula of SEPs' anisotropy time profile as a function of particles' mean free path for impulsive events. In this paper, we determine SEPs' mean free path by fitting the anisotropy time profiles from Shalchi et al.'s analytical formula to spacecraft observations. This new method can be called an analytical method. In addition, we obtain SEPs' mean free path with the traditional simulation methods. Finally, we compare the mean free path obtained with the simulation method to that of the analytical method to show that the analytical method, with some minor modifications, can give us a good, quick approximation of SEPs' mean free path for impulsive events.

Critical node treatment in the analytic function expansion method for Pin Power Reconstruction

International Nuclear Information System (INIS)

Gao, Z.; Xu, Y.; Downar, T.

2013-01-01

Pin Power Reconstruction (PPR) was implemented in PARCS using the eight term analytic function expansion method (AFEN). This method has been demonstrated to be both accurate and efficient. However, similar to all the methods involving analytic functions, such as the analytic node method (ANM) and AFEN for nodal solution, the use of AFEN for PPR also has potential numerical issue with critical nodes. The conventional analytic functions are trigonometric or hyperbolic sine or cosine functions with an angular frequency proportional to buckling. For a critic al node the buckling is zero and the sine functions becomes zero, and the cosine function become unity. In this case, the eight terms of the analytic functions are no longer distinguishable from ea ch other which makes their corresponding coefficients can no longer be determined uniquely. The mode flux distribution of critical node can be linear while the conventional analytic functions can only express a uniform distribution. If there is critical or near critical node in a plane, the reconstructed pin power distribution is often be shown negative or very large values using the conventional method. In this paper, we propose a new method to avoid the numerical problem wit h critical nodes which uses modified trigonometric or hyperbolic sine functions which are the ratio of trigonometric or hyperbolic sine and its angular frequency. If there are no critical or near critical nodes present, the new pin power reconstruction method with modified analytic functions are equivalent to the conventional analytic functions. The new method is demonstrated using the L336C5 benchmark problem. (authors)

Critical node treatment in the analytic function expansion method for Pin Power Reconstruction

Energy Technology Data Exchange (ETDEWEB)

Gao, Z. [Rice University, MS 318, 6100 Main Street, Houston, TX 77005 (United States); Xu, Y. [Argonne National Laboratory, 9700 South Case Ave., Argonne, IL 60439 (United States); Downar, T. [Department of Nuclear Engineering, University of Michigan, 2355 Bonisteel blvd., Ann Arbor, MI 48109 (United States)

2013-07-01

Pin Power Reconstruction (PPR) was implemented in PARCS using the eight term analytic function expansion method (AFEN). This method has been demonstrated to be both accurate and efficient. However, similar to all the methods involving analytic functions, such as the analytic node method (ANM) and AFEN for nodal solution, the use of AFEN for PPR also has potential numerical issue with critical nodes. The conventional analytic functions are trigonometric or hyperbolic sine or cosine functions with an angular frequency proportional to buckling. For a critic al node the buckling is zero and the sine functions becomes zero, and the cosine function become unity. In this case, the eight terms of the analytic functions are no longer distinguishable from ea ch other which makes their corresponding coefficients can no longer be determined uniquely. The mode flux distribution of critical node can be linear while the conventional analytic functions can only express a uniform distribution. If there is critical or near critical node in a plane, the reconstructed pin power distribution is often be shown negative or very large values using the conventional method. In this paper, we propose a new method to avoid the numerical problem wit h critical nodes which uses modified trigonometric or hyperbolic sine functions which are the ratio of trigonometric or hyperbolic sine and its angular frequency. If there are no critical or near critical nodes present, the new pin power reconstruction method with modified analytic functions are equivalent to the conventional analytic functions. The new method is demonstrated using the L336C5 benchmark problem. (authors)

Neutron Flux Interpolation with Finite Element Method in the Nuclear Fuel Cell Calculation using Collision Probability Method

International Nuclear Information System (INIS)

Shafii, M. Ali; Su'ud, Zaki; Waris, Abdul; Kurniasih, Neny; Ariani, Menik; Yulianti, Yanti

2010-01-01

Nuclear reactor design and analysis of next-generation reactors require a comprehensive computing which is better to be executed in a high performance computing. Flat flux (FF) approach is a common approach in solving an integral transport equation with collision probability (CP) method. In fact, the neutron flux distribution is not flat, even though the neutron cross section is assumed to be equal in all regions and the neutron source is uniform throughout the nuclear fuel cell. In non-flat flux (NFF) approach, the distribution of neutrons in each region will be different depending on the desired interpolation model selection. In this study, the linear interpolation using Finite Element Method (FEM) has been carried out to be treated the neutron distribution. The CP method is compatible to solve the neutron transport equation for cylindrical geometry, because the angle integration can be done analytically. Distribution of neutrons in each region of can be explained by the NFF approach with FEM and the calculation results are in a good agreement with the result from the SRAC code. In this study, the effects of the mesh on the k eff and other parameters are investigated.

Analytic treatment of nuclear spin-lattice relaxation for diffusion in a cone model

Science.gov (United States)

Sitnitsky, A. E.

2011-12-01

We consider nuclear spin-lattice relaxation rate resulted from a diffusion equation for rotational wobbling in a cone. We show that the widespread point of view that there are no analytical expressions for correlation functions for wobbling in a cone model is invalid and prove that nuclear spin-lattice relaxation in this model is exactly tractable and amenable to full analytical description. The mechanism of relaxation is assumed to be due to dipole-dipole interaction of nuclear spins and is treated within the framework of the standard Bloemberger, Purcell, Pound-Solomon scheme. We consider the general case of arbitrary orientation of the cone axis relative the magnetic field. The BPP-Solomon scheme is shown to remain valid for systems with the distribution of the cone axes depending only on the tilt relative the magnetic field but otherwise being isotropic. We consider the case of random isotropic orientation of cone axes relative the magnetic field taking place in powders. Also we consider the cases of their predominant orientation along or opposite the magnetic field and that of their predominant orientation transverse to the magnetic field which may be relevant for, e.g., liquid crystals. Besides we treat in details the model case of the cone axis directed along the magnetic field. The latter provides direct comparison of the limiting case of our formulas with the textbook formulas for free isotropic rotational diffusion. The dependence of the spin-lattice relaxation rate on the cone half-width yields results similar to those predicted by the model-free approach.

Nuclear and radiochemistry

CERN Document Server

Konya, Jozsef

2012-01-01

The field of nuclear and radiochemistry is wide-reaching, with results having functions and use across a variety of disciplines. Drawing on 40 years of experience in teaching and research, this concise book explains the basic principles and applications of the primary areas of nuclear and radiochemistry. Separate chapters cover each main area of recent radiochemistry. This includes nuclear medicine and chemical aspects of nuclear power plants, namely the problems of nuclear wastes and nuclear analysis (both bulk and surface analysis), with the analytical methods based on the interactions of

Evaluation of the effect of coal cleaning of fugitive elements. Part II. Analytical methods. Final report, Phase II

Energy Technology Data Exchange (ETDEWEB)

Bosshart, R.E.; Price, A.A.; Ford, C.T.

1980-03-01

This report contains the analytical and test methods which were used routinely at Bituminous Coal Research, Inc. during the project. The procedures contained herein should aid coal industry laboratories and others, including commercial laboratories, who might be required to determine trace elements in coal. Some of the procedures have been presented in previous BCR reports; however, this report includes additional procedures which are described in greater detail. Also presented are many as the more basic coal methods which have been in use at BCR for many years, or which have been adapted or refined from other standard reference sources for coal and water. The basis for choosing specific analytical procedures for trace elements in coal is somewhat complex. At BCR, atomic absorption was selected as the basic method in the development of these procedures. The choice was based on sensitivity, selectivity, accuracy, precision, practicability, and economy. Whenever possible, the methods developed had to be both adequate and amenable for use by coal industry laboratories by virtue of relative simplicity and cost. This is not to imply that the methods described are simple or inexpensive; however, atomic abosrption techniques do meet these criteria in relation to more complex and costly methods such as neutron activation, mass spectrometry, and x-ray fluorescence, some of which require highly specialized personnel as well as access to sophisticated nuclear and computational facilities. Many of the analytical procedures for trace elements in coal have been developed or adapted specifically for the BCR studies. Their presentation is the principal purpose of this report.

Analytical resource assessment method for continuous (unconventional) oil and gas accumulations - The "ACCESS" Method

Science.gov (United States)

Crovelli, Robert A.; revised by Charpentier, Ronald R.

2012-01-01

The U.S. Geological Survey (USGS) periodically assesses petroleum resources of areas within the United States and the world. The purpose of this report is to explain the development of an analytic probabilistic method and spreadsheet software system called Analytic Cell-Based Continuous Energy Spreadsheet System (ACCESS). The ACCESS method is based upon mathematical equations derived from probability theory. The ACCESS spreadsheet can be used to calculate estimates of the undeveloped oil, gas, and NGL (natural gas liquids) resources in a continuous-type assessment unit. An assessment unit is a mappable volume of rock in a total petroleum system. In this report, the geologic assessment model is defined first, the analytic probabilistic method is described second, and the spreadsheet ACCESS is described third. In this revised version of Open-File Report 00-044 , the text has been updated to reflect modifications that were made to the ACCESS program. Two versions of the program are added as appendixes.

Propulsion and launching analysis of variable-mass rockets by analytical methods

Directory of Open Access Journals (Sweden)

D.D. Ganji

2013-09-01

Full Text Available In this study, applications of some analytical methods on nonlinear equation of the launching of a rocket with variable mass are investigated. Differential transformation method (DTM, homotopy perturbation method (HPM and least square method (LSM were applied and their results are compared with numerical solution. An excellent agreement with analytical methods and numerical ones is observed in the results and this reveals that analytical methods are effective and convenient. Also a parametric study is performed here which includes the effect of exhaust velocity (Ce, burn rate (BR of fuel and diameter of cylindrical rocket (d on the motion of a sample rocket, and contours for showing the sensitivity of these parameters are plotted. The main results indicate that the rocket velocity and altitude are increased with increasing the Ce and BR and decreased with increasing the rocket diameter and drag coefficient.

Biodiesel Analytical Methods: August 2002--January 2004

Energy Technology Data Exchange (ETDEWEB)

Van Gerpen, J.; Shanks, B.; Pruszko, R.; Clements, D.; Knothe, G.

2004-07-01

Biodiesel is an alternative fuel for diesel engines that is receiving great attention worldwide. The material contained in this book is intended to provide the reader with information about biodiesel engines and fuels, analytical methods used to measure fuel properties, and specifications for biodiesel quality control.

A Generalized Pivotal Quantity Approach to Analytical Method Validation Based on Total Error.

Science.gov (United States)

Yang, Harry; Zhang, Jianchun

2015-01-01

The primary purpose of method validation is to demonstrate that the method is fit for its intended use. Traditionally, an analytical method is deemed valid if its performance characteristics such as accuracy and precision are shown to meet prespecified acceptance criteria. However, these acceptance criteria are not directly related to the method's intended purpose, which is usually a gurantee that a high percentage of the test results of future samples will be close to their true values. Alternate "fit for purpose" acceptance criteria based on the concept of total error have been increasingly used. Such criteria allow for assessing method validity, taking into account the relationship between accuracy and precision. Although several statistical test methods have been proposed in literature to test the "fit for purpose" hypothesis, the majority of the methods are not designed to protect the risk of accepting unsuitable methods, thus having the potential to cause uncontrolled consumer's risk. In this paper, we propose a test method based on generalized pivotal quantity inference. Through simulation studies, the performance of the method is compared to five existing approaches. The results show that both the new method and the method based on β-content tolerance interval with a confidence level of 90%, hereafter referred to as the β-content (0.9) method, control Type I error and thus consumer's risk, while the other existing methods do not. It is further demonstrated that the generalized pivotal quantity method is less conservative than the β-content (0.9) method when the analytical methods are biased, whereas it is more conservative when the analytical methods are unbiased. Therefore, selection of either the generalized pivotal quantity or β-content (0.9) method for an analytical method validation depends on the accuracy of the analytical method. It is also shown that the generalized pivotal quantity method has better asymptotic properties than all of the current

Implementation of a communication and control network for the instruments of a nuclear analytical laboratory

International Nuclear Information System (INIS)

Cunya, Eduardo; Baltuano, Oscar; Bedregal, Patricia

2013-01-01

This paper describes the implementation of a communication network and control for a conventional laboratory instruments and nuclear analytical processes based on CAN open field bus to control devices and machines. Hardware components and software developed as well as installation and configuration tools for incorporating new instruments to the network re presented. (authors).

Nuclear methods monitor nutrition

International Nuclear Information System (INIS)

Allen, B.J.

1988-01-01

Neutron activation of nitrogen and hydrogen in the body, the isotope dilution technique and the measurement of naturally radioactive potassium in the body are among the new nuclear methods, now under collaborative development by the Australian Nuclear Scientific and Technology Organization and medical specialists from several Sydney hospitals. These methods allow medical specialists to monitor the patient's response to various diets and dietary treatments in cases of cystic fibrosis, anorexia nervosa, long-term surgical trauma, renal diseases and AIDS. ills

Approximate analytical methods for solving ordinary differential equations

CERN Document Server

Radhika, TSL; Rani, T Raja

2015-01-01

Approximate Analytical Methods for Solving Ordinary Differential Equations (ODEs) is the first book to present all of the available approximate methods for solving ODEs, eliminating the need to wade through multiple books and articles. It covers both well-established techniques and recently developed procedures, including the classical series solution method, diverse perturbation methods, pioneering asymptotic methods, and the latest homotopy methods.The book is suitable not only for mathematicians and engineers but also for biologists, physicists, and economists. It gives a complete descripti

Statistical evaluation of the analytical method involved in French nuclear glasses leaching rate determination

Energy Technology Data Exchange (ETDEWEB)

Broudic, V.; Marques, C.; Bonnal, M

2004-07-01

Chemical durability studies of nuclear glasses involves a large number of water leaching experiments at different temperatures and pressures on both, glasses doped with fission products and actinides and non radioactive surrogates. The leaching rates of these glasses are evaluated through ICPAES analysis of the leachate over time. This work presents a statistical evaluation of the analysis method used to determine the concentrations of various vitreous matrix constituents: Si, B, Na, Al, Ca, Li as major elements and Ba, Cr, Fe, Mn, Mo, Ni, P, Sr, Zn, Zr as minor elements. Calibration characteristics, limits of detection, limits of quantification and uncertainties quantification are illustrated with different examples of analysis performed on surrogates and on radioactive leachates in glove box. (authors)

Statistical evaluation of the analytical method involved in French nuclear glasses leaching rate determination

International Nuclear Information System (INIS)

Broudic, V.; Marques, C.; Bonnal, M.

2004-01-01

Chemical durability studies of nuclear glasses involves a large number of water leaching experiments at different temperatures and pressures on both, glasses doped with fission products and actinides and non radioactive surrogates. The leaching rates of these glasses are evaluated through ICPAES analysis of the leachate over time. This work presents a statistical evaluation of the analysis method used to determine the concentrations of various vitreous matrix constituents: Si, B, Na, Al, Ca, Li as major elements and Ba, Cr, Fe, Mn, Mo, Ni, P, Sr, Zn, Zr as minor elements. Calibration characteristics, limits of detection, limits of quantification and uncertainties quantification are illustrated with different examples of analysis performed on surrogates and on radioactive leachates in glove box. (authors)

Nuclear forensics-metrological basis for legal defensibility

International Nuclear Information System (INIS)

Leggitt, J.; Inn, K.; Goldberg, S.; Essex, R.; LaMont, S.; Chase, S.

2009-01-01

The admissibility of nuclear forensics measurements and opinions derived from them in US Federal and State courts are based on criteria established by the US Supreme Court in the case of Daubert v. Merrell Dow and the 2000 Amendment of Rule 702 of the Federal Rules of Evidence. These criteria are being addressed by new efforts that include the development of certified reference materials (CRMs) to provide the basis for analytical method development, optimization, calibration, validation, quality control, testing, readiness, and declaration of measurement uncertainties. Quality data is crucial for all stages of the program, from R and D, and database development, to actual casework. Weakness at any point in the program can propagate to reduce the confidence of final conclusions. The new certified reference materials will provide the necessary means to demonstrate a high level of metrological rigor for nuclear forensics evidence and will form a foundation for legally defensible nuclear chemical analysis. The CRMs will allow scientists to devise validated analytical methods, which can be corroborated by independent analytical laboratories. CRMs are required for ISO accreditation of many different analytical techniques which may be employed in the analysis of interdicted nuclear materials. (author)

Examination of fast reactor fuels, FBR analytical quality assurance standards and methods, and analytical methods development: irradiation tests. Progress report, April 1--June 30, 1976, and FY 1976

International Nuclear Information System (INIS)

Baker, R.D.

1976-08-01

Characterization of unirradiated and irradiated LMFBR fuels by analytical chemistry methods will continue, and additional methods will be modified and mechanized for hot cell application. Macro- and microexaminations will be made on fuel and cladding using the shielded electron microprobe, emission spectrograph, radiochemistry, gamma scanner, mass spectrometers, and other analytical facilities. New capabilities will be developed in gamma scanning, analyses to assess spatial distributions of fuel and fission products, mass spectrometric measurements of burnup and fission gas constituents and other chemical analyses. Microstructural analyses of unirradiated and irradiated materials will continue using optical and electron microscopy and autoradiographic and x-ray techniques. Analytical quality assurance standards tasks are designed to assure the quality of the chemical characterizations necessary to evaluate reactor components relative to specifications. Tasks include: (1) the preparation and distribution of calibration materials and quality control samples for use in quality assurance surveillance programs, (2) the development of and the guidance in the use of quality assurance programs for sampling and analysis, (3) the development of improved methods of analysis, and (4) the preparation of continuously updated analytical method manuals. Reliable analytical methods development for the measurement of burnup, oxygen-to-metal (O/M) ratio, and various gases in irradiated fuels is described

Applications of nuclear analytical techniques to environmental studies

International Nuclear Information System (INIS)

Freitas, M.C.; Marques, A.P.; Reis, M.A.; Pacheco, A.M.G.; Barros, L.I.C.

2001-01-01

A few examples of application of nuclear-analytical techniques to biological monitors - natives and transplants - are given herein. Parmelia sulcata Taylor transplants were set up in a heavily industrialized area of Portugal - the Setubal peninsula, about 50 km south of Lisbon - where indigenous lichens are rare. The whole area was 10x15 km around an oil-fired power station, and a 2.5x2.5 km grid was used. In north-western Portugal, native thalli of the same epiphytes (Parmelia spp., mostly Parmelia sulcata Taylor) and bark from olive trees (Olea europaea) were sampled across an area of 50x50 km, using a 10x10 km grid. This area is densely populated and features a blend of rural, urban-industrial and coastal environments, together with the country's second-largest metro area (Porto). All biomonitors have been analyzed by INAA and PIXE. Results were put through nonparametric tests and factor analysis for trend significance and emission sources, respectively

Harmonization of health related environmental measurements using nuclear and isotopic techniques. Proceedings of an international symposium

International Nuclear Information System (INIS)

1997-01-01

One of the particular strengths of nuclear methods is in analytical quality assurance, including the validation of analytical methods and the development of new analytical reference materials. These methodologies are therefore helping to harmonize the data produced not only by nuclear techniques themselves, but also by other non-nuclear methods of analysis. The aim of this symposium was to provide an international forum for discussion of these topics. Its programme covered a wide variety of applications of nuclear (and related) analytical techniques (mainly neutron activation analysis, energy dispersive X ray fluorescence, particle induced X ray emission and inductively coupled plasma-mass spectrometry) as used in the study of air particulates, solid waste products, sediments, food, water, human tissues, biomonitors and other kinds of environmental samples

Analytical method of waste allocation in waste management systems: Concept, method and case study

Energy Technology Data Exchange (ETDEWEB)

Bergeron, Francis C., E-mail: francis.b.c@videotron.ca

2017-01-15

Waste is not a rejected item to dispose anymore but increasingly a secondary resource to exploit, influencing waste allocation among treatment operations in a waste management (WM) system. The aim of this methodological paper is to present a new method for the assessment of the WM system, the “analytical method of the waste allocation process” (AMWAP), based on the concept of the “waste allocation process” defined as the aggregation of all processes of apportioning waste among alternative waste treatment operations inside or outside the spatial borders of a WM system. AMWAP contains a conceptual framework and an analytical approach. The conceptual framework includes, firstly, a descriptive model that focuses on the description and classification of the WM system. It includes, secondly, an explanatory model that serves to explain and to predict the operation of the WM system. The analytical approach consists of a step-by-step analysis for the empirical implementation of the conceptual framework. With its multiple purposes, AMWAP provides an innovative and objective modular method to analyse a WM system which may be integrated in the framework of impact assessment methods and environmental systems analysis tools. Its originality comes from the interdisciplinary analysis of the WAP and to develop the conceptual framework. AMWAP is applied in the framework of an illustrative case study on the household WM system of Geneva (Switzerland). It demonstrates that this method provides an in-depth and contextual knowledge of WM. - Highlights: • The study presents a new analytical method based on the waste allocation process. • The method provides an in-depth and contextual knowledge of the waste management system. • The paper provides a reproducible procedure for professionals, experts and academics. • It may be integrated into impact assessment or environmental system analysis tools. • An illustrative case study is provided based on household waste

Analytical method of waste allocation in waste management systems: Concept, method and case study

International Nuclear Information System (INIS)

Bergeron, Francis C.

2017-01-01

Waste is not a rejected item to dispose anymore but increasingly a secondary resource to exploit, influencing waste allocation among treatment operations in a waste management (WM) system. The aim of this methodological paper is to present a new method for the assessment of the WM system, the “analytical method of the waste allocation process” (AMWAP), based on the concept of the “waste allocation process” defined as the aggregation of all processes of apportioning waste among alternative waste treatment operations inside or outside the spatial borders of a WM system. AMWAP contains a conceptual framework and an analytical approach. The conceptual framework includes, firstly, a descriptive model that focuses on the description and classification of the WM system. It includes, secondly, an explanatory model that serves to explain and to predict the operation of the WM system. The analytical approach consists of a step-by-step analysis for the empirical implementation of the conceptual framework. With its multiple purposes, AMWAP provides an innovative and objective modular method to analyse a WM system which may be integrated in the framework of impact assessment methods and environmental systems analysis tools. Its originality comes from the interdisciplinary analysis of the WAP and to develop the conceptual framework. AMWAP is applied in the framework of an illustrative case study on the household WM system of Geneva (Switzerland). It demonstrates that this method provides an in-depth and contextual knowledge of WM. - Highlights: • The study presents a new analytical method based on the waste allocation process. • The method provides an in-depth and contextual knowledge of the waste management system. • The paper provides a reproducible procedure for professionals, experts and academics. • It may be integrated into impact assessment or environmental system analysis tools. • An illustrative case study is provided based on household waste

Analytical hierarchy process for the selection of nuclear reactors for Mexico

International Nuclear Information System (INIS)

Martin-Del-Campo, C.; Nelson, P. F.; Francois, J. L.

2008-01-01

The Analytical Hierarchy Process (AHP) was applied as a decision making technique to select the next new nuclear power reactor for Mexico. The main objective is to select the most suitable nuclear reactor technology for Mexico, to start the bidding process within one or two years, and the reactor to initiate commercial operation by 2016. Four alternatives which comply with these specific restrictions were compared: the Advanced Boiling Water Reactor (AB WR) from General Electric, Hitachi and Toshiba; the European Pressurized Water Reactor (ERR) from AREVA; the pressurized water reactor - advanced passive plant, AP1000, from Westinghouse; and the Economic Simplified Boiling Water Reactor (ESBWR) from General Electric. The evaluation criteria include economic and safety indicator, some of them quantitative and others qualitative. Additional complexity to the solution of this problem is that there are stakeholders that can be involved in the definition of the evaluation criteria and in the definition of relative importance between them, according to each stakeholder interests or benefits. Only the two main stakeholders were considered, these are the Federal Commission of Electricity (Comision Federal de Electricidad, CFE) and the National Commission of Nuclear Safety and Safeguards (Comision Nacional de Seguridad Nuclear y Salvaguardias, CNSNS). Considering the evaluation criteria used and the authors' assessment of their importance, the ABWR was ranked the highest. Sensitivity analyses were performed in order to define the most suitable reactor for the needs of Mexico. (authors)

SPANDOM - source projection analytic nodal discrete ordinates method

International Nuclear Information System (INIS)

Kim, Tae Hyeong; Cho, Nam Zin

1994-01-01

We describe a new discrete ordinates nodal method for the two-dimensional transport equation. We solve the discrete ordinates equation analytically after the source term is projected and represented in polynomials. The method is applied to two fast reactor benchmark problems and compared with the TWOHEX code. The results indicate that the present method accurately predicts not only multiplication factor but also flux distribution

Transport methods: general. 1. The Analytical Monte Carlo Method for Radiation Transport Calculations

International Nuclear Information System (INIS)

Martin, William R.; Brown, Forrest B.

2001-01-01

We present an alternative Monte Carlo method for solving the coupled equations of radiation transport and material energy. This method is based on incorporating the analytical solution to the material energy equation directly into the Monte Carlo simulation for the radiation intensity. This method, which we call the Analytical Monte Carlo (AMC) method, differs from the well known Implicit Monte Carlo (IMC) method of Fleck and Cummings because there is no discretization of the material energy equation since it is solved as a by-product of the Monte Carlo simulation of the transport equation. Our method also differs from the method recently proposed by Ahrens and Larsen since they use Monte Carlo to solve both equations, while we are solving only the radiation transport equation with Monte Carlo, albeit with effective sources and cross sections to represent the emission sources. Our method bears some similarity to a method developed and implemented by Carter and Forest nearly three decades ago, but there are substantive differences. We have implemented our method in a simple zero-dimensional Monte Carlo code to test the feasibility of the method, and the preliminary results are very promising, justifying further extension to more realistic geometries. (authors)

The creation of the analytical information system to serve the process of complex decommissioning of nuclear submarines (NSM) and surface ships (SS) with nuclear power installations (NPI)

International Nuclear Information System (INIS)

Terentiev, V.G.; Yakovlev, N.E.; Tyurin, A.V.

2002-01-01

Management of the decommissioning of nuclear vessels includes information collection, accumulation, systematisation and analysis on the complex utilization of nuclear submarines and surface ships with nuclear power installations and on treatment of spent nuclear fuel and radioactive wastes. The relevant data on radiation and ecology, science and technology, law and economy, administration and management should be properly processed. The general objective of the analytical information system (AIS) development, described in the present paper, is the efficiency upgrading for nuclear submarine utilization management and decision making. The report considers information provision and functioning principles as well as software/hardware solutions associated with the AIS creation. (author)

Standard test methods for chemical and spectrochemical analysis of nuclear-Grade silver-indium-cadmium alloys

CERN Document Server

American Society for Testing and Materials. Philadelphia

1990-01-01

1.1 These test methods cover procedures for the chemical and spectrochemical analysis of nuclear grade silver-indium-cadmium (Ag-In-Cd) alloys to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Silver, Indium, and Cadmium by a Titration Method 7-15 Trace Impurities by Carrier-Distillation Spectro- chemical Method 16-22 1.3 The values stated in SI units are to be regarded as the standard. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. For specific hazard and precautionary statements, see Section 5 and Practices E50. 7.1 This test method is applicable to the determination of silver, indium, and cadmium in alloys of approximately 80 % silver, 15 % indium, and 5 % cadmium used in nuclear reactor control r...

Analytical method for optimization of maintenance policy based on available system failure data

International Nuclear Information System (INIS)

Coria, V.H.; Maximov, S.; Rivas-Dávalos, F.; Melchor, C.L.; Guardado, J.L.

2015-01-01

An analytical optimization method for preventive maintenance (PM) policy with minimal repair at failure, periodic maintenance, and replacement is proposed for systems with historical failure time data influenced by a current PM policy. The method includes a new imperfect PM model based on Weibull distribution and incorporates the current maintenance interval T 0 and the optimal maintenance interval T to be found. The Weibull parameters are analytically estimated using maximum likelihood estimation. Based on this model, the optimal number of PM and the optimal maintenance interval for minimizing the expected cost over an infinite time horizon are also analytically determined. A number of examples are presented involving different failure time data and current maintenance intervals to analyze how the proposed analytical optimization method for periodic PM policy performances in response to changes in the distribution of the failure data and the current maintenance interval. - Highlights: • An analytical optimization method for preventive maintenance (PM) policy is proposed. • A new imperfect PM model is developed. • The Weibull parameters are analytically estimated using maximum likelihood. • The optimal maintenance interval and number of PM are also analytically determined. • The model is validated by several numerical examples

New Analytical Method for the Determination of Metronidazole in ...

African Journals Online (AJOL)

New Analytical Method for the Determination of Metronidazole in Human Plasma: Application to Bioequivalence Study. ... Methods: Metronidazole was extracted from human plasma through one step of ... http://dx.doi.org/10.4314/tjpr.v11i5.14.

Development and validation of analytical methods for dietary supplements

International Nuclear Information System (INIS)

Sullivan, Darryl; Crowley, Richard

2006-01-01

The expanding use of innovative botanical ingredients in dietary supplements and foods has resulted in a flurry of research aimed at the development and validation of analytical methods for accurate measurement of active ingredients. The pressing need for these methods is being met through an expansive collaborative initiative involving industry, government, and analytical organizations. This effort has resulted in the validation of several important assays as well as important advances in the method engineering procedures which have improved the efficiency of the process. The initiative has also allowed researchers to hurdle many of the barricades that have hindered accurate analysis such as the lack of reference standards and comparative data. As the availability for nutraceutical products continues to increase these methods will provide consumers and regulators with the scientific information needed to assure safety and dependable labeling

Performance of analytical methods for tomographic gamma scanning

International Nuclear Information System (INIS)

Prettyman, T.H.; Mercer, D.J.

1997-01-01

The use of gamma-ray computerized tomography for nondestructive assay of radioactive materials has led to the development of specialized analytical methods. Over the past few years, Los Alamos has developed and implemented a computer code, called ARC-TGS, for the analysis of data obtained by tomographic gamma scanning (TGS). ARC-TGS reduces TGS transmission and emission tomographic data, providing the user with images of the sample contents, the activity or mass of selected radionuclides, and an estimate of the uncertainty in the measured quantities. The results provided by ARC-TGS can be corrected for self-attenuation when the isotope of interest emits more than one gamma-ray. In addition, ARC-TGS provides information needed to estimate TGS quantification limits and to estimate the scan time needed to screen for small amounts of radioactivity. In this report, an overview of the analytical methods used by ARC-TGS is presented along with an assessment of the performance of these methods for TGS

Meeting of socialist conntries' representatives on problems of nuclear materials analyses

International Nuclear Information System (INIS)

Pacak, P.; Moravec, J.; Krtil, J.; Sus, F.

1982-01-01

A meeting of representatives of the socialist countries was held in Prague from May 18 to 22, 1981, to discuss cooperation in the field of analytical control of nuclear materials. The Czechoslovak delegation informed the participants of the extent and results of the work of the Central Control Laboratory of the Nuclear Research Institute in Rez. A brief survey is given of the nondestructive methods of measuring the physical parameters of nuclear fuel, the methods of destructive determination of uranium and plutonium and the methods of preparation of standard materials for mass spectrometry which the Central Control Laboratory has introduced and verified for securing analytical control of nuclear materials. (B.S.)

Analytic observables in nuclear physics

International Nuclear Information System (INIS)

Borbely, I.

1980-05-01

The analytical dependence of quantum mechanical observables on their variables is discussed by using the assumption that the corresponding probability amplitudes are analytic functions. The properties of the cross section in the energy plane for spinless particles as well as the properties of the most general polarization observables in the cosdelta plane are considered in detail. In particular, the strength of the transfer pole for polarization observables is given. The practical possibilities to extract the different orbital momentum components of nuclei by extrapolation techniques are briefly outlined. (author)

Characterization of Analytical Reference Glass-1 (ARG-1)

International Nuclear Information System (INIS)

Smith, G.L.

1993-12-01

High-level radioactive waste may be immobilized in borosilicate glass at the West Valley Demonstration Project, West Valley, New York, the Defense Waste Processing Facility (DWPF), Aiken, South Carolina, and the Hanford Waste Vitrification Project (HWVP), Richland, Washington. The vitrified waste form will be stored in stainless steel canisters before its eventual transfer to a geologic repository for long-term disposal. Waste Acceptance Product Specifications (WAPS) (DOE 1993), Section 1.1.2 requires that the waste form producers must report the measured chemical composition of the vitrified waste in their production records before disposal. Chemical analysis of glass waste forms is receiving increased attention due to qualification requirements of vitrified waste forms. The Pacific Northwest Laboratory (PNL) has been supporting the glass producers' analytical laboratories by a continuing program of multilaboratory analytical testing using interlaboratory ''round robin'' methods. At the PNL Materials Characterization Center Analytical Round Robin 4 workshop ''Analysis of Nuclear Waste Glass and Related Materials,'' January 16--17, 1990, Pleasanton, California, the meeting attendees decided that simulated nuclear waste analytical reference glasses were needed for use as analytical standards. Use of common standard analytical reference materials would allow the glass producers' analytical laboratories to calibrate procedures and instrumentation, to control laboratory performance and conduct self-appraisals, and to help qualify their various waste forms

Analytical mass formula and nuclear surface properties in the ETF approximation. Part I: symmetric nuclei

Science.gov (United States)

Aymard, François; Gulminelli, Francesca; Margueron, Jérôme

2016-08-01

The problem of determination of nuclear surface energy is addressed within the framework of the extended Thomas Fermi (ETF) approximation using Skyrme functionals. We propose an analytical model for the density profiles with variationally determined diffuseness parameters. In this first paper, we consider the case of symmetric nuclei. In this situation, the ETF functional can be exactly integrated, leading to an analytical formula expressing the surface energy as a function of the couplings of the energy functional. The importance of non-local terms is stressed and it is shown that they cannot be deduced simply from the local part of the functional, as it was suggested in previous works.

Analytic continuation of quantum Monte Carlo data. Stochastic sampling method

Energy Technology Data Exchange (ETDEWEB)

Ghanem, Khaldoon; Koch, Erik [Institute for Advanced Simulation, Forschungszentrum Juelich, 52425 Juelich (Germany)

2016-07-01

We apply Bayesian inference to the analytic continuation of quantum Monte Carlo (QMC) data from the imaginary axis to the real axis. Demanding a proper functional Bayesian formulation of any analytic continuation method leads naturally to the stochastic sampling method (StochS) as the Bayesian method with the simplest prior, while it excludes the maximum entropy method and Tikhonov regularization. We present a new efficient algorithm for performing StochS that reduces computational times by orders of magnitude in comparison to earlier StochS methods. We apply the new algorithm to a wide variety of typical test cases: spectral functions and susceptibilities from DMFT and lattice QMC calculations. Results show that StochS performs well and is able to resolve sharp features in the spectrum.

Nuclear analytical techniques applied to characterization of atmospheric aerosols in Amazon Region

International Nuclear Information System (INIS)

Gerab, Fabio; Artaxo, Paulo

1996-01-01

This work presents the atmospheric aerosols characterization that exist in different regions of Amazon basin. The biogenic aerosol emission by forest, as well as the atmospheric emissions of particulate materials due to biomass burning, were analyzed. Samples of aerosol particles were collected during three years in two different locations of Amazon region using Stacked Unit Filters. In order to study these samples some analytical nuclear techniques were used. The high concentrations of aerosols as a result of biomass burning process were observed in the period of june-september

A literature review of methods of analysis of organic analytes in radioactive wastes with an emphasis on sources from the United Kingdom

International Nuclear Information System (INIS)

Clauss, S.A.; Bean, R.M.

1993-09-01

This report, compiled by Pacific Northwest Laboratory (PNL), examines literature originating through the United Kingdom (UK) nuclear industry relating to the analyses of organic constituents of radioactive waste. Additionally, secondary references from the UK and other counties, including the United States, have been reviewed. The purpose of this literature review was to find analytical methods that would apply to the mixed-waste matrices found at Hanford

Macro elemental analysis of food samples by nuclear analytical technique

Science.gov (United States)

Syahfitri, W. Y. N.; Kurniawati, S.; Adventini, N.; Damastuti, E.; Lestiani, D. D.

2017-06-01

Energy-dispersive X-ray fluorescence (EDXRF) spectrometry is a non-destructive, rapid, multi elemental, accurate, and environment friendly analysis compared with other detection methods. Thus, EDXRF spectrometry is applicable for food inspection. The macro elements calcium and potassium constitute important nutrients required by the human body for optimal physiological functions. Therefore, the determination of Ca and K content in various foods needs to be done. The aim of this work is to demonstrate the applicability of EDXRF for food analysis. The analytical performance of non-destructive EDXRF was compared with other analytical techniques; neutron activation analysis and atomic absorption spectrometry. Comparison of methods performed as cross checking results of the analysis and to overcome the limitations of the three methods. Analysis results showed that Ca found in food using EDXRF and AAS were not significantly different with p-value 0.9687, whereas p-value of K between EDXRF and NAA is 0.6575. The correlation between those results was also examined. The Pearson correlations for Ca and K were 0.9871 and 0.9558, respectively. Method validation using SRM NIST 1548a Typical Diet was also applied. The results showed good agreement between methods; therefore EDXRF method can be used as an alternative method for the determination of Ca and K in food samples.

A study on environmental pollution monitoring and occupational health in the Capital Iron and Steel Company, Beijing, China, using nuclear and related analytical techniques

International Nuclear Information System (INIS)

Chai Zhifang; Qian Qinfang; Feng Xiangqian; Ding Wenjun; Kuang Minxu; Wang Hongyu; Zhang Yongchen

2000-01-01

Since the First Research Coordination Meeting in Vienna, 20-24 October 1997, on the CRP on Assessment of Levels and Health-effects of Airborne Particulate Matter in Mining, Metal Refining and Metal Working Industries using Nuclear and related Analytical Techniques, our research group has completed the work plan defined by the contract with the Agency, including: (1) collection of airborne particulate, plant and soil samples from sites around the Capital Iron and Steel Company and of human hair, urine, and blood samples from the exposed workers and the control group; (2) validation of the analytical methods (NAA, XRF, SRXRF, JCP-AES etc.) by analyzing appropriate reference materials and by participating in relevant Agency's quality assurance exercises; and (3) analysis of part of the collected samples and preliminary discussion on the available analytical results. Finally, plan for future work was outlined as well. (author)

Development of the fundamental techniques for nuclear forensics

Energy Technology Data Exchange (ETDEWEB)

Park, Jongho; Song, Kyuseok; Ha, Younggeun; Lee, Sunyoung; Choi, Heedong

2013-08-15

The main goal of this project is to develop the fundamental techniques of physical and chemical analysis of the target materials, and data interpretation methods to identify the origin and the production attributions of intercepted illicit nuclear or radioactive materials. This also includes production of analytical data for domestic nuclear materials to be used in establishment of national nuclear material data library. As the result of the R and D of this project, we developed the analytical techniques for H and O isotopes to identify the origin of the target samples, the techniques of chemical treatments of water type and soil type samples, and the fundamental research on the gamma spectroscopy for nuclear forensics. We also performed the study on the national collaboration plan on nuclear forensics, and fundamental research and the target materials and analytical requirements for analytical data production of domestic nuclear materials to construct a national data library. Most of the R and D's in the schedule of this project have not been performed due to the early termination of the project by the decision of the government.

Development of the fundamental techniques for nuclear forensics

International Nuclear Information System (INIS)

Park, Jongho; Song, Kyuseok; Ha, Younggeun; Lee, Sunyoung; Choi, Heedong

2013-08-01

The main goal of this project is to develop the fundamental techniques of physical and chemical analysis of the target materials, and data interpretation methods to identify the origin and the production attributions of intercepted illicit nuclear or radioactive materials. This also includes production of analytical data for domestic nuclear materials to be used in establishment of national nuclear material data library. As the result of the R and D of this project, we developed the analytical techniques for H and O isotopes to identify the origin of the target samples, the techniques of chemical treatments of water type and soil type samples, and the fundamental research on the gamma spectroscopy for nuclear forensics. We also performed the study on the national collaboration plan on nuclear forensics, and fundamental research and the target materials and analytical requirements for analytical data production of domestic nuclear materials to construct a national data library. Most of the R and D's in the schedule of this project have not been performed due to the early termination of the project by the decision of the government

International meeting 'Selected topics on nuclear methods for non-nuclear applications'. Proceedings

International Nuclear Information System (INIS)

Stoyanov, Ch.

2007-01-01

The volume includes the presentations given on the International Meeting 'Selected Topics on Nuclear Methods for Non-nuclear Applications'. The meeting was organized by the Project CECOA. The Project 'CEnter for COoerative Activities' (CECOA) of the Institute for Nuclear Research and Nuclear Energy (INRNE) of Bulgarian Academy of Sciences is part of the Program 'Creating of Infrastructure' of Bulgarian Ministry of Science and Education. The CECOA-project unifies the groups of INRNE doing research in the field of nuclear methods. Four Laboratories of INRNE are members of CECOA-project: Moessbauer Spectroscopy and Low Radioactivity Measurements, High-Resolution Gamma-Spectroscopy, Neutron Methods in Condensed Matter, Neutron Optics and Structure Analysis. Taking into account the leading role of education on nuclear physics the Project includes program devoted to the training on nuclear physics. The presented volume contains 23 contributed papers. The contributions are separated in 6 sections. The section 'Nano technology' includes 5 papers. The activity in this field within the Project reveals the collaboration with other Institutes of Bulgarian Academy of Sciences as well as large international contacts. The section 'Radioecology and Radioactive Waste' is two fold. Part of the contributions of the section manifests the connection of the CECOA with small enterprises. The contacts are on the level of common projects concerning the investigations, remediation and release of radioactively contaminated terrain, soils, water, buildings and materials around the former uranium processing industry. Another part of the section is devoted to the application of nuclear methods to the treatment of radioactive waste produced by nuclear power stations. The section 'Neutron Physics' reveals the activity within the Project connected with the study of new materials using polarized neutrons and neutron diffraction methods. The section 'Nuclear Physics' is an introduction to some

Five-point Element Scheme of Finite Analytic Method for Unsteady Groundwater Flow

Institute of Scientific and Technical Information of China (English)

Xiang Bo; Mi Xiao; Ji Changming; Luo Qingsong

2007-01-01

In order to improve the finite analytic method's adaptability for irregular unit, by using coordinates rotation technique this paper establishes a five-point element scheme of finite analytic method. It not only solves unsteady groundwater flow equation but also gives the boundary condition. This method can be used to calculate the three typical questions of groundwater. By compared with predecessor's computed result, the result of this method is more satisfactory.

Nuclear physics methods in materials research

International Nuclear Information System (INIS)

Bethge, K.; Baumann, H.; Jex, H.; Rauch, F.

1980-01-01

Proceedings of the seventh divisional conference of the Nuclear Physics Division held at Darmstadt, Germany, from 23rd through 26th of September, 1980. The scope of this conference was defined as follows: i) to inform solid state physicists and materials scientists about the application of nuclear physics methods; ii) to show to nuclear physicists open questions and problems in solid state physics and materials science to which their methods can be applied. According to the intentions of the conference, the various nuclear physics methods utilized in solid state physics and materials science and especially new developments were reviewed by invited speakers. Detailed aspects of the methods and typical examples extending over a wide range of applications were presented as contributions in poster sessions. The Proceedings contain all the invited papers and about 90% of the contributed papers. (orig./RW)

In Situ Analytical Characterization of Contaminated Sites Using Nuclear Spectrometry Techniques. Review of Methodologies and Measurements

International Nuclear Information System (INIS)

2017-01-01

Past and current human activities can result in the contamination of sites by radionuclides and heavy metals. The sources of contamination are various. The most important sources for radionuclide release include global fallout from nuclear testing, nuclear and radiological accidents, waste production from nuclear facilities, and activities involving naturally occurring radioactive material (NORM). Contamination of the environment by heavy metals mainly originates from industrial applications and mineralogical background concentration. Contamination of sites by radionuclides and heavy metals can present a risk to people and the environment. Therefore, the estimation of the contamination level and the identification of the source constitute important information for the national authorities with the responsibility to protect people and the environment from adverse health effects. In situ analytical techniques based on nuclear spectrometry are important tools for the characterization of contaminated sites. Much progress has been made in the design and implementation of portable systems for efficient and effective monitoring of radioactivity and heavy metals in the environment directly on-site. Accordingly, the IAEA organized a Technical Meeting to review the current status and trends of various applications of in situ nuclear spectrometry techniques for analytical characterization of contaminated sites and to support Member States in their national environmental monitoring programmes applying portable instrumentation. This publication represents a comprehensive review of the in situ gamma ray spectrometry and field portable X ray fluorescence analysis techniques for the characterization of contaminated sites. It includes papers on the use of these techniques, which provide useful background information for conducting similar studies, in the following Member States: Argentina, Australia, Brazil, Czech Republic, Egypt, France, Greece, Hungary, Italy, Lithuania

Directory of Analytical Methods, Department 1820

International Nuclear Information System (INIS)

Whan, R.E.

1986-01-01

The Materials Characterization Department performs chemical, physical, and thermophysical analyses in support of programs throughout the Laboratories. The department has a wide variety of techniques and instruments staffed by experienced personnel available for these analyses, and we strive to maintain near state-of-the-art technology by continued updates. We have prepared this Directory of Analytical Methods in order to acquaint you with our capabilities and to help you identify personnel who can assist with your analytical needs. The descriptions of the various capabilities are requester-oriented and have been limited in length and detail. Emphasis has been placed on applications and limitations with notations of estimated analysis time and alternative or related techniques. A short, simplified discussion of underlying principles is also presented along with references if more detail is desired. The contents of this document have been organized in the order: bulky analysis, microanalysis, surface analysis, optical and thermal property measurements

Characterization of Nuclear Materials Using Complex of Non-Destructive and Mass-Spectroscopy Methods of Measurements

International Nuclear Information System (INIS)

Gorbunova, A.; Kramchaninov, A.

2015-01-01

Information and Analytical Centre for nuclear materials investigations was established in Russian Federation in the February 2 of 2009 by ROSATOM State Atomic Energy Corporation (the order #80). Its purpose is in preventing unauthorized access to nuclear materials and excluding their illicit traffic. Information and Analytical Centre includes analytical laboratory to provide composition and properties of nuclear materials of unknown origin for their identification. According to Regulation the Centre deals with: · identification of nuclear materials of unknown origin to provide information about their composition and properties; · arbitration analyzes of nuclear materials; · comprehensive research of nuclear and radioactive materials for developing techniques characterization of materials; · interlaboratory measurements; · measurements for control and accounting; · confirmatory measurements. Complex of non-destructive and mass-spectroscopy techniques was developed for the measurements. The complex consists of: · gamma-ray techniques on the base of MGAU, MGA and FRAM codes for uranium and plutonium isotopic composition; · gravimetrical technique with gamma-spectroscopy in addition for uranium content; · calorimetric technique for plutonium mass; · neutron multiplicity technique for plutonium mass; · measurement technique on the base of mass-spectroscopy for uranium isotopic composition; · measurement technique on the base of mass-spectroscopy for metallic impurities. Complex satisfies the state regulation requirements of ensuring the uniformity of measurements including the Russian Federation Federal Law on Ensuring the Uniformity of Measurements #102-FZ, Interstate Standard GOST R ISO/IEC 17025-2006, National Standards of Russian Federation GOST R 8.563-2009, GOST R 8.703-2010, Federal Regulations NRB-99/2009, OSPORB 99/2010. Created complex is provided in reference materials, equipment end certificated techniques. The complex is included in accredited

Methods of analytical check for highly pure tungsten

International Nuclear Information System (INIS)

Miklin, D.G.; Karpov, Yu.A.; Orlova, V.A.

1993-01-01

The review is devoted to the methods of high-purity tungsten analysis. Current trends in the development of this branch of analytical chemistry are considered. Application of both instrument mass-spectrometry analysis and optico-spectral, activation methods and mass-spectrometry ones with inductively-bound plasma in combination with preliminary isolation of the basis and impurity concentration is expected to be the most actual

Pyrrolizidine alkaloids in honey: comparison of analytical methods

NARCIS (Netherlands)

Kempf, M.; Wittig, M.; Reinhard, A.; Ohe, von der K.; Blacquière, T.; Raezke, K.P.; Michel, R.; Schreier, P.; Beuerle, T.

2011-01-01

Pyrrolizidine alkaloids (PAs) are a structurally diverse group of toxicologically relevant secondary plant metabolites. Currently, two analytical methods are used to determine PA content in honey. To achieve reasonably high sensitivity and selectivity, mass spectrometry detection is demanded. One

Contribution to the analysis of hydrogenated amorphous silicon by nuclear methods

International Nuclear Information System (INIS)

Jeannerot, Luc.

1981-01-01

The physico chemical characterization of hydrogenated amorphous silicon thin films (0,5 to 2 μm thick) makes use of nuclear microanalysis for quantitative determination and depth profiling of the elements hydrogen, oxygen, argon and carbon. Concerning the methods, performances of the hydrogen analysis using the 1 H( 15 N, αγ) nuclear reaction are presented emphasizing the precision and the analytical consequences of the interaction ion-material. For charged particles data processing (mainly Rutherford backscattering) computer treatments have been developed either for concentration profile obtention as for spectra prediction of given material configurations. The essential results concerning hydrogenated silicon prepared by RF sputtering are on one hand the correlation between the oxygen incorporation and the beam-induced hydrogen effusion and in the other hand the role of the substrate in the impurities incorporation. From the study of the elaboration conditions of the material a tentative interpretation is made for the incorporation and the role of oxygen [fr

Long-Term Prediction of Satellite Orbit Using Analytical Method

Directory of Open Access Journals (Sweden)

Jae-Cheol Yoon

1997-12-01

Full Text Available A long-term prediction algorithm of geostationary orbit was developed using the analytical method. The perturbation force models include geopotential upto fifth order and degree and luni-solar gravitation, and solar radiation pressure. All of the perturbation effects were analyzed by secular variations, short-period variations, and long-period variations for equinoctial elements such as the semi-major axis, eccentricity vector, inclination vector, and mean longitude of the satellite. Result of the analytical orbit propagator was compared with that of the cowell orbit propagator for the KOREASAT. The comparison indicated that the analytical solution could predict the semi-major axis with an accuarcy of better than ~35meters over a period of 3 month.

The experience of nuclear objects of the national nuclear center of the republic of Kazakhstan vulnerability analysis conducting with the help of assess analytic system

International Nuclear Information System (INIS)

Bogomolov, D.V.; Kozlov, N.I.

2002-01-01

Full text: In the Republic of Kazakhstan there is a number of nuclear objects which are potentially attractive to terrorists and criminal groups. They are also nuclear objects of the National Nuclear Center of the Republic of Kazakhstan (NNC RK) where there are research nuclear reactors with highly enriched nuclear fuel and nuclear materials storage. Within the international collaboration in the field of non-proliferation between the Republic of Kazakhstan and the United States of America in the period of 1996-1998 scientists of the Institute of Atomic Energy (IAE) of the NNC RK together with colleagues from the USA had conducted the system of works concerning vulnerability analysis of three nuclear objects of the NNC RK (reactor complexes IGR, 'Baikal-1' and WWR-K). It also concerned working out the projects of physical protection systems of the mentioned above objects modernization based on the conducted vulnerability analysis. These works included: identification of potential outer and inner threat for nuclear objects of the NNC RK; conducting of the analysis of vulnerability and expected risk of prospective threats for nuclear objects of the NNC RK with the help of analytical program for conducting of ASSESS nuclear objects vulnerability diagnosis; expert estimation of the results received in the course of vulnerability analysis and working out of recommendations on modernization of the systems of NNC RK nuclear objects (reactor complexes IGR, 'Baikal-1' and VVR-K) physical protection; working out of conceptual projects of NNC RK nuclear objects physical protection systems modification. The key point of the work was the vulnerability analysis conducting which required detailed examination of the basic data that provide modeling of aims, routes of movement and evaluation of potential violators detection probability in the protected zones, buildings and reactor systems premises. Analytic programming system of vulnerability estimation and protection effectiveness

Certified reference materials and reference methods for nuclear safeguards and security.

Science.gov (United States)

Jakopič, R; Sturm, M; Kraiem, M; Richter, S; Aregbe, Y

2013-11-01

Confidence in comparability and reliability of measurement results in nuclear material and environmental sample analysis are established via certified reference materials (CRMs), reference measurements, and inter-laboratory comparisons (ILCs). Increased needs for quality control tools in proliferation resistance, environmental sample analysis, development of measurement capabilities over the years and progress in modern analytical techniques are the main reasons for the development of new reference materials and reference methods for nuclear safeguards and security. The Institute for Reference Materials and Measurements (IRMM) prepares and certifices large quantities of the so-called "large-sized dried" (LSD) spikes for accurate measurement of the uranium and plutonium content in dissolved nuclear fuel solutions by isotope dilution mass spectrometry (IDMS) and also develops particle reference materials applied for the detection of nuclear signatures in environmental samples. IRMM is currently replacing some of its exhausted stocks of CRMs with new ones whose specifications are up-to-date and tailored for the demands of modern analytical techniques. Some of the existing materials will be re-measured to improve the uncertainties associated with their certified values, and to enable laboratories to reduce their combined measurement uncertainty. Safeguards involve the quantitative verification by independent measurements so that no nuclear material is diverted from its intended peaceful use. Safeguards authorities pay particular attention to plutonium and the uranium isotope (235)U, indicating the so-called 'enrichment', in nuclear material and in environmental samples. In addition to the verification of the major ratios, n((235)U)/n((238)U) and n((240)Pu)/n((239)Pu), the minor ratios of the less abundant uranium and plutonium isotopes contain valuable information about the origin and the 'history' of material used for commercial or possibly clandestine purposes, and

Atominform's activities as the information and analytical center of nuclear industry and power of Russia

International Nuclear Information System (INIS)

Reshetko, Y.V.

1993-01-01

The Central Research Institute of Management, Economics and Information, Atominform, is a division of information-analytical support of scientific, production and commercial efforts of the nuclear industry and is also involved in the most ''traditional'' information activity. These ''traditional'' lines of activity include: compilation and maintenance of all types of data bases and their reference facilities; library activities; information support; information flows both between the nuclear industry enterprises and through exchange with information bodies of the state system of scientific and technical information and other branches of the national economy; introduction of the state-of-the-art information technologies into the information practice. (orig.)

An analytical-numerical comprehensive method for optimizing the fringing magnetic field

International Nuclear Information System (INIS)

Xiao Meiqin; Mao Naifeng

1991-01-01

The criterion of optimizing the fringing magnetic field is discussed, and an analytical-numerical comprehensive method for realizing the optimization is introduced. The method mentioned above consists of two parts, the analytical part calculates the field of the shims, which corrects the fringing magnetic field by using uniform magnetizing method; the numerical part fulfils the whole calculation of the field distribution by solving the equation of magnetic vector potential A within the region covered by arbitrary triangular meshes with the aid of finite difference method and successive over relaxation method. On the basis of the method, the optimization of the fringing magnetic field for a large-scale electromagnetic isotope separator is finished

State of practice and emerging application of analytical techniques of nuclear forensic analysis: highlights from the 4th Collaborative Materials Exercise of the Nuclear Forensics International Technical Working Group (ITWG)

International Nuclear Information System (INIS)

Schwantes, J.M.; Pellegrini, K.L.; Marsden, Oliva

2017-01-01

The Nuclear Forensics International Technical Working Group (ITWG) recently completed its fourth Collaborative Materials Exercise (CMX-4) in the 21 year history of the Group. This was also the largest materials exercise to date, with participating laboratories from 16 countries or international organizations. Exercise samples (including three separate samples of low enriched uranium oxide) were shipped as part of an illicit trafficking scenario, for which each laboratory was asked to conduct nuclear forensic analyses in support of a fictitious criminal investigation. In all, over 30 analytical techniques were applied to characterize exercise materials, for which ten of those techniques were applied to ITWG exercises for the first time. An objective review of the state of practice and emerging application of analytical techniques of nuclear forensic analysis based upon the outcome of this most recent exercise is provided. (author)

State of practice and emerging application of analytical techniques of nuclear forensic analysis: highlights from the 4th Collaborative Materials Exercise of the Nuclear Forensics International Technical Working Group (ITWG)

International Nuclear Information System (INIS)

Schwantes, Jon M.; Marsden, Oliva; Pellegrini, Kristi L.

2016-01-01

The Nuclear Forensics International Technical Working Group (ITWG) recently completed its fourth Collaborative Materials Exercise (CMX-4) in the 21 year history of the Group. This was also the largest materials exercise to date, with participating laboratories from 16 countries or international organizations. Moreover, exercise samples (including three separate samples of low enriched uranium oxide) were shipped as part of an illicit trafficking scenario, for which each laboratory was asked to conduct nuclear forensic analyses in support of a fictitious criminal investigation. In all, over 30 analytical techniques were applied to characterize exercise materials, for which ten of those techniques were applied to ITWG exercises for the first time. We performed an objective review of the state of practice and emerging application of analytical techniques of nuclear forensic analysis based upon the outcome of this most recent exercise is provided.

FORECASTING PILE SETTLEMENT ON CLAYSTONE USING NUMERICAL AND ANALYTICAL METHODS

Directory of Open Access Journals (Sweden)

Ponomarev Andrey Budimirovich

2016-06-01

Full Text Available In the article the problem of designing pile foundations on claystones is reviewed. The purpose of this paper is comparative analysis of the analytical and numerical methods for forecasting the settlement of piles on claystones. The following tasks were solved during the study: 1 The existing researches of pile settlement are analyzed; 2 The characteristics of experimental studies and the parameters for numerical modeling are presented, methods of field research of single piles’ operation are described; 3 Calculation of single pile settlement is performed using numerical methods in the software package Plaxis 2D and analytical method according to the requirements SP 24.13330.2011; 4 Experimental data is compared with the results of analytical and numerical calculations; 5 Basing on these results recommendations for forecasting pile settlement on claystone are presented. Much attention is paid to the calculation of pile settlement considering the impacted areas in ground space beside pile and the comparison with the results of field experiments. Basing on the obtained results, for the prediction of settlement of single pile on claystone the authors recommend using the analytical method considered in SP 24.13330.2011 with account for the impacted areas in ground space beside driven pile. In the case of forecasting the settlement of single pile on claystone by numerical methods in Plaxis 2D the authors recommend using the Hardening Soil model considering the impacted areas in ground space beside the driven pile. The analyses of the results and calculations are presented for examination and verification; therefore it is necessary to continue the research work of deep foundation at another experimental sites to improve the reliability of the calculation of pile foundation settlement. The work is of great interest for geotechnical engineers engaged in research, design and construction of pile foundations.

Modern methods in analytical acoustics lecture notes

CERN Document Server

Crighton, D G; Williams, J E Ffowcs; Heckl, M; Leppington, F G

1992-01-01

Modern Methods in Analytical Acoustics considers topics fundamental to the understanding of noise, vibration and fluid mechanisms. The series of lectures on which this material is based began by some twenty five years ago and has been developed and expanded ever since. Acknowledged experts in the field have given this course many times in Europe and the USA. Although the scope of the course has widened considerably, the primary aim of teaching analytical techniques of acoustics alongside specific areas of wave motion and unsteady fluid mechanisms remains. The distinguished authors of this volume are drawn from Departments of Acoustics, Engineering of Applied Mathematics in Berlin, Cambridge and London. Their intention is to reach a wider audience of all those concerned with acoustic analysis than has been able to attend the course.

OPTIMAL METHOD FOR PREPARATION OF SILICATE ROCK SAMPLES FOR ANALYTICAL PURPOSES

Directory of Open Access Journals (Sweden)

Maja Vrkljan

2004-12-01

Full Text Available The purpose of this study was to determine an optimal dissolution method for silicate rock samples for further analytical purposes. Analytical FAAS method of determining cobalt, chromium, copper, nickel, lead and zinc content in gabbro sample and geochemical standard AGV-1 has been applied for verification. Dissolution in mixtures of various inorganic acids has been tested, as well as Na2CO3 fusion technique. The results obtained by different methods have been compared and dissolution in the mixture of HNO3 + HF has been recommended as optimal.

Integration of nuclear spectrometry methods as a new approach to material research. Final report of a coordinated research project 2006-2009

International Nuclear Information System (INIS)

2011-10-01

In 2006, the IAEA initiated a coordinated research project (CRP) on 'Unification of Nuclear Spectrometries: Integrated Techniques as a New Tool for Material Research' as one of the elements of a project on 'Improvements in Nuclear Spectrometry Applications'. The major objective was to assist laboratories in Member States in enhancing proper utilization of nuclear analytical methods and to help them develop nuclear instruments for special applications. An overall objective of the CRP was to help Member States to improve characterization of materials by the effective utilization of nuclear spectrometry instruments and techniques as well as by developing integrated/unified instruments and analytical methodologies in support of environmental pollution monitoring, industry, study of cultural heritage, human health, agriculture, etc. These techniques can be used in small laboratories as well as in state of the art synchrotron sources. The specific research objectives of the CRP included development (or upgrading) of integrated multifunctional instruments based on nuclear spectrometries and related techniques as well as development of software for the handling and operation of integrated multifunctional instruments, including data acquisition. The CRP also covered: development (or upgrading) of integrated analytical approaches/methodologies and software for processing and presentation of data collected by multifunctional instruments; extension of the applications of integrated/unified instruments; and synergistic and complementary use of nuclear spectrometries, with the aim of assisting end users of nuclear spectrometries in various fields. The CRP covered a period of four years (2006-2009). Twelve laboratories from both developed and developing Member States and the IAEA's Laboratories participated. The first research coordination meeting (RCM) was held in Vienna, from 16 to 20 April 2007. The participants presented progress reports, reviewed the status of the

A comparison of response spectrum and direct integration analysis methods as applied to a nuclear component support structure

International Nuclear Information System (INIS)

Bryan, B.J.; Flanders, H.E. Jr.

1992-01-01

Seismic qualification of Class I nuclear components is accomplished using a variety of analytical methods. This paper compares the results of time history dynamic analyses of a heat exchanger support structure using response spectrum and time history direct integration analysis methods. Dynamic analysis is performed on the detailed component models using the two methods. A nonlinear elastic model is used for both the response spectrum and direct integration methods. A nonlinear model which includes friction and nonlinear springs, is analyzed using time history input by direct integration. The loads from the three cases are compared

A rapid alpha spectrometric method for estimation of 233U in bulk of thorium

International Nuclear Information System (INIS)

Rao, K.S.; Sankar, R.; Dhami, P.S.; Tripathi, S.C.; Gandhi, P.M.

2015-01-01

Analytical methods play important role in entire nuclear fuel cycle. Almost all the methods find applications in some way or the other in nuclear industry. Methods which cannot be directly used owing to selectivity, find application after chemical separation of analyte from interfering components. The analytical techniques used in PUREX process are almost well matured whereas in THOREX process the analytical techniques are constantly evolving as regards to simplicity, accuracy and time of analysis

Analytical detection techniques for droplet microfluidics—A review

International Nuclear Information System (INIS)

Zhu, Ying; Fang, Qun

2013-01-01

Graphical abstract: -- Highlights: •This is the first review paper focused on the analytical techniques for droplet-based microfluidics. •We summarized the analytical methods used in droplet-based microfluidic systems. •We discussed the advantage and disadvantage of each method through its application. •We also discuss the future development direction of analytical methods for droplet-based microfluidic systems. -- Abstract: In the last decade, droplet-based microfluidics has undergone rapid progress in the fields of single-cell analysis, digital PCR, protein crystallization and high throughput screening. It has been proved to be a promising platform for performing chemical and biological experiments with ultra-small volumes (picoliter to nanoliter) and ultra-high throughput. The ability to analyze the content in droplet qualitatively and quantitatively is playing an increasing role in the development and application of droplet-based microfluidic systems. In this review, we summarized the analytical detection techniques used in droplet systems and discussed the advantage and disadvantage of each technique through its application. The analytical techniques mentioned in this paper include bright-field microscopy, fluorescence microscopy, laser induced fluorescence, Raman spectroscopy, electrochemistry, capillary electrophoresis, mass spectrometry, nuclear magnetic resonance spectroscopy, absorption detection, chemiluminescence, and sample pretreatment techniques. The importance of analytical detection techniques in enabling new applications is highlighted. We also discuss the future development direction of analytical detection techniques for droplet-based microfluidic systems

Analytic nuclear forces and molecular properties from full configuration interaction quantum Monte Carlo

International Nuclear Information System (INIS)

Thomas, Robert E.; Overy, Catherine; Opalka, Daniel; Alavi, Ali; Knowles, Peter J.; Booth, George H.

2015-01-01

Unbiased stochastic sampling of the one- and two-body reduced density matrices is achieved in full configuration interaction quantum Monte Carlo with the introduction of a second, “replica” ensemble of walkers, whose population evolves in imaginary time independently from the first and which entails only modest additional computational overheads. The matrices obtained from this approach are shown to be representative of full configuration-interaction quality and hence provide a realistic opportunity to achieve high-quality results for a range of properties whose operators do not necessarily commute with the Hamiltonian. A density-matrix formulated quasi-variational energy estimator having been already proposed and investigated, the present work extends the scope of the theory to take in studies of analytic nuclear forces, molecular dipole moments, and polarisabilities, with extensive comparison to exact results where possible. These new results confirm the suitability of the sampling technique and, where sufficiently large basis sets are available, achieve close agreement with experimental values, expanding the scope of the method to new areas of investigation

Analytic Methods Used in Quality Control in a Compounding Pharmacy.

Science.gov (United States)

Allen, Loyd V

2017-01-01

Analytical testing will no doubt become a more important part of pharmaceutical compounding as the public and regulatory agencies demand increasing documentation of the quality of compounded preparations. Compounding pharmacists must decide what types of testing and what amount of testing to include in their quality-control programs, and whether testing should be done in-house or outsourced. Like pharmaceutical compounding, analytical testing should be performed only by those who are appropriately trained and qualified. This article discusses the analytical methods that are used in quality control in a compounding pharmacy. Copyright© by International Journal of Pharmaceutical Compounding, Inc.

Analytical maximum-likelihood method to detect patterns in real networks

International Nuclear Information System (INIS)

Squartini, Tiziano; Garlaschelli, Diego

2011-01-01

In order to detect patterns in real networks, randomized graph ensembles that preserve only part of the topology of an observed network are systematically used as fundamental null models. However, the generation of them is still problematic. Existing approaches are either computationally demanding and beyond analytic control or analytically accessible but highly approximate. Here, we propose a solution to this long-standing problem by introducing a fast method that allows one to obtain expectation values and standard deviations of any topological property analytically, for any binary, weighted, directed or undirected network. Remarkably, the time required to obtain the expectation value of any property analytically across the entire graph ensemble is as short as that required to compute the same property using the adjacency matrix of the single original network. Our method reveals that the null behavior of various correlation properties is different from what was believed previously, and is highly sensitive to the particular network considered. Moreover, our approach shows that important structural properties (such as the modularity used in community detection problems) are currently based on incorrect expressions, and provides the exact quantities that should replace them.

Optimization of instrumental neutron activation analysis method by means of 2k experimental design technique aiming the validation of analytical procedures

International Nuclear Information System (INIS)

Petroni, Robson; Moreira, Edson G.

2013-01-01

In this study optimization of procedures and standardization of Instrumental Neutron Activation Analysis (INAA) methods were carried out for the determination of the elements arsenic, chromium, cobalt, iron, rubidium, scandium, selenium and zinc in biological materials. The aim is to validate the analytical methods for future accreditation at the National Institute of Metrology, Quality and Technology (INMETRO). The 2 k experimental design was applied for evaluation of the individual contribution of selected variables of the analytical procedure in the final mass fraction result. Samples of Mussel Tissue Certified Reference Material and multi-element standards were analyzed considering the following variables: sample decay time, counting time and sample distance to detector. The standard multi-element concentration (comparator standard), mass of the sample and irradiation time were maintained constant in this procedure. By means of the statistical analysis and theoretical and experimental considerations it was determined the optimized experimental conditions for the analytical methods that will be adopted for the validation procedure of INAA methods in the Neutron Activation Analysis Laboratory (LAN) of the Research Reactor Center (CRPq) at the Nuclear and Energy Research Institute (IPEN - CNEN/SP). Optimized conditions were estimated based on the results of z-score tests, main effect and interaction effects. The results obtained with the different experimental configurations were evaluated for accuracy (precision and trueness) for each measurement. (author)

Development of a neutronics code based on analytic function expansion nodal method for pebble-type High Temperature Gas-cooled Reactor design

Energy Technology Data Exchange (ETDEWEB)

Cho, Nam Zin; Lee, Joo Hee; Lee, Jae Jun; Yu, Hui; Lee, Gil Soo [Korea Advanced Institute of Science and Tehcnology, Daejeon (Korea, Republic of)

2006-03-15

There is growing interest in developing Pebble Bed Reactors(PBRs) as a candidate of Very High Temperature gas-cooled Reactors(VHTRs). Until now, most existing methods of nuclear design analysis for this type of reactors are base on old finite-difference solvers or on statistical methods. And other existing nodal cannot be adapted for this kind of reactors because of transverse integration problem. In this project, we developed the TOPS code in three dimensional cylindrical geometry based on Analytic Function Expansion Nodal (AFEN) method developed at KAIST. The TOPS code showed better results in computing time than FDM and MCNP. Also TOPS showed very accurate results in reactor analysis.

Development of a neutronics code based on analytic function expansion nodal method for pebble-type High Temperature Gas-cooled Reactor design

International Nuclear Information System (INIS)

Cho, Nam Zin; Lee, Joo Hee; Lee, Jae Jun; Yu, Hui; Lee, Gil Soo

2006-03-01

There is growing interest in developing Pebble Bed Reactors(PBRs) as a candidate of Very High Temperature gas-cooled Reactors(VHTRs). Until now, most existing methods of nuclear design analysis for this type of reactors are base on old finite-difference solvers or on statistical methods. And other existing nodal cannot be adapted for this kind of reactors because of transverse integration problem. In this project, we developed the TOPS code in three dimensional cylindrical geometry based on Analytic Function Expansion Nodal (AFEN) method developed at KAIST. The TOPS code showed better results in computing time than FDM and MCNP. Also TOPS showed very accurate results in reactor analysis

EPA's analytical methods for water: The next generation

International Nuclear Information System (INIS)

Hites, R.A.; Budde, W.L.

1991-01-01

By the late 1970s, it had become clear to EPA that organic compounds were polluting many of the nation's waters. By 1977, as a result of a lawsuit by several environmentally concerned plaintiffs, EPA had focused on a list of 114 'priority' organic pollutants. Its long-term goal was the regulation of specific compounds that were found to pose significant environmental problems, a daunting task. Tens of thousands of samples needed to be measured by hundreds of different laboratories. Clearly, there were concerns about the comparability of data among laboratories. The result was a series of laboratory-based analytical 'methods.' These EPA methods are detailed, step-by-step directions (recipes) that describe everything the analyst needs to know to complete a satisfactory analysis. During the 1970s the first set of methods was developed; this was the '600 series' for the analysis of organic compounds in wastewater. In 1979 and the 1980s, a set of '500 series' methods, focusing on drinking water, was developed. By now, many of the 500 and 600 series methods are in widespread use, and it is clear that there are considerably overlaps among the methods in terms of both procedures and analytes. Indiana University was asked by EPA to consider the question, 'Is it possible to revise or eliminate some of the 500 and 600 series methods and effect a savings of time and money?' This and related questions were studied and recommendations were developed

Application of capability indices and control charts in the analytical method control strategy.

Science.gov (United States)

Oliva, Alexis; Llabres Martinez, Matías

2017-08-01

In this study, we assessed the usefulness of control charts in combination with the process capability indices, C pm and C pk , in the control strategy of an analytical method. The traditional X-chart and moving range chart were used to monitor the analytical method over a 2-year period. The results confirmed that the analytical method is in-control and stable. Different criteria were used to establish the specifications limits (i.e. analyst requirements) for fixed method performance (i.e. method requirements). If the specification limits and control limits are equal in breadth, the method can be considered "capable" (C pm  = 1), but it does not satisfy the minimum method capability requirements proposed by Pearn and Shu (2003). Similar results were obtained using the C pk index. The method capability was also assessed as a function of method performance for fixed analyst requirements. The results indicate that the method does not meet the requirements of the analytical target approach. A real-example data of a SEC with light-scattering detection method was used as a model whereas previously published data were used to illustrate the applicability of the proposed approach. © 2017 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Capabilities of the Institute of Nuclear Physics (Kazakhstan) for technical expertise of seized nuclear and other radioactive materials

International Nuclear Information System (INIS)

Lukashenko, S.; Chakrov, P.; Gorlachyov, I.; Knyazev, B.; Yakushev, E.

2002-01-01

Full text: Institute of Nuclear Physics of the National Nuclear Center of the Republic of Kazakhstan (INP NNC RK) widely uses the nuclear-physical and others analytical methods which were used during the last years to carry out technical expertise of the nuclear and radioactive materials as well. The spectrometric methods for determination radionuclide composition. INP NNC RK has modern spectrometric equipment for solving all types of analytical and radio analytical problems including: gamma spectrometers - planar, coaxial and well type, alpha spectrometers ('Canberra'), liquid scintillation counter 'TriCarb 3100', beta spectrometers. An original procedures with own software are developed for each spectrometric device. Mass-spectrometric methods. The thermion mass - spectrometry (TI-MS) with prism ionic optics are used for environment objects and nuclear materials analysis. Now the operations on determination of plutonium and uranium isotope composition of the environmental objects of former Semipalatinsk nuclear test site by usage of this method are under way. Scanning electron microscopy (SEM). At the INP, SEM techniques have been used traditionally in studies of irradiated metal materials (original surface, fracture surfaces, cross sections), but rather recently they were successfully applied for characterization of 'hot particles' from nuclear testing site, polymer materials, and also uranium fuel pellets. (The microscope used in AMRAY-1200B equipped with ANS X-ray analyzer). Determination methods of macro - and microelements composition. For determination of macro - and microelement composition the set of various methods are used, including: neutron - activation analysis, atomic - emission spectrometry with high - frequency inductively- coupled plasma, roentgen fluorescent analysis, traditional chemical methods: titrimetry, voltamperometry etc. For determination the most difficult elements - carbon and oxygen the nuclear reactions method is developed at the

Development and implementation of methods for determination of the origin of nuclear materials

International Nuclear Information System (INIS)

Wallenius, M.; Pajo, L.; Mayer, K.

2001-01-01

The determination of the origin of seized nuclear material is important for authorities in the context of the criminal investigation, in order to return the material to its last legal owner and to help preventing any further diversion of material from this source. Origin determination is based on a complex pattern of parameters obtained through analytical measurements. The information required to determine the origin of nuclear materials may be divided into two categories: endogenous information (e.g. age or mode of production of the material) which is self-explanatory; whereas exogenous information (e.g. dimensions, surface roughness, impurities) requires a database to which the parameters can be compared. The Institute for Transuranium Elements has developed methods to determine characteristic parameters like impurities, surface roughness, or microstructural information. Furthermore, a database was set up containing relevant information on reactor fuels. (author)

Analytical chromatography. Methods, instrumentation and applications

International Nuclear Information System (INIS)

Yashin, Ya I; Yashin, A Ya

2006-01-01

The state-of-the-art and the prospects in the development of main methods of analytical chromatography, viz., gas, high performance liquid and ion chromatographic techniques, are characterised. Achievements of the past 10-15 years in the theory and general methodology of chromatography and also in the development of new sorbents, columns and chromatographic instruments are outlined. The use of chromatography in the environmental control, biology, medicine, pharmaceutics, and also for monitoring the quality of foodstuffs and products of chemical, petrochemical and gas industries, etc. is considered.

The Emergence of the Analytical Method

DEFF Research Database (Denmark)

Plum, Maja

2012-01-01

accountability, visibility and documentation. It is argued that pedagogy is generated as a sequential and unit-specified way of working on the production of ‘the learning child’, forming a time- and material-optimising approach. Hereby, the nursery teacher, as a daily scientific researcher, comes to serve...... the nation by an ongoing observational intervention, producing the learning foundation for the entrepreneurial citizen, and thus the nation as a knowledge society in a globalised world. This is what this article terms the emergence of the analytical method....

Nuclear steam supply system and method of installation

International Nuclear Information System (INIS)

Tower, S.N.; Christenson, J.A.; Braun, H.E.

1989-01-01

This patent describes a method of providing a nuclear reactor power plant at a predetermined use site accessible by predetermined navigable waterways. The method is practiced with apparatus including a nuclear reactor system. The system has a nuclear steam-supply section. The method consists of: constructing a nuclear reactor system at a manufacturing site remote from the predetermined use site but accessible to the predetermined waterways for transportation from the manufacturing site to the predetermined use site, the nuclear reactor system including a barge with the nuclear steam supply section constructed integrally with the barge. Simultaneously with the construction of the nuclear reactor system, constructing facilities at the use site to be integrated with the nuclear reactor system to form the nuclear-reactor power plant; transporting the nuclear reactor system along the waterways to the predetermined use site; at the use site joining the removal parts of the altered nuclear reactor system to the remainder of the altered nuclear reactor system to complete the nuclear reactor system; and installing the nuclear reactor system at the predetermined use site and integrating the nuclear reactor system to interact with the facilities constructed at the predetermined use site to form the nuclear-reactor power plant

Techniques and methods in nuclear materials traceability

International Nuclear Information System (INIS)

Persiani, P.J.

1996-01-01

The nonproliferation community is currently addressing concerns that the access to special nuclear materials may increase the illicit trafficking in weapons-usable materials from civil and/or weapons material stores and/or fuel cycles systems. Illicit nuclear traffic usually involves reduced quantities of nuclear materials perhaps as samplings of a potential protracted diversionary flow from sources to users. To counter illicit nuclear transactions requires the development of techniques and methods in nuclear material traceability as an important phase of a broad forensic analysis capability. This report discusses how isotopic signatures and correlation methods were applied to determine the origins of Highly Enriched Uranium (HEU) and Plutonium samples reported as illicit trafficking in nuclear materials

Analytical methods applied to water pollution

International Nuclear Information System (INIS)

Baudin, G.

1977-01-01

A comparison of different methods applied to water analysis is given. The discussion is limited to the problems presented by inorganic elements, accessible to nuclear activation analysis methods. The following methods were compared: activation analysis: with gamma-ray spectrometry, atomic absorption spectrometry, fluorimetry, emission spectrometry, colorimetry or spectrophotometry, X-ray fluorescence, mass spectrometry, voltametry, polarography or other electrochemical methods, activation analysis-beta measurements. Drinking-water, irrigation waters, sea waters, industrial wastes and very pure waters are the subjects of the investigations. The comparative evaluation is made on the basis of storage of samples, in situ analysis, treatment and concentration, specificity and interference, monoelement or multielement analysis, analysis time and accuracy. The significance of the neutron analysis is shown. (T.G.)

An analytical optimization method for electric propulsion orbit transfer vehicles

International Nuclear Information System (INIS)

Oleson, S.R.

1993-01-01

Due to electric propulsion's inherent propellant mass savings over chemical propulsion, electric propulsion orbit transfer vehicles (EPOTVs) are a highly efficient mode of orbit transfer. When selecting an electric propulsion device (ion, MPD, or arcjet) and propellant for a particular mission, it is preferable to use quick, analytical system optimization methods instead of time intensive numerical integration methods. It is also of interest to determine each thruster's optimal operating characteristics for a specific mission. Analytical expressions are derived which determine the optimal specific impulse (Isp) for each type of electric thruster to maximize payload fraction for a desired thrusting time. These expressions take into account the variation of thruster efficiency with specific impulse. Verification of the method is made with representative electric propulsion values on a LEO-to-GEO mission. Application of the method to specific missions is discussed

Fail-safe reactivity compensation method for a nuclear reactor

Science.gov (United States)

Nygaard, Erik T.; Angelo, Peter L.; Aase, Scott B.

2018-01-23

The present invention relates generally to the field of compensation methods for nuclear reactors and, in particular to a method for fail-safe reactivity compensation in solution-type nuclear reactors. In one embodiment, the fail-safe reactivity compensation method of the present invention augments other control methods for a nuclear reactor. In still another embodiment, the fail-safe reactivity compensation method of the present invention permits one to control a nuclear reaction in a nuclear reactor through a method that does not rely on moving components into or out of a reactor core, nor does the method of the present invention rely on the constant repositioning of control rods within a nuclear reactor in order to maintain a critical state.

Development of nuclear analytical methods at the Helongjiang Institute (PRC) and the Far-Eastern Branch, USSR Academy of Sciences

International Nuclear Information System (INIS)

GuoLiang, Wu; Duyuan, Xiao; Haoqing, Peng; Ivanenko, V.V.; Buznik, V.M.

1992-01-01

The common character of the problems associated with the use of mineral resources in the northeastern part of the People's Republic of China and in far-eastern Russia has resulted in collaborative development of nuclear-physical analysis methods by the Heilongjiang Academy of Sciences (HAS) and the Far-Eastern Branch Academy of Sciences (HAS) and the Far-Eastern Branch Academy of Sciences (FEBAS) of Russia. A joint Chinese-Soviet Laboratory of nuclear analysis has been established. At the HAS Institute of Physics, a portable analyzer and other products have been developed for use in mineral prospecting and metal identification. The energy resolution for Fe-K line is 61%, and the measuring range covers 0.01 to 100%

X-ray fluorescence in Member States: Philippines. XRF activities at Analytical Measurements Research Group, Philippine Nuclear Research Institute

International Nuclear Information System (INIS)

Pabroa, Corazon B.; Castaneda, Soledad S.; Almoneda, Rosalina V.; Sucgang, Raymond J.; Racho, Joseph Michael D.; Morco, Ryan P.; Cuyco, Danilo; Jimenez, Gloria; Santos, Flora L.

2008-01-01

Full text: XRF analysis and activities of the Analytical Measurements Research (AMR) Group (see Fig.1) of the Philippine Nuclear Research Institute (PNRI) focus on both research and analytical services. Air pollution research, in particular source apportionment studies, requires multi-elemental data for a substantial number of samples. In the PNRI, energy-dispersive X-ray fluorescence (EDXRF) has been used as an effective tool for providing such multi-elemental data. With the latest acquisition of the Panalytical Epsilon 5 (E5) EDXRF system, the process of quantification has become easier and faster with the auto-quantify method. Other research involvements of the group are in the analysis of samples in relation to mineral explorations and the elemental characterization of water in support for isotope hydrology research. The AMR group, as part of its function to provide analytical services, offers qualitative or semi quantitative analysis of solid samples using the auto quantify method, quantitative analysis of environmental samples using the emission-transmission method and quantitative analysis of air particulate matter collected on filters. Telephone wire materials sold in junkshops (alleged to have been pilfered from installed telephone lines of a major telecommunications company in the country) and materials being assessed in relation to patent claims are other examples of samples submitted for analytical services. As mentioned, a useful feature of the E5 system is the use of the auto-quantify (AQ) method. Calibration lines used for this type of application are obtained using the fundamental parameter (FP) model. For AQ applications, accurate results are obtained for samples prepared as fused glass beads in which the whole matrix is known. However, only qualitative or semi quantitative analysis can be applied for other types of solid samples. The AQ method was adapted for the multi-elemental analysis of air particulates using the MicroMatter standards to set

Standard test methods for chemical and mass spectrometric analysis of nuclear-grade gadolinium oxide (Gd2O3) powder

CERN Document Server

American Society for Testing and Materials. Philadelphia

2006-01-01

1.1 These test methods cover procedures for the chemical and mass spectrometric analysis of nuclear-grade gadolinium oxide powders to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Carbon by Direct CombustionThermal Conductivity C1408 Test Method for Carbon (Total) in Uranium Oxide Powders and Pellets By Direct Combustion-Infrared Detection Method Total Chlorine and Fluorine by Pyrohydrolysis Ion Selective Electrode C1502 Test Method for Determination of Total Chlorine and Fluorine in Uranium Dioxide and Gadolinium Oxide Loss of Weight on Ignition 7-13 Sulfur by CombustionIodometric Titration Impurity Elements by a Spark-Source Mass Spectrographic C761 Test Methods for Chemical, Mass Spectrometric, Spectrochemical,Nuclear, and Radiochemical Analysis of Uranium Hexafluoride C1287 Test Method for Determination of Impurities In Uranium Dioxide By Inductively Coupled Plasma Mass Spectrometry Gadolinium Content in Gadolinium Oxid...

A first course in ordinary differential equations analytical and numerical methods

CERN Document Server

Hermann, Martin

2014-01-01

This book presents a modern introduction to analytical and numerical techniques for solving ordinary differential equations (ODEs). Contrary to the traditional format—the theorem-and-proof format—the book is focusing on analytical and numerical methods. The book supplies a variety of problems and examples, ranging from the elementary to the advanced level, to introduce and study the mathematics of ODEs. The analytical part of the book deals with solution techniques for scalar first-order and second-order linear ODEs, and systems of linear ODEs—with a special focus on the Laplace transform, operator techniques and power series solutions. In the numerical part, theoretical and practical aspects of Runge-Kutta methods for solving initial-value problems and shooting methods for linear two-point boundary-value problems are considered. The book is intended as a primary text for courses on the theory of ODEs and numerical treatment of ODEs for advanced undergraduate and early graduate students. It is assumed t...

Nuclear methods on service of mountain manufacture Navoi Mining-Metallurgical complex

International Nuclear Information System (INIS)

Kucherskiy, N.I.

2004-01-01

Full text: On a number of the major minerals, such as gold, uranium, copper, tungsten, potash salts, phosphorites, caolines, etc. Uzbekistan on the confirmed stocks and predicted resources occupies leading places among the states of the world. The basic deposits of gold and uranium are concentrated in Central-Kysylkum region, which is field of activity of Navoi mining-metallurgical combine. In industrial divisions of the combine, located in five areas of republic about 60000 persons are engaged. At all stages of manufacture of gold (since investigation) analytical maintenance has extremely important role. In NMMC radioanalytical methods are widely used, in particular, on mine 'Muruntau' the unique gamma-activation analysis laboratory has been constructed and entered into operation. For the period of operation of laboratory, i.e. since 1977, it is executed more than nine millions analyses of geological tests with extremely high expressness (about tens seconds). It is used x-ray-radiometric method for large-portion (by dumper) sortings and on lumpy separation of ores. With the help of high-sensitivity radiometric means of measurements it is possible to develop phosphorites for reception of phosphoric fertilizers. Nuclear-physical methods are applied to the decision of other problems. Thus, due to application of nuclear-physical methods of the operative control of technological processes of mining manufacture, quality management of ores, the account of quantity of products of extraction and their preliminary enrichment, the actual problem - increase in profitability of all mining manufacture NMMC is solved

Local CC2 response method based on the Laplace transform: Analytic energy gradients for ground and excited states

Energy Technology Data Exchange (ETDEWEB)

Ledermüller, Katrin; Schütz, Martin, E-mail: martin.schuetz@chemie.uni-regensburg.de [Institute of Physical and Theoretical Chemistry, University of Regensburg, Universitätsstraße 31, D-93040 Regensburg (Germany)

2014-04-28

A multistate local CC2 response method for the calculation of analytic energy gradients with respect to nuclear displacements is presented for ground and electronically excited states. The gradient enables the search for equilibrium geometries of extended molecular systems. Laplace transform is used to partition the eigenvalue problem in order to obtain an effective singles eigenvalue problem and adaptive, state-specific local approximations. This leads to an approximation in the energy Lagrangian, which however is shown (by comparison with the corresponding gradient method without Laplace transform) to be of no concern for geometry optimizations. The accuracy of the local approximation is tested and the efficiency of the new code is demonstrated by application calculations devoted to a photocatalytic decarboxylation process of present interest.

Local CC2 response method based on the Laplace transform: analytic energy gradients for ground and excited states.

Science.gov (United States)

Ledermüller, Katrin; Schütz, Martin

2014-04-28

A multistate local CC2 response method for the calculation of analytic energy gradients with respect to nuclear displacements is presented for ground and electronically excited states. The gradient enables the search for equilibrium geometries of extended molecular systems. Laplace transform is used to partition the eigenvalue problem in order to obtain an effective singles eigenvalue problem and adaptive, state-specific local approximations. This leads to an approximation in the energy Lagrangian, which however is shown (by comparison with the corresponding gradient method without Laplace transform) to be of no concern for geometry optimizations. The accuracy of the local approximation is tested and the efficiency of the new code is demonstrated by application calculations devoted to a photocatalytic decarboxylation process of present interest.

Local CC2 response method based on the Laplace transform: Analytic energy gradients for ground and excited states

International Nuclear Information System (INIS)

Ledermüller, Katrin; Schütz, Martin

2014-01-01

A multistate local CC2 response method for the calculation of analytic energy gradients with respect to nuclear displacements is presented for ground and electronically excited states. The gradient enables the search for equilibrium geometries of extended molecular systems. Laplace transform is used to partition the eigenvalue problem in order to obtain an effective singles eigenvalue problem and adaptive, state-specific local approximations. This leads to an approximation in the energy Lagrangian, which however is shown (by comparison with the corresponding gradient method without Laplace transform) to be of no concern for geometry optimizations. The accuracy of the local approximation is tested and the efficiency of the new code is demonstrated by application calculations devoted to a photocatalytic decarboxylation process of present interest

Carbon and nitrogen determination in Zr by photon or proton activation analysis. Comparison between the results obtained by this method and other analytical techniques

International Nuclear Information System (INIS)

Petit, J.; Gosset, J.; Engelmann, C.

1977-01-01

Carbon and nitrogen are determined by the following nuclear reactions: 12 C(γ,n) 11 C and 14 N(p,α) 11 C. The performances of the method and the main interferences are considered. The process developed for the separation of carbon-11 from zirconium is described and its efficiency evaluated. The results obtained are compared with those given by different laboratories using various analytical techniques [fr

Absolute nuclear material assay

Science.gov (United States)

Prasad, Manoj K [Pleasanton, CA; Snyderman, Neal J [Berkeley, CA; Rowland, Mark S [Alamo, CA

2010-07-13

A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

Implementation of quality assurance and quality control in the Nuclear Analytical Laboratory of the Estonian Radiation Protection Centre

International Nuclear Information System (INIS)

Koeoep, T.; Jakobson, E.

2002-01-01

The Analytical Laboratory of the Estonian Radiation Protection Centre is in the process of implementing the system of Quality Assurance (QA) and Quality Control (QC) in the framework of the IAEA TC Project RER/2/004/ 'QA/QC of Nuclear Analytical Techniques'. The draft Quality Manual with annexes has been prepared accordingly to the ISO 17025 Guide, documents and other printed material delivered on the seminars of the project. The laboratory supply has been supplemented with necessary equipment for guaranteeing of quality. Proficiency testing included in the project has been performed successfully. (author)

Meeting report on third regional workshop on quality assurance and quality control of nuclear analytical techniques

International Nuclear Information System (INIS)

2002-01-01

Over the last 20 years, the Agency, through its Technical Co-operation Programme, has helped to establish many nuclear analytical laboratories in nuclear institutions and universities of Member States. The project RER/2/004 has been approved in 1999 for a period of two years aiming at the implementation of a comprehensive QA/QC protocol in laboratories of Member States following the ISO guide 17025. The project involved 13 laboratories from 12 countries. This report presents the project setup, intended outputs and outcomes, achievements and conclusions. It also contains reports from participating laboratories. Each of the reports has been provided with an abstract and indexed separately

Radiochemical methodologies applied to analytical characterization of low and intermediate level wastes from nuclear power plants

International Nuclear Information System (INIS)

Monteiro, Roberto Pellacani G.; Júnior, Aluísio Souza R.; Kastner, Geraldo F.; Temba, Eliane S.C.; Oliveira, Thiago C. de; Amaral, Ângela M.; Franco, Milton B.

2017-01-01

The aim of this work is to present radiochemical methodologies developed at CDTN/CNEN in order to answer a program for isotopic inventory of radioactive wastes from Brazilian Nuclear Power Plants. In this program some radionuclides, 3 H, 14 C, 55 Fe, 59 Ni, 63 Ni, 90 Sr, 93 Zr, 94 Nb, 99 Tc, 129 I, 235 U, 238 U, 238 Pu, 239 + 240 Pu, 241 Pu, 242 Pu, 241 Am, 242 Cm e 243 + 244 Cm, were determined in Low Level Wastes (LLW) and Intermediate Level Wastes (ILW) and a protocol of analytical methodologies based on radiochemical separation steps and spectrometric and nuclear techniques was established. (author)

Survey of Nuclear Methods in Chemical Technology

International Nuclear Information System (INIS)

Broda, E.

1966-01-01

An attempt is made to classify nuclear methods on a logical basis to facilitate assimilation by the technologist. The three main groups are: (I) Tracer methods, (II) Methods based on the influence of absorbers on radiations to be measured, and (III) Radiation chemical methods. The variants of the first two groups are discussed in some detail, and typical examples are given. Group I can be subdivided into (1) Indicator methods, (2) Emanation methods, (3) Radioreagent methods, and (4) Isotope dilution methods, Group II into (5) Activation methods, (6) Absorption methods, (7) Induced Nuclear Reaction methods, (8) Scattering methods, and (9) Fluorescence methods. While the economic benefits due to nuclear methods already run into hundreds of millions of dollars annually, owing to radiation protection problems radiochemical methods in the strict sense are not widely used in actual production. It is suggested that more use should be made of pilot plant tracer studies of chemical processes as used in industry. (author)

The implementation of a simplified spherical harmonics semi-analytic nodal method in PANTHER

International Nuclear Information System (INIS)

Hall, S.K.; Eaton, M.D.; Knight, M.P.

2013-01-01

Highlights: ► An SP N nodal method is proposed. ► Consistent CMFD derived and tested. ► Mark vacuum boundary conditions applied. ► Benchmarked against other diffusions and transport codes. - Abstract: In this paper an SP N nodal method is proposed which can utilise existing multi-group neutron diffusion solvers to obtain the solution. The semi-analytic nodal method is used in conjunction with a coarse mesh finite difference (CMFD) scheme to solve the resulting set of equations. This is compared against various nuclear benchmarks to show that the method is capable of computing an accurate solution for practical cases. A few different CMFD formulations are implemented and their performance compared. It is found that the effective diffusion coefficent (EDC) can provide additional stability and require less power iterations on a coarse mesh. A re-arrangement of the EDC is proposed that allows the iteration matrix to be computed at the beginning of a calculation. Successive nodal updates only modify the source term unlike existing CMFD methods which update the iteration matrix. A set of Mark vacuum boundary conditions are also derived which can be applied to the SP N nodal method extending its validity. This is possible due to a similarity transformation of the angular coupling matrix, which is used when applying the nodal method. It is found that the Marshak vacuum condition can also be derived, but would require the significant modification of existing neutron diffusion codes to implement it

Prediction of polymer flooding performance using an analytical method

International Nuclear Information System (INIS)

Tan Czek Hoong; Mariyamni Awang; Foo Kok Wai

2001-01-01

The study investigated the applicability of an analytical method developed by El-Khatib in polymer flooding. Results from a simulator UTCHEM and experiments were compared with the El-Khatib prediction method. In general, by assuming a constant viscosity polymer injection, the method gave much higher recovery values than the simulation runs and the experiments. A modification of the method gave better correlation, albeit only oil production. Investigation is continuing on modifying the method so that a better overall fit can be obtained for polymer flooding. (Author)

Analytical Chemistry Division : annual report for the year 1980

International Nuclear Information System (INIS)

Sathe, R.M.

1981-01-01

The research and development activities of the Analytical Chemistry Division of the Bhabha Atomic Research Centre, during 1980 are reported in the form of abstracts. Various methods nuclear, spectral, thermal, electrochemical ion exchange developed for chemical analysis are described. Solvent extraction studies are also reviewed. (M.G.B.)

Optimization of instrumental neutron activation analysis method by means of 2{sup k} experimental design technique aiming the validation of analytical procedures

Energy Technology Data Exchange (ETDEWEB)

Petroni, Robson; Moreira, Edson G., E-mail: rpetroni@ipen.br, E-mail: emoreira@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2013-07-01

In this study optimization of procedures and standardization of Instrumental Neutron Activation Analysis (INAA) methods were carried out for the determination of the elements arsenic, chromium, cobalt, iron, rubidium, scandium, selenium and zinc in biological materials. The aim is to validate the analytical methods for future accreditation at the National Institute of Metrology, Quality and Technology (INMETRO). The 2{sup k} experimental design was applied for evaluation of the individual contribution of selected variables of the analytical procedure in the final mass fraction result. Samples of Mussel Tissue Certified Reference Material and multi-element standards were analyzed considering the following variables: sample decay time, counting time and sample distance to detector. The standard multi-element concentration (comparator standard), mass of the sample and irradiation time were maintained constant in this procedure. By means of the statistical analysis and theoretical and experimental considerations it was determined the optimized experimental conditions for the analytical methods that will be adopted for the validation procedure of INAA methods in the Neutron Activation Analysis Laboratory (LAN) of the Research Reactor Center (CRPq) at the Nuclear and Energy Research Institute (IPEN - CNEN/SP). Optimized conditions were estimated based on the results of z-score tests, main effect and interaction effects. The results obtained with the different experimental configurations were evaluated for accuracy (precision and trueness) for each measurement. (author)

Nuclear legislation: analytical study. Regulatory and institutional framework for nuclear activities

International Nuclear Information System (INIS)

2001-01-01

Australia' s basic legislation in the nuclear field consists in five Acts passed by the Federal Parliament. These Acts are as follow: the South Pacific nuclear free zone treaty Act; the nuclear non-proliferation act; the Australian nuclear science and technology organisation act; the Australian nuclear science and technology organisation amendment act; the radiation protection and nuclear safety act. The two first Acts were prompted by the need for domestic legislation to implement Australia 's international obligations. The third arose from a long-standing recognition that the Atomic energy Act was inappropriate as the legislative basis for the activities of Australia 's national nuclear organisation. For its part the fourth Act introduced some necessary changes into the Australian nuclear science and technology organisation Act. Finally, the fifth act establishes a regime to regulate the operation of nuclear installations and the management of radiation sources, where the activities are undertaken by Commonwealth entities. Each of these Acts is discussed in more details in this work. (N.C.)

Groundwater Seepage Estimation into Amirkabir Tunnel Using Analytical Methods and DEM and SGR Method

OpenAIRE

Hadi Farhadian; Homayoon Katibeh

2015-01-01

In this paper, groundwater seepage into Amirkabir tunnel has been estimated using analytical and numerical methods for 14 different sections of the tunnel. Site Groundwater Rating (SGR) method also has been performed for qualitative and quantitative classification of the tunnel sections. The obtained results of above mentioned methods were compared together. The study shows reasonable accordance with results of the all methods unless for two sections of tunnel. In these t...

Maintenance experiences at analytical laboratory at the Tokai reprocessing plant

International Nuclear Information System (INIS)

Suzuki, Hisanori; Nagayama, Tetsuya; Horigome, Kazushi; Ishibashi, Atsushi; Kitao, Takahiko; Surugaya, Naoki

2014-01-01

The Tokai Reprocessing Plant (TRP) is developing the technology to recover uranium and plutonium from spent nuclear fuel. There is an analytical laboratory which was built in 1977, as one of the most important facilities for process and material control analyses at the TRP. Samples taken from each process are analyzed by various analytical methods using hot cells, glove boxes and hume-hoods. A large number of maintenance work have been so far carried out and different types of experience have been accumulated. This paper describes our achievements in the maintenance activities at the analytical laboratory at the TRP. (author)

Some questions of using coding theory and analytical calculation methods on computers

International Nuclear Information System (INIS)

Nikityuk, N.M.

1987-01-01

Main results of investigations devoted to the application of theory and practice of correcting codes are presented. These results are used to create very fast units for the selection of events registered in multichannel detectors of nuclear particles. Using this theory and analytical computing calculations, practically new combination devices, for example, parallel encoders, have been developed. Questions concerning the creation of a new algorithm for the calculation of digital functions by computers and problems of devising universal, dynamically reprogrammable logic modules are discussed

Waste Tank Organic Safety Program: Analytical methods development. Progress report, FY 1994

International Nuclear Information System (INIS)

Campbell, J.A.; Clauss, S.A.; Grant, K.E.

1994-09-01

The objectives of this task are to develop and document extraction and analysis methods for organics in waste tanks, and to extend these methods to the analysis of actual core samples to support the Waste Tank organic Safety Program. This report documents progress at Pacific Northwest Laboratory (a) during FY 1994 on methods development, the analysis of waste from Tank 241-C-103 (Tank C-103) and T-111, and the transfer of documented, developed analytical methods to personnel in the Analytical Chemistry Laboratory (ACL) and 222-S laboratory. This report is intended as an annual report, not a completed work

Contribution to the development of new analytical methods by the coupling between capillary electrophoresis and mass spectrometry (ICP-MS and ESI-MS): applications to the nuclear and biological fields; Contribution au developpement de nouvelles methodes analytiques par le couplage entre l'electrophorese capillaire et la spectrometrie de masse (ICP-MS et ESI-MS): applications dans les domaines nucleaires et biologiques

Energy Technology Data Exchange (ETDEWEB)

Pitois, A

2006-04-15

The coupling between chromatographic and electrophoretic separation techniques and mass spectrometry is used to combine the efficiency of the separation technique to the selectivity and sensitivity of the detectors. In this work, the number of applications of the CE-MS couplings has been increased. New analytical methods have been set up in the nuclear and biological fields. New analytical methods for the determination of fission products (cesium and lanthanides) have been developed by CE-ICP-MS. They enable to determine both concentration and isotopic composition of the fission products for very low detection limits (ng/mL by CE-Q-ICPMS, pg/mL by CE-HR-ICP-MS), since all the isobaric interferences are resolved. Moreover, only some nano-liters of sample are necessary to perform the analysis. These method have been applied with success to a simulated sample of spent fuel, to a nuclear sample from PUREX process and to a leaching of MOX fuel. Then, lanthanides have been analysed by CE-ESI-MS and the capability of ESI-MS to provide structural information has been studied. Elementary information has been obtained for strong potentials. Structural information has been obtained for low potentials. Finally, a new analytical method by CE-ESI-MS for the determination of 10B-boronophenylalanine (10B-BPA) has been developed for Boron Neutron Capture Therapy (BNCT). It has been applied to the cellular lines F98 and HUVEC. This CE-ESI-MS method has been validated by HR-ICP-MS. It enables a direct quantification of the chemical form 10B-BPA in samples of limited size (some nano-liters) and for low concentrations (ng/mL). As a consequence, this CE-ESI-MS method has enabled the study of the kinetics of 10B-BPA release and uptake for the F98 cells. (author)

Fundamentals of nuclear chemistry

International Nuclear Information System (INIS)

Majer, V.

1982-01-01

The author of the book has had 25 years of experience at the Nuclear Chemistry of Prague Technical University. In consequence, the book is intended as a basic textbook for students of this field. Its main objectives are an easily understandable presentation of the complex subject and in spite of the uncertainty which still characterizes the definition and subjects of nuclear chemistry - a systematic classification and logical structure. Contents: 1. Introduction (history and definition); 2. General nuclear chemistry (physical fundamentals, hot atom chemistry, interaction of nuclear radiation with matter, radioactive elements, isotope effects, isotope exchange, chemistry of radioactive trace elements); 3. Methods of nuclear chemistry of nuclear chemistry (radiochemical methods, activation, separation and enrichment chemistry); 4. Preparative nuclear chemistry (isotope production, labelled compounds); 5. Analytival nuclear chemistry; 6. Applied nuclear chemistry (isotope applications in general physical and analytical chemistry). The book is supplemented by an annex with tables, a name catalogue and a subject index which will facilitate access to important information. (RB) [de

Earthquake response of nuclear reactor buildings deeply embedded in soil

International Nuclear Information System (INIS)

Masao, T.; Takasaki, Y.; Hirasawa, M.; Okajima, M.; Yamamoto, S.; Kawata, E.; Koori, Y.; Ochiai, S.; Shimizu, N.

1980-01-01

This paper is concerned with experimental and analytical studies to investigate dynamic behavior of deeply embedded structures such as nuclear reactor buildings. The principal points studied are as follows: (1) Examination of stiffness and radiation damping effects according to embedded depth, (2) verification for distributions of earth pressure according to embedded depth, (3) differences of response characteristics during oscillation according to embedded depth, and (4) proposal of an analytical method for seismic design. Experimental studies were performed by two ways: forced vibration test, and earthquake observation against a rigid body model embedded in soil. Three analytical procedures were performed to compare experimental results and to examine the relation between each procedure. Finally, the dynamic behavior for nuclear reactor buildings with different embedded depths were evaluated by an analytical method. (orig.)

Tank 48H Waste Composition and Results of Investigation of Analytical Methods

Energy Technology Data Exchange (ETDEWEB)

Walker , D.D. [Westinghouse Savannah River Company, AIKEN, SC (United States)

1997-04-02

This report serves two purposes. First, it documents the analytical results of Tank 48H samples taken between April and August 1996. Second, it describes investigations of the precision of the sampling and analytical methods used on the Tank 48H samples.

Literature Review on Processing and Analytical Methods for ...

Science.gov (United States)

Report The purpose of this report was to survey the open literature to determine the current state of the science regarding the processing and analytical methods currently available for recovery of F. tularensis from water and soil matrices, and to determine what gaps remain in the collective knowledge concerning F. tularensis identification from environmental samples.

An analytical method of estimating Value-at-Risk on the Belgrade Stock Exchange

Directory of Open Access Journals (Sweden)

Obadović Milica D.

2009-01-01

Full Text Available This paper presents market risk evaluation for a portfolio consisting of shares that are continuously traded on the Belgrade Stock Exchange, by applying the Value-at-Risk model - the analytical method. It describes the manner of analytical method application and compares the results obtained by implementing this method at different confidence levels. Method verification was carried out on the basis of the failure rate that demonstrated the confidence level for which this method was acceptable in view of the given conditions.

Thermal Lens Spectroscopy as a 'new' analytical tool for actinide determination in nuclear reprocessing processes

International Nuclear Information System (INIS)

Canto, Fabrice; Couston, Laurent; Magnaldo, Alastair; Broquin, Jean-Emmanuel; Signoret, Philippe

2008-01-01

Thermal Lens Spectroscopy (TLS) consists of measuring the effects induced by the relaxation of molecules excited by photons. Twenty years ago, the Cea already worked on TLS. Technologic reasons impeded. But, needs in sensitive analytical methods coupled with very low sample volumes (for example, traces of Np in the COEX TM process) and also the reduction of the nuclear wastes encourage us to revisit this method thanks to the improvement of optoelectronic technologies. We can also imagine coupling TLS with micro-fluidic technologies, decreasing significantly the experiments cost. Generally two laser beams are used for TLS: one for the selective excitation by molecular absorption (inducing the thermal lens) and one for probing the thermal lens. They can be coupled with different geometries, collinear or perpendicular, depending on the application and on the laser mode. Also, many possibilities of measurement have been studied to detect the thermal lens signal: interferometry, direct intensities variations, deflection etc... In this paper, one geometrical configuration and two measurements have been theoretically evaluated. For a single photodiode detection (z-scan) the limit of detection is calculated to be near 5*10 -6 mol*L -1 for Np(IV) in dodecane. (authors)

An Analytical Method of Auxiliary Sources Solution for Plane Wave Scattering by Impedance Cylinders

DEFF Research Database (Denmark)

Larsen, Niels Vesterdal; Breinbjerg, Olav

2004-01-01

Analytical Method of Auxiliary Sources solutions for plane wave scattering by circular impedance cylinders are derived by transformation of the exact eigenfunction series solutions employing the Hankel function wave transformation. The analytical Method of Auxiliary Sources solution thus obtained...

Analytical Energy Gradients for Excited-State Coupled-Cluster Methods

Science.gov (United States)

Wladyslawski, Mark; Nooijen, Marcel

The equation-of-motion coupled-cluster (EOM-CC) and similarity transformed equation-of-motion coupled-cluster (STEOM-CC) methods have been firmly established as accurate and routinely applicable extensions of single-reference coupled-cluster theory to describe electronically excited states. An overview of these methods is provided, with emphasis on the many-body similarity transform concept that is the key to a rationalization of their accuracy. The main topic of the paper is the derivation of analytical energy gradients for such non-variational electronic structure approaches, with an ultimate focus on obtaining their detailed algebraic working equations. A general theoretical framework using Lagrange's method of undetermined multipliers is presented, and the method is applied to formulate the EOM-CC and STEOM-CC gradients in abstract operator terms, following the previous work in [P.G. Szalay, Int. J. Quantum Chem. 55 (1995) 151] and [S.R. Gwaltney, R.J. Bartlett, M. Nooijen, J. Chem. Phys. 111 (1999) 58]. Moreover, the systematics of the Lagrange multiplier approach is suitable for automation by computer, enabling the derivation of the detailed derivative equations through a standardized and direct procedure. To this end, we have developed the SMART (Symbolic Manipulation and Regrouping of Tensors) package of automated symbolic algebra routines, written in the Mathematica programming language. The SMART toolkit provides the means to expand, differentiate, and simplify equations by manipulation of the detailed algebraic tensor expressions directly. The Lagrangian multiplier formulation establishes a uniform strategy to perform the automated derivation in a standardized manner: A Lagrange multiplier functional is constructed from the explicit algebraic equations that define the energy in the electronic method; the energy functional is then made fully variational with respect to all of its parameters, and the symbolic differentiations directly yield the explicit

Analytical chemistry methods for boron carbide absorber material. [Standard

Energy Technology Data Exchange (ETDEWEB)

DELVIN WL

1977-07-01

This standard provides analytical chemistry methods for the analysis of boron carbide powder and pellets for the following: total C and B, B isotopic composition, soluble C and B, fluoride, chloride, metallic impurities, gas content, water, nitrogen, and oxygen. (DLC)

Review and evaluation of spark source mass spectrometry as an analytical method

International Nuclear Information System (INIS)

Beske, H.E.

1981-01-01

The analytical features and most important fields of application of spark source mass spectrometry are described with respect to the trace analysis of high-purity materials and the multielement analysis of technical alloys, geochemical and cosmochemical, biological and radioactive materials, as well as in environmental analysis. Comparisons are made to other analytical methods. The distribution of the method as well as opportunities for contract analysis are indicated and developmental tendencies discussed. (orig.) [de

Nuclear data evaluation method and evaluation system

International Nuclear Information System (INIS)

Liu Tingjin

1995-01-01

The evaluation methods and Nuclear Data Evaluation System have been developed in China. A new version of the system has been established on Micro-VAX2 computer, which is supported by IAEA under the technology assistance program. The flow chart of Chinese Nuclear Data Evaluation System is shown out. For last ten years, the main efforts have been put on the double differential cross section, covariance data and evaluated data library validation. The developed evaluation method and Chinese Nuclear Data Evaluation System have been widely used at CNDC and in Chinese Nuclear Data Network for CENDL. (1 tab., 15 figs.)

An interactive website for analytical method comparison and bias estimation.

Science.gov (United States)

Bahar, Burak; Tuncel, Ayse F; Holmes, Earle W; Holmes, Daniel T

2017-12-01

Regulatory standards mandate laboratories to perform studies to ensure accuracy and reliability of their test results. Method comparison and bias estimation are important components of these studies. We developed an interactive website for evaluating the relative performance of two analytical methods using R programming language tools. The website can be accessed at https://bahar.shinyapps.io/method_compare/. The site has an easy-to-use interface that allows both copy-pasting and manual entry of data. It also allows selection of a regression model and creation of regression and difference plots. Available regression models include Ordinary Least Squares, Weighted-Ordinary Least Squares, Deming, Weighted-Deming, Passing-Bablok and Passing-Bablok for large datasets. The server processes the data and generates downloadable reports in PDF or HTML format. Our website provides clinical laboratories a practical way to assess the relative performance of two analytical methods. Copyright © 2017 The Canadian Society of Clinical Chemists. Published by Elsevier Inc. All rights reserved.

An analytic method for S-expansion involving resonance and reduction

Energy Technology Data Exchange (ETDEWEB)

Ipinza, M.C.; Penafiel, D.M. [Departamento de Fisica, Universidad de Concepcion (Chile); DISAT, Politecnico di Torino (Italy); Istituto Nazionale di Fisica Nucleare (INFN), Sezione di Torino (Italy); Lingua, F. [DISAT, Politecnico di Torino (Italy); Ravera, L. [DISAT, Politecnico di Torino (Italy); Istituto Nazionale di Fisica Nucleare (INFN), Sezione di Torino (Italy)

2016-11-15

In this paper we describe an analytic method able to give the multiplication table(s) of the set(s) involved in an S-expansion process (with either resonance or 0{sub S}-resonant-reduction) for reaching a target Lie (super)algebra from a starting one, after having properly chosen the partitions over subspaces of the considered (super)algebras. This analytic method gives us a simple set of expressions to find the subset decomposition of the set(s) involved in the process. Then, we use the information coming from both the initial (super)algebra and the target one for reaching the multiplication table(s) of the mentioned set(s). Finally, we check associativity with an auxiliary computational algorithm, in order to understand whether the obtained set(s) can describe semigroup(s) or just abelian set(s) connecting two (super)algebras. We also give some interesting examples of application, which check and corroborate our analytic procedure and also generalize some result already presented in the literature. (copyright 2016 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

Analytical method used for intermediate products in continuous distillation of furfural

Energy Technology Data Exchange (ETDEWEB)

Wang, Z.L.; Jia, M.; Wang, L.J.; Deng, Y.X.

1981-01-01

During distillation of furfural, analysis of main components in the crude furfural condensate and intermediate products is very important. Since furfural and methylfurfural are homologous and both furfural and acetone contain a carbonyl group, components in the sample must be separated before analysis. An improved analytical method has been studied, the accuracy and precision of which would meet the requirement of industrial standards. The analytical procedure was provided as follows: to determine the furfural content with gravimetric method of barbituric acid; to determine the methanol content with dichromate method after precipitating furfural and acetone, and distilling the liquid for analysis; and to determine the methylfurfural content with bromide-bromate method, which can be used only in the sample containing higher content of methylfurfural. For the sample in low content, the gas-liquid chromatographic method can be used. 7 references.