WorldWideScience
1

The application of a figure of merit for nuclear explosive utility as a metric for material attractiveness in a nuclear material theft scenario  

British Library Electronic Table of Contents (United Kingdom)

Effective integration of nonproliferation management into the design process is key to the broad deployment of advanced nuclear energy systems, and is an explicit goal of the Laser Inertial Fusion Energy (LIFE) project at Lawrence Livermore National Laboratory. The nuclear explosives utility of a nuclear material to a state (proliferator) or sub-state (terrorist) is a critical factor to be assessed and is one aspect of material attractiveness. In this work, we approached nuclear explosives utility through the calculation of a ''figure of merit'' (FOM) that has recently been developed to capture the relative viability and difficulty of constructing nuclear explosives starting from various nuclear material forms and compositions. We discuss the integration of the figure of merit ...

2010-01-01

2

Nuclear forensics in law enforcement applications  

International Nuclear Information System (INIS)

Over the past several years, the Livermore Forensic Science Center has conducted analyses of nuclear-related samples in conjunction with domestic and international criminal investigations. Law enforcement officials have sought conventional and nuclear-forensic analyses of questioned specimens that have typically consisted of miscellaneous metal species or actinide salts. The investigated activities have included nuclear smuggling and the proliferation of alleged fissionable materials, nonradioactive hoaxes such as 'Red Mercury', and the interdiction of illegal laboratories engaged in methamphetamine synthesis. (author)

1998-09-01

3

Documentation of a model action plan to deter illicit nuclear trafficking  

International Nuclear Information System (INIS)

Theft, illegal possession, smuggling, or attempted unauthorized sale of nuclear and radiological materials remains a worldwide problem. The Nuclear Smuggling International Technical Working Group (ITWG) has adopted a model action plan to guide investigation of these cases through a systematic approach to nuclear forensics. The model action plan was recently documented and provides recommendations concerning incident response, collection of evidence in conformance with required legal standards, laboratory sampling and distribution of samples, radioactive materials analysis, including categorization and characterization of samples, forensics analysis of conventional evidence, and case development including interpretation of forensic signatures. (author)

2008-05-01

4

Personal nuclear accident dosimetry at Sandia National Laboratories  

Energy Technology Data Exchange (ETDEWEB)

DOE installations possessing sufficient quantities of fissile material to potentially constitute a critical mass, such that the excessive exposure of personnel to radiation from a nuclear accident is possible, are required to provide nuclear accident dosimetry services. This document describes the personal nuclear accident dosimeter (PNAD) used by SNL and prescribes methodologies to initially screen, and to process PNAD results. In addition, this report describes PNAD dosimetry results obtained during the Nuclear Accident Dosimeter Intercomparison Study (NAD23), held during 12-16 June 1995, at Los Alamos National Laboratories. Biases for reported neutron doses ranged from -6% to +36% with an average bias of +12%.

1996-09-01

5

Nuclear forensics support. Reference manual  

International Nuclear Information System (INIS)

Illicit trafficking of nuclear and other radioactive material has been an issue of concern since the first seizures in the early 1990s. By the end of 2004 Member States had confirmed 540 cases, while about another 500 remain unconfirmed. Most of the confirmed cases have a criminal dimension, even if they were not for known terrorist purposes. The attacks of September 2001 in the USA dramatically emphasized the requirement for the enhanced control and security of nuclear and other radioactive material. In response to a resolution by the IAEA General Conference in September 2002 the IAEA has adopted an integrated approach to protection against nuclear terrorism. This brings together IAEA activities concerned with the physical protection of nuclear material and nuclear installations, nuclear ...

6

Exploiting industrial robotics  

International Nuclear Information System (INIS)

Advances in robotic technologies reflected in commercially available and demonstrated capabilities provide exceptional alternatives to the designer of new and upgraded production processes. This paper discusses the states of the art of these technologies, describes some of the research and application engineering which has extended and exploited these capabilities, and provides some conceptual synthesis of advanced robotics and other industrial automation to hypothetical nuclear industry/laboratory tasks. Nuclear industry applications are oriented upon tasks in hazardous and contaminating environments and with hazardous materials.

1990-01-15

7

Assessing thermochromatography as a separation method for nuclear forensics. Current capability vis-a-vis forensic requirements  

International Nuclear Information System (INIS)

Nuclear forensic science has become increasingly important for global nuclear security. However, many current laboratory analysis techniques are based on methods developed without the imperative for timely analysis that underlies the post-detonation forensics mission requirements. Current analysis of actinides, fission products, and fuel-specific materials requires time-consuming chemical separation coupled with nuclear counting or mass spectrometry. High-temperature gas-phase separations have been used in the past for the rapid separation of newly created elements/isotopes and as a basis for chemical classification of that element. We are assessing the utility of this method for rapid separation in the gas-phase to accelerate the separations of radioisotopes germane to post-detonation nuclear forensic investigations. The existing state of the art for thermo ...

2011-07-01

8

DECOVALEX - Mathematical models of coupled T-H-M processes for nuclear waste repositories. Executive summary for Phases I,II and III  

Energy Technology Data Exchange (ETDEWEB)

This executive summary presents the motivation, structure, objectives, methodologies and results of the first stage of the international DECOVALEX project - DECOVALEX I (1992-1995). The acronym stands for Development of Coupled Models and their Validation against Experiment in Nuclear Waste Isolation, and the project is an international effort to develop mathematical models, numerical methods and computer codes for coupled thermo-hydro-mechanical processes in fractured rocks and buffer materials for geological isolation of spent nuclear fuel and other radioactive wastes, and validate them against laboratory and field experiments. 24 refs.

1996-06-01

9

ITWG - A platform for international cooperation in nuclear forensics  

International Nuclear Information System (INIS)

Reporting of the first nuclear trafficking incidents began in the early 1990's. The incidents were handled on a national level, using the resources and expertise available in the respective states. However, it soon became evident that fighting this illicit movement of nuclear material across borders would require international cooperation and a systematic and methodological approach. To this end, the G-8 states encouraged the creation of a dedicated group of experts. The Nuclear Smuggling International Technical Working Group (ITWG) was created in the mid 1990's under the auspices of the G-8, following the 1995 Ottawa summit and the 1996 nuclear security summit held in Moscow. The group reports regularly to the Nuclear Safety and Security Group (NSSG) of the G-8. The ITWG has been working towards a sustainable mechanism to help resolve the international problem ...

10

The Nuclear Smuggling International Technical Working Group: Making a difference in combating illicit trafficking  

International Nuclear Information System (INIS)

Full text: The ITWG was first formed in 1995 for the purpose of fostering international cooperation for combating illicit trafficking of nuclear materials. The initial focus for the ITWG was on the development of nuclear forensics to help answer attribution questions regarding nuclear materials of unknown origin. More recently, the ITWG has also expanded its focus to include detection of nuclear materials during transit. This paper presents some of the key developments by this group and their potential impact for combating nuclear smuggling. The initial focus of the ITWG was to write a status report on international cooperation on nuclear smuggling forensic analysis. This 26-page report summarized previous work on nuclear forensics and gave an initial analysis on prioritizing ...

2002-10-21

11

Nevada Nuclear Waste Storage Investigations: Exploratory Shaft Facility fluids and materials evaluation  

Energy Technology Data Exchange (ETDEWEB)

The objective of this study was to determine if any fluids or materials used in the Exploratory Shaft Facility (ESF) of Yucca Mountain will make the mountain unsuitable for future construction of a nuclear waste repository. Yucca Mountain, an area on and adjacent to the Nevada Test Site in southern Nevada, USA, is a candidate site for permanent disposal of high-level radioactive waste from commercial nuclear power and defense nuclear activities. To properly characterize Yucca Mountain, it will be necessary to construct an underground test facility, in which in situ site characterization tests can be conducted. The candidate repository horizon at Yucca Mountain, however, could potentially be compromised by fluids and materials used in the site characterization tests. To minimize this possibility, Los Alamos National Laboratory was directed to evaluate the kinds ...

1988-11-01

12

CANDU 6 fuel behaviour in power ramp conditions  

International Nuclear Information System (INIS)

The facilities in the Institute for Nuclear Research at Pitesti allow the testing, handling and examination of nuclear fuel and irradiated materials. The most important facilities are the TRIGA Steady State Research and Material Test Reactor and the Post-Irradiation Examination Laboratory (PIEL). The purpose of this work is to determine by post-irradiation examination, the behavior of CANDU fuel, irradiated in 14 MW TRIGA reactor. The fuel was irradiated in power ramp conditions. The results of post-irradiation examination are: - Visual inspection and photography of the outer appearance of sheath; - Profilometry (diameter, bending, ovality) and length measuring; - Determination of axial and radial distribution of the fusion products activity by gamma scanning and tomography; - Microstructural characterization by metallographic and ceramographic analyzes; - Mechanical properties ...

2009-10-12

13

Ion-Track Membranes and Their Use in Biological and Medical Applications  

International Nuclear Information System (INIS)

This report is a brief review of biological and medical applications of ion-track membranes. The review aims at informing nuclear physicists about alternative (i.e. non-fundamental-science) use of heavy ion accelerators such as production of micro- and nano-porous materials. The ion-track membranes produced this way are employed in life sciences and numerous technological applications. The author focuses on recent results from the Flerov laboratory in co-operation with other scientific institutions and industrial partners.

2007-05-22

14

FY 1999 Laboratory Directed Research and Development annual report  

Energy Technology Data Exchange (ETDEWEB)

A short synopsis of each project is given covering the following main areas of research and development: Atmospheric sciences; Biotechnology; Chemical and instrumentation analysis; Computer and information science; Design and manufacture engineering; Ecological science; Electronics and sensors; Experimental technology; Health protection and dosimetry; Hydrologic and geologic science; Marine sciences; Materials science; Nuclear science and engineering; Process science and engineering; Sociotechnical systems analysis; Statistics and applied mathematics; and Thermal and energy systems.

2000-06-13

15

Nuclear forensics-metrological basis for legal defensibility  

International Nuclear Information System (INIS)

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 ...

2009-12-01

16

United States Domestic Research Reactor Infrastrucutre TRIGA Reactor Fuel Support  

Energy Technology Data Exchange (ETDEWEB)

The United State Domestic Research Reactor Infrastructure Program at the Idaho National Laboratory manages and provides project management, technical, quality engineering, quality inspection and nuclear material support for the United States Department of Energy sponsored University Reactor Fuels Program. This program provides fresh, unirradiated nuclear fuel to Domestic University Research Reactor Facilities and is responsible for the return of the DOE-owned, irradiated nuclear fuel over the life of the program. This presentation will introduce the program management team, the universities supported by the program, the status of the program and focus on the return process of irradiated nuclear fuel for long term storage at DOE managed receipt facilities. It will include lessons learned from research reactor facilities that have successfully shipped spent fuel ...

2011-03-01

17

Nuclear criticality safety experiments, calculations, and analyses - 1958 to 1982. Volume 2. Summaries. Complilation of papers from the Transactions of the American Nuclear Society  

Energy Technology Data Exchange (ETDEWEB)

This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains-in chronological order-the full-text summaries, reproduced here by ...

1982-10-21

18

The effect of flow velocity on pitting corrosion and stress corrosion cracking of reactor materials  

International Nuclear Information System (INIS)

This paper describes two research programs which are currently underway in the author's laboratory to investigate the effect of fluid flow on the degradation of power plant materials in high temperature/high pressure aqueous environments. These programs include the design and operation of a controlled hydrodynamic corrosion testing apparatus that can be used to study the general and localized corrosion characteristics of alloys in simulated nuclear reactor environments, and a study of the effect of flow velocity on the stress corrosion cracking of ASTM A508 C1.2 steel and Type 304SS in simulated BWR heat transport fluids.

19

Development of the SRS environmental counting laboratory gamma spectroscopy system  

International Nuclear Information System (INIS)

The Savannah River Site (SRS), one of several U.S. Department of Energy (DOE) facilities, produces nuclear materials for national defense and for other government and civilian uses. SRS ceased production of defense materials in 1988, and the site's main activities now involve waste management and environmental restoration. These programs have generated extensive effluent monitoring and environmental surveillance programs for the Environmental Monitoring Section (EMS), which performs #approx#105,000 radiological analyses on 30,000 samples a year. Gamma spectroscopy is performed on an estimated 10,000 samples annually. This report describes a program to develop and improve the EMS system.

1996-06-16

20

Brookhaven highlights. [Fiscal year 1992, October 1, 1991--September 30, 1992  

Energy Technology Data Exchange (ETDEWEB)

This publication provides a broad overview of the research programs and efforts being conducted, built, designed, and planned at Brookhaven National Laboratory. This work covers a broad range of scientific disciplines. Major facilities include the Alternating Gradient Synchrotron (AGS), with its newly completed booster, the National Synchrotron Light Source (NSLS), the High Flux Beam Reactor (HFBR), and the RHIC, which is under construction. Departments within the laboratory include the AGS department, accelerator development, physics, chemistry, biology, NSLS, medical, nuclear energy, and interdepartmental research efforts. Research ranges from the pure sciences, in nuclear physics and high energy physics as one example, to environmental work in applied science to study climatic effects, from efforts in biology which are a component of the human genome project to the study, production, and ...

1992-12-31

21

Brookhaven highlights  

Energy Technology Data Exchange (ETDEWEB)

This publication provides a broad overview of the research programs and efforts being conducted, built, designed, and planned at Brookhaven National Laboratory. This work covers a broad range of scientific disciplines. Major facilities include the Alternating Gradient Synchrotron (AGS), with its newly completed booster, the National Synchrotron Light Source (NSLS), the High Flux Beam Reactor (HFBR), and the RHIC, which is under construction. Departments within the laboratory include the AGS department, accelerator development, physics, chemistry, biology, NSLS, medical, nuclear energy, and interdepartmental research efforts. Research ranges from the pure sciences, in nuclear physics and high energy physics as one example, to environmental work in applied science to study climatic effects, from efforts in biology which are a component of the human genome project to the study, production, and ...

1992-01-01

22

Establishment of an Undergraduate Research and Training Program in Radiochemistry at Florida Memorial University, a Historically Black College or University (HBCU)  

Science.gov (United States)

With the passing of the Energy Policy Act of 2005, the United States is experiencing for the first time in over two decades, what some refer to as the 'Nuclear Renaissance'. The US Nuclear Regulatory Commission (NRC) recognizes this surge in application submissions and is committed to reviewing these applications in a timely manner to support the country's growing energy demands. Notwithstanding these facts, it is understood that the nuclear industry requires appropriately trained and educated personnel to support the growing needs of the nuclear industry and the US NRC. Equally important is the need to educate the next generation of students in nuclear non-proliferation, nuclear forensics and various aspects of homeland security for the national laboratories and the Department of Defense. From mechanical engineers ...

2009-08-19

23

NSF-NIST Interaction in Chemistry, Materials Research, Molecular Biosciences, Bioengineering and Chemical Engineering  

Science.gov (United States)

NSF-NIST Interaction in Chemistry, Materials Research, Molecular Biosciences, Bioengineering, and ... Laboratory (CSTL). Materials research is centralized in the Materials Science and Engineering ...

24

Traces of evidence. Nuclear forensics and illicit trafficking  

International Nuclear Information System (INIS)

An IAEA databank lists a number of reported cases of illicitly trafficked nuclear or other radioactive materials. Apart from the traditional concern with nuclear proliferation, the post September 11th public is now wary of a possible attack by terrorists with a nuclear or radiation dispersion device (RDD). Until now, the seized quantities have not been sufficient to manufacture a nuclear explosive device, but they might be enough to construct an RDD. Recognizing the latent global challenge to public health and safety, the G8 States (Japan, USA, Germany, France, UK, Italy, Canada, and Russia) have called for 'joint international efforts to identify and suppress illicit supply' of, and demand for, nuclear material and to deter potential traffickers. One measure gaining in significance is to identify seized material and ...

2003-06-01

25

Science and Technology Review July/August 2010  

Energy Technology Data Exchange (ETDEWEB)

This issue has the following articles: (1) Deterrence with a Minimum Nuclear Stockpile - Commentary by Bruce T. Goodwin; (2) Enhancing Confidence in the Nation's Nuclear Stockpile - Livermore experts are participating in a national effort aimed at predicting how nuclear weapon materials and systems will likely change over time; (3) Narrowing Uncertainties - For climate modeling and many other fields, understanding uncertainty, or margin of error, is critical; (4) Insight into a Deadly Disease - Laboratory experiments reveal the pathogenesis of tularemia in host cells, bringing scientists closer to developing a vaccine for this debilitating disease. (5) Return to Rongelap - On the Rongelap Atoll, Livermore scientists are working to minimize radiological exposure for natives now living on or wishing to return to the islands.

2010-05-27

26

Measurements to be taken after a nuclear accident in order to limit the uptake of radionuclides from the soil by nutrition crops  

International Nuclear Information System (INIS)

By the department Radio-ecology of the Laboratory for Radiation Research, in the period 1981 up to 1989 inclusive, the transfer has been studied, from soil to plant, of a number of important activation and fission products, originating in the nuclear-power production in nuclear power plants. The purpose of this study was twofold: on the one side the quantification of this transfer for various agrarian systems and on the other side to find out in how far, after an accidental contamination, certain agriculture activities can influence essentially the transfer and subsequently the radiation burden for the population. Emphasis lay, the last years, in particular upon this second aspect. The results of this study form essential basic data for diffusion models for radioactive materials which, in turn, are important in estimating the effects of measures. (author). 6 refs.; 4 figs.

28

Ceramic Composite Materials  

International Science & Technology Center (ISTC)

Development of Ceramic Composite Materials and Structural Elements for High-Temperature Nuclear Reactors

29

Effectiveness of storage practices in mitigating aging degradation during reactor layup  

Energy Technology Data Exchange (ETDEWEB)

One of the issues identified in the US Nuclear Regulatory Commission`s Nuclear Plant Aging Research program plan is the need to understand the state of ``mothballed`` or other out-of-service equipment to ensure subsequent safe operation. Programs for proper storage and preservation of materials and components are required by NRC regulations (10 CFR 50, Appendix B). However, materials and components have been seriously degraded due to improper storage, protection, or layup, at facilities under construction as well as those with operating licenses. Pacific Northwest Laboratory has evaluated management of aging for unstarted or mothballed nuclear power plants. The investigations revealed that no uniform guidance in the industry addresses reactor layup. In each case investigated, layup was not initiated in a timely manner, primarily because of schedule uncertainty. ...

1995-09-01

30

Integration of advanced nuclear materials separation processes  

Energy Technology Data Exchange (ETDEWEB)

This is the final report of a two-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). This project has examined the fundamental chemistry of plutonium that affects the integration of hydrothermal technology into nuclear materials processing operations. Chemical reactions in high temperature water allow new avenues for waste treatment and radionuclide separation.Successful implementation of hydrothermal technology offers the potential to effective treat many types of radioactive waste, reduce the storage hazards and disposal costs, and minimize the generation of secondary waste streams. The focus has been on the chemistry of plutonium(VI) in solution with carbonate since these are expected to be important species in the effluent from hydrothermal oxidation of Pu-containing organic wastes. The authors investigated the structure, solubility, and ...

1998-12-31

31

Response of a Spent Fuel Transportation Cask to a Tunnel Fire Event  

Energy Technology Data Exchange (ETDEWEB)

The staff of the Spent Fuel Project Office at the U.S. Nuclear Regulatory Commission undertook the investigation and thermal analysis of the Baltimore tunnel fire event. This event occurred in the Howard Street tunnel, in Baltimore, Maryland, on July 18, 2001. The staff was tasked with assessing the consequences of this event on the transportation of spent nuclear fuel. This paper describes the staff's coordination with the following government and laboratory organizations: the National Transportation Safety Board (NTSB), to determine the details of the train derailment and fire; the National Institute of Standards and Technology (NIST), to quantify the thermal conditions within the tunnel; the Center for Nuclear Waste Regulatory Analysis (CNWRA), to validate the NIST evaluations, and the Pacific Northwest National Laboratory (PNNL), to assist in the thermal analysis. The ...

2003-02-25

32

Studies on the CRUD Deposition on Fuel Cladding Surface Using AOA Water Chemistry Loop  

International Nuclear Information System (INIS)

Axial offset anomaly (AOA) is caused by the deposition of crud on the fuel cladding of a PWR. When significant levels of crud build up on the cladding, boron can accumulate in the pores of the crud as a concentrated solution or solid phase, and cause the flux depression. Numerous studies have been conducted on the primary water chemistry to reduce the amount of crud in the primary circuit to avoid radioactivity buildup and unexpected power transition in the plant. However, experiments on the crud are restricted in the laboratory because the crud is a highly radioactive material. The objective of this study is to develop a test method for simulating the deposition of crud in a nuclear power plant

2010-10-01

33

Problems and approach to geological disposal of radioactive waste  

International Nuclear Information System (INIS)

This feature articles described a concept and technical problems of geological disposal of high-level radioactive waste in the civil engineering. It consists of six papers such as the present statues and subjects of geological disposal by KITAYAMA Kazumi, the diastrophism, igneous activity, and upheaval and erosion by YAMAZAKI Haruo, the groundwater flow and evaluation of nuclear transfer by IJIRI Yuji, evaluation of alteration of cement materials in the ultra-long period by HAGA Kazuko, The Mizunami Underground Research Laboratory in course of construction by SAKAMAKI Masanori, and interview of the ninetieth president of JSCE (Japan Society of Civil Engineers), he places his hope on JSCE and civil engineers by KISHI Kiyoshi. (S.Y.)

2006-11-01

34

Introduction of microbial nutrients in a nuclear fuel waste disposal vault as a result of excavation and operation activities  

International Nuclear Information System (INIS)

A nuclear fuel waste disposal vault would not likely be a sterile environment. Bacterial activity would be expected in those areas of the vault conducive to bacterial life, i.e., where effects of heat, moisture content, radiation and compaction would not prevent or severely restrict bacterial life and where suitable and sufficient nutrients would be present. An inventory of bacterial nutrients that would be emplaced 'intentionally' with vault materials (fuel waste, waste containers, buffer and backfill materials) has been made previously. This report assesses bacterial nutrients that would be added 'inadvertently' to a vault in the form of residues of materials used to excavate and operate a vault. Measurements of blasting material residues in the various water supplies, excavated broken rock (muck) and in cores drilled in old and new tunnel walls were made at AECL's Underground ...

1987-08-27

35

Awards 1988-1991 Curriculum Development in Mathematics-- Calculus and the Bridge to Calculus  

Science.gov (United States)

... curricula and prototypical instructional materials have been emphasized. The program has provided ... materials are adapted and implemented on a state-wide basis. The laboratory materials and the text ...

36

CRC manual of nuclear medicine: Procedures. Fourth Edition  

Energy Technology Data Exchange (ETDEWEB)

This book discusses the procedures applied for the clinical nuclear medicine laboratory. The procedures are presented as proven guidelines. The chapters are included on quality assurance, radionuclide handling, and radiation safety.

1983-01-01

37

Nuclear forensics  

International Nuclear Information System (INIS)

Nuclear forensics is the analysis of nuclear materials recovered from either the capture of unused materials, or from the radioactive debris following a nuclear explosion and can contribute significantly to the identification of the sources of the materials and the industrial processes used to obtain them. In the case of an explosion, nuclear forensics can also reconstruct key features of the nuclear device. Nuclear forensic analysis works best in conjunction with other law enforcement, radiological protection dosimetry, traditional forensics, and intelligence work to provide the basis for attributing the materials and/or nuclear device to its originators. Nuclear forensics is a piece of the overall attribution process, not a stand-alone ...

2010-02-01

38

Advanced Fuel/Cladding Testing Capabilities in the ORNL High Flux Isotope Reactor  

Energy Technology Data Exchange (ETDEWEB)

The ability to test advanced fuels and cladding materials under reactor operating conditions in the United States is limited. The Oak Ridge National Laboratory (ORNL) High Flux Isotope Reactor (HFIR) and the newly expanded post-irradiation examination (PIE) capability at the ORNL Irradiated Fuels Examination Laboratory provide unique support for this type of advanced fuel/cladding development effort. The wide breadth of ORNL's fuels and materials research divisions provides all the necessary fuel development capabilities in one location. At ORNL, facilities are available from test fuel fabrication, to irradiation in HFIR under either thermal or fast reactor conditions, to a complete suite of PIEs, and to final product disposal. There are very few locations in the world where this full range of capabilities exists. New testing capabilities at HFIR have been developed that allow testing of ...

2009-09-01

39

The Laboratory for Research on the Structure of Matter (LRSM...  

Science.gov (United States)

as one of the first Materials Research Laboratories to be funded by the forerunner of DARPA. In 1972 funding was taken over by the National Science Foundation's Division of...

2011-08-18

40

Structural aging program to assess the adequacy of critical concrete components in nuclear power plants  

International Nuclear Information System (INIS)

The Structural Aging (SAG) Program is carried out by the Oak Ridge National Laboratory (ORNL) under sponsorship of the United States Nuclear Regulatory Commission (USNRC). The Program has evolved from preliminary studies conducted to evaluate the long-term environmental challenges to light-water reactor safety-related concrete civil structures. An important conclusion of these studies was that a damage methodology, which can provide a quantitative measure of a concrete structure's durability with respect to potential future requirements, needs to be developed. Under the SAG Program, this issue is being addressed through: establishment of a structural materials information center, evaluation of structural component assessment and repair technologies, and development of a quantitative methodology for structural aging determinations. Progress to date of each of these activities is presented as well as future plans. 7 refs., 5 ...

1989-08-14

41

The national nuclear material tracking system. A Korea's countermeasure against nuclear terrorism  

International Nuclear Information System (INIS)

Since nuclear terrorism has been identified as a real threat, the Korean government has earnestly developed elementary technologies and sub-systems for establishing an integrated defensive system against nuclear terrorism, which is based on the concept of defense-in-depth. This paper introduces the gist and implications of the studies that have been conducted in building the national nuclear material tracking system for preventing and intercepting the illicit trafficking and transporting of nuclear material in Korea. (orig.)

2011-07-01

42

Facilities Condition and Hazards Assessment for Materials and Fuel Complex Facilities MFC-799, 799A, and 770C  

Energy Technology Data Exchange (ETDEWEB)

The Materials & Fuel Complex (MFC) facilities 799 Sodium Processing Facility (a single building consisting of two areas: the Sodium Process Area (SPA) and the Carbonate Process Area (CPA), 799A Caustic Storage Area, and 770C Nuclear Calibration Laboratory have been declared excess to future Department of Energy mission requirements. Transfer of these facilities from Nuclear Energy to Environmental Management, and an associated schedule for doing so, have been agreed upon by the two offices. The prerequisites for this transfer to occur are the removal of nonexcess materials and chemical inventory, deinventory of the calibration source in MFC-770C, and the rerouting and/or isolation of utility and service systems. This report provides a description of the current physical condition and any hazards (material, chemical, nuclear or ...

2009-11-01

43

Atomic detectives. An introduction to nuclear forensics  

International Nuclear Information System (INIS)

Nuclear forensics is a relatively new scientific branch whose aim it is to read out material inherent information from nuclear material. On the basis of material taken in safe-keeping in Germany, the procedure is illustrated and the limits and possibilities of nuclear forensics are shown, in particular the statements that can be made concerning the material, and the relation of the material with respect to a certain location of origin or manufacturing process. (orig.)

44

The utilization of non-destructive method for in-service inspections in nuclear power components  

International Nuclear Information System (INIS)

To ensure safe and reliable power production nuclear power plants must be operated at high level. Non destructive in-service inspections are inseparable part of the effort. Non destructive in-service inspections are essential on the ground of degradation mechanisms existence in nuclear power components. Degradation processes are constituent of operation of each industrial installation including nuclear power plants. Mission of non-destructive testing is degradation detection, closer characterization of its parameters (dimensions) and to supply as much information as possible to nuclear power plant operator. Eddy current testing method can be assigned to surface - volumetric methods. Method enables inspection of electrically conductive materials. It is particularly suitable for inspection of non-ferromagnetic materials like austenitic stainless steel and brass. ...

2006-01-01

45

Gamma and X-ray shielding compositions utilizing bauxite - Red Mud regional research laboratory (CSIR), Bhopal, India  

International Nuclear Information System (INIS)

Available in abstract form only. Full text of publication follows: The application spectrum of X-ray and Gamma radiation is increasing exponentially in the area of diagnostic, nuclear medicine, food preservation, nuclear power plants and strategic utilities. To prevent the harmful effects of these radiations, shielding materials based on lead metal and its compounds are being used historically, which are toxic in nature. To protect environment it has become necessary to develop non-toxic lead free shielding materials. The use of titanium metal and its compounds as synthetic rock i.e. SYNROC are reported to be very effective non-toxic shielding materials for various applications. Red mud waste generated in aluminum producing industries possesses a unique mineralogical compositions containing fairly high quantity of titanium oxide and iron oxide useful for making non toxic shielding ...

2007-09-02

46

Fuel Assembly Materials under Dry Storage  

International Science & Technology Center (ISTC)

Behavior of Nuclear Reactor Fuel Assembly Materials during Their Long-Term Dry Storage

47

Current status and future plan of JMTR Hot Laboratory  

Energy Technology Data Exchange (ETDEWEB)

The newly developed techniques by the Hot Laboratory (JMTR HL) have provided for us the key information on behavior of specimens due to mechanical / physical / chemical / synergistic effects of radiation, stress and water for fission and fusion reactor environment. These techniques are focused on several topics as follows; (1) miniaturized specimen test for the development of fusion reactor materials, (2) slow strain rate tensile testing (SSRT) and crack propagation measuring tests for the study of Irradiation Assisted Stress Corrosion Cracking (IASCC) of core internals of LWR, (3) handling technique on specimens including tritium for the research and development of tritium breeders and neutron multiplier as fusion blanket materials, (4) joining method using the Tungsten Inert Gas (TIG) welding technique for re-assembling of capsule and re-fabrication of specimen and (5) nondestructive evaluation using ultrasonic wave and ...

1999-08-01

48

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

International Nuclear Information System (INIS)

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 ...

2010-11-15

50

Accelerated aging tests for radiation degradation of organic materials  

International Nuclear Information System (INIS)

(Jun 1984). United States Clough, RL Gillen, KT Sandia Nat'l Laboratories

1984-06-03

51

Course, Curriculum, and Laboratory Improvement (CCLI)  

Science.gov (United States)

... teaching and learning; Creating learning materials and teaching strategies; Developing faculty ... achieve educational innovations. Educational Materials Development (EMD): A project under the former ...

55

Dissolution Kinetics of Zirconia Calcine  

International Nuclear Information System (INIS)

Liquid radioactive raffinates from nuclear fuel reprocessing at the Idaho National Engineering and Environmental Laboratory were solidified, or calcines, in a fluidized bed reactor at approximately 500 C to form a dry granular material. This calcine has been provisionally stored near-surface in concrete-encased stainless steel bins at the Idaho Nuclear Technology Engineering Center. Research addressing the permanent immobilization of radioactive waste has been ongoing. One option is to separate the radioactive constituents from the calcine, thereby reducing the radioactive waste volume to be ultimately stored at a national nuclear waste repository. Nitric acid dissolution of the calcine is a key front-end unit operation in the separations option. In order to design calcine dissolution equipment, quantification of dissolution reaction rate parameters is required. A ...

56

International Safeguards Technology and Policy Education and Training Pilot Programs  

Energy Technology Data Exchange (ETDEWEB)

A major focus of the National Nuclear Security Administration-led Next Generation Safeguards Initiative (NGSI) is the development of human capital to meet present and future challenges to the safeguards regime. An effective university-level education in safeguards and related disciplines is an essential element in a layered strategy to rebuild the safeguards human resource capacity. NNSA launched two pilot programs in 2008 to develop university level courses and internships in association with James, Martin Center for Nonproliferation Studies (CNS) at the Monterey Institute of International Studies (MIIS) and Texas A&M University (TAMU). These pilot efforts involved 44 students in total and were closely linked to hands-on internships at Los Alamos National Laboratory (LANL) and Lawrence Livermore National Laboratory (LLNL). The Safeguards and Nuclear Material Management ...

2009-06-16

57

Determination of radon-222 concentration in inside environments of the Instituto de Engenharia Nuclear, Brazil; Determinacao da concentracao de radonio-222 nos ambientes internos das instalacoes do Instituto de Engenharia Nuclear  

Energy Technology Data Exchange (ETDEWEB)

The gotten concentrations of radon-222 in the installations of the IEN had been determined using the active and passive methods. The active method consisted on the use of the alpha spectrometry with a portable equipment Tracerlab Instruments WLM- Plus. In the determination for the passive method, one used detectors of nuclear strokes of type LEXAN. The raised values had been gotten in the wastes deposit and its annexes, room of the press and laboratory of wastes handling. It was observed, in this sector, an instantaneous measure of alpha spectrometry, concentrations around 1000 Bq.m-3, which had over all to the function of storage, the sector, a great volume of natural radioactive materials, especially of radium-226. This determination was carried through in an extreme situation of ventilation zero, where the gates had been kept closed during the execution of the same one. It was observed, however, a considerable fall, with ...

2000-07-01

58

Nuclear Forensics' role in analyzing nuclear trafficking activities  

International Nuclear Information System (INIS)

Nuclear forensics aims at identifying origin and intended use of nuclear material using information inherent to the nuclear material.The information gathered in nuclear forensics include isotopic composition, elemental composition, impurities and age of the material, macroscopic appearance and microstructure. The information so collected helps to solve criminal cases and put the individuals involved in nuclear trafficking in jails. The information also helps to improve safeguards and physical protection measures at place of theft or diversion to prevent future thefts or diversions.

2010-05-10

59

Spent fuel transportation cask response to a tunnel fire scenario  

Energy Technology Data Exchange (ETDEWEB)

On July 18, 2001, a freight train carrying hazardous (non-nuclear) materials derailed and caught fire while passing through the Howard Street railroad tunnel in downtown Baltimore, Maryland. The United States Nuclear Regulatory Commission (USNRC), one of the agencies responsible for ensuring the safe transportation of radioactive materials in the United States, undertook an investigation of the train derailment and fire to determine the possible regulatory implications of this particular event for the transportation of spent nuclear fuel by railroad. Shortly after the accident occurred, the USNRC met with the National Transportation Safety Board (NTSB), the U.S. agency responsible for determining the cause of transportation accidents, to discuss the details of the accident and the ensuing fire. Following these discussions, the USNRC assembled a team of experts from the National ...

2004-07-01

60

Sodium hideout studies in steam generator crevices  

International Nuclear Information System (INIS)

The steam generator availability is one of the important problems encountered during the pressurized water nuclear plant operation. Various kinds of corrosion phenomena were observed in the past. These phenomena result from the concentration of impurities mainly in three locations in the steam generators: the tubesheet crevices, the tube support plate crevices, and the sludge pile. Corrections were made in the design and the materials used but a number of steam generators suffer or will suffer from corrosion processes inducing in many cases forcing their replacement. In order to prevent or to retard the corrosions several laboratories have performed experiments to reproduce and to study the corrosion processes. The first step of the degradation is the concentration of chemical species. A method using /sup 24/Na as a radioactive tracer was used to establish the concentration kinetics of caustic which was identified as the ...

61

FFTF operating experience, 1982-1984  

International Nuclear Information System (INIS)

The Fast Flux Test Facility (FFTF) is a 400 Mwt sodium-cooled fast reactor operating at the Hanford Engineering Development Laboratory, Richland, Washington, to conduct fuels and materials testing in support of the US Liquid Metal Fast Breeder Reactor (LMFBR) program. Startup and initial power testing included a comprehensive series of nonnuclear and nuclear tests to verify the thermal, hydraulic, and neutronic characteristics of the plant. A specially designed series of natural circulation tests were then performed to demonstrate the inherent safety features of the plant. Early in 1982, the FFTF began its first 100-day irradiation cycle. Since that time the plant has operated very well, achieving a cycle capacity factor of 94% in the most recent irradiation cycle. Seventy-five specific test assemblies and 25,000 individual fuel pins have been irradiated, some in excess of 80 MWd/Kg.

1984-04-09

62

Environmental status of Technical Area 49, Los Alamos, New Mexico  

Energy Technology Data Exchange (ETDEWEB)

A series of experiments involving high explosives and radioactive materials were conducted at Los Alamos, New Mexico, primarily to understand certain safety aspects of operational nuclear weapons. The experiments were conducted underground in large diameter holes as deep as 120 ft. The location was selected because it had geologic and hydrologic characteristics that assured complete containment of the experiments and precluded any possible contamination of groundwater. Important features verified by the USGS included the absence of any recharge and about 1200 feet of dry rock above the groundwater aquifer. Residual materials dispersed by detonation of the high explosives remain at the bottom of the experimental holes. The materials of significance from an environmental standpoint include about 40 kg of plutonium, 93 kg of enriched uranium, at least 82 kg of depleted uranium, 13 kg of beryllium, and an ...

1987-11-01

63

Characterization of spent fuel approved testing material: ATM-103  

Energy Technology Data Exchange (ETDEWEB)

The characterization data obtained to date are described for Approved Testing Material (ATM)-103, which is spent fuel from Assembly D101 of pressurized-water reactor Calvert Cliffs, No. 1. This report is one in a series being written by the Materials Characterization Center (MCC) at Pacific Northwest Laboratory (PNL) on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well-characterized spent fuel for testing in the US nuclear waste repository program. ATM-103 consists of 176 full-length irradiated fuel rods with rod-average burnups of about 2600 GJ/kgM (30 MWd/kgM) and less than 1% fission gas release. Characterization data include 1) as-fabricated fuel design, irradiation history, and subsequent storage and handling; 2) isotopic gamma scans; 3) fission gas analyses; 4) ceramography of the fuel and metallography of the cladding; 5) special fuels studies involving ...

1988-04-01

64

Characterization of spent fuel approved testing material--ATM-104  

Energy Technology Data Exchange (ETDEWEB)

The characterization data obtained to date are described for Approved Testing Material 104 (ATM-104), which is spent fuel from Assembly DO47 of the Calvert Cliffs Nuclear Power Plant (Unit 1), a pressurized-water reactor. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory (PNL) on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well-characterized spent fuel for testing in the US Department of Energy Office of Civilian Radioactive Waste Management (OCRWM) Program. ATM-104 consists of 128 full-length irradiated fuel rods with rod-average burnups of about 42 MWd/kgM and expected fission gas release of about 1%. A variety of analyses were performed to investigate cladding characteristics, radionuclide inventory, and redistribution of fission products. Characterization data include (1) fabricated fuel ...

1991-12-01

65

Characterization of spent fuel approved testing material---ATM-105  

Energy Technology Data Exchange (ETDEWEB)

The characterization data obtained to data are described for Approved Testing Material 105 (ATM-105), which is spent fuel from Bundles CZ346 and CZ348 of the Cooper Nuclear Power Plant, a boiling-water reactor. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory (PNL) on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well-characterized spent fuel for testing in the US Department of Energy Office of Civilian Radioactive Waste Management (OCRWM) Program. ATM-105 consists of 88 full-length irradiated fuel rods with rod-average burnups of about 2400 GJ/kgM (28 MWd/kgM) and expected fission gas release of about 1%. Characterization data include (1) descriptions of as-fabricated fuel design, irradiation history, and subsequent storage and handling; (2) isotopic gamma scans; (3) fission gas analyses; (4) ...

1991-12-01

66

IAEA and nuclear forensics  

International Nuclear Information System (INIS)

Nuclear forensics can provide information about the history, intended use and potentially the origin of nuclear or radioactive material. For these reasons, it is an important tool for improving nuclear security and combating illicit trafficking of nuclear and other radioactive materials. The IAEA is currently working on enhancing knowledge, techniques, procedures and cooperation in the field of nuclear forensics. Some of the work currently being undertaken by the IAEA includes the development of a five day training workshop on basic methods for radiological crime scene activities, to ensure adequate control of evidence, including for nuclear forensics purposes, a coordinated research project on the application of nuclear forensics in illicit trafficking, and a proposal for international cooperation ...

67

NPD Canada's first nuclear power station  

Energy Technology Data Exchange (ETDEWEB)

This talk reviews the history of the Canadian nuclear-electric program highlighting Canada's first nuclear power station, the Nuclear Power Demonstration or NPD. NPD was commissioned and delivered electricity to Canadian consumers for the first time on june 4, 1962. The Canadian nuclear-electric program is based on the CANDU-PHW (Canadian Deuterium Uranium - Pressurized Heavy Water) concept which was conceived between 1955 and 1958 at the Chalk River Nuclear Laboratory (CRNL) of AECL, located a few miles from Deep River. This talk covers the history of the Canadian nuclear-electric activities dating back to 1939.

2002-07-01

68

OAK RIDGE NATIONAL LABORATORY UNION CARBIDE CORPORATION NUCLEAR ...  

Science.gov (United States)

W. Wayne Scott, Chattanooga State Technical Institute, 4501 Amnico Highway,. Chattanooga, Tennessee 3401. Robert L. Seale, University of Arizona, Tuscon, ...

69

Nuclear waste plans enter critical phase  

Energy Technology Data Exchange (ETDEWEB)

A brief article considers the possible result of the enquiry into Nirex`s plan to build an underground rock laboratory at Sellafield in relation to radioactive waste disposal in the UK. (UK).

1996-10-31

70

Real-time 3-D SAFT-UT system evaluation and validation  

International Nuclear Information System (INIS)

SAFT-UT technology is shown to provide significant enhancements to the inspection of materials used in US nuclear power plants. This report provides guidelines for the implementation of SAFT-UT technology and shows the results from its application. An overview of the development of SAFT-UT is provided so that the reader may become familiar with the technology. Then the basic fundamentals are presented with an extensive list of references. A comprehensive operating procedure, which is used in conjunction with the SAFT-UT field system developed by Pacific Northwest Laboratory (PNL), provides the recipe for both SAFT data acquisition and analysis. The specification for the hardware implementation is provided for the SAFT-UT system along with a description of the subsequent developments and improvements. One development of technical interest is the SAFT real time processor. Performance of the real-time processor is impressive ...

1993-05-17

71

Laboratory robotics projects in the Analytical Development Division at the Savannah River Laboratory  

International Nuclear Information System (INIS)

To encourage the application of robotics technology for routine radiobench applications, a laboratory dedicated to the research and development of contained robotic systems is being constructed. The facility will have several robots located in laminar flow hoods, and the hoods are being designed to allow the possibility for multiple robots to work together. This paper presents both the design features of the hoods and the general layout of the laboratory, and also discusses an application of a robotic system for the routine nuclear counting of gamma tube samples. The gamma tube system is presently operating in one of the routine analysis laboratories. 5 figs.

72

Defense Threat Reduction Agency Radiochemical Needs  

International Nuclear Information System (INIS)

The United States Government (USG) first developed nuclear forensics-related capabilities to analyze radiological and nuclear materials, including underground nuclear test debris and interdicted materials. Nuclear forensics is not a new mission for Department of Defense (DoD). The department's existing nuclear forensics capability is the result of programs that span six (6) decades and includes activities to assess foreign nuclear weapons testing activities, monitor and verify nuclear arms control treaties, and to support intelligence and law enforcement activities. Today, nuclear forensics must support not only weapons programs and nuclear smuggling incidents, but also the scientific analysis and subsequent attribution of terrorists' use of radiological or ...

2009-08-19

74

A CONCEPT FOR NATIONAL NUCLEAR FORENSIC LIBRARIES  

International Nuclear Information System (INIS)

The interpretation of data from the nuclear forensic analysis of illicit nuclear material of unknown origin requires comparative data from samples of known origin. One way to provide such comparative data is to create a system of national nuclear forensics libraries, in which each participating country stores information about nuclear or other radioactive material that either resides in or was manufactured by that country. Such national libraries could provide an authoritative record of the material located in or produced by a particular country, and thus forms an essential prerequisite for a government to investigate illicit uses of nuclear or other radioactive material within its borders. We describe the concept of the national nuclear forensic library, recommendations for ...

2010-07-11

75

Nuclear forensic investigations with a focus on plutonium  

International Nuclear Information System (INIS)

Since the beginning of the 1990s when the first seizures of nuclear material were reported, the IAEA has recorded over 200 cases of illicit trafficking of nuclear materials. Despite the decreasing frequency of nuclear material seizures, particularly the ones involving weapons-grade material, the issue continues to attract public attention and is a reason for concern due to the hazard associated with such materials. Once illicitly trafficked nuclear material has been intercepted, the questions of its intended use and origin are to be addressed. Especially the origin is of prime importance in order to close the gaps and improve the physical protection at the sites where the theft or diversion occurred. To answer these questions, a dedicated nuclear forensics ...

2007-10-11

76

Detection of previous neutron irradiation and reprocessing of uranium materials for nuclear forensic purposes  

International Nuclear Information System (INIS)

The paper describes novel analytical methods developed for the detection of previous neutron irradiation and reprocessing of illicit nuclear materials, which is an important characteristic of nuclear materials of unknown origin in nuclear forensics. Alpha spectrometry and inductively coupled plasma sector-field mass spectrometry (ICP-SFMS) using solution nebulization and direct, quasi-non-destructive laser ablation as sample introduction were applied for the measurement of trace-level "2"3"2U, "2"3"6U and plutonium isotopes deriving from previous neutron irradiation of uranium-containing nuclear materials. The measured radionuclides and isotope ratios give important information on the raw material used for fuel production and enable confirm the supposed provenance of illicit nuclear ...

2009-04-01

77

Subcritical Noise Analysis Measurements with Fresh and Spent Research Reactor Fuels Elements  

Energy Technology Data Exchange (ETDEWEB)

The verification of the subcriticality is of utmost importance for the safe transportation and storage of nuclear reactor fuels. Transportation containers and storage facilities are designed such that nuclear fuels remain in a subcritical state. Such designs often involve excess conservatism because of the lack of relevant experimental data to verify the accuracy of Monte Carlo codes used in nuclear criticality safety analyses. A joint experimental research program between Oak Ridge National Laboratory, Westinghouse Safety Management Solutions, Inc., and the University of Missouri was initiated to obtain measured quantities that could be directly related to the subcriticality of simple arrays of Missouri University Research Reactor (MURR) fuel elements. A series of measurement were performed to assess the reactivity of materials such as BORAL, stainless steel, aluminum, and lead ...

1999-02-01

78

Regulatory compliance | Mott MacDonald  

Wastenet

...broad range of experience in designing and building research and development laboratories for products such as vaccines, blood and sera, biological products, medical devices, solid dosage forms , highly potent products and cytotoxic material. We also have experience in a range of modular laboratories for TSE research, ...

79

Laboratory Evaluation of Base Materials for Neutralization of the Contaminated Aquifer at the F-Area Seepage Basins  

Energy Technology Data Exchange (ETDEWEB)

Laboratory studies were performed to support field-testing of base injection into the F-Area Seepage Basins groundwater. The general purpose of these experiments is to provide information to guide the test of base injection and to identify potential adverse effects.

2001-09-11

80

The Performance of Spent Fuel Casks in Severe Tunnel Fires  

International Nuclear Information System (INIS)

The Nuclear Regulatory Commission (NRC), working with the National Institute of Standards and Technology (NIST), Pacific Northwest National Laboratory (PNNL), and the National Transportation Safety Board (NTSB), performed analyses to predict the response of various spent fuel transportation cask designs when exposed to a fire similar to that which occurred in the Howard Street railroad tunnel in downtown Baltimore, Maryland on July 18, 2001. The thermal performance of three different spent fuel cask designs (HOLTEC HI-STAR 100, TransNuclear TN-68, and NAC-LWT) was evaluated with the ANSYSR and COBRA-SFS analysis codes, utilizing boundary conditions for the tunnel fire obtained using NIST's Fire Dynamics Simulator (FDS) code. NRC Staff evaluated the potential for a release of radioactive material from each of the three transportation casks analyzed for the Baltimore tunnel fire scenario. The results of ...

2005-11-01

81

Progress at LAMPF, 1992--1993  

Energy Technology Data Exchange (ETDEWEB)

This Progress Report describes the operation of the Los Alamos Meson Physics Facility (LAMPF) and the research programs carried out there for the years 1992 and 1993. The accelerator operated for over 100 days in 1992, providing beams of H{sup +}, H{sup {minus}}, and polarized H{sup {minus}} for a rich and varied research program in nuclear physics. The accelerator had only fair beam availability in 1992 (for example, the average H{sup +} beam availability was 72%), caused largely by problems in the 201-MHz rf system. A major effort was expended to address these problems before the 1993 run. These efforts were rewarded by good beam availability in 1993 and few problems with the 201-MHz system. LAMPF operated remarkably smoothly during 1993, in the midst of a period of great uncertainty in the future of the facility and the downsizing of MP Division, which led to the loss of a large number of key people to positions elsewhere in the Laboratory. ...

1994-07-25

82

Nuclear Reactor Sharing Program  

Energy Technology Data Exchange (ETDEWEB)

The Ohio State University Research Reactor (OSURR) is licensed to operate at a maximum power level of 500 kW. A pool-type reactor using flat-plate, low enriched fuel elements, the OSURR provides several experimental facilities including two 6-inch i.d. beam ports, a graphite thermal column, several graphite-isotope-irradiation elements, a pneumatic transfer system (Rabbit), various dry tubes, and a Central Irradiation Facility (CIF). The core arrangement and accessibility facilitates research programs involving material activation or core parameter studies. The OSURR control room is large enough to accommodate laboratory groups which can use control instrumentation for monitoring of experiments. The control instrumentation is relatively simple, without a large amount of duplication. This facilitates opportunities for hands-on experience in reactor operation by nuclear engineering students making reactor parameter ...

1994-09-01

83

Fabrication of zircon for disposition of weapons plutonium  

International Nuclear Information System (INIS)

This is the final report of a one-year, Laboratory-Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). In an effort to address the problems of long term storage and nuclear waste minimization, zircon has been proposed as a host medium for plutonium and other actinides recovered from dismantled nuclear weapons. The objective of this work is to investigate the feasibility of large scale fabrication of Pu-bearing zircon. Since PuO_2 is thermodynamically less stable than ZrO_2, it is expected that the process parameters determined for synthesizing ZrSiO_4 (zircon) would be applicable to those for PuSiO_4 (Pu-zircon). Furthermore, since the foremost concern in plutonium processing is the potential for contamination release, this work emphasizes the development of process parameters, using zircon first, to anticipate potential material problems ...

84

DEVELOPMENT OF PROTOTYPE TITANATE ION EXCHANGE LOADED MEMBRANES FOR STRONTIUM, CESIUM AND ACTINIDE DECONTAMINATION FROM AQUEOUS MEDIA  

International Nuclear Information System (INIS)

We have successfully incorporated high surface area particles of titanate ion exchange materials (monosodium titanate and crystalline silicotitanate) with acceptable particle size distribution into porous and inert support membrane fibrils consisting of polytetrafluoroethylene (Teflon(reg_sign)), polyethylene and cellulose materials. The resulting membrane sheets, under laboratory conditions, were used to evaluate the removal of surrogate radioactive materials for cesium-137 and strontium-90 from high caustic nuclear waste simulants. These membrane supports met the nominal requirement for nonchemical interaction with the embedded ion exchange materials and were porous enough to allow sufficient liquid flow. Some of this 47-mm size stamped out prototype titanium impregnated ion exchange membrane discs was found to remove more than 96% of dissolved cesium-133 and ...

2008-05-30

85

Tamper indicating packaging  

International Nuclear Information System (INIS)

Protecting sensitive items from undetected tampering in an unattended environment is crucial to the success of non-proliferation efforts relying on the verification of critical activities. Tamper Indicating Packaging (TIP) technologies are applied to containers, packages, and equipment that require an indication of a tamper attempt. Examples include: the transportation and storage of nuclear material, the operation and shipment of surveillance equipment and monitoring sensors, and the retail storage of medicine and food products. The spectrum of adversarial tampering ranges from attempted concealment of a pin-hole sized penetration to the complete container replacement, which would involve counterfeiting efforts of various degrees. Sandia National Laboratories (SNL) has developed a technology base for advanced TIP materials, sensors, designs, and processes which can be adapted to various future ...

1994-07-17

86

Initiation of depleted uranium oxide and spent fuel testing for the spent fuel sabotage aerosol ratio programme  

Energy Technology Data Exchange (ETDEWEB)

We provide a detailed overview of an on-going, multinational test programme that is developing aerosol data for some spent fuel sabotage scenarios on spent fuel transport and storage casks. Experiments are being performed to quantify the aerosolised materials plus volatilised fission products generated from actual spent fuel and surrogate material test rods, due to impact by a high-energy/density device. The programme participants in the United States plus Germany, France and the United Kingdom, part of the international Working Group for Sabotage Concerns of Transport and Storage Casks (WGSTSC) have strongly supported and coordinated this research programme. Sandia National Laboratories has the lead role for conducting this research programme; test programme support is provided by both the US Department of Energy and the US Nuclear Regulatory Commission. We provide a summary of the overall, multiphase ...

2004-07-01

87

Initiation of depleted uranium oxide and spent fuel testing for the spent fuel sabotage aerosol ratio programme  

International Nuclear Information System (INIS)

We provide a detailed overview of an on-going, multinational test programme that is developing aerosol data for some spent fuel sabotage scenarios on spent fuel transport and storage casks. Experiments are being performed to quantify the aerosolised materials plus volatilised fission products generated from actual spent fuel and surrogate material test rods, due to impact by a high-energy/density device. The programme participants in the United States plus Germany, France and the United Kingdom, part of the international Working Group for Sabotage Concerns of Transport and Storage Casks (WGSTSC) have strongly supported and coordinated this research programme. Sandia National Laboratories has the lead role for conducting this research programme; test programme support is provided by both the US Department of Energy and the US Nuclear Regulatory Commission. We provide a summary of the overall, multiphase ...

88

Initiation of depleted uranium oxide and spent fuel testing for the spent fuel sabotage aerosol ratio program.  

Energy Technology Data Exchange (ETDEWEB)

The authors provide a detailed overview of an on-going, multinational test program that is developing aerosol data for some spent fuel sabotage scenarios on spent fuel transport and storage casks. Experiments are being performed to quantify the aerosolized materials plus volatilized fission products generated from actual spent fuel and surrogate material test rods, due to impact by a high-energy-density device. The program participants in the United States plus Germany, France and the United Kingdom, part of the international Working Group for Sabotage Concerns of Transport and Storage Casks (WGSTSC) have strongly supported and coordinated this research program. Sandia National Laboratories has the lead role for conducting this research program; test program support is provided by both the US Department of Energy and the US Nuclear Regulatory Commission. The authors provide a summary of the overall, ...

2004-08-01

89

Initiation of depleted uranium oxide and spent fuel testing for the spent fuel sabotage aerosol ratio program  

International Nuclear Information System (INIS)

The authors provide a detailed overview of an on-going, multinational test program that is developing aerosol data for some spent fuel sabotage scenarios on spent fuel transport and storage casks. Experiments are being performed to quantify the aerosolized materials plus volatilized fission products generated from actual spent fuel and surrogate material test rods, due to impact by a high-energy-density device. The program participants in the United States plus Germany, France and the United Kingdom, part of the international Working Group for Sabotage Concerns of Transport and Storage Casks (WGSTSC) have strongly supported and coordinated this research program. Sandia National Laboratories has the lead role for conducting this research program; test program support is provided by both the US Department of Energy and the US Nuclear Regulatory Commission. The authors provide a summary of the overall, ...

90

Applications of polymeric smart materials to environmental problems.  

UK PubMed Central (United Kingdom)

New methods for the reduction and remediation of hazardous wastes like carcinogenic organic solvents, toxic materials, and nuclear contamination are vital to environmental health. Procedures for effective...Full Text Available

1997-02-01

91

Nuclear raw materials: Developing resources through technical co-operation  

International Nuclear Information System (INIS)

This article presents an overview of the IAEA's technical co-operation activities in the field of nuclear raw materials, particularly looking at recent developments and trends influencing future directions

1993-09-01

92

Abstracts of 5. International conference 'Nuclear and Radiation Physics'  

International Nuclear Information System (INIS)

The 5-th International conference 'Nuclear and Radiation Physics' was held in Almaty (Kazakhstan) 26-29 September 2005. Besides basic problems of nuclear and solid state physics the conference paid considerable attention to applied topics important for industry and science in Kazakhstan; they include fuel and construction materials for nuclear power production, new technologies and materials for their production, materials for hydrogen power production, handling and utilization of radioactive waste, analytical methods for combating with illicit trafficking of nuclear and radioactive materials, technologies for reduction and assessment of environmental risk from radiation-hazardous materials and sites, production and application of isotopes, application of nuclear technologies in ...

2005-09-26

94

Fuel cycle of reactor SVBR-100  

International Nuclear Information System (INIS)

... fast reactors fbr type reactors fuels liquid metal cooled reactors materials nuclear

95

NASA - A Cosmic Inkblot Test  

Science.gov (United States)

material may survive intact and mix back into interstellar gas clouds, helping to fuel the next generation of stars. NASA's Jet Propulsion Laboratory, Pasadena, Calif.,...

2011-08-10

98

Sandia National Laboratories support of the Iraq Nuclear Facility Dismantlement and Disposal Program.  

Energy Technology Data Exchange (ETDEWEB)

Because of past military operations, lack of upkeep and looting there are now enormous radioactive waste problems in Iraq. These waste problems include destroyed nuclear facilities, uncharacterized radioactive wastes, liquid radioactive waste in underground tanks, wastes related to the production of yellow cake, sealed radioactive sources, activated metals and contaminated metals that must be constantly guarded. Iraq currently lacks the trained personnel, regulatory and physical infrastructure to safely and securely manage these facilities and wastes. In 2005 the International Atomic Energy Agency (IAEA) agreed to organize an international cooperative program to assist Iraq with these issues. Soon after, the Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) was initiated by the U.S. Department of State (DOS) to support the IAEA and assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled ...

2009-03-01

99

RangerMaster{trademark}: Real-time pattern recognition software for in-field analysis of radiation sources  

Energy Technology Data Exchange (ETDEWEB)

RangerMaster{trademark} is the embedded firmware for Quantrad Sensor`s integrated nuclear instrument package, the Ranger{trademark}. The Ranger{trademark}, which is both a gamma-ray and neutron detection system, was originally developed at Los Alamos National Laboratory for in situ surveys at the Plutonium Facility to confirm the presence of nuclear materials. The new RangerMaster{trademark} software expands the library of isotopes and simplifies the operation of the instrument by providing an easy mode suitable for untrained operators. The expanded library of the Ranger{trademark} now includes medical isotopes {sup 99}Tc, {sup 201}Tl, {sup 111}In, {sup 67}Ga, {sup 133}Xe, {sup 103}Pa, and {sup 131}I; industrial isotopes {sup 241}Am, {sup 57}Co, {sup 133}Ba, {sup 137}Cs, {sup 40}K, {sup 60}Co, {sup 232}Th, {sup 226}Ra, and {sup 207}Bi; and nuclear materials {sup ...

1998-12-31

100

Department of Nuclear Safety Research and Nuclear Facilities annual report 1995  

Energy Technology Data Exchange (ETDEWEB)

The report presents a summary of the work of the Department of Nuclear Safety Research and Nuclear Facilities in 1995. The department`s research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 5 tabs., 21 ills.

1996-03-01

101

Spent Fuel Transportation Package Response to the Baltimore Tunnel Fire Scenario  

International Nuclear Information System (INIS)

On July 18, 2001, a freight train carrying hazardous (non-nuclear) materials derailed and caught fire while passing through the Howard Street railroad tunnel in downtown Baltimore, Maryland. The United States Nuclear Regulatory Commission (USNRC), one of the agencies responsible for ensuring the safe transportation of radioactive materials in the United States, undertook an investigation of the train derailment and fire to determine the possible regulatory implications of this particular event for the transportation of spent nuclear fuel by railroad. Shortly after the accident occurred, the USNRC met with the National Transportation Safety Board (NTSB, the U.S. agency responsible for determining the cause of transportation accidents), to discuss the details of the accident and the ensuing fire. Following these discussions, the USNRC assembled a team of experts from the National ...

2006-11-01

102

Bibliography of the technical literature of the Materials Joining Group, 1951--1991  

Energy Technology Data Exchange (ETDEWEB)

This document contains a listing of the written scientific information originating in the Materials Joining (formerly the Welding and Brazing Group), Metals and Ceramics Division, Oak Ridge National Laboratory during 1951 through June 1991. This registry of documents is as much as possible, in the order of issue date.

1991-12-01

103

Laboratory for characterization of spent nuclear fuel and high/medium level radioactive waste. Experimental results and performances  

International Nuclear Information System (INIS)

During the phases of separation, treatment, conditioning and storage of radioactive waste, destructive and nondestructive methods for their characterization are needed. In order to satisfy this necessity, in the frame of the National Program of Research and Development, the 'Laboratory for characterization of spent nuclear fuel and high/medium level radioactive waste- LABORAD' was created. The purpose of the project was to accredit the analysis methods available in the laboratory, and also to develop new methods for the characterization of the radioactive waste. A special attention was paid to the high-level radioactive waste and spent nuclear fuel characterization that require special facilities for handling. These facilities (e.g. hot cells, remote handlers, transport container) are already available in our institute. Experimental results and performances obtained during validation of the methods are ...

2009-05-27

104

Initiation of depleted uranium oxide and spent fuel testing for the spent fuel sabotage aerosol ratio program  

Energy Technology Data Exchange (ETDEWEB)

We provide a detailed overview of an ongoing, multinational test program that is developing aerosol data for some spent fuel sabotage scenarios on spent fuel transport and storage casks. Experiments are being performed to quantify the aerosolized materials plus volatilized fission products generated from actual spent fuel and surrogate material test rods, due to impact by a high energy density device, HEDD. The program participants in the U.S. plus Germany, France, and the U.K., part of the international Working Group for Sabotage Concerns of Transport and Storage Casks, WGSTSC have strongly supported and coordinated this research program. Sandia National Laboratories, SNL, has the lead role for conducting this research program; test program support is provided by both the U.S. Department of Energy and Nuclear Regulatory Commission. WGSTSC partners need this research to better understand potential ...

2004-07-01

105

Challenges in ensuring radiological safety and nuclear forensic for malicious acts involving nuclear and other radioactive material  

International Nuclear Information System (INIS)

Nuclear and other radioactive materials may get smuggled into the country aimed at malicious acts. Radioactive material detected accidentally or during inspection at the entry points/national borders may indicate illicit trafficking for the purpose of nuclear/radiological terrorism. As country requires prevention and preparedness for response to these malicious acts, nuclear forensic techniques are to be developed incorporating radiological safety aspects. Nuclear forensics helps in determining the origin, intended use, legal owner and the smuggled route etc. by using fingerprinting as well as comparison with reference data. The suggested sequence of methods for analysis of radioactive material/samples will be radiological assessment, physical characterization, traditional forensic analysis, isotope analysis along with elemental/chemical ...

2010-11-15

106

Effect of boric acid on steam generator corrosion  

International Nuclear Information System (INIS)

Project RPS116, ''Implementation of Boric Acid in the Field,'' was designed to demonstrate that a selected steam generator boric acid treatment is effective in arresting the progressing of denting in an operating steam generator. The PWR nuclear steam generators chosen for the testing were those at the Indian Point Unit 3 nuclear site. Hydrogen monitoring measurements and eddy current examinations had indicated that the Indian Point Unit 3, Series 44 steam generators had already reached an advanced stage of denting and tube support plate ligament discontinuities were observed. The objective of the boric acid treatment was to reduce the rate of denting by attempting to reproduce in the field the positive results achieved with boric acid in laboratory-simulated denting tests. Laboratory testing has indicated that implementation of a four day low power (25% power) boric acid soak with 50 ppm boron as boric ...

1985-03-01

107

Laboratory Directed Research and Development (LDRD) on Mono-uranium Nitride Fuel Development for SSTAR and Space Applications  

Energy Technology Data Exchange (ETDEWEB)

The US National Energy Policy of 2001 advocated the development of advanced fuel and fuel cycle technologies that are cleaner, more efficient, less waste-intensive, and more proliferation resistant. The need for advanced fuel development is emphasized in on-going DOE-supported programs, e.g., Global Nuclear Energy Initiative (GNEI), Advanced Fuel Cycle Initiative (AFCI), and GEN-IV Technology Development. The Directorates of Energy & Environment (E&E) and Chemistry & Material Sciences (C&MS) at Lawrence Livermore National Laboratory (LLNL) are interested in advanced fuel research and manufacturing using its multi-disciplinary capability and facilities to support a design concept of a small, secure, transportable, and autonomous reactor (SSTAR). The E&E and C&MS Directorates co-sponsored this Laboratory Directed Research & Development (LDRD) Project on ...

2006-02-09

108

Review of the study and application on nuclear forensic analysis  

International Nuclear Information System (INIS)

For the interests of national security, many scientists who work in the field of nuclear forensic analysis have carried out extensive work in the past on the detection of radioactive material and attributions study, developed a series of scientific and technical means to trace and detect illicit circulation of nuclear materials used to weapons and other radioactive materials which impair public security. All these questions relate to physical, chemical, biological attribution of materials. The nuclear forensic analysis has already become a special, up-to-date sphere of learning. The goal of the study of nuclear forensics is to prevent terrorists from acquiring not only nuclear weapons but also mate- rials that can be used to make such weapons, including radioactive materials for ...

2009-12-01

109

The use of the isotope "3"2P in the study of some ecological aspects of a laboratory stream ecosystem  

International Nuclear Information System (INIS)

A laboratory stream consisting of two stream sections interrupted by two pools was filled with a mixture of tap water and organically enriched water from rivers nearby. Bottom sediment material, Potamogeton pectinatus, macro-invertebrate organisms, as well as the mosquito fish, Aplocheilichthys johnstonii were collected from rivers around Johannesburg and introduced into the laboratory stream. After initial acclimatization, the distribution of the isotope "3"2P through this laboratory stream was followed. Absorption of this isotope by benthic algae, Potamogeton pectinatus, several macro-invertebrate organisms as well as Aplocheilichthys johnstonii was recorded.

110

Optimization of an interlaboratory program for the certification of a multi-element plagiogneiss reference material  

International Nuclear Information System (INIS)

A sample of garnet-biotite plagiogneiss, GBPg-1 is currently being developed as a certified reference material at the Vinogradov Institute of Geochemistry. It was used as the sample that was distributed round 7 of International Proficiency Testing Program (GeoPT7) and was analyzed by 76 geoanalytical laboratories around the world. Twenty Russian laboratories involved in the interlaboratory experiment also analyzed GBPg-1. The resultant analytical data obtained from these two experiments has allowed GBPg-1 to be certified as a state standard sample for 50 elements. It also enabled a comparison of the quality of data developed by the Russian and international geoanalytical laboratories, to optimize the outcome of this interlaboratory experiment.

2003-02-03

111

Materials issues in coal-fired combined cycle power generation systems: laboratory versus plant testing  

Energy Technology Data Exchange (ETDEWEB)

The successful development of coal-fired combined cycle power generation systems require that all component parts are manufactured from appropriate materials and that these materials give predictable in-service performance. High temperature corrosion resulting from coal-derived particulates, deposition and gaseous species, is potentially life limiting for many components in these systems. Realistic laboratory test methods are outlined for gasifier and gas turbine environments and these have been combined with a materials assessment method based on accurate dimensional metrology. Such tests have allowed the production of models of materials performance as well as accurate comparisons between laboratory and plant derived data. These initial models predict the performance of materials well in the gas turbine environment, but tend to ...

1997-12-31

112

Materials/manufacturing element of the Advanced Turbine System Program  

Energy Technology Data Exchange (ETDEWEB)

One of the supporting elements of the Advanced Turbine Systems (ATS) Program is the materials/manufacturing technologies task. The objective of this element is to address critical materials issues for both industrial and utility gas turbines. DOE Oak Ridge Operations Office (ORO) will manage this element of the program, and a team from DOE-ORO and Oak Ridge National Laboratory is coordinating the planning for the materials/manufacturing effort. This paper describes that planning activity which is in the early stages.

1994-08-01

113

Radiation processing in Hungary  

Energy Technology Data Exchange (ETDEWEB)

Hungary has 10.7 million population in 100,000 km/sup 2/ territory. The gross national product is about $3,000 per capita per year. Hungary is a country with highly developed agriculture and medium degree developed industries. The Hungarian economy is an open economy because more than 40% of the national income is earned by export. The research and development works on various radiation processing have been performed for 25 years. In the Central Research Institute for Physics of the Hungarian Academy of Sciences, a laboratory was organized for the basic research of radiation chemistry and the moderator materials for nuclear reactors. Also the activities in the Central Research Institute for Chemistry, the Institute of Isotopes, the Research Institute for Plastics Industry, and the Central Research Institute for Food Industry are briefly reported. The largest radiation processing unit in Hungary is the automatic ...

1982-01-01

114

Quarterly progress report for the Chemical and Energy Research Section of the Chemical Technology Division: January--March 1997  

Energy Technology Data Exchange (ETDEWEB)

This report summarizes the major activities conducted in the Chemical and Energy Research Section of the Chemical Technology Division (CTD) at Oak Ridge National Laboratory (ORNL) during the period January--March 1997. Created in March 1997 when the CTD Chemical Development and Energy Research sections were combined, the Chemical and Energy Research Section conducts basic and applied research and development in chemical engineering, applied chemistry, and bioprocessing, with an emphasis on energy-driven technologies and advanced chemical separations for nuclear and waste applications. The report describes the various tasks performed within seven major areas of research: Hot Cell Operations, Process Chemistry and Thermodynamics, Molten Salt Reactor Experiment (MSRE) Remediation Studies, Chemistry Research, Separations and Materials Synthesis, Solution Thermodynamics, and Biotechnology Research. The name of a technical ...

1998-01-01

115

DYMAC communications system  

Energy Technology Data Exchange (ETDEWEB)

The DYMAC Communications System is part of a nuclear safeguards system called DYMAC - short for DYnamic Materials ACcountability - that gathers accountability information at the Los Alamos Scientific Laboratory (LASL) Plutonium Processing Facility. The communications system handles transmissions between data-entry terminals and nondestructive assay (NDA) instruments located in the facility, and a computer located in an adjacent building. System design emphasizes reliability rather than high speed to ensure the integrity of data transmissions. This manual is directed toward the person responsible for maintaining the DYMAC Communication System. It describes the components that make up the communications network, explains how they operate, and gives detailed information about all of the connections. Many of the system components are commercially available; some have been modified at LASL for DYMAC purposes; others were ...

1980-01-01

116

Accelerated aging tests of liners for uranium mill tailings disposal  

Energy Technology Data Exchange (ETDEWEB)

This document describes the results of accelerated aging tests to determine the long-term effectiveness of selected impoundment liner materials in a uranium mill tailings environment. The study was sponsored by the US Department of Energy under the Uranium Mill Tailings Remedial Action Project. The study was designed to evaluate the need for, and the performance of, several candidate liners for isolating mill tailings leachate in conformance with proposed Environmental Protection Agency and Nuclear Regulatory Commission requirements. The liners were subjected to conditions known to accelerate the degradation mechanisms of the various liners. Also, a test environment was maintained that modeled the expected conditions at a mill tailings impoundment, including ground subsidence and the weight loading of tailings on the liners. A comparison of installation costs was also performed for the candidate liners. The laboratory ...

1981-11-01

117

APSTNG: Neutron interrogation for detection of nuclear and CW weapons, explosives, and drugs  

Energy Technology Data Exchange (ETDEWEB)

A recently developed neutron diagnostic probe system has the potential to satisfy a significant number of van-mobile and fixed- portal requirements for nondestructive verification of sealed munitions and detection of contraband explosives and drugs. The probe is based on a unique associated-particle sealed-tube neutron generator (APSTNG) that interrogates the object of interest with a low-intensity beam of 14-MeV neutrons generated from the deuterium-tritium reaction and that detects the alpha-particle associated with each neutron. Gamma-ray spectra of resulting neutron inelastic scattering and fission reactions identify nuclides associated with all major chemicals in chemical warfare agents, explosives, and drugs, as well as many pollutants and fissile and fertile special nuclear material. Flight times determined from determined from detection times of the gamma-rays and alpha-particles yield a separate tomographic image of each identified ...

1992-07-01

118

Nuclear astrophysics with radioactive ion beams  

International Nuclear Information System (INIS)

Nuclear astrophysics seeks for a possible explanation of the observed abundance distribution of various elements and their isotopes in the universe. Most of the relevant nuclear reactions take place in thermally equilibrium environments with bare nuclei, rather than accelerated and head-on colliding situations with low ionisation states of reactant atoms and molecules that are emulated in the laboratories. Moreover, the temperature of the astrophysical environments is quite often low compared to the centre-of-mass energy of the projectile nuclides, that is required for the reaction to be meaningfully investigated in the laboratory. Therefore, an extrapolation of the data on the reaction cross sections to very low energies and to extremely high density situations is generally called for, which are substantially altered every now and then for a number of astrophysically important reactions. The ...

119

Nuclear Forensics and Attribution for Improved Energy Security: The Use of Taggants in Nuclear Fuel  

International Nuclear Information System (INIS)

The Global Nuclear Energy Partnership (GNEP), recently announced by DOE Secretary Bodman, poses significant new challenges with regard to securing, safeguarding, monitoring and tracking nuclear materials. In order to reduce the risk of nuclear proliferation, new technologies must be developed to reduce the risk that nuclear material can be diverted from its intended use. Regardless of the specific nature of the fuel cycle, nuclear forensics and attribution will play key roles to ensure the effectiveness of nonproliferation controls and to deter the likelihood of illicit activities. As the leader of the DHS nuclear and radiological pre-detonation attribution program, LLNL is uniquely positioned to play a national leadership role in this effort. Ensuring that individuals or organizations engaged in illicit trafficking are ...

120

International technical working group cooperation to counter illicit nuclear trafficking  

International Nuclear Information System (INIS)

The Nuclear Smuggling International Technical Working Group (ITWG) is an international group of nuclear forensic experts that cooperate to deter the illicit trafficking of nuclear materials. The objective of the ITWG is to provide a common approach and effective technical solutions to governments who request assistance in nuclear forensics. The ITWG was chartered in 1996 and since that time more than 28 nations and organizations have participated in 9 international meetings and 2 analytical round-robin trials. Soon after its founding the ITWG adopted a general framework to guide nuclear forensics investigations that includes recommendations for nuclear crime scene security and analysis, the best application of radioanalytical methods, the conduct of traditional forensic analysis of contaminated materials, and effective ...

2004-10-01

121

Materials/manufacturing element of the Advanced Turbine Systems Program  

Energy Technology Data Exchange (ETDEWEB)

The technology based portion of the Advanced Turbine Systems Program (ATS) contains several subelements which address generic technology issues for land-based gas-turbine systems. One subelement is the Materials/ Manufacturing Technology Program which is coordinated by DOE Oak Ridge Operations and Oak Ridge National Laboratory (ORNL). The work in this subelement is being performed predominantly by industry with assistance from universities and the national laboratories. Projects in this sub-element are aimed toward hastening the incorporation of new materials and components in gas turbines.

1995-12-31

122

Electromagnetic coupling of high-altitude, nuclear electromagnetic pulses  

International Nuclear Information System (INIS)

We have used scale models to measure the predicted coupling of electromagnetic fields simulating the effects of high-altitude nuclear electromagnetic pulses (HEMP) on the interior surfaces of electronic components. Predictive tools for exterior coupling are adequate. For interior coupling, however, such tools are in their infancy. Our methodological approach combines analytical, computational, and laboratory techniques in a complementary way to take advantage of their separate strengths. Computer models are a promising tool, as they can be used to treat complex objects with arbitrary shapes, dielectrics, and cables, and multiple apertures. Laboratory tests can expand the domain of investigation even further.

1984-11-01

123

Idaho National Laboratory 2013-2022 Ten-Year Site Plan  

Energy Technology Data Exchange (ETDEWEB)

The Idaho National Laboratory (INL) Ten-Year Site Plan (TYSP) describes the strategy for accomplishing the long-term objective of transforming the laboratory to meet Department of Energy (DOE) national nuclear research and development (R&D) goals, as outlined in DOE strategic plans. The plan links R&D mission goals and INL core capabilities with infrastructure requirements (single- and multi-program), establishs the 10-year end-state vision for INL complexes, and identifies and prioritizes infrastructure needs and capability gaps. The TYSP serves as the basis for documenting and justifying infrastructure investments proposed as part of the FY 2013 budget formulation process.

2011-06-01

124

Environmental Measurements Laboratory fiscal year 1998: Accomplishments and technical activities  

Energy Technology Data Exchange (ETDEWEB)

The Environmental Measurements Laboratory (EML) is government-owned, government-operated, and programmatically under the DOE Office of Environmental Management. The Laboratory is administered by the Chicago Operations Office. EML provides program management, technical assistance and data quality assurance for measurements of radiation and radioactivity relating to environmental restoration, global nuclear nonproliferation, and other priority issues for the Department of Energy, as well as for other government, national, and international organizations. This report presents the technical activities and accomplishments of EML for Fiscal Year 1998.

1999-01-01

125

Energy and technology review  

Energy Technology Data Exchange (ETDEWEB)

The state of the laboratory address by LLNL Director Roger Batzel is summarized, and a breakdown of the laboratory funding is given. The Livermore defense-related committment is described, including the design and development of advanced nuclear weapons as well as research in inertial confinement fusion, nonnuclear ordnance, and particle beam technology. LLNL is also applying its scientific and engineering resources to the dual challenge of meeting future energy needs without degrading the quality of the biosphere. Some representative examples are given of the supporting groups vital for providing the specialized expertise and new technologies required by the laboratory's major research programs. (GHT)

1982-07-01

126

Real time operating system for a nuclear power plant computer  

International Nuclear Information System (INIS)

A quadruply redundant synchronous fault tolerant processor (FTP) is now under fabrication at the C.S. Draper Laboratory to be used initially as a trip monitor for the Experimental Breeder Reactor EBR-II operated by the Argonne National Laboratory in Idaho Falls, Idaho. The real time operating system for this processor is described.

1986-09-01

127

Study of the physical and mechanical changes in packaging materials used in radiation processing - measuring methods of physical and mechanical properties  

International Nuclear Information System (INIS)

The behaviour of the packaging materials under radiation field has a great importance in radiation processing, because, in most cases, they are finally responsible for the preservation of the beneficent changes achieved in irradiated products. For example, in radiation sterilisation and food irradiation, the packages must preserve the sterilisation, respectively the sanitisation. They must preserve also the physical barrier feature. The radiation effects on plastics were extensively studied in the last decades for nuclear industry and more recently for radiation processing. The two major effects of nuclear radiation on polymeric materials are the degradation and cross-linking. The degradation consists in breaking of macromolecules after interaction with nuclear particles, amplified by the free radicals which persist long periods, especially in crystalline polymers. Oxygen could ...

128

Institutional models for nuclear fuel cycle facilities  

International Nuclear Information System (INIS)

The possibility of having properly designed multinational fuel cycle agreements which would contribute to public acceptance of nuclear energy are explored. The advantages of existing international cooperation in the field of uranium enrichment and nuclear waste disposal and reprocessing are discussed. The possible forms of multinational co-operation under an international organisation, committed the non-proliferation and operating under international law and covering storage facilities, security of raw materials and the nuclear fuel cycle are summarised in model form. (U.K.).

129

The Coming Nuclear Renaissance for Next Generation Safeguards Specialists--Maximizing Potential and Minimizing the Risks  

Energy Technology Data Exchange (ETDEWEB)

This document is intended to provide an overview of the workshop entitled 'The Coming Nuclear Renaissance for the Next Generation Safeguards Experts-Maximizing Benefits While Minimizing Proliferation Risks', conducted at Oak Ridge National Laboratory (ORNL) in partnership with the Y-12 National Security Complex (Y-12) and the Savannah River National Laboratory (SRNL). This document presents workshop objectives; lists the numerous participant universities and individuals, the nuclear nonproliferation lecture topics covered, and the facilities tours taken as part of the workshop; and discusses the university partnership sessions and proposed areas for collaboration between the universities and ORNL for 2009. Appendix A contains the agenda for the workshop; Appendix B lists the workshop attendees and presenters with contact information; Appendix C contains graphics of the evaluation form ...

2009-01-01

130

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

International Nuclear Information System (INIS)

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, ...

2001-10-01

131

International symposium on nuclear security. Book of extended synopses  

International Nuclear Information System (INIS)

The International Symposium on Nuclear Security took place within a context of international acknowledgement that the threat of nuclear terrorism required dedicated action by the international community, States, industry and others. The Symposium dealt with those issues involved in protecting nuclear and other radioactive material from criminals. It also took place against a backdrop of renewed interest in nuclear technology: increased use of nuclear power, and increased use of radioactive isotopes in medicine and in industry. These are welcome developments, since nuclear energy and technology can indeed contribute to the technological and economic welfare of many countries, without compromising public health or the environment. In this context, security measures should not impede State programmes for peaceful use of ...

2003-11-05

132

Metal finishing and vacuum processes groups, Materials Fabrication Division progress report, March-May 1984  

Energy Technology Data Exchange (ETDEWEB)

Progress is reported in fabrication and coating activities being conducted for the weapons program, nuclear test program, nuclear design program, magnetic fusion program, and miscellaneous applications. (DLC)

1984-07-11

133

Different aspects of safety in Nuclear Fuel Plant at Pitesti, Romania  

International Nuclear Information System (INIS)

Nuclear Fuel Plant (FCN) is a facility that produces fuel bundles of CANDU-6 type for the CANDU nuclear power plant. Only natural and depleted uranium in bulk and itemized form are present as nuclear materials in this facility. Uranium and wastes from the plant are handled, processed, treated and stored throughout the entire facility. The nuclear materials with natural and depleted uranium are entirely under nuclear safeguards. The amount of uranium present in the plant in different forms and activities together with zircaloy, beryllium and other hazardous substances, wastes, explosive materials at high temperatures, etc. lead to special measures undertaken by Nuclear Safety Department (DNS) to ensure nuclear safety. Different aspects of safety are continuously monitored in the ...

2009-10-12

134

Development of engineered structural barriers for nuclear-waste packages  

Energy Technology Data Exchange (ETDEWEB)

The development of structural barriers for nuclear waste packages involves selection of candidate materials, their screening by mechanical and corrosion testing, rigorous accelerated testing, and evaluation and comparison with other package elements. This document presents results from work conducted on titanium and ferrous alloys.

1981-09-01

135

Radiation testing of organic ion exchange resins  

International Nuclear Information System (INIS)

A number of ion exchange materials are being evaluated as part of the Tank Waste Remediation System (TWRS) Pacific Northwest Laboratory (PNL) Pretreatment Project for the removal of "1"3"7Cs from aqueous tank wastes. Two of these materials are organic resins; a phenol-formaldehyde resin (Duolite CS-100) produced by Rohm and Haas Co. (Philadelphia, Pennsylvania) and a resorcinol-formaldehyde (RF) resin produced by Boulder Scientific Co. (Mead, Colorado). One of the key parameters in the assessment of the organic based ion exchange materials is its useful lifetime in the radioactive and chemical environment that will be encountered during waste processing. The focus of the work presented in this report is the radiation stability of the CS-100 and the RF resins. The scope of the testing included one test with a sample of the CS-100 resin and testing of two batches of the RF resin (BSC-187 and BSC-210). ...

1983-04-11

136

Radiation testing of organic ion exchange resins  

Energy Technology Data Exchange (ETDEWEB)

A number of ion exchange materials are being evaluated as part of the Tank Waste Remediation System (TWRS) Pacific Northwest Laboratory (PNL) Pretreatment Project for the removal of {sup 137}Cs from aqueous tank wastes. Two of these materials are organic resins; a phenol-formaldehyde resin (Duolite CS-100) produced by Rohm and Haas Co. (Philadelphia, Pennsylvania) and a resorcinol-formaldehyde (RF) resin produced by Boulder Scientific Co. (Mead, Colorado). One of the key parameters in the assessment of the organic based ion exchange materials is its useful lifetime in the radioactive and chemical environment that will be encountered during waste processing. The focus of the work presented in this report is the radiation stability of the CS-100 and the RF resins. The scope of the testing included one test with a sample of the CS-100 resin and testing of two batches of the RF resin (BSC-187 and BSC-210). ...

1995-09-01

137

Study on reactor building structure using ultrahigh strength materials - Part 9: Summary of the study  

International Nuclear Information System (INIS)

Considerations for longevity of nuclear facilities and ease of decommissioning are of great importance for future nuclear power plants. To this end, a concept of an optimal structural concept for nuclear reactor buildings has been studied: the main feature of this concept is to utilize large-sized, light weight prefabricated members with ultrahigh strength materials. The following two items have been selected to study the prospective structure: (1) Applicability of ultrahigh strength materials for reinforced concrete shear walls (2) Construction using large sized prefabricated members As the first step (1), material and structural tests using ultrahigh strength materials, and the subsequent analysis of those tests for reinforced concrete shear walls, has been conducted. The positive results of this study show a bright future for the use of ...

1993-08-15

138

Accelerating the disposition of transuranic waste from LANL - 9495  

Energy Technology Data Exchange (ETDEWEB)

Los Alamos National Laboratory (LANL) was established during World War II with a single mission -- to design and build an atomic bomb. In the 65 years since, nuclear weapons physics, design and engineering have been the Laboratory's primary and sustaining mission. Experimental and process operations -- and associated cleanout and upgrade activities -- have generated a significant inventory of transuranic (TRU) waste that is stored at LANL's Technical Area 54, Material Disposal Area G (MDA G). When the Waste Isolation Pilot Plant (WIPP) opened its doors in 1999, LANL's TRU inventory totaled about 10,200 m{sup 3}, with a plutonium 239-equivalent curie (PE Ci) content of approximately 250,000 curies. By December 2008, a total of about 2,300 m3 (61,000 PE Ci) had been shipped to WIPP from LANL. This has resulted in a net reduction of about 1,000 m{sup 3} of TRU inventory over that ...

2009-01-01

139

Examination of the natural radioactivity of building materials  

International Nuclear Information System (INIS)

Most important radionuclides naturally appearing in minerals used to form building materials are described. The frequently met ranges of concentrations of these radionuclides in the building materials composed from natural products as well as from power-plant wastes and metallurgic plant wastes are discussed and propositions concerning the limitation of presence of radioactive nuclides in the building materials are given, with special concern paid to materials for dwelling and public utility buildings. The elaborated technique of measuring potassium 40, radium 226 and thorium 228 concentrations is presented. Data on the organization of controlling-and-measuring laboratories in this field are given. (author).

1982-01-01

140

RECENT ACTIVITIES AT THE CENTER FOR SPACE NUCLEAR RESEARCH FOR DEVELOPING NUCLEAR THERMAL ROCKETS  

Energy Technology Data Exchange (ETDEWEB)

Nuclear power has been considered for space applications since the 1960s. Between 1955 and 1972 the US built and tested over twenty nuclear reactors/ rocket-engines in the Rover/NERVA programs. However, changes in environmental laws may make the redevelopment of the nuclear rocket more difficult. Recent advances in fuel fabrication and testing options indicate that a nuclear rocket with a fuel form significantly different from NERVA may be needed to ensure public support. The Center for Space Nuclear Research (CSNR) is pursuing development of tungsten based fuels for use in a NTR, for a surface power reactor, and to encapsulate radioisotope power sources. The CSNR Summer Fellows program has investigated the feasibility of several missions enabled by the NTR. The potential mission benefits of a nuclear rocket, historical achievements of the previous programs, and ...

2001-09-01

142

Studies of activated carbon and carbon black for supercapacitor applications  

Energy Technology Data Exchange (ETDEWEB)

Carbon Black and activated carbon materials providing high surface areas and a distinct pore distribution are prime materials for supercapacitor applications at frequencies < 0.5 Hz. A number of these materials were tested for their specific capacitance, surface and pore size distribution. High capacitance electrodes were manufactured on the laboratory scale with attention to ease of processability. (author) 1 fig., 1 ref.

1999-08-01

143

Medical explorations by radioisotopes in Lebanon  

International Nuclear Information System (INIS)

This study mainly concerns medical explorations by radioisotopes. Detectors with medical exams and applications are described. Ionisation chambers, semiconductor detectors and scintillation counters are also presented. Uses of radioisotopes in medicine in vivo and in vitro techniques are explained. Examples of scintiscanning are given like: angiography, nuclear cardiography and thyroid scintiscanning. The importance of the study is to present a panorama of nuclear medicine laboratories -at the time- in hospitals in Lebanon.

144

Experimental and evaluated nuclear plus interference cross sections for light charged particles  

Energy Technology Data Exchange (ETDEWEB)

Experimental and evaluated integral parameters derived from nuclear plus interference differential elastic scattering cross sections are presented for all projectile/target combinations of the particles p, d, t, /sup 3/He, and ..cap alpha... The data include reaction rates, average fractional energy losses per collision and per unit path length, and average laboratory scattering cosines. The resulting parameters are of potential use in analysis of charged-particle transport.

1980-07-04

145

A passion for physics  

Energy Technology Data Exchange (ETDEWEB)

This is an account of the initial struggles and subsequently successful career of a young woman growing up in prewar Australia with the overriding desire to become a physicist despite various problems and prejudices. The book provides first-hand accounts of wartime radar research and development in Australia; the immediately post-war era in nuclear physics at the Cavendish Laboratory, Cambridge; and work in the Nuclear Physics Division at AERE Harwell in the period from the 1950s onwards. (UK).

1991-01-01

146

Nuclear forensics  

International Nuclear Information System (INIS)

Increasing threat by terrorists for a possible nuclear attack is particularly alarming in recent years. The likelihood of such an event is highly uncertain but cannot be ruled out. The consequence of such an event would be highly disastrous and the implications could be far-reaching both socially and politically. It is feared that significant amount of nuclear weapons materials may be kept under poor security. Therefore, there is a greater demand with utmost priority to curb nuclear terrorism by adapting proper security measures. One of the most important measures is to stop illicit trafficking of nuclear materials which are the source of building nuclear explosive devices. According to the IAEA illicit trafficking database (ITDB) report, a total number of 252 incidents were reported in 2006, of which 150 occurred in 2006 and the remaining ...

2010-11-15

147

Argonne National Laboratory-East evolution of solid waste management  

Energy Technology Data Exchange (ETDEWEB)

The purpose of this report is to provide the reader with a basic understanding of Argonne National Laboratory`s current general refuse disposal and material recycling programs, how they were developed, and where they are going. In order to better understand the current situation, a brief description of the facilities past practices is explained. ANL is a multi-program research and development center owned by DOE and operated by the University of Chicago. Argonne`s primary facilities are on a 1,700 acre site, 27 miles southwest of Chicago. Fifty-seven major buildings house approximately 4,500 employees at the site.

1996-07-01

148

Comparison of effectiveness of three radon detectors (LR115, CR39 and silicon diode pin) placed in a cylindrical device -theory and experimental techniques  

Energy Technology Data Exchange (ETDEWEB)

Researchers at the Laboratory of Nuclear Microanalysis in Besancon (France) are developing and improving radon measurements in order to detect and analyse, more precisely radon emanation anomalies in both fields of Earth Sciences and Radioprotection. In order to characterize radon emanation, two complementary techniques are developed; continuous measurement through a portable proportional counter and passive measurements by nuclear track detectors for both fieldwork and laboratory analysis. A mathematical model is being devised to interpret the nuclear track detector response. This model is performed according to the device characteristics: type of detectors, shape and size of cells and whether a membrane is used or not. In addition to the theoritical study, experimental radon concentration measurements will be reported. (author).

1993-12-31

149

Comparison of effectiveness of three radon detectors (LR115, CR39 and silicon diode pin) placed in a cylindrical device -theory and experimental techniques  

International Nuclear Information System (INIS)

Researchers at the Laboratory of Nuclear Microanalysis in Besancon (France) are developing and improving radon measurements in order to detect and analyse, more precisely radon emanation anomalies in both fields of Earth Sciences and Radioprotection. In order to characterize radon emanation, two complementary techniques are developed; continuous measurement through a portable proportional counter and passive measurements by nuclear track detectors for both fieldwork and laboratory analysis. A mathematical model is being devised to interpret the nuclear track detector response. This model is performed according to the device characteristics: type of detectors, shape and size of cells and whether a membrane is used or not. In addition to the theoritical study, experimental radon concentration measurements will be reported. (author).

150

Development of Nuclear Materials and Degradation Database  

International Nuclear Information System (INIS)

There are about 440 operating nuclear power reactors in the world including 20 units from Korea. The average age of the reactors is more than 20 years and many of them are approaching to their original 30 or 40 years licensing terms. Even though some failures were reported in components or pipes of nuclear power plants (NPPs), these NPPs are considered to be too valuable to stop their operation at the end of design life. Therefore, the long-term operation of NPPs has become a worldwide trend based on technical and economic consideration. In order to ensure safe long-term operation of NPPs, it is increasingly necessary to adopt new approaches to deal with nuclear materials aging and degradation. Proactive Material Degradation Assessment (PMDA) is one of the key elements of these new approaches. Many kinds of background information such as materials and ...

2010-10-01

151

Age determination of plutonium material in nuclear forensics by thermal ionisation mass spectrometry  

International Nuclear Information System (INIS)

Age is a key parameter when deducing the history of plutonium material, i.e. the plutonium produced in the nuclear reactors. This is of vital importance, when a smuggled plutonium sample has been seized and the origin has to be determined. A methodology is described which allows accurately to determine the age of plutonium material by thermal ionisation mass spectrometry using independent parent/daughter relations. This has been demonstrated for Reference Materials of known ages as well as for real samples. The already established method using gamma spectrometry is compared to this. (orig.)

2000-02-01

152

Results of the Interlaboratory Exercise CSN/CIEMAT-100 Among Environmental Radioactivity Laboratories (Soil); Resultados del Ejercicio Interlaboratorios de Radiactividad Ambiental CSN/CIEMAT-00 (Suelo)  

Energy Technology Data Exchange (ETDEWEB)

The document describes the outcome of the CSN/CIEMAT-00 interlaboratory test comparison among environmental radioactivity laboratories. the exercise was organised according to the ISO-43 and the ISO/IUPAC/AOAC Harmonized Protocol for the proficiency testing of analytical laboratories. the test sample was a soil containing environmental levels of K-40, Ra-226, Ac-228, Sr-90, Cs-137, Cs-134, Pu (239-240) y Am-241. the Universidad Autonoma de Barcelona prepared the material and reported adequate statistical studies of homogeneity. The results of the exercise were computed for 30 participating laboratories, and their analytical performance was assessed using the u-score approach. A raised percentage of satisfactory laboratory performance has been obtained for all the analysis, being the best performance in gamma measurements. The exercise has drawn that several ...

2002-07-01

153

Waste minimization and pollution prevention in D&D operations at the Argonne National Laboratory-East site  

Energy Technology Data Exchange (ETDEWEB)

Argonne National Laboratory (ANL) is implementing waste minimization and pollution prevention activities into its conduct of decontamination and decommissioning (D&D) projects. Many of these activities are rather straight forward and simple approaches, yet they are often overlooked and not implemented as often as they should or could be. Specific activities involving recycling and reuse of materials and structures, which have proven useful in lowering decommissioning and disposal costs on D&D projects at ANL are presented.

1996-07-01

154

Nuclear data interface retrospective  

Energy Technology Data Exchange (ETDEWEB)

The Nuclear Data Interface (NDI) code library and data formats are the standards for multigroup nuclear data at Los Alamos National Laboratory. NDI's analysis, design, implementation, testing, integration, and maintenance required a ten person-year and ongoing effort by the Nuclear Data Team. Their efforts provide a unique, contemporary experience in producing a standard component library. In reflection upon that experience at NDI's decennial, we have identified several factors critical to NDI's success: it addressed real problems with appropriate simplicity, it fully supported all users, it added extra value through the code to the raw nuclear data, and its team went the distance from analysis through maintenance. In this report we review these critical success factors and discuss their implications for future standardization projects.

2008-01-01

155

Nuclear cask testing films misleading and misused  

Energy Technology Data Exchange (ETDEWEB)

In 1977 and 1978, Sandia National Laboratories, located in Albuquerque, New Mexico, and operated for the US Department of Energy (DOE), filmed a series of crash and fire tests performed on three casks designed to transport irradiated nuclear fuel assemblies. While the tests were performed to assess the applicability of scale and computer modeling techniques to actual accidents, films of them were quickly pressed into service by the DOE and nuclear utilities as ``proof`` to the public of the safety of the casks. In the public debate over the safety of irradiated nuclear fuel transportation, the films have served as the mainstay for the nuclear industry. Although the scripts of all the films were reviewed by USDOE officials before production, they contain numerous misleading concepts and images, and omit significant facts. The shorter versions eliminated qualifying statements ...

1991-10-01

156

Multivariate statistics in the identification of unknown nuclear material  

International Nuclear Information System (INIS)

The identification, and hence origin determination, of unknown nuclear material that might be found undeclared away from designated locations in the nuclear fuel cycle, is an important task in the frame of nuclear forensics. Material with forensic importance can be found at the microscopic level as particles in environmental samples indicating possible clandestine production of fissile material, and as bulky samples in the case of illicit trafficking of nuclear material. The objective of this work is to present, at a theoretical level, an isotopic finger-printing methodology which would determine the origin of unknown nuclear material with forensic importance. This is demonstrated for the case when the unknown nuclear material is spent ...

2004-10-25

157

Granite Countertops and Radiation | Radiation Protection | US EPA  

Wastenet

... Top of page Testing Radiation coming from granite countertops results from natural radioactive material in the granite. Identifying the presence and concentration of radioactive elements in granite requires expensive and sophisticated portable instruments or laboratory equipment. These instruments and equipment require proper calibration, and interpretation of ...

158

International forensics cooperation: reviewing frameworks, goals and capabilities  

International Nuclear Information System (INIS)

Full text: There have been many recent calls for increased international cooperation in the field of nuclear forensics. While much is already being done, for example by the International Technical Working Group on Nuclear Smuggling and International Atomic Energy Agency, more effort is needed as cooperation on real-world incidents is often ad hoc. As a result, incidents - particularly diversions of nuclear material - are not effectively investigated, and opportunities to keep dangerous materials out of the hands of terrorists or proliferators are missed. Forensics techniques can be used to investigate many types of incidents involving illicit uses of nuclear or radiological material, but the need for cooperation can be seen most clearly in the area of illicit trafficking where collaboration is needed now. Here governments have had some ...

159

Development of nanocomposite polymer materials for electrical and electronic applications  

International Nuclear Information System (INIS)

Some results and experimental procedures of laboratory are reported in the frame of researches conducted for the development of new nanostructured composite materials. These new materials, which are constituted by an organic phase: the polymer and an inorganic phase: the silicate, are being strongly investigated nowadays so it is expected that they could provide, among other, better electrical insulation properties and flame-delay in electrical and electronic applications. The laboratory experimental work has been developed from two families of polymers, thermoplastics and thermosets and clays silicates providing lamellar type. There are now some preliminary results, such as obtaining thin films of these nanocomposite materials, their complete characterization by X-ray diffraction, scanning microscopy and thermogravimetric analysis, they do well to wait for future research ...

2007-01-01

160

Development and validation of control materials for the measurement of vitamin D3 in selected US foods  

British Library Electronic Table of Contents (United Kingdom)

As part of the United States Department of Agricultures (USDA) National Food and Nutrient Analysis Program (NFNAP), food composition data for vitamin D in the USDA National Nutrient Database for Standard Reference are being updated and expanded, focusing on high priority foods and validated analytical methodology. A lack of certified reference materials and analytical methods validated for these key foods required the development of five matrix-specific control composite materials (CC) (canned salmon and vitamin D3 fortified cereal, orange juice, milk, and cheese). Each of six experienced laboratories (research and commercial) analyzed vitamin D3 in five subsamples of each CC in five separate analytical batches, with one subsample of each material in each run. Research laboratories perform...

2008-01-01

161

Decree of the Czechoslovak Atomic Energy Commission No. 436/1990 on quality assurance of selected facilities with respect to nuclear safety of nuclear facilities  

International Nuclear Information System (INIS)

The Decree specifies basic quality assurance requirements applicable to machines, their parts and materials, civil engineering structures, means for automated control of technological processes including hardware and software, and electricity supply systems related to nuclear safety of nuclear facilities, and stipulates binding procedures for the implementation of technical and organizational provisions associated with the quality of selected equipment to ensure nuclear safety of nuclear facilities. Safety classes are defined for selected equipment. Requirements laid on safety assurance documentation are specified, and requirements placed on safety assurance programmes, their preparation, finalization and approval are defined. Quality assurance requirements are also specified with respect to the designing, manufacture, construction, operation, repair, modification and ...

1995-02-01

162

LLNL casting technology  

Energy Technology Data Exchange (ETDEWEB)

Competition to produce cast parts of higher quality, lower rejection rate, and lower cost is a fundamental factor in the global economy. To gain an edge on foreign competitors, the US casting industry must cut manufacturing costs and reduce the time from design to market. Casting research and development (R&D) are the key to increasing US compentiveness in the casting arena. Lawrence Livermore National Laboratory (LLNL) is the home of a wide range of R&D projects that push the boundaries of state-of-the art casting. LLNL casting expertise and technology include: casting modeling research and development, including numerical simulation of fluid flow, heat transfer, reaction/solidification kinetics, and part distortion with residual stresses; special facilities to cast toxic material; extensive experience casting metals and nonmetals; advanced measurement and instrumentation systems. Department of Energy (DOE) funding provides the ...

1994-01-01

163

Data interpretation in nuclear forensics  

International Nuclear Information System (INIS)

Nuclear Forensics is a key element in the response process which is initiated after detection of illicit nuclear or other radioactive material. Credible nuclear forensics relies on appropriate sampling procedures, on validated analytical methods and on thorough data analysis and interpretation. Nuclear forensics aims at providing clues on the history and the potential origin of the material. Elemental and isotopic composition of the material, as well as its macroscopic and microscopic appearance reflect the technological processes used for the fabrication of the material. The nuclear forensic analysis first of all results in measurement data. Through appropriate processing of these data information on the nature and the history of the material can be obtained. A number of data ...

164

Thorium dioxide: properties and nuclear applications  

Energy Technology Data Exchange (ETDEWEB)

This is the sixth book on reactor materials published under sponsorship of the Naval Reactors Office of the United States Department of Energy, formerly the United States Atomic Energy Commission. This book presents a comprehensive compilation of the most significant properties of thorium dioxide, much like the book Uranium Dioxide: Properties and Nuclear Applications presented information on the fuel material used in the Shippingport Pressurized Water Reactor core.

1984-01-01

165

Explosion protection in nuclear power plants with LWR and HTR reactors. As of August 14, 1989. Explosionsschutz in Kernkraftwerken mit Leichtwasser- und Hochtemperaturreaktoren (allgemeine und fallbezogene Anforderungen). Vom 14. August 1989  

Energy Technology Data Exchange (ETDEWEB)

The technical rule intends to maintain the function of the safety facilities in case of explosion hazards resulting from materials capable of generating explosive atmospheres or forming explosive mixtures if such materials are brought or released into the nuclear facility or are generated on site. (orig.).

1989-12-07

166

Explosion protection in nuclear power plants with LWR and HTR reactors (general and case depending requirements). Explosionsschutz in Kernkraftwerken mit Leichtwasser- und Hochtemperaturreaktoren (allgemeine und fallbezogene Anforderungen)  

Energy Technology Data Exchange (ETDEWEB)

The technical rule intends to maintain the function of the safety facilities in case of explosion hazards resulting from materials capable of generating explosive atmospheres or forming explosive mixtures if such materials are brought or released into the nuclear facility or are generated on site. (orig.).

1989-01-01

167

A mobile remote sensing laboratory for water vapor, trace gas, aerosol, and wind speed measurements  

Energy Technology Data Exchange (ETDEWEB)

The Lawrence Livermore National Laboratory has developed a mobile field laboratory for remote measurement of atmospheric processes and observables that are important in global climate change, dispersal of hazardous materials, and atmospheric pollution. Specific observables of interest are water vapor, trace gases, aerosol size and density, wind, and temperature. The goal is to study atmospheric processes continuously for extended periods in remote field locations. This laboratory has just reached field ready status with sensors for aerosol and trace gas measurement based on established techniques. A development program is underway to enhance the sensor suite with several new techniques and instruments that are expected to significantly extend the state of the art in remote trace gas analysis. The new sensors will be incorporated into the lab during the next two years.

1993-03-19

168

Study of the application of BATAN's equipment for nuclear forensic activities  

International Nuclear Information System (INIS)

Nuclear forensic activities, such as in illicit trafficking, can solve a problem who did it and can gain the basis for a response. Other than that, the forensics can be also applied to solve on what are materials, who is responsible, is there more, where was material diverted and what route did the material taken. BATAN, in fact , owns a lot of equipment which can be supported for nuclear forensics activities, such as, Transmission Electron Microscope (TEM), Scanning Electron Microscope (SEM) as well as X-Ray Diffraction (XRD). For the first step, BATAN has to be an active, participate member of The International Technical Working Group on Nuclear Smuggling (ITWG). BATAN can then collaborate not only with Indonesia Arm Forces and Police, but also with other foreign institutions to develop this activity with mutual advantages agreement.

2005-10-01

169

Matrix diffusion studies by electrical conductivity methods. Comparison between laboratory and in-situ measurements  

Energy Technology Data Exchange (ETDEWEB)

Traditional laboratory diffusion experiments in rock material are time consuming, and quite small samples are generally used. Electrical conductivity measurements, on the other hand, provide a fast means for examining transport properties in rock and allow measurements on larger samples as well. Laboratory measurements using electrical conductivity give results that compare well to those from traditional diffusion experiments. The measurement of the electrical resistivity in the rock surrounding a borehole is a standard method for the detection of water conducting fractures. If these data could be correlated to matrix diffusion properties, in-situ diffusion data from large areas could be obtained. This would be valuable because it would make it possible to obtain data very early in future investigations of potentially suitable sites for a repository. This study compares laboratory electrical ...

1998-09-01

170

Direct conversion of surplus fissile materials, spent nuclear fuel, and other materials to high-level-waste glass  

Energy Technology Data Exchange (ETDEWEB)

With the end of the cold war the United States, Russia, and other countries have excess plutonium and other materials from the reductions in inventories of nuclear weapons. The United States Academy of Sciences (NAS) has recommended that these surplus fissile materials (SFMs) be processed so they are no more accessible than plutonium in spent nuclear fuel (SNF). This spent fuel standard, if adopted worldwide, would prevent rapid recovery of SFMs for the manufacture of nuclear weapons. The NAS recommended investigation of three sets of options for disposition of SFMs while meeting the spent fuel standard: (1) incorporate SFMs with highly radioactive materials and dispose of as waste, (2) partly burn the SFMs in reactors with conversion of the SFMs to SNF for disposal, and (3) dispose of the SFMs in deep boreholes. The US Government is investigating these options ...

1995-01-31

171

Overview of the 1995 NATO ARW on nuclear submarine decommissioning and related problems  

International Nuclear Information System (INIS)

The NATO Advanced Research Workshop on Nuclear Submarine Decommissioning and Related Problems was held in Moscow June 19--22, 1995. It was preceded by a visit to the Zvezdotchka Shipyard at Severodvinsk, a repair and maintenance yard for Russian nuclear submarines, for a subgroup of the workshop attendees. Most of the material in this paper is drawn directly form the workshop proceedings. Slightly less than 500 nuclear ships and submarines (the vast majority are submarines) have been constructed by the countries with nuclear navies. This includes approximately 250 by Russia, 195 by the United States, 23 by the United Kingdom, 11 by France and 6 by China. By the year 2000 it is expected that approximately one-half of these nuclear vessels will be removed from service and in various states of decommissioning. A newspaper account in June 1997 indicated that 156 ...

1997-11-21

172

Application of proportional counters in Polish medicine and agriculture  

Energy Technology Data Exchange (ETDEWEB)

In the laboratory of Elementary Particle Physics and Detectors at the Faculty of Physics and Nuclear Techniques of the University of Mining and Metallurgy, research works on the development of proportional counters for the detection of X- and soft {gamma}-rays and {alpha}, {beta} particles have been carried out As a result of optimization of counters characteristic parameters such as: energy resolution, life time, count rate effect and temperature effect the operating stability has been reached and the elaborated detectors have been applied not only in research laboratories, but also in Polish industry, medicine and agriculture. Examples of above mentioned applications have been presented in the paper. (author). 7 refs, 7 figs, 1 tab.

1996-12-31

173

Characterization of nuclear fuels by ICP mass-spectrometric techniques  

British Library Electronic Table of Contents (United Kingdom)

Isotopic analyses of radioactive materials such as irradiated nuclear fuel are of major importance for the optimization of the nuclear fuel cycle and for safeguard aspects. Among the mass-spectrometric techniques available, inductively coupled plasma mass spectrometry (ICP-MS) and thermal ionization mass spectrometry are the most frequently applied methods for nuclear applications. Because of the low detection limits, the ability to analyze the isotopic composition of the elements and the applicability of the techniques for measuring stable as well as radioactive nuclides with similar sensitivity, both mass-spectrometric techniques are an excellent amendment to classical radioactivity counting methods. The paper describes selected applications of multicollector ICP-MS in combination with c...

2008-01-01

174

Photovoltaics: Program overview, fiscal year 1992  

Energy Technology Data Exchange (ETDEWEB)

The US DOE`s Photovoltaics program has helped photovoltaic technologies evolve from materials and concepts in the laboratories to competitive products rolling off automated assembly lines. This document is divided into the following sections: 1992 PV program accomplishments, expanding markets for photovoltaic systems, developing today`s systems with utilities and industry, working with industry to advance the technology, cooperative research to improve materials and devices, selected achievements in cooperative R and D, and PV program services. Figs, tabs.

1993-03-01

175

Liposome technology. Volume II: Incorporation of drugs, proteins and genetic material  

Energy Technology Data Exchange (ETDEWEB)

These three volumes cover liposome technology in pharmacology and medicine. Contributors emphasize methodology used in their own laboratories, and include a brief introduction, coverage of relevant literature, applications and critical evaluations for the methods they describe. Volume II presents procedures for the entrapment of a number of drugs, including genetic material, into selected types of liposomes.

1984-01-01

176

Increasing the level of coal charge crushing  

Science.gov (United States)

Coarse components in the charge, i.e. >6 mm material, display higher ash, a lower volatile matter and a smaller proportion of caking components. Bulk density and moisture levels were studied over a wide range of size reductions (60-85% blast furnace coke. Laboratory work should be checked in practical runs working with 74-76% <3 mm charge material.

1982-08-01

177

Bibliography of the technical literature of the Materials Joining Group, Metals and Ceramics Division, 1951--June 1989  

Energy Technology Data Exchange (ETDEWEB)

This document contains a listing of the written scientific information originating in the Materials Joining (formerly the Welding and Brazing Group), Metals and Ceramics Division, Oak Ridge National Laboratory during 1951 through June 1989. This registry of documents is as much as possible, in the order of issue date. A complete cross-referenced listing of the technical literature of the Metals and Ceramics Division is also available.

1989-10-01

178

Bibliography of the technical literature of the Materials Joining Group, Metals and Ceramics Division, 1951 through June 1987  

Energy Technology Data Exchange (ETDEWEB)

This document contains a listing of the written scientific information originating in the Materials Joining Group (formerly the Welding and Brazing Group), Metals and Ceramics Division, Oak Ridge National Laboratory during 1951 through June 1987. It is a registry of about 400 documents as nearly as possible in the order in which they were issued.

1987-08-01

179

Introduction of Member State Support Program (MSSP) of Korea  

International Nuclear Information System (INIS)

The demand of nuclear energy is sharply increasing to solve the energy and environment problems all over the world. The interest and support on the field of nuclear energy in Korea are enlarging as the acceptance of ordering nuclear power plant of UAE. The attention of safeguards is needed to maintain peaceful use of nuclear material and the nuclear nonproliferation as the increasing demand of nuclear energy. The International Atomic Energy Agency (IAEA) invests more in research and development to achieve the effective and efficient implementation of safeguards. Research and development (R and D) in safeguards approaches, procedures and techniques is essential to meeting the safeguards challenges of the future. The IAEA has conducted the R and D program through member state support program (MSSP) since 1977. The objective of this paper is to ...

2010-10-01

180

Interfacial Charge Transport in Organic Electronic Materials: the Key to a New Electronics Technology  

Energy Technology Data Exchange (ETDEWEB)

This is the final report of a three-year, Laboratory Directed Research and Development (LDRD) project at Los Alamos National Laboratory (LANL). The primary aim of this project is to obtain a basic scientific understanding of electrical transport processes at interfaces that contain an organic electronic material. Because of their processing advantages and the tunability of their electronic properties, organic electronic materials are revolutionizing major technological areas such as information display. We completed an investigation of the fundamental electronic excitation energies in the prototype conjugated polymer MEH-PPV. We completed a combined theoretical/experimental study of the energy relation between charged excitations in a conjugated polymer and the metal at a polymer/metal interface. We developed a theoretical model that explains injection currents at polymer/metal interfaces. We have made ...

1999-06-04

181

Summary of non-US national and international radioactive waste management programs 1981  

Energy Technology Data Exchange (ETDEWEB)

Many nations and international agencies are working to develop improved technology and industrial capability for neuclear fuel cycle and waste management operations. The effort in some countries is limited to research in university laboratories on treating low-level waste from reactor plant operations. In other countries, national nuclear research institutes are engaged in major programs in all phases of the fuel cycle and waste management, and there is a national effort to commercialize fuel cycle operations. Since late 1976, staff members of Pacific Northwest Laboratory have been working under US Department of Energy sponsorship to assemble and consolidate openly available information on foreign and international nuclear waste management programs and technology. This report summarizes the information collected on the status of fuel cycle and waste management programs in selected countries making major ...

1981-06-01

182

Activities on free electron laser in Japan  

International Nuclear Information System (INIS)

The free-electron laser (FEL) projects that are currently in progress in Japan are discussed. Particular attention is given to the storage ring FELs at the Electrotechnical Laboratory, the Institute for Molecular Physics, and the Kyushu University; the superconducting linear accelerator (SC linac) FELs being developed at the Japan Atomic Energy Research Institute; and the RF-linac FEL being developed by the Nuclear Engineering Research Laboratory of the University of Tokyo, the Institute of Scientific and Industrial Research of Osaka University, the Mitsubishi Electric Company, and Tokyo Institute of Technology. Consideration is also given to the microtron FEL being constructed at the Nihon University; the induction-linac and pulseline FELs of the Institute of Laser Engineering of Osaka University, the Institute of Physical and Chemical Research, the National Laboratory for High-Energy Physics, and ...

1989-04-24

183

Entombment Using Cementitious Materials: Design Considerations and International Experience  

Energy Technology Data Exchange (ETDEWEB)

Cementitious materials have physical and chemical properties that are well suited for the requirements of radioactive waste management. Namely, the materials have low permeability and durability that is consistent with the time frame required for short-lived radionuclides to decay. Furthermore, cementitious materials can provide a long-term chemical environment that substantially reduces the mobility of some long-lived radionuclides of concern for decommissioning (e.g., C-14, Ni-63, Ni-59). Because of these properties, cementitious materials are common in low-level radioactive waste disposal facilities throughout the world and are an attractive option for entombment of nuclear facilities. This paper describes design considerations for cementitious barriers in the context of performance over time frames of a few hundreds of years (directed toward short-lived radionuclides) and time ...

2002-08-01

184

Entombment Using Cementitious Materials: Design Considerations and International Experience  

Energy Technology Data Exchange (ETDEWEB)

Cementitious materials have physical and chemical properties that are well suited for the requirements of radioactive waste management. Namely, the materials have low permeability and durability that is consistent with the time frame required for short-lived radionuclides to decay. Furthermore, cementitious materials can provide a long-term chemical environment that substantially reduces the mobility of some long-lived radionuclides of concern for decommissioning (e.g., C-14, Ni-63, Ni-59). Because of these properties, cementitious materials are common in low-level radioactive waste disposal facilities throughout the world and are an attractive option for entombment of nuclear facilities. This paper describes design considerations for cementitious barriers in the context of performance over time frames of a few hundreds of years (directed toward short-lived radionuclides) and time ...

2002-05-15

185

Investigation of the isotopic composition of lead and of trace elements concentrations in natural uranium materials as a signature in nuclear forensics  

International Nuclear Information System (INIS)

Lead is contained as trace element in uranium ores and propagates throughout the production process to intermediate products like yellow cake or uranium oxide. The lead isotopes in such material originate from two sources: natural lead and radiogenic lead. The variability of the isotopic composition of lead in ores and yellow cakes was studied and the applicability of this parameter for nuclear forensic investigations was investigated. Furthermore, the chemical impurities contained in these materials were measured in order to identify characteristic differences between materials from different mines. For the samples investigated, it could be shown, that the lead isotopic composition varies largely from mine to mine and it may be used as one of the parameters to distinguish between materials of different origins. Some of the chemical impurities show a similar pattern and support the ...

186

Procedures and interpretation of oxygen diffusion and burn up trials in the laboratory and in situ; Procedures et interpretation des essais de diffusion et de consommation d'oxygene en laboratoire et in situ  

Energy Technology Data Exchange (ETDEWEB)

The development of soil cover with capillary effect required laboratory experiments where diffusion was studied. The effective diffusion coefficients D of materials in the different layers were determined, as well as the reaction constants of reactive materials. Once soil cover is in place, its efficiency can be controlled by oxygen burn up trials in situ. In the specific case where the materials that comprise the soil cover consume oxygen, even in small quantities, the usual interpretation of these trials is not applicable. In this poster presentation, the authors proposed different procedures for long term trials, in situ and in the laboratory, as well as a new interpretation method based on the use of numerical solutions to the modified Fick equations of diffusion for reactive materials. Special emphasis is placed on the proper enunciation of the laws and the ...

2000-07-01

187

Effectively use corrosion testing  

Energy Technology Data Exchange (ETDEWEB)

The proper selection of materials of construction is necessary to provide process equipment with optimum performance and corrosion resistance. If properly chosen, the selected material should deteriorate at a uniform, predictable rate, which will allow for maintenance or replacement at scheduled intervals. This concept of risk assessment for predictive maintenance is a minimum requirement for proper materials selection. Materials selection is based on prior service history, field corrosion tests, pilot-plant tests, and laboratory bench-top tests--in that relative order of usefulness. Corrosion test methods are usually divided into two groups: laboratory and field (plant-site) tests. The main difference between the two is that field test specimens are exposed to actual process conditions will all of the variables involved, while laboratory ...

1995-04-01

188

Effect of environmental variables on localized corrosion of high-performance container materials  

Energy Technology Data Exchange (ETDEWEB)

Electrochemical cyclic potentiodynamic polarization (CPP) experiments were performed on several candidate high-performance waste package container materials to evaluate their susceptibility to localized corrosion in aqueous environments relevant to the potential underground high-level nuclear waste repository. This paper presents the results of this study showing the effects of chloride ion (Cl) concentrations, pH, temperature, and electrochemical potential scan rate on the pitting corrosion behavior of these materials.

1997-01-01

189

Nuclear material attractiveness: an assessment of material from PHWR's in a closed thorium fuel cycle  

International Nuclear Information System (INIS)

This paper examines the attractiveness of material mixtures containing special nuclear materials (SNM) associated with reprocessing and the thorium-based LWR fuel cycle. This paper expands upon the results from earlier studies that examined the attractiveness of SNM associated with the reprocessing of spent light water reactor (LWR) fuel by various reprocessing schemes and the recycle of plutonium as a mixed oxide (MOX) fuel in LWR. This study shows that "2"3"3U that is produced in thorium-based fuel cycles is very attractive for weapons use. Consistent with other studies, these results also show that all fuel cycles examined to date need to be rigorously safeguarded and provided moderate to high levels of physical protection. These studies were performed at the request of the United States Department of Energy (DOE), and are based on the calculation of 'attractiveness levels' that has been couched in terms chosen for ...

190

The review of radioactive waste management in the world  

International Nuclear Information System (INIS)

Radioactive waste is generally classified on the basis of how much radiation and the type of radiation it emits as well as the length of time over which it will continue to emit radiation. Many activities dealing with radioactive materials produce nuclear wastes, including civilian nuclear power programs (nuclear Power plant operations and nuclear fuel-cycle activities), defense nuclear programs (nuclear weapons production, naval nuclear reactor programs, and related R and D), and industrial and institutional activities (scientific research, medical operations, and other industrial uses of Radioisotopic sources or Radio chemicals). To minimize the potential adverse health and environment impacts to people and other systems including of animals, plant and etc, during the entire lifetime of the radionuclides involved, ...

191

Inter-comparison of some environmental radioactivity monitoring items for Guangdong Daya Bay Nuclear Power Plant  

International Nuclear Information System (INIS)

This paper introduces the inter-comparison results of some environmental radioactivity monitoring items for Daya Bay nuclear power plant. The inter-comparison was organized by China Institute for Radiation Protection and five laboratories participated in it. The compared items included total #beta# in kelp and sediment, "3H in water, "9"0Sr in soil, artificial nuclides "1"1"0"mAg, "2"4"1Am, "1"0"9Cd, "5"7Co in kelp and sediment. Inter-comparison results are analyzed as well

2003-01-01

192

Determination of the content of elements in some wild medicinal plants of Uzbekistan by radioactivation analysis  

Energy Technology Data Exchange (ETDEWEB)

The authors have developed a complex of activation methods of analysis using a nuclear reactor (nuclear activation analysis) and a cyclotron (charged-particle activation analysis). The methods have been used to determine the concentrations of more than 20 elements in five medicinal plants native to Uzbekistan: Syrian rue (Peganum harmala L.), plantain (Plantago lanceolata), peppermint (Mentha piperata L.), sage (Salvia officinalis L.), and ziziphora (Ziziphora bungeana Yur.). The results of radio-activation analysis were compared with the results of standard spectral analysis performed in another laboratory and the accuracy of the procedures developed was evaluated on the basis of the results.

1987-06-01

193

A study on diagnostic techniques of pump operating condition  

Energy Technology Data Exchange (ETDEWEB)

The scope and contents investigate and reviewed are as follows : establishment of study plan and references survey, review of related problems and inservice test standards of safety injection pump in use nuclear power plant, review of the study results in laboratory, the theoretical investigation of temperature rise according to mini-flow rate of pump, mini-flow rate working characteristics of high and low pressure injection pumps at nuclear power plants, setup of testing equipment for measuring ampere, discharge pressure and vibration, selection and behaviors analysis of major parameters concerning pump degradation.

1998-03-15

194

Novel Processing of Unique Ceramic-Based Nuclear Materials and Fuels  

Energy Technology Data Exchange (ETDEWEB)

Advances in nuclear reactor technology and the use of gas-cooled fast reactors require the development of new materials that can operate at the higher temperatures expected in these systems. These include refractory alloys base on Nb, Zr, Ta, Mo, W, and Re; ceramics and composites such as those based on silicon carbide (SiCf-SiC); carbon-carbon composites; and advanced coatings. Besides the ability to handle higher expected temperatures, effective heat transfer between reactor componets is necessary for improved efficiency. Improving thermal conductivity of the materials used in nuclear fuels and other temperature critical components can lower the center-line fuel temperature and thereby enhance durability and reduce the risk of premature failure.

2008-11-30

195

Radiation methods in research of ancient monuments  

Energy Technology Data Exchange (ETDEWEB)

A 'Laboratory of Quantitative Methods in Monument Research' is being built at the CTU Prague. Its primary orientation is the investigation of historic architecture, although other objects of art can also be investigated. In the first phase, two radiation methods are being established, but it is set up in such a way, that various other methods can readily be added in its future development. The radiation methods chosen for the initial development of the laboratory are: thermoluminescence dating and X-ray fluorescence analysis. The design of the automated TL-reader, built in our laboratories, is adjusted for the purpose of dating of historic brick architecture (which, of course, does not exclude applications for ceramics and other materials). The investigation of renaissance architecture in southern Bohemia and Moravia is under preparation as the first large campaign of this kind in the ...

2000-11-15

196

Radiation methods in research of ancient monuments  

International Nuclear Information System (INIS)

A 'Laboratory of Quantitative Methods in Monument Research' is being built at the CTU Prague. Its primary orientation is the investigation of historic architecture, although other objects of art can also be investigated. In the first phase, two radiation methods are being established, but it is set up in such a way, that various other methods can readily be added in its future development. The radiation methods chosen for the initial development of the laboratory are: thermoluminescence dating and X-ray fluorescence analysis. The design of the automated TL-reader, built in our laboratories, is adjusted for the purpose of dating of historic brick architecture (which, of course, does not exclude applications for ceramics and other materials). The investigation of renaissance architecture in southern Bohemia and Moravia is under preparation as the first large campaign of this kind in the Czech Republic. ...

2000-11-15

197

Ageing of fibre reinforced polymer composite selected as a bearing material for Rams of 540 MWe fuelling machine  

International Nuclear Information System (INIS)

Fibre-reinforced-polymer-composite material has been suggested as a bearing material to overcome tribological problems witnessed during the testing of Ram assembly of the 540 MWe fuelling machine at RTD. After successful trials at B-Ram the composite material has been adapted for B-RAM, C-Ram and RDB head at fuelling machines being tested at RTD, Hall 7 and at Tarapur. Laboratory evaluations were also carried out at Tribology Lab RTD to study effect of radiation on the composite. Paper deals with the various aspects of life prediction of this material in term of wear and radiation damage. (author)

2006-11-01

198

Nuclear waste treatment program: Annual report for FY 1987  

Energy Technology Data Exchange (ETDEWEB)

Two of the US Department of Energy's (DOE) nuclear waste management-related goals are to ensure that waste management is not an obstacle to the further development of light-water reactors and the closure of the nuclear fuel cycle and to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Remedial Action and Waste Technology of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific ...

1988-09-01

199

HISTORICAL AMERICAN ENGINEERING RECORD - IDAHO NATIONAL ENGINEERING AND ENVIRONMENTAL LABORATORY, TEST AREA NORTH, HAER NO. ID-33-E  

Energy Technology Data Exchange (ETDEWEB)

Test Area North (TAN) was a site of the Aircraft Nuclear Propulsion (ANP) Project of the U.S. Air Force and the Atomic Energy Commission. Its Cold War mission was to develop a turbojet bomber propelled by nuclear power. The project was part of an arms race. Test activities took place in five areas at TAN. The Assembly & Maintenance area was a shop and hot cell complex. Nuclear tests ran at the Initial Engine Test area. Low-power test reactors operated at a third cluster. The fourth area was for Administration. A Flight Engine Test facility (hangar) was built to house the anticipated nuclear-powered aircraft. Experiments between 1955-1961 proved that a nuclear reactor could power a jet engine, but President John F. Kennedy canceled the project in March 1961. ANP facilities were adapted for new reactor projects, the most important of which were Loss of Fluid Tests (LOFT), part of ...

2005-02-01

200

A pilot application of risk-based methods to establish in-service inspection priorities for nuclear components at Surry Unit 1 Nuclear Power Station  

International Nuclear Information System (INIS)

As part of the Nondestructive Evaluation Reliability Program sponsored by the US Nuclear Regulatory Commission, the Pacific Northwest Laboratory is developing a method that uses risk-based approaches to establish in-service inspection plans for nuclear power plant components. This method uses probabilistic risk assessment (PRA) results and Failure Modes and Effects Analysis (FEMA) techniques to identify and prioritize the most risk-important systems and components for inspection. The Surry Nuclear Power Station Unit 1 was selected for pilot applications of this method. The specific systems addressed in this report are the reactor pressure vessel, the reactor coolant, the low-pressure injection, and the auxiliary feedwater. The results provide a risk-based ranking of components within these systems and relate the target risk to target failure probability values for individual components. These results ...

201

Recycle of iodine-loaded silver mordenite by hydrogen reduction  

Science.gov (United States)

In 1977 and 1978, workers at Idaho National Engineering Laboratory (INEL) developed and tested a process for the regeneration and reuse of silver mordenite, AgZ, used to trap iodine from the dissolver off-gas stream of a nuclear fuel reprocessing plant. We were requested by the Airborne Waste Management Program Office of the Department of Energy to perform a confirmatory recycle study using repeated loadings at about 150/sup 0/C with elemental iodine, each followed by a drying step at 300/sup 0/C, then by iodine removal using elemental hydrogen at 500/sup 0/C. The results of our study show that AgZ can be recycled. There was considerable difficulty in stripping the iodine at 500/sup 0/C.; however, this step went reasonably well at 550/sup 0/C or slightly higher, with no apparent loss in the iodine-loading capacity of the AgZ. Large releases of elemental iodine occurred during the drying stage and the early part of the stripping stage. Lead ...

1982-11-01

202

Quarterly progress report for the Chemical and Energy Research Section of the Chemical Technology Division: October-December 1997  

Energy Technology Data Exchange (ETDEWEB)

This report summarizes the major activities conducted in the Chemical and Energy Research Section of the Chemical Technology Division at Oak Ridge National Laboratory (ORNL) during the period October--December 1997. The section conducts basic and applied research and development in chemical engineering, applied chemistry, and bioprocessing, with an emphasis on energy-driven technologies and advanced chemical separations for nuclear and waste applications. The report describes the various tasks performed within six major areas of research: Hot Cell Operations, Process Chemistry and Thermodynamics, Separations and Materials Synthesis, Fluid Structure and Properties, Biotechnology Research, and Molecular Studies. The name of a technical contact is included with each task described, and readers are encouraged to contact these individuals if they need additional information. Activities conducted within the area of Hot Cell ...

1999-02-01

203

Laboratory test on soil-structure interaction with backfill soil using non-linear material (embedment effect tests on soil-structure interaction)  

International Nuclear Information System (INIS)

A series of Model Tests of Embedment Effect on Reactor Buildings has been carried out by the Nuclear Power Engineering Corporation (NUPEC), under the sponsorship of the Ministry of International Trade and Industry (MITI) of Japan. Seismic response of an embedded reactor building is greatly affected by the non-linearity of the backfill soil. However, quite few experimental data have been obtained so far. The objective of this study is to qualitatively evaluate the non-linear behavior of the backfill soil through shaking table tests. Its effects to the seismic response of a reactor building constructed at a soft rock site can be made clear through the tests. Non-linear effects of the backfill soil on the seismic response of the embedded reactor building model were evaluated experimentally. Based on the sinusoidal and seismic wave excitation tests, the following conclusions were obtained regarding the changes in vibrational characteristics of the building model which ...

1993-08-15

204

FFTF operational results: startup to 100 MWd/kg  

International Nuclear Information System (INIS)

The Fast Flux Test Facility (FFTF) is a 400-MW(t) sodium-cooled fast reactor operating at the Hanford Engineering Development Laboratory in Richland, Washington, to conduct fuels and materials testing in support of the US liquid-metal fast breeder reactor program. Startup and initial power testing included a comprehensive series of nuclear and nonnuclear tests to verify the thermal and neutronic characteristics of the plant and to demonstrate its inherent safety features. Extensive reactor core characterization measurements were completed to provide the neutron and gamma spectra, fission rates, and other physics data needed to design and evaluate tests irradiated in the FFTF. A specially designed series of natural-circulation tests was performed to demonstrate the inherent safety features of the plant. Early in 1982 the FFTF began its first 100-d irradiation cycle. Since that time the plant has operated beyond expectations; ...

205

Computer modelling of eddy current probes for ISI of pressure tube/calandria tube assemblies in PHWRs  

International Nuclear Information System (INIS)

Non-destructive Evaluation (NDE) plays a major role in ensuring the safe and reliable operation of PHWRs which are the mainstay of India's nuclear power programme. An important in-service inspection (ISI) requirement in these reactors is carried out through Eddy Current Testing (ECT) of the pressure tube (PT)/calandria tube (CT) assemblies. The material of construction of these assemblies is zircaloy-2. The two main objectives of this ISI are the detection of garter spring between CT and PT and the profiling of gap between CT and PT. The paper discusses the work carried out at the authors' laboratory on the development of ECT probes for ISI of PT/CT assemblies. Emphasis has been given on the work done on the design and optimisation of the probes using computer modeling. A 2-D finite element code has been developed for this purpose. The code is developed around a diffusion equation which can be derived from Maxwell's ...

1991-12-01

206

Accelerator technology program. Progress report, April-December 1978  

Science.gov (United States)

This report presents highlights of activities in the Acceleartor Technology (AT) Division from April through December 1978. The report is divided into 10 sections to cover work done by the four groups that make up AT Division (AT-1, AT-2, AT-3, and AT-4). Section I is a brief summary of the whole report. Sections II through VI describe work done by At-1, the Linac Technology Group. Subjects covered are the Pion Generation for Medical Irradiation Program, the Electronuclear Fuel-Producing Accelerator Program, the Gyrocon rf Amplifier Program, the Electron Linear Accelerator Program, and the Free Electron Laser Program. Section VII covers the Linear Accelerator Beam Dynamics development, and Sec. VIII deals with work with the H/sup -/ Ion Source. Most of the work in Secs. VII and VIII was done by AT-2, the Special Projects Group, although work on factors influencing emittance growth was done by MP-9, and results on emittance growth in the new European Council for ...

1980-05-01

207

Future needs and requirements for AMS "1"4C standards and reference materials  

International Nuclear Information System (INIS)

"1"4C measurement uses a number of standards and reference materials with different properties. Historically the absolute calibration of "1"4C measurement was tied to 1890 wood, through the 'primary' standard of NBS-OxI (produced by the National Bureau of Standards, now NIST - National Institute of Standards and technology) subsequently replaced by NBS-OxII. These are both internationally calibrated and certified materials, whose "1"4C activities are known absolutely. A second tier of materials, often called secondary standards or reference materials, and including internationally recognised materials such as ANU-sucrose (now also IAEA-C6), Chinese - sucrose and the IAEA C1-C6 series, augmented by additional oxalic acid samples are also used routinely. The activity of these materials has been estimated from large numbers of measurements made by many ...

2004-08-01

208

Meier associates and Pacific Northwest Laboratory staff exchange: Transfer of corrosion monitoring expertise to assess and develop in-line inspection tools for corrosion control  

Energy Technology Data Exchange (ETDEWEB)

Staff exchanges, such as the one described in this report, are intended to facilitate communication and collaboration among scientists and engineers at DOE laboratories, in US industry, and academia. During the past 5 years, PNL has developed prototype instrumentation to automate the data collection required for electrochemical determination of corrosion rates and behavior of materials in various electrically conductive environments. The last version is labeled the Sentry 100 prototype corrosion data scanner. Applications include these in the pulp and paper industry and at hazardous waste sites.

1995-04-01

209

A decade of waste and pollution management  

Energy Technology Data Exchange (ETDEWEB)

The purpose of this report is to provide the reader with a basic understanding of Argonne National Laboratory`s current general refuse disposal and material recycling programs, how they were developed, and where they are going. In order to better understand the current situation, a brief description of the facilities past practices is explained. ANL is a multi-program research and development center owned by the U.S. Department of Energy (DOE) and operated by the University of Chicago. Argonne`s primary facilities are on a 1,700 acre site, 27 miles southwest of Chicago. Fifty-seven major buildings house approximately 4,500 employees at the site.

1996-10-01

210

Investigation of selected trace elements as nuclear forensics signatures  

International Nuclear Information System (INIS)

Nuclear material is either a product of technological processing of natural source material or it is entirely of anthropogenic origin. Consequently, nuclear material carries 'tool-marks' or 'fingerprints' of the process it was subjected to. Uranium fuels are examples of the first category, while plutonium belongs to the second category. The nature of these production processes is reflected in the elemental and isotopic composition of the material as well as in its microscopic and macroscopic appearance. All of these parameters can be determined using appropriate analytical techniques and they may result in important conclusions on the history and on the origin of the material. Therefore, they provide the most essential contribution to the prevention of future diversions of nuclear material from the ...

211

Implementation of integrated safeguards in Nuclear Fuel Plant at Pitesti, Romania  

International Nuclear Information System (INIS)

The nuclear activity was conducted for many years in Romania under Traditional Safeguards (TS) and has developed in good conditions the specific nuclear safeguards. Now there is a good opportunity to improve the performance and quality of the safeguards activity and at the same time to increase the accountancy and control of nuclear materials by passing to Integrated Safeguards (IS) implementation. The legal framework is the Law 100/2000 for ratification of the Protocol between Romania and International Atomic Energy Agency (IAEA), additional completion to the Agreement between the Socialist Republic of Romania Government and IAEA relating to safeguards. It is part of the Treaty on the non-proliferation of nuclear weapons published in the Official Gazette no. 3/31 January 1970, and the Additional Protocol published in the Official Gazette no. 295/ 29.06.2000. The first discussion ...

2009-10-12

212

Criticality safety analysis for mockup facility  

Energy Technology Data Exchange (ETDEWEB)

Benchmark calculations for SCALE4.4 CSAS6 module have been performed for 31 UO{sub 2} fuel, 15MOX fuel and 10 metal material criticality experiments and then calculation biases of the SCALE 4.4 CSAS6 module have been revealed to be 0.00982, 0.00579 and 0.02347, respectively. When CSAS6 is applied to the criticality safety analysis for the mockup facility in which several kinds of nuclear material components are included, the calculation bias of CSAS6 is conservatively taken to be 0.02347. With the aid of this benchmarked code system, criticality safety analyses for the mockup facility at normal and hypothetical accidental conditions have been carried out. It appears that the maximum K{sub eff} is 0.28356 well below than the critical limit, K{sub eff}=0.95 at normal condition. In a hypothetical accidental condition, the maximum K{sub eff} is found to be 0.73527 much lower than the subcritical limit. For another hypothetical ...

2000-03-01

213

Sample requirements and design of an inter-laboratory trial for radiocarbon laboratories  

International Nuclear Information System (INIS)

An on-going inter-comparison programme which is focused on assessing and establishing consensus protocols to be applied in the identification, selection and sub-sampling of materials for subsequent "1"4C analysis is described. The outcome of the programme will provide a detailed quantification of the uncertainties associated with "1"4C measurements including the issues of accuracy and precision. Such projects have become recognised as a fundamental aspect of continuing laboratory quality assurance schemes, providing a mechanism for the harmonisation of measurements and for demonstrating the traceability of results. The design of this study and its rationale are described. In summary, a suite of core samples has been defined which will be made available to both AMS and radiometric laboratories. These core materials are representative of routinely dated material and their ages span ...

2000-10-01

214

The proton microprobe: Applications in the biomedical field  

Energy Technology Data Exchange (ETDEWEB)

This book explores the development, present, and future applications of proton microprobes in the micrometer range. Among the topics discussed: the use of proton beams for analytical purposes; techniques of focusing or collimating ion beams; improving and measuring beam spots; the analytical capabilities of the nuclear microprobe in comparison to other micro techniques; and applications and results by several internationally known microprobe laboratories.

1986-01-01

215

DECOVALEX - Mathematical models of coupled T-H-M processes for nuclear waste repositories. Report of phase III  

Energy Technology Data Exchange (ETDEWEB)

This report presents the methodologies and results of the field/laboratory experiments and mathematical modeling defined for the phase III of the project. Results from test cases 2-6 are given in separate chapters of the report (which have been indexed separately), and the last chapter discusses the lessons learned from the three phases of the DECOVALEX project.

1995-12-01

216

Cumulative kaon production by 10 GeV protons  

International Nuclear Information System (INIS)

The K"+- and K"-meson cumulative production cross sections are measured at 119"0 in the laboratory system on nuclei Be, Al, Cu and Ta bombarded by 10 GeV protons. Spectra of the K"-mesons consisting of only sea quarks show universal features characteristic of the spectra of cumulative particles, which contain valence quarks. Evidence is obtained for the fact that the energy density in a flucton can exceed the mean nuclear density by an order of magnitude.

217

Advances on experimental techniques for the characterization of THM behaviour of bentonite  

Energy Technology Data Exchange (ETDEWEB)

The design of high level radioactive waste (HLW) repositories in deep geological media in which bentonite clay is proposed as a sealing material leads to the need of further studying the behaviour of highly compacted expansive soils when subjected to mechanical, hydraulic and thermal changes. Laboratory tests may help to understand the processes that take place in the clay barrier under simple and controlled conditions and to develop the governing equations. The laboratory tests enable to isolate the different processes, making their interpretation easier, and provide with fundamental data concerning the parameters to be used in the models. The extremely low permeability of these materials, their avidity for water (high suction) and their high swelling capacity make necessary the modification of the conventional laboratory techniques and procedures to determine basic physical ...

2005-07-01

218

Security features of a nuclear material accounting system  

Energy Technology Data Exchange (ETDEWEB)

The Los Alamos Nuclear Material Accounting and Safeguards System (MASS) is a near-real-time accountability system for bulk materials, discrete items, and material undergoing dynamic processing. MASS has evolved from an eighty-column card based process control system to a very sophisticated computer system. The security of the MASS computer system is provide through various access controls. There are two kinds of access control to be addressed. They are physical access control to the hardware which make up the system, and access control to the software. There are many features which provide a measure of security to the hardware that will be discussed. Access to the software is controlled by a security password. Access to various transaction activities in the system is controlled through the level of MASS user privilege. Details of MASS user privilege will be discussed.

1988-01-01

219

Recovery of reactor pressure vessel materials from radiation hardening and embrittlement after a year of irradiation of microtensile and Charpy-V specimens in a nuclear power plant  

International Nuclear Information System (INIS)

Weld metal, base material and stainless steel overlay specimens for Charpy tests and static tensile tests were irradiated for a year in a power reactor of the Bohunice nuclear power plant in place of the evaluated surveillance specimens. The material of the specimens was identical with that of the WWER-440 reactor pressure vessels, and was exposed to a fluence of (1.2 - 4.5) x 10"2"3 m"-"2 (E > 0.5 MeV) at approximately 270 degC. Some of the irradiated as well as unirradiated specimens were subjected to regeneration annealing at 475 degC for 168 h. The behavior of the materials after irradiation and annealing was evaluated. (author). 33 tabs., 32 figs., 8 refs.

220

Radon diffusion studies through building construction materials using solid state nuclear track detectors  

International Nuclear Information System (INIS)

Radon appears mainly by diffusion processes from the point of origin following #alpha#- decay of "2"2"6Ra in underground soil and building materials used, in the construction of floors, walls, and ceiling. The transport phenomenon of radon through diffusion is a significant contributor to indoor radon entry. In the present study radon diffusion through sand, cement, mixtures of sand + cement (1:1), sand + cement (2:1), sand + cement (3:1), sand + cement (4:1) has been carried out using LR-115 type II solid state nuclear track detectors (SSNTDs). The radon diffusion coefficient and diffusion lengths have been calculated for different materials. The effect of compaction, which changes the porosity and permeability of the materials, on radon diffusion has also been studied. (author)

2003-10-16

221

National and International Security Applications of Cryogenic Detectors - Mostly Nuclear Safeguards  

International Nuclear Information System (INIS)

As with science, so with security--in both arenas, the extraordinary sensitivity of cryogenic sensors enables high-confidence detection and high-precision measurement even of the faintest signals. Science applications are more mature, but several national and international security applications have been identified where cryogenic detectors have high potential payoff. International safeguards and nuclear forensics are areas needing new technology and methods to boost speed, sensitivity, precision and accuracy. Successfully applied, improved nuclear materials analysis will help constrain nuclear materials diversion pathways and contribute to treaty verification. Cryogenic microcalorimeter detectors for X-ray, gamma-ray, neutron, and alpha-particle spectrometry are under development with these aims in mind. In each case the unsurpassed energy resolution of microcalorimeters reveals ...

2009-12-16

222

UMCP-BG and E collaboration in nuclear power engineering in the framework of DOE-Utility Nuclear Power Engineering Education Matching Grant Program  

Energy Technology Data Exchange (ETDEWEB)

The DOE-Utility Nuclear Power Engineering Education Matching Grant Program has been established to support the education of students in Nuclear Engineering Programs to maintain a knowledgeable workforce in the United States in order to keep nuclear power as a viable component in a mix of energy sources for the country. The involvement of the utility industry ensures that this grant program satisfies the needs and requirements of local nuclear energy producers and at the same time establishes a strong linkage between education and day-to-day nuclear power generation. As of 1997, seventeen pairs of university-utility partners existed. UMCP was never a member of that group of universities, but applied for the first time with a proposal to Baltimore Gas and Electric Company in January 1999 [1]. This proposal was generously granted by BG&E [2,3] in the form of a gift in the ...

2000-03-01

223

Status of the ANS low power and shutdown PRA standard  

Energy Technology Data Exchange (ETDEWEB)

The Low Power and Shutdown (LPSD) PRA (Probabilistic Risk Assessment) Standard (ANS-58.22) is currently being drafted by a Writing Group under the auspices of the Risk Informed Standards Committee of the American Nuclear Society (ANS). The Writing Group includes representatives from nuclear utilities, US Nuclear Regulatory Commission (NRC), national laboratories, universities, and consultants with substantial experience producing LPSD PRAs. This draft standard is scheduled to be released for public comment in the second quarter of 2004, with publication by the end of 2004. The LPSD PRA Standard is based on a mature technology that shares many requirements with full power PRAs. It will provide specific methods and criteria whereby PRAs of appropriate quality and scope can be used in the conduct of plant decision-making and other activities, including addressing NRC requirements. This paper presents the ...

2004-07-01

224

Radioactive decay data tables  

Energy Technology Data Exchange (ETDEWEB)

The estimation of radiation dose to man from either external or internal exposure to radionuclides requires a knowledge of the energies and intensities of the atomic and nuclear radiations emitted during the radioactive decay process. The availability of evaluated decay data for the large number of radionuclides of interest is thus of fundamental importance for radiation dosimetry. This handbook contains a compilation of decay data for approximately 500 radionuclides. These data constitute an evaluated data file constructed for use in the radiological assessment activities of the Technology Assessments Section of the Health and Safety Research Division at Oak Ridge National Laboratory. The radionuclides selected for this handbook include those occurring naturally in the environment, those of potential importance in routine or accidental releases from the nuclear fuel cycle, those of current interest in ...

1981-01-01

225

Laser application in the fabrication of gas-tagged capsules. A leak detection system  

Energy Technology Data Exchange (ETDEWEB)

Encapsulation of a unique isotopic blend of krypton and xenon gas employs a special application of laser technology. The encapsulated gas is then used as the primary medium for detection and identification of failed nuclear fuel rods. The use of gas tagging as a means of detecting and identifying failed nuclear fuel rods has been successfully demonstrated and used by the Argonne National Laboratory, Experimental Breeder Reactor (EBR-2) Project, and the Westinghouse Hanford Company (WHC), Fast Flux Test Facility (FFTF) Fast Breeder Reactor Program. The Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan has selected this leak detection system for use in their MONJU Prototype Reactor fuel assemblies. The MONJU reactor is almost identical in design to the highly successful FFTF reactor, which is currently in standby status.

1993-12-01

226

Hot Cell Facility (HCF) Safety Analysis Report  

Energy Technology Data Exchange (ETDEWEB)

This Safety Analysis Report (SAR) is prepared in compliance with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports, and has been written to the format and content guide of DOE-STD-3009-94 Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports. The Hot Cell Facility is a Hazard Category 2 nonreactor nuclear facility, and is operated by Sandia National Laboratories for the Department of Energy. This SAR provides a description of the HCF and its operations, an assessment of the hazards and potential accidents which may occur in the facility. The potential consequences and likelihood of these accidents are analyzed and described. Using the process and criteria described in DOE-STD-3009-94, safety-related structures, systems and components are identified, and the important safety functions of each SSC are described. Additionally, information which ...

2000-11-01

227

Applicability of structural wall test results to seismic design of nuclear facilities  

International Nuclear Information System (INIS)

A review of tests on earthquake-resistant reinforced concrete structural walls is presented. Laboratory tests of isolated walls and construction joints are discussed. Where appropriate, design recommendations are given. The review indicates only few experimental data are available for short walls which are directly applicable to nuclear power plant design. In particular, tests of short rectangular walls subjected to load reversals are needed. Tests are also needed to determine the damping and frequency characteristics of cracked short walls. Analytical and experimental results should be correlated so that the hysteretic response observed in tests can be realistically related to the analytical response 'demand' of nuclear power plant structures. (Auth.).

228

Study of nuclear materials by neutron scattering.  

Science.gov (United States)

Following studies on fiber and sheet texture of hexagonal crystal system in 1988, work has been extended to tube texture. Using the zircaloy-4 fuel cladding of Wolsung-type reactor as specimen, six pole figures for different crystallographic planes were m...

1990-01-01

229

Isotopic composition of elements in extra-terrestrial materials 1  

Energy Technology Data Exchange (ETDEWEB)

The present review focuses on the isotropic composition in extra-terrestrial materials. There are many different factors in the variation in isotopic abundance between terrestrial and extra-terrestrial materials. Major factors in unusual isotopic composition are roughly grouped into three categories: factors associated with fractionation of isotopes, nuclear reaction or radioactive disintegration. Fractionation takes place due to differences in mass among various isotopes. There are physical and chemical factors. Physical ones include vaporization and condensation which meteorites may experience during their formation while the chemical ones include chemical reactions and chemical equilibration. There phenomena are mentioned as factors in the variation in isotopic ratio which is associated with nuclear reactions. An important nuclear reaction is the formation of elements that has ...

1989-02-01

230

Hydrogen in metals  

International Nuclear Information System (INIS)

An important application of metal hydrides is as a moderator material in nuclear reactors. The fundamental properties of hydrides are illustrated and an impression given of the current research into hydrogen in transition metals. Phase diagrams, magnetic properties, temperature dependence of the diffusion coefficient, energy level schemes and superconductivity are considered. (C.F.).

231

Borehole Plugging Program  

International Nuclear Information System (INIS)

Activities are reported in programs to locate, test, and select materials for borehole plugs near nuclear waste repositories. Background information concerning borehole plugging is presented and work to date is summarized. Borehole sealants considered are listed and recommended steps to plug boreholes are given. Planned research is summarized.

232

Elk and Deer Study, Material Disposal Area G, Technical Area 54: Source document  

Energy Technology Data Exchange (ETDEWEB)

As nuclear research has become more prevalent, environmental contamination from the disposal of radioactive waste has become a prominent issue. At Los Alamos National Laboratory (LANL) in northern New Mexico, radioactive contamination from disposal operations has raised some very specific concerns. Material Disposal Area G (Area G) is the primary low-level radioactive waste disposal site at LANL and occupies an area adjacent to land belonging to the Native American community of the Pueblo of San Ildefonso. Analyses of soil and vegetation collected from the perimeter of Area G have shown concentrations of radionuclides greater than background concentrations established for northern New Mexico. As a result, Pueblo residents had become concerned that contaminants from Area G could enter tribal lands through various ecological pathways. The residents specifically questioned the safety of consuming meat from elk and deer that ...

1999-09-01

233

New facility design and work method for the quantitative fit testing laboratory. Master's thesis  

Energy Technology Data Exchange (ETDEWEB)

The United States Air Force School of Aerospace Medicine (USAFSAM) tests the quantitative fit of masks which are worn by military personnel during nuclear, biological, and chemical warfare. Subjects are placed in a Dynatech-Frontier Fit Testing Chamber, salt air is fed into the chamber, and samples of air are drawn from the mask and the chamber. The ratio of salt air outside the mask to salt air inside the mask is called the quantitative fit factor. A motion-time study was conducted to evaluate the efficiency of the layout and work method presently used in the laboratory. A link analysis was done to determine equipment priorities, and the link data and design guidelines were used to develop three proposed laboratory designs. The proposals were evaluated by projecting the time and motion efficiency, and the energy expended working in each design. Also evaluated were the lengths of the equipment links for each proposal, and ...

1989-05-01

234

A Radiation Laboratory Curriculum Development at Western Kentucky University  

Science.gov (United States)

We present the latest developments for the radiation laboratory curriculum at the Department of Physics and Astronomy of Western Kentucky University. During the last decade, the Applied Physics Institute (API) at WKU accumulated various equipment for radiation experimentation. This includes various neutron sources (computer controlled d-t and d-d neutron generators, and isotopic 252 Cf and PuBe sources), the set of gamma sources with various intensities, gamma detectors with various energy resolutions (NaI, BGO, GSO, LaBr and HPGe) and the 2.5-MeV Van de Graaff particle accelerator. XRF and XRD apparatuses are also available for students and members at the API. This equipment is currently used in numerous scientific and teaching activities. Members of the API also developed a set of laboratory activities for undergraduate students taking classes from the physics curriculum (Nuclear Physics, Atomic Physics, and Radiation ...

2009-03-10

235

Understanding and protecting steam generator materials  

Science.gov (United States)

Solid solution-strengthened nickel base alloys have been used for nuclear stream generator tubing in pressurized water reactors since the beginnings of commercial nuclear power. The purpose of this paper is to recap and update the authors understanding of the relationship between processing, resulting structure, and properties for Alloy 600 and to discuss the requirements for optimized performance in both primary and secondary environments. Potential replacement materials and their performance will be discussed. Also discussed is the role and importance of system chemistry, bulk and local, and control and its relationship to performance. A discussion of potential mechanisms of environmentally assisted failure is also discussed.

1986-01-01

236

Understanding and protecting steam generator materials  

International Nuclear Information System (INIS)

Solid solution-strengthened nickel base alloys have been used for nuclear stream generator tubing in pressurized water reactors since the beginnings of commercial nuclear power. The purpose of this paper is to recap and update the authors understanding of the relationship between processing, resulting structure, and properties for Alloy 600 and to discuss the requirements for optimized performance in both primary and secondary environments. Potential replacement materials and their performance will be discussed. Also discussed is the role and importance of system chemistry, bulk and local, and control and its relationship to performance. A discussion of potential mechanisms of environmentally assisted failure is also discussed.

1986-11-16

237

End user needs for enhanced IAEA Safeguards Information Management Capabilities  

International Nuclear Information System (INIS)

The International Atomic Energy Agency is undertaking a program for strengthening its safeguards on the recognition that safeguards must give assurance not only of the non-diversion of declared material or that declared facilities are not being misused, but also of the absence of any undeclared nuclear activities in States which have signed comprehensive safeguards agreements with the Agency. The IAEA has determined that the detection of undeclared nuclear activities and the creation of confidence in the continuing peaceful use of declared material and facilities is largely dependent on more information being made available to the Agency and on the capability of the Agency to make more effective use of this additional information, as well as existing information.

238

Reference materials to evaluate measurement systems for the nutrient composition of foods: results from USDA?s National Food and Nutrient Analysis Program (NFNAP)  

British Library Electronic Table of Contents (United Kingdom)

Over a 6.5-year period a total of 2554 values were reported by nine laboratories for 259 certified or reference nutrient concentrations in 26 certified reference materials (CRM) submitted to contract laboratories, blinded, as part of the qualifying process for analytical contracts and in the routine sample stream as part of the National Food and Nutrient Analysis Program. Each value was converted to a Z?-score, reflecting the difference from the assigned value related to the combined expected analytical uncertainty plus the uncertainty in the CRM value. Z?-scores >|3.0| were considered unacceptable. For some nutrients (Na, folate, dietary fiber, pantothenic acid, thiamin, tocopherols, carotenoids, monounsaturated, and polyunsaturated fatty acids), >20% of Z?-scores were >|3.0|. For total f...

2007-01-01

239

Insitu Assessment of Contaminant Containment Systems  

Environmental Research Database

Objectives(1) Evaluate various insitu techniques for determination of the permeability of slurry walls and investigate the extent of material disturbance and fracturing during drilling and testing.~%~~%~(2) Perform laboratory tests of block samples obtained from the field testing site and compare the results with field measurements.~%~~%~(3) Investigate the mechanisms of drilling using a newly developed instrumented self-boring device and develop a theoretical framework for drilling mechanisms in soils.~% [continued...]DescriptionCement-bentonite and clay liner systems are used as components of containment systems by the environmental industry to control the migration of pollution. In the interest of public safety, following construction, there is a requirement to test these structures in orde to assess if they meet the design critetia. At present this is done only indirectly via ...

2006-01-30

240

FY 1992 Measurements and Characterization Branch annual report  

Energy Technology Data Exchange (ETDEWEB)

The Measurements and Characterization Branch actively supports the advancement of DOE/NREL goals for the development and implementation of the solar photovoltaic (PV) technology. The primary focus of the laboratories is to provide state-of-the-art analytical capabilities for materials and device characterization and fabrication. The branch houses a comprehensive facility that Is capable of providing information on the full range of PV components. A major objective of the branch is to aggressively pursue collaborative research with other government laboratories, universities, and industrial firms for the advancement of Pv technologies. Members of the branch disseminate research findings to the technical community in publications and presentations. The Measurements and Characterization Branch encompasses seven coordinated research groups, providing integrated research and development that covers all aspects of photovoltaic ...

1993-03-01

241

Studies of nuclear processes at the Triangle Universities Nuclear Laboratory. Progress report, 1 September 1995--31 August 1996  

Energy Technology Data Exchange (ETDEWEB)

The Triangle Universities Nuclear Laboratory (TUNL)--a collaboration of Duke University, North Carolina State University, and the University of North Carolina at Chapel Hill--has had a very productive year. This report covers parts of the second and third year of a three-year grant between the US Department of Energy and the three collaborating universities. The TUNL research program focuses on the following areas: precision test of parity-invariance violation in resonance neutron scattering at LANSCE/LANL; parity violation measurements using charged-particle resonances in A = 20--40 targets and the A = 4 system at TUNL; chaotic behavior in the nuclei {sup 30}P and {sup 34}Cl from studies of eigenvalue fluctuations in nuclear level schemes; search for anomalies in the level density (pairing phase transition) in 1f-2p shell nuclei using GEANIE at LANSCE/LANL; parity-conserving time-reversal noninvariance tests using {sup ...

1996-09-01

242

Automation in a material processing/storage facility  

Energy Technology Data Exchange (ETDEWEB)

The Savannah River Site (SRS) is currently developing a new facility, the Actinide Packaging and Storage Facility (APSF), to process and store legacy materials from the United States nuclear stockpile. A variety of materials, with a variety of properties, packaging and handling/storage requirements, will be processed and stored at the facility. Since these materials are hazardous and radioactive, automation will be used to minimize worker exposure. Other benefits derived from automation of the facility include increased throughput capacity and enhanced security. The diversity of materials and packaging geometries to be handled poses challenges to the automation of facility processes. In addition, the nature of the materials to be processed underscores the need for safety, reliability and serviceability. The application of automation in this facility must, ...

1997-05-01

243

Radioxenons: Their role in monitoring a Comprehensive Test Ban Treaty  

Energy Technology Data Exchange (ETDEWEB)

Monitoring for xenon radionuclides which are produced in a nuclear detonation can provide a strong deterrent to the violation of a Comprehensive nuclear Test Ban Treaty (CTBT). There are 18 known radioactive xenon isotopes produced in nuclear fission with half-lives ranging from less than one second to 11.9 days. However, only four of these remain in significant amounts more than a day after a detonation. In order for radioxenon monitoring to be practical, it was necessary to develop an automated measurement system which could operate unattended for periods of months, measure the entire spectrum of radioxenons, and provide hundreds of times better sensitivities than current laboratory procedures. This capability was developed at the US Department of Energy`s Pacific Northwest National Laboratory based on rapid separation of atmospheric xenon coupled with a unique high sensitivity ...

1996-06-01

244

Progress at LAMPF. Progress report, January-December 1985  

Energy Technology Data Exchange (ETDEWEB)

Research performed at LAMPF during 1985 is reported in the areas of: nuclear and particle physics; atomic and molecular physics; materials science; radiation-effects studies; biomedical research and instrumentation; nuclear chemistry; radioisotope production; and physics theory. Also reported are the status of LAMPF-II, facility development work, and accelerator operations. (LEW)

1986-05-01

245

Pneumatic conveying of sensitive compounds during nuclear fuel fabrication  

International Nuclear Information System (INIS)

Any transport of nuclear material is associated with the risk of contamination after release into working areas or environment. stationary installed safe geometry vessels with pneumatic transfer between them offer unique safety features and reduce operating costs. The article describes the case of HTR fuel spheres, where a specially designed conveying system has been developed and the prototype conveyor has been tested.

246

Numerical analysis of the fusion of nuclear combustible rods under LOCA - type accidents  

International Nuclear Information System (INIS)

The study of the melting of combustible rods is of great importance for the safety analysis of nuclear reactors. Due to the special characteristics of the problem, a sharp interface between the solid and liquid region does not exist, but appears a 'mushy' region in which the material is partially melted. The Finite Element Method is employed here, together with a regularized enthalpy formulation. Finally, the results obtained are presented and discussed. (Author).

1983-12-13

247

Life time management at the Dukovany nuclear power plant  

International Nuclear Information System (INIS)

The paper discusses the role of the Life Management Programme in ensuring a safe operation of the Dukovany nuclear power plant. The Programme involves the following major items: (i) primary circuit materials degradation assessment, (ii) pipeline damage control by the Flow Assisted Corrosion Monitoring and Prediction Programme, and (iii) the DIALIFE diagnostic system. (author)

248

Dust and waterfree technology for demolition works in nuclear environments and other sensitive areas  

International Nuclear Information System (INIS)

At the University of Karlsruhe experiments were carried out from 1997 to 1999 to get fundamentals of flow characteristics of pneumatic extracted materials. The results could be used to develop a concept for demolition suitable for extraction and removing high-density concrete. The concept fulfills all demands of a closed nuclear area, especially of dust abatement. (orig.)

249

Assisting Eastern European countries in the setting up of a national response to nuclear smuggling  

International Nuclear Information System (INIS)

The paper will report the experience gained in the implementation of the national assistance projects, including the detailed assessment of the national situation compared to the ITWG Model Action Plan, the upgrading of the technical skills, the training of national experts and the joint analysis of nuclear material at ITU. The status of the work with the 13 future Member States to the European Union will also be reported on during the conference

2001-10-01

250

Robotics and teleoperator-controlled devices  

International Nuclear Information System (INIS)

This paper presents a rationale for and a summary of tasks and missions to which mobile and stationary robots and other teleoperator-controlled devices could be assigned in response to the accidental release of radioactive and other hazardous/toxic materials to the environment. Many of these vehicles and devices currently support operation and maintenance of nuclear power plants and other nuclear industry facilities. This paper also discusses specific missions for these devices at the Three Mile Island and Chernobyl nuclear power plant sites at the time of the accidents. Also discussed is the status of devices under development for future applications, as well as research on robotics.

251

Radiation safety in industrial applications  

International Nuclear Information System (INIS)

Oil and gas industry is the largest user of radioactive materials in Nigeria. They make use of radiation generators, sealed and unsealed radioactive sources.Some of these are potentially dangerous to human health and environment if not properly controlled. here is also the need to maintain control over occupational exposures to radiation, as well as to protect the public and the environment through proper management of wastes that may be radiologically hazardous. To minimize these, effective regulatory infrastructure is being put in place.For a smooth take-off of the nuclear power program, the National Nuclear Regulatory Authority and other stake holders in the nuclear industry need to start to put together licensing procedure for these.

2008-03-17

252

Nuclear data activity at Atomic Energy Research Establishment, Savar, Dhaka  

Energy Technology Data Exchange (ETDEWEB)

The nuclear data activity at AERE, Savar is briefly presented in this paper. Major thrust is on the customization of cross section libraries for general purpose reactor and shielding calculations. The processing codes that are available are NJOY91.91, some AMPX-Modules and the modules in SCALE-PC. Recent measurements on cross section data over the energy range 13-15 MeV at the Institute of Nuclear science and Technology have been reviewed. Measurements and calculations are based on the determination of excitation functions of neutron induced reactions on the elements and isotopes of FRT-relevant structural materials. (author).

1995-03-01

253

Fission yield measurements by inductively coupled plasma mass-spectrometry  

International Nuclear Information System (INIS)

Correct prediction of the fission products inventory in irradiated nuclear fuels is essential for accurate estimation of fuel burnup, establishing proper requirements for spent fuel transportation and storage, materials accountability and nuclear forensics. Such prediction is impossible without accurate knowledge of neutron induced fission yields. The uncertainty of the fission yields reported in the ENDF/B-VII.0 library is not uniform across all of the data and much of the improvement is desired for certain fissioning isotopes and fission products. We discuss our measurements of cumulative fission yields in nuclear fuels irradiated in thermal and fast reactor spectra using Inductively Coupled Plasma Mass Spectrometry. (author)

2009-11-01

254

Fission yield measurements by inductively coupled plasma mass-spectrometry  

British Library Electronic Table of Contents (United Kingdom)

Correct prediction of the fission products inventory in irradiated nuclear fuels is essential for accurate estimation of fuel burnup, establishing proper requirements for spent fuel transportation and storage, materials accountability and nuclear forensics. Such prediction is impossible without accurate knowledge of neutron induced fission yields. The uncertainty of the fission yields reported in the ENDF/B-VII.0 library is not uniform across all of the data and much of the improvement is desired for certain fissioning isotopes and fission products. We discuss our measurements of cumulative fission yields in nuclear fuels irradiated in thermal and fast reactor spectra using Inductively Coupled Plasma Mass Spectrometry.

2009-01-01

255

Deployment Scenarios for Nuclear Waste Management  

International Nuclear Information System (INIS)

A major objective of the DOE Advanced Fuel Cycle Initiative, AFCI, is to explore technologies that may reduce the long-term environmental burden of nuclear energy through more efficient disposal of waste materials. In this work, the potential impact of the AFCI technology and its beneficial effects on waste management and its ability to meet waste management objectives are demonstrated. In addition, practical scenarios to improve permanent disposal utilization and/or reduce the temporary spent nuclear fuel (SNF) storage inventory by closing the fuel cycle through transition to fast reactor (FR) converters are also discussed. (authors)

256

Corrosion and reliability of PWR power plants  

International Nuclear Information System (INIS)

Corrosion is increasingly becoming an important factor reducing the reliability of many nuclear power plant components. The significance is evaluated of corrosion phenomena with respect to the reliability of primary circuit components of LWR's, viz., the reactor pressure vessel, primary piping, steam generator, and fuel elements. The mechanism of corrosion phenomena is explained and methods of minimizing their effects are presented. An analysis is made of the needs to solve the corrosion problems of nuclear power plants from the point of view of Czechoslovak producers and research and development activities. International cooperation is reviewed and main problems are formulated on which the solution of corrosion problems of structural materials used in WWER type nuclear power plants should be focussed. (author).

257

Artificial intelligence: the future in nuclear plant maintenance  

Energy Technology Data Exchange (ETDEWEB)

The role of robotics and remote handling equipment in future nuclear power plant maintenance activities is discussed in the context of artificial intelligence applications. Special requirements manipulators, control systems, and man-machine interfaces for nuclear applications are noted. Tasks might include inspection with cameras, eddy current probes, and leak detectors; the collection of material samples; radiation monitoring; and the disassembly, repair and reassembly of a variety of system components. A robot with vision and force sensing and an intelligent control system that can access a knowledge base is schematically described. Recent advances in image interpretation systems are also discussed.

1984-12-01

258

Artificial intelligence: the future in nuclear plant maintenance  

International Nuclear Information System (INIS)

The role of robotics and remote handling equipment in future nuclear power plant maintenance activities is discussed in the context of artificial intelligence applications. Special requirements manipulators, control systems, and man-machine interfaces for nuclear applications are noted. Tasks might include inspection with cameras, eddy current probes, and leak detectors; the collection of material samples; radiation monitoring; and the disassembly, repair and reassembly of a variety of system components. A robot with vision and force sensing and an intelligent control system that can access a knowledge base is schematically described. Recent advances in image interpretation systems are also discussed.

1984-09-23

259

In field nuclear forensics: An overview of applicable instrumentation  

International Nuclear Information System (INIS)

Recent seizures of nuclear materials, and particularly of fissionable nuclear materials, have resulted in an increased awareness of the need for fieldable instrumentation for the detection and characterization of suspect packages and materials. The ability to perform in-field assessments of materials contained in suspect packages is important for several reasons. First, and most importantly, determination of the type and quantity of material provides information critical to personnel safety. The personnel at potential risk may include both the general population in the area of the package and incident response personnel. Additionally, it would be advantageous to gain information that could result in attribution of the suspect package to a particular facility or pathway as soon as possible after interception. Limited access to a suspect ...

1997-06-12

260

Enhancement of the decontamination factor for liquid radioactive waste and other radioactive materials  

International Nuclear Information System (INIS)

Decommissioning of radiological and nuclear installations is for this century the new challenge. One of the performance criteria is the reduction of total quantities of radioactive materials (liquid or solid) arising from dismantling and decontamination of radiological and nuclear installations. In this work we present a new application of the water soluble polymers used as: - flocculation agents in treatment and conditioning process within the management of radioactive liquid materials; - strippable coatings on solid materials based on the water soluble polymers. The parameters of water soluble polymers made in our Institute by radiation processing have been analysed, namely the molecular average weight, composition, and efficiency of utilization of these polymeric materials as well as the content of ash, additives, decontamination factor, consumption per ...

2003-10-20

261

Support vector machines for nuclear reactor state estimation  

Energy Technology Data Exchange (ETDEWEB)

Validation of nuclear power reactor signals is often performed by comparing signal prototypes with the actual reactor signals. The signal prototypes are often computed based on empirical data. The implementation of an estimation algorithm which can make predictions on limited data is an important issue. A new machine learning algorithm called support vector machines (SVMS) recently developed by Vladimir Vapnik and his coworkers enables a high level of generalization with finite high-dimensional data. The improved generalization in comparison with standard methods like neural networks is due mainly to the following characteristics of the method. The input data space is transformed into a high-dimensional feature space using a kernel function, and the learning problem is formulated as a convex quadratic programming problem with a unique solution. In this paper the authors have applied the SVM method for data-based state estimation in nuclear ...

2000-02-14

262

Nuclear cask testing films misleading and misused  

Energy Technology Data Exchange (ETDEWEB)

In 1977 and 1978, Sandia National Laboratories, located in Albuquerque, New Mexico, and operated for the US Department of Energy (DOE), filmed a series of crash and fire tests performed on three casks designed to transport irradiated nuclear fuel assemblies. While the tests were performed to assess the applicability of scale and computer modeling techniques to actual accidents, films of them were quickly pressed into service by the DOE and nuclear utilities as proof'' to the public of the safety of the casks. In the public debate over the safety of irradiated nuclear fuel transportation, the films have served as the mainstay for the nuclear industry. Although the scripts of all the films were reviewed by USDOE officials before production, they contain numerous misleading concepts and images, and omit significant facts. The shorter versions eliminated qualifying ...

1991-10-01

263

Influence of organizational factors on performance reliability  

International Nuclear Information System (INIS)

This is the first volume of a two-volume report. Volume 2 will be published at a later date. This report presents the results of a research project conducted by Brookhaven National Laboratory for the United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. The purpose of the project was to develop a general methodology to be use in the assessment of the organizational factors which affect performance reliability (safety) in a nuclear power plant. The research described in this report includes the development of the Nuclear Organization and Management Analysis Concept (GNOMIC). This concept characterizes the organizational factors that impact safety performance in a nuclear power plant and identifies some methods for systematically measuring and analyzing the influence of these factors on safety performance. This report is divided into ...

264

Weather ability studies of phenolic resin coated woods and glass fiber reinforced laminates  

International Nuclear Information System (INIS)

Phenolic resins have made a major breakthrough in the field of high technology in 80's. These are now active participants of "high tech' areas ranging from electronics, computers, communication, outer space, aerospace, advanced materials, bio materials and technology. A phenol - formaldehyde (1:1.5) resin having resin content of 70% synthesized in the laboratory has been applied for wood coating and reinforcing glass fiber. The weatherability and solvent resistance of these items have been studied and results discussed keeping in view the envisaged application for structural materials and chemical equipment. The toxic materials released during contact with solvents for chemical applications and during degradation general have been monitored. The results are discussed with reference to environmental pollution due to these resins and their composites under different conditions. ...

1997-09-01

265

Modeling of Anisotropic Inelastic Behavior  

Energy Technology Data Exchange (ETDEWEB)

An experimental capability, developed at Lawrence Livermore National Laboratory (LLNL), is being used to study the yield behavior of elastic-plastic materials. The objective of our research is to develop better constitutive equations for polycrystalline metals. We are experimentally determining the multidimensional yield surface of the material, both in its initial state and as it evolves during large inelastic deformations. These experiments provide a more complete picture of material behavior than can be obtained from traditional uniaxial tests. Experimental results show that actual material response can differ significantly from that predicted by simple idealized models. These results are being used to develop improved constitutive models of anisotropic plasticity for use in continuum computer codes.

2000-02-25

266

Ensuring the 50 year life of a fissile material container  

Energy Technology Data Exchange (ETDEWEB)

Sandia was presented with an opportunity in 1993 to design containers for the long term storage and transport of fissile material. This program was undertaken at the direction of the US Department of Energy and in cooperation with Lawrence Livermore National Laboratory and Los Alamos National Laboratory which were tasked with developing the internal fixturing for the contents. The hardware is being supplied by Allied Signal Federal Manufacturing and Technologies, and the packaging will occur at Mason and Hangar Corporation`s Pantex Plant. The unique challenge was to design a container that could be sealed with the fissile material contents; and, anytime during the next 50 years, the container could be transported with only the need for the pre-shipment leak test. This required not only a rigorous design capable of meeting the long term storage and transportation requirements, but also resulted in ...

1997-12-01

267

Ceramic/polymer functionally graded material (FGM) lightweight armor system  

Energy Technology Data Exchange (ETDEWEB)

This is the final report of a two-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). Functionally graded material is an enabling technology for lightweight body armor improvements. The objective was to demonstrate the ability to produce functionally graded ceramic-polymer and ceramic-metal lightweight armor materials. This objective involved two aspects. The first and key aspect was the development of graded-porosity boron-carbide ceramic microstructures. The second aspect was the development of techniques for liquid infiltration of lightweight metals and polymers into the graded-porosity ceramic. The authors were successful in synthesizing boron-carbide ceramic microstructures with graded porosity. These graded-porosity boron-carbide hot-pressed pieces were then successfully liquid-infiltrated in vacuum with molten aluminum at 1,300 C, and ...

1998-12-31

268

Origin determination of plutonium material in nuclear forensics  

International Nuclear Information System (INIS)

Plutonium, seized from illicit trafficking in nuclear materials, can originate from several, distinct sources. The primary focus of nuclear-forensics investigations of confiscated Pu is to specify correctly its origin. Such specification is possible by means of accurate determination the Pu isotopic composition. Five Pu samples of different origins were analysed by thermal-ionisation mass spectrometry. The source (i.e., the type of production reactor) of each sample was determined by comparing the measured Pu isotopic composition with that calculated by one of two reactor-production computer codes, ORIGEN2 and SCALE. These results, in conjunction with the age determination of each sample, allow us to deduce the origin of each. (author)

2000-11-01

269

Diffusivity and Absorptivity of EuCl3 in a LiCl-KCl Molten Salt  

Energy Technology Data Exchange (ETDEWEB)

Pyrochemical processing of nuclear fuels using molten salts has attracted much attention because of its potential to be applied for a future spent nuclear fuel management. In the pyrochemical processing, there are a number of steps to electro-refine and electro-win each element of lanthanides and actinides, commonly called trans-uranic elements (TRU). In order to materialize the pyrochemical processing in the nuclear power plant environments, qualitatively and quantitatively monitoring of each elements is necessary. Thus, we have undertaken to develop an on-line observing system of the TRU in LiCl-KCl molten salt media by using electrochemical and spectroscopic methods. In this work, the electrochemical and spectroscopic behaviors of europium as a proxy material for TRU were investigated simultaneously in the LiCl-KCl molten salt.

2009-05-15

270

Diffusivity and Absorptivity of EuCl3 in a LiCl-KCl Molten Salt  

International Nuclear Information System (INIS)

Pyrochemical processing of nuclear fuels using molten salts has attracted much attention because of its potential to be applied for a future spent nuclear fuel management. In the pyrochemical processing, there are a number of steps to electro-refine and electro-win each element of lanthanides and actinides, commonly called trans-uranic elements (TRU). In order to materialize the pyrochemical processing in the nuclear power plant environments, qualitatively and quantitatively monitoring of each elements is necessary. Thus, we have undertaken to develop an on-line observing system of the TRU in LiCl-KCl molten salt media by using electrochemical and spectroscopic methods. In this work, the electrochemical and spectroscopic behaviors of europium as a proxy material for TRU were investigated simultaneously in the LiCl-KCl molten salt

2009-05-01

271

Evaluation of a permeable reactive barrier technology for use at Rocky Flats Environmental Technology Site (RFETS)  

Energy Technology Data Exchange (ETDEWEB)

Three reactive materials were evaluated at laboratory scale to identify the optimum treatment reagent for use in a Permeable Reactive Barrier Treatment System at Rocky Flats Environmental Technology Site (RFETS). The contaminants of concern (COCS) are uranium, TCE, PCE, carbon tetrachloride, americium, and vinyl chloride. The three reactive media evaluated included high carbon steel iron filings, an iron-silica alloy in the form of a foam aggregate, and a peculiar humic acid based sorbent (Humasorb from Arctech) mixed with sand. Each material was tested in the laboratory at column scale using simulated site water. All three materials showed promise for the 903 Mound Site however, the iron filings were determined to be the least expensive media. In order to validate the laboratory results, the iron filings were further tested at a pilot scale (field columns) ...

2000-01-01

272

Production capabilities in US nuclear reactors for medical radioisotopes  

Energy Technology Data Exchange (ETDEWEB)

The availability of reactor-produced radioisotopes in the United States for use in medical research and nuclear medicine has traditionally depended on facilities which are an integral part of the US national laboratories and a few reactors at universities. One exception is the reactor in Sterling Forest, New York, originally operated as part of the Cintichem (Union Carbide) system, which is currently in the process of permanent shutdown. Since there are no industry-run reactors in the US, the national laboratories and universities thus play a critical role in providing reactor-produced radioisotopes for medical research and clinical use. The goal of this survey is to provide a comprehensive summary of these production capabilities. With the temporary shutdown of the Oak Ridge National Laboratory (ORNL) High Flux Isotope Reactor (HFIR) in November 1986, the radioisotopes required for DOE-supported ...

1992-11-01

273

Conventional and unconventional political participation  

Energy Technology Data Exchange (ETDEWEB)

A non-recursive model is proposed and empirically tested with data of opponents of nuclear power. In explaining conventional and unconventional participation the theory of collective action is applied and modified in two respects: the perceived influence on the elimination of collective evils are taken into account; the selective incentives considered are non-material ones. These modifications proved to be valid: the collective good variables and non-material incentives were important determinants for the two forms of participation. Another result was that there is a reciprocal causal relationship between conventional and unconventional participation.

1985-01-01

274

Materials testing and failure analysis activities at the Wilsonville Advanced Coal Liquefaction Research and Development Facility  

Science.gov (United States)

Oak Ridge National Laboratory (ORNL) has for over ten years provided materials testing and failure analysis services to various coal conversion and utilization facilities in the United States. ORNL was involved in these types of activities at all four of the major coal liquefaction pilot plants. This paper presents a summary of activities at Wilsonville over the past two and one-half years. Some details of these activities are discussed below. Failure analysis of elastomers, stainless steels, and alloys is discussed. 6 refs., 9 figs., 13 tabs.

1989-01-01

275

Corrosion studies at the Wilsonville, Alabama, coal liquefaction facility during 1983  

Science.gov (United States)

During 1983, Oak Ridge National Laboratory continued a study of materials performance at the Wilsonville, Alabama, Advanced Coal Liquefaction Research and Development Facility. Materials performance was evaluated by exposure and analysis of corrosion coupons and U-bend specimens, chemical analysis of related process streams, and ultrasonic determination of the thickness of walls of various components. The results of these studies are useful to current plant operators and to designers of future large-scale plants. 18 references, 4 figures, 12 tables.

1984-10-01

276

Ambient Air Radionuclide Concentrations at and near TA-50 from 2003 through the First Quarter of 2004  

Energy Technology Data Exchange (ETDEWEB)

The Meteorology and Air Quality (MAQ) group at Los Alamos National Laboratory maintains and operates a large network of environmental air samplers called AIRNET. Some of these samplers are located near Material Disposal Area C at TA-50, a low-level radioactive waste burial site in the semiarid environment of the Pajarito Plateau, near Los Alamos. AIRNET sampling media consist of a filter and silica gel. They are exchanged once every 2 weeks. Presented are 5 months of air sampling results for 5 stations operating in the vicinity of Material Disposal Area C.

2005-09-05

277

Activities performed within the program of Nuclear Safety Research on structural and cladding materials for innovative reactor systems able to transmute nuclear waste  

International Nuclear Information System (INIS)

Full text: The transmutation of nuclear waste to reduce the burden on a geological repository is a relevant topic within the Program of Nuclear Safety Research of the Research Centre Karlsruhe. Several studies have confirmed that a high efficiency of transmutation of actinides is reached in fast neutron spectrum reactor system. Therefore, an important effort is dedicated to the study of transmutation strategies with different fast reactors and their associated technologies. Moreover, in international contexts as Generation IV International Forum (GIF) and Sustainable Nuclear Energy Technology Platform (SNETP), fast reactors are considered in the frame of sustainable development of nuclear energy and reduction of waste. The systems that are currently under investigation, in the frame of the different fuel cycle scenarios, are liquid metal cooled and gas cooled fast reactors as well as Accelerator Driven ...

2009-10-05

278

RAAN Conference. Support of Nuclear Power. Opening talk  

International Nuclear Information System (INIS)

Nuclear power in Romania was initiated on the basis of CANDU reactor type technology, an option found to fulfill the requirements for a sustainable economic development, to support the electric energy demand of the country and to ensure the population and environment protection. The construction of the Cernavoda NPP was heavily based on the Romanian industry participation and basic and applied nuclear research national resources. The experience acquired from Cernavoda NPP Unit 1 will be fructified in the construction of Units 2-5 to be built. The Romanian Ministry of Education and Research implemented a nuclear national program for research and development taking into account the European Union requirements and recommendations, the cooperation with the IAEA - Vienna and the Romanian government policy on short and medium terms in the nuclear field. The research-development program targeted: the reactor ...

2002-09-06

279

NOAA National Status and Trends Program Tenth Round Intercomparison for Trace Metals in Marine Sediments and Biological Tissues. National Status and Trends Program for marine environmental quality: Technical memo  

Energy Technology Data Exchange (ETDEWEB)

A total of forty participants were included in the exercise, including NOAA, USEPA, state, Australian, Canadian, Mexican and Argentinean laboratories. Two samples were sent by NRC to each participant: a contaminated marine sediment from the vicinity of New York Bay and a freeze dried mussel (Mytilus edulis) from Charlottenlund, Denmark. Laboratories were also asked to analyze two certified reference materials NIST SRM 1566a, and NRC BCSS-1. The elements to be determined were Al, Cr, Fe, Ni, Cu, Zn, As, Se, Ag, Cd, Sn, Hg, and Pb for both matrices, plus Be, Si, Mn, Sb, and Tl for the sediments. An accepted mean and confidence interval were calculated for each analyte in the two unknown samples. Laboratory biases were identified and an overall rating of superior, good, fair or others was assigned to each laboratory.

1996-11-01

280

ESTABLISHMENT OF AN ENVIRONMENTAL CONTROL TECHNOLOGY LABORATORY WITH A CIRCULATING FLUIDIZED-BED COMBUSTION SYSTEM  

Energy Technology Data Exchange (ETDEWEB)

This report is to present the progress made on the project ''Establishment of an Environmental Control Technology Laboratory (ECTL) with a Circulating Fluidized-Bed Combustion (CFBC) System'' during the period January 1, 2005 through March 31, 2005. The following tasks have been completed. First, the renovation of the new Combustion Laboratory is nearly complete, and the construction of the Circulating Fluidized-Bed (CFB) Combustor Building is in the final stages. Second, the fabrication and manufacture of the CFBC Facility is being discussed with a potential contractor. Discussions with potential contactor regarding the availability of materials and current machining capabilities have resulted in the modification of the original designs. The selection of the fabrication contractor for the CFBC Facility is expected during the next quarter. Third, co-firing experiments conducted with coal ...

2005-04-30

281

Application and experience of low alloy steel main coolant lines in PWRs  

Energy Technology Data Exchange (ETDEWEB)

The significant technical and industrial aspects which have led to main coolant line (MCL) materials selection are addressed from a long term experience and operational practice point of view. They are based on the Siemens/KWU developed basic material concept for its nuclear power plants. It considers the choice of appropriate materials, the evaluation and qualification of the materials and the materials manufacturer, the use of appropriate semi-finished products, the tailoring of material and semi-finished products to the specific requirements of the various systems, the application of adequate manufacturing processes and the proof of the requirements by specifying proper tests and examinations. The main systems are assigned to safety classes in accordance with their safety relevance. Summarizing the operation time of ...

1996-08-01

282

Treatment and recycling of spent nuclear fuel. Actinide partitioning - Application to waste management  

International Nuclear Information System (INIS)

subsequent to its in-reactor dwell time, spent fuel still contains large amounts of materials that are recoverable, for value-added energy purposes (uranium, plutonium), together with fission products, and minor actinides, making up the residues from nuclear reactions. The treatment and recycling of spent nuclear fuel, as implemented in France, entail that such materials be chemically partitioned. The development of the process involved, and its deployment on an industrial scale stand as a high achievement of French science, and technology. Treatment and recycling allow both a satisfactory management of nuclear waste to be implemented, and substantial savings, in terms of fissile material. Bolstered of late as it has been, due to spectacularly skyrocketing uranium prices, this strategy is bound to become indispensable, with the advent of the next generation of ...

2008-01-01

283

Use of internal quality control materials for the preparation and maintenance of reliable methods for the measurement of lead in blood  

Energy Technology Data Exchange (ETDEWEB)

The performance of a group of reference laboratories measuring lead in blood, has been monitored by an intensive external quality assessment programme, since 1974. Performance was similar to that observed in other, larger quality control surveys but rapidly improved following detailed investigations of critical factors in the analytical methodology. The introduction of a rigorous internal quality control protocol, with all laboratories using the same well-characterised materials, has produced external quality control results that are both accurate and very tightly distributed. Between-laboratory coefficients of variation of less than 5%, less than 6% and less than 20% are now obtained at concentrations of over 1.0 ..mu..mol/l (20.7 ..mu..g/dl), 0.5-1.0 ..mu..mol/l (10-20 ..mu..g/dl) and less than 0.5 ..mu..mol/l (10 ..mu..g/dl), respectively. These results represent the best that can be achieved by ...

1988-12-01

284

A summary of neutron radiography and neutron radioscopy applications at the University of Michigan Phoenix Memorial Laboratory  

International Nuclear Information System (INIS)

Neutron radiography and neutron radioscopy are rapidly becoming the valuable tools for nondestructive testing and basic research. The Phoenix Memorial Laboratory has developed a neutron facility capable of both film neutron radiography and real time neutron radioscopy, and has used this facility to study several phenomena of interest to the researchers in many areas. Neutrons can be used for imaging the phenomena that X-ray cannot image, such as the presence, absence or movement of hydrogenous materials inside metals such as aluminum or steel. There are three basic methods for obtaining images using neutrons: high resolution film neutron radiography, real-time neutron radioscopy and transfer film neutron radiography. The neutron radiography facility at Phoenix Memorial Laboratory, the neutron radioscopic imaging systems, the neutron radiographic detectors, lubrication studies, spray imaging, flow in porous media, ...

1992-03-01

285

Use of portable HPGE detector and multichannel analyzer for in-situ gamma spectrometry of soil  

International Nuclear Information System (INIS)

Measurement of fission and activation products in the soil or over a plane grass land of a nuclear power station environment is required to find out the long term changes. The inventory of radionuclides in the soil is routinely determined by soil sampling, processing and gamma spectrometry in the laboratory. The method although is proven and accurate is time consuming and largely dependent on homogenous distribution. Therefore, an alternative and rapid method of in-situ gamma spectrometry using portable devices was standardized to determine the concentration of radionuclides in soil, for regular environmental monitoring as well as during emergency condition. The paper presents the methodology, ready to use factors and compares the results of a few measurements made in the environment of Tarapur Atomic Power Station by both in-situ and laboratory methods. (author)

2005-11-23

286

Explosive performance on the non-proliferation experiment  

Energy Technology Data Exchange (ETDEWEB)

The non-proliferation experiment, originally called the chemical kiloton experiment, was planned and executed by Lawrence Livermore National Laboratory to investigate the seismic yield relationship and distinguishing seismic signals between a nuclear event and a large mass conventional explosion. The Los Alamos National Laboratory planned and conducted experiments to further their studies of the source function for signals observed seismically. Since all investigations were contingent on the performance of the emplaced chemical explosive, an array of diagnostic measurements was fielded in the emplaced explosive. The CORRTEX system was used to investigate the explosive initiation and to determine the detonation velocities in multiple levels and in numerous directions. A description of the CORRTEX experiments fielded, a review of the data obtained and some interpretations of the data are reported.

1994-03-01

287

Cost-time management for environmental restoration activities at the Department of Energy`s Idaho National Engineering Laboratory, Idaho Chemical Processing Plant  

Energy Technology Data Exchange (ETDEWEB)

Cost-time management methods have been developed by Westinghouse to examine business applications from a cost-time perspective. The initial application of cost-time management within Westinghouse was targeted at reducing cycle time in the manufacturing sector. As a result of the tremendous success of reduced cycle time in manufacturing, Westinghouse initiated application of the management technique to Environmental Restoration activities at its Government Owned Contractor Operated facilities. The Westinghouse initiative was proposed in support of the Department of Energy`s goals for cost effective Environmental Restoration activities. This paper describes the application of the cost-time method to Environmental Restoration work currently being performed at the Idaho National Engineering Laboratory (INEL) for the Department of Energy (DOE) by Westinghouse Idaho Nuclear Company (WINCO).

1992-05-22

288

Cost-time management for environmental restoration activities at the Department of Energy's Idaho National Engineering Laboratory, Idaho Chemical Processing Plant  

International Nuclear Information System (INIS)

Cost-time management methods have been developed by Westinghouse to examine business applications from a cost-time perspective. The initial application of cost-time management within Westinghouse was targeted at reducing cycle time in the manufacturing sector. As a result of the tremendous success of reduced cycle time in manufacturing, Westinghouse initiated application of the management technique to Environmental Restoration activities at its Government Owned Contractor Operated facilities. The Westinghouse initiative was proposed in support of the Department of Energy's goals for cost effective Environmental Restoration activities. This paper describes the application of the cost-time method to Environmental Restoration work currently being performed at the Idaho National Engineering Laboratory (INEL) for the Department of Energy (DOE) by Westinghouse Idaho Nuclear Company (WINCO).

1992-08-23

289

Characterization of physically vapor deposited AF2400 thin films  

Energy Technology Data Exchange (ETDEWEB)

Anti-reflective coatings made with Teflon AF2400 had the highest damage thresholds recorded for physical vapor deposited coatings at the Lawrence Livermore National Laboratory damage facility. Physical vapor deposited layers of Teflon AF2400, a perfluorinated amorphous polymer, maintained the bulk optical properties of a high transmittance from 200 nm to 1600 nm, and a low refractive index. In addition, the refractive index can be intentionally reduced by control of two common deposition parameters, deposition rate and substrate temperature. Scanning electron microscopy and nuclear magnetic resonance observations indicated that morphological changes caused the variations in the refractive index rather than compositional changes. The coatings adhered to fused silica and silicon wafers under normal laboratory handling conditions.

1993-11-01

290

Brookhaven National Laboratory Coastal Meteorology Program, 1972-1983  

Energy Technology Data Exchange (ETDEWEB)

Research conducted at Brookhaven National Laboratory under the Coastal Meteorology and Diffusion Research Program from 1972 to 1983 is summarized by the following study areas: Diffusion Studies, Boundary Layer Studies, Coastal Meteorology Studies, Air-Sea Interaction Studies, Coastal Transport and Diffusion Climatology, Seabreeze Modeling and Instrument Development, all supported by the US Department of Energy. Studies supported by the Nuclear Regulatory Commission, the National Science Foundation and the American Petroleum Institute are also described. A summary of a Workshop on Coastal Atmospheric Transport Processes, an account of studies in progress, recommendations for future research and a description of facilities and instrumentation available are also included. A list of all publications and presentations prepared as part of the program is given with abstracts. 7 figures, 1 table.

1983-06-01

291

Thermal- and radiation-induced interactions of water on U02 surfaces.  

Energy Technology Data Exchange (ETDEWEB)

Most plans for the disposition of surplus nuclear materials involve storage in sealed containers where the evolution of gases from reactions of adsorbed water could present both pressure and flammability hazards[l] . Despite efforts such as calcining the material to minimize the water content prior to packaging, both residual moisture and readsorbed water may be present in the final containers . Given the anticipated temperature excursions during transportation and storage, this water may thermally desorb, increasing the pressure, and/or thermally dissociate to produce H2 gas, increasing flammability hazards . In addition, the radiation from the nuclear material may induce radiolysis of the water with the likely products being water vapor, H2, 02 and H2O2. In order to better understand the relative importance of the thermal- and radiationinduced chemistry, we have studied the ...

2003-01-01

292

Resource Letter: Quantum Chromodynamics  

CERN Document Server

This Resource Letter provides a guide to the literature on Quantum Chromodynamics (QCD), the relativistic quantum field theory of the strong interactions. Journal articles, books, and other documents are cited for the following topics: quarks and color, the parton model, Yang-Mills theory, experimental evidence for color, QCD as a color gauge theory, asymptotic freedom, QCD for heavy hadrons, QCD on the lattice, the QCD vacuum, pictures of quark confinement, early and modern applications of perturbative QCD, the determination of the strong coupling and quark masses, QCD and the hadron spectrum, hadron decays, the quark-gluon plasma, the strong nuclear interaction, and QCD's role in nuclear physics. The letter {E} after an item indicates elementary level or material of general interest to persons becoming informed in the field. The letter {I}, for intermediate level, indicates material of a somewhat more ...

2010-01-01

293

Materials and Components Technology Division research summary, 1992  

Energy Technology Data Exchange (ETDEWEB)

The Materials and Components Technology Division (MCT) provides a research and development capability for the design, fabrication, and testing of high-reliability materials, components, and instrumentation. Current divisional programs related to nuclear energy support the development of the Integral Fast Reactor (IFR): life extension and accident analyses for light water reactors (LWRs); fuels development for research and test reactors; fusion reactor first-wall and blanket technology; and safe shipment of hazardous materials. MCT Conservation and Renewables programs include major efforts in high-temperature superconductivity, tribology, nondestructive evaluation (NDE), and thermal sciences. Fossil Energy Programs in MCT include materials development, NDE technology, and Instrumentation design. The division also has a complementary instrumentation effort in support of Arms Control ...

1992-11-01

294

Development of `health and environmental safety assessment network system (HESANS)`  

Energy Technology Data Exchange (ETDEWEB)

With the recent advance of the utilization of nuclear energy in a large scale, social interest is being focussed in the potential risk which the nuclear technology will accompany. Especially after the accidents in Chernobyl and other nuclear facilities, serious anxiety to the utilization of nuclear energy is prevailing among the general public. In order to meet the anxiety and distrust of the population in the use of the nuclear power, the health effect or risk which radioactive materials released into the environment will bring about should be comprehensively and properly evaluated, and then should be widely reported to the population. The development of HESANS code system (Health and Environmental Safety Assessment Network System) was planned to set up such a comprehensive computer code that covers a whole pathway of radioactive material ...

1994-03-01

295

The electromechanical battery: The new kid on the block  

Energy Technology Data Exchange (ETDEWEB)

In a funded program at the Lawrence Livermore National Laboratory new materials and novel designs are being incorporated into a new approach to an old concept -- flywheel energy storage. Modular devices, dubbed ``electromechanical batteries`` (EMB) are being developed that should represent an important alternative to the electrochemical storage battery for use in electric vehicles or for stationary applications, such as computer back-up power or utility load-leveling.

1993-08-01

296

Sweetening Orenburg natural gas by removing mercaptans on a natural clinoptilolite through its treatment with hydrocloric acid  

Energy Technology Data Exchange (ETDEWEB)

Laboratory research data is used as the basis for recommendations to be used in selecting a modification regime employing the treatment of clinoptilolite with NS1 to remove mercaptans from natural gas. The dynamic activity of the modified clinoptilolite is seven times greater than the activity of nontreated material.

1982-01-01

297

Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado. Volume 5, Addenda D6--D8 to Appendix D: Final report  

Energy Technology Data Exchange (ETDEWEB)

This volume contains appendices D6 through D8 containing laboratory test data: from MK-F investigation, 1987, Old Rifle and New Rifle sites; on bentonite amended radon barrier material; and from MK-F investigation, 1987, riprap tests.

1990-02-01

298

Industrial ecology at Lawrence Livermore National Laboratory summary statement  

Energy Technology Data Exchange (ETDEWEB)

At Livermore our hope and our intention is to make important contributions to global sustainability by basing both our scientific and technological research and our business practices on the principles of industrial ecology. Current efforts in the following fields are documented: global security, global ecology, energy for transportation, fusion energy, materials sciences, environmental technology, and bioscience.

1996-06-04

299

Fabrication of a 275/sup 0/C geothermal temperature tool  

Energy Technology Data Exchange (ETDEWEB)

The fabrication of a Prototype 275/sup 0/C Geothermal Temperature Tool is reviewed. This tool fabrication uses hybrid circuits that were developed at Sandia National Laboratories and are now being built at Teledyne Philbrick. To achieve high-temperature operation, the standard military specification hybrid technology was modified in fabrication processes and materials.

1981-01-01

300

Annotated bibliography of Accelerator Technology Division research and development, 1978-1985  

International Nuclear Information System (INIS)

A bibliography is presented of unclassified published and in-house technical material written by members of the Accelerator Technology Division, Los Alamos National Laboratory, since its inception in January, 1978. The author and subject concordances in this report provide cross-reference to detailed citations kept in a computer database and a microfilm file of the documents. The citations include an abstract and other notes, and can be searched for key words and phrases.

301

Effect of chloride concentration and pH on pitting corrosion of waste package container materials  

Energy Technology Data Exchange (ETDEWEB)

Electrochemical cyclic potentiodynamic polarization experiments were performed on several candidate waste package container materials to evaluate their susceptibility to pitting corrosion at 90 degrees C in aqueous environments relevant to the potential underground high-level nuclear waste repository. Results indicate that of all the materials tested, Alloy C-22 and Ti Grade-12 exhibited the maximum corrosion resistance, showing no pitting or observable corrosion in any environment tested. Efforts were also made to study the effect of chloride ion concentration and pH on the measured corrosion potential (Ecorr), critical pitting and protection potential values.

1996-12-01

302

Corrosion 2003. Conference papers on CD-ROM  

Energy Technology Data Exchange (ETDEWEB)

Papers are presented under 38 symposia. Subjects included reinforced concrete, protective coatings and linings, cathodic/anodic protection, chemical cleaning of boilers, managing corrosion with plastics, water treatment, HRSG boiler tube failure analysis, corrosion in oil and gas production, corrosion in petroleum refining and gas, processing, pipelines and tanks, high temperature materials, chemical process industry, aerospace equipment, materials technology developments for incinerators and waste fuel-fired processors, materials and corrosion in fossil-fuels conversion and combustion, corrosion in nuclear systems, marine corrosion, building systems, corrosion mechanisms, corrosion inhibitors and corrosion monitoring and measurement.

2003-07-01

303

Accelerated-aging tests for predicting radiation degradation of organic materials  

Energy Technology Data Exchange (ETDEWEB)

Long-term aging of organic materials in reactor containment buildings has become a major issue within the nuclear community. In this article, the status of radiation-aging qualification test requirements in several countries is reviewed, and problems with the current aging methodologies are described. These problems include dose-rate and synergistic effects and environmental synergisms, which have been found for many different polymeric materials. A number of approaches to improved accelerated-radiation-aging tests for prediction of long-term aging behavior are discussed together with their limitations.

1984-03-01

304

Accelerated-aging tests for predicting radiation degradation of organic materials  

International Nuclear Information System (INIS)

Long-term aging of organic materials in reactor containment buildings has become a major issue within the nuclear community. In this article, the status of radiation-aging qualification test requirements in several countries is reviewed, and problems with the current aging methodologies are described. These problems include dose-rate and synergistic effects and environmental synergisms, which have been found for many different polymeric materials. A number of approaches to improved accelerated-radiation-aging tests for prediction of long-term aging behavior are discussed together with their limitations.

1984-01-01

305

Uranium-233 waste definition: Disposal options, safeguards, criticality control, and arms control  

Energy Technology Data Exchange (ETDEWEB)

The US investigated the use of {sup 233}U for weapons, reactors, and other purposes from the 1950s into the 1970s. Based on the results of these investigations, it was decided not to use {sup 233}U on a large scale. Most of the {sup 233}U-containing materials were placed in long-term storage. At the end of the cold war, the US initiated, as part of its arms control policies, a disposition program for excess fissile materials. Other programs were accelerated for disposal of radioactive wastes placed in storage during the cold war. Last, potential safety issues were identified related to the storage of some {sup 233}U-containing materials. Because of these changes, significant activities associated with {sup 233}U-containing materials are expected. This report is one of a series of reports to provide the technical bases for future decisions on how to manage this material. A basis for ...

1998-07-07

306

LIFE Materials: Phase Formation and Transformations in Transmutation Fuel Materials for the LIFE Engine Part I - Path Forward Volume 3  

Energy Technology Data Exchange (ETDEWEB)

The current specifications of the LLNL fusion-fission hybrid proposal, namely LIFE, impose severe constraints on materials, and in particular on the nuclear fissile or fertile nuclear fuel and its immediate environment. This constitutes the focus of the present report with special emphasis on phase formation and phase transformations of the transmutation fuel and their consequences on particle and pebble thermal, chemical, and mechanical integrities. We first review the work that has been done in recent years to improve materials properties under the Gen-IV project, and with in particular applications to HTGR and MSR, and also under GNEP and AFCI in the USA. Our goal is to assess the nuclear fuel options that currently exist together with their issues. Among the options, it is worth mentioning TRISO, IMF, and molten salts. The later option will not be discussed in details since an ...

2008-12-19

307

BS in Ceramic and Materials Engineering at Clemson  

Science.gov (United States)

Description of courses, curriculum and degree program. "Ceramic and materials engineers design, develop, and participate in the manufacture of both standard and new materials intended for use in a wide variety of industries with diverse applications. These range from the semi-conductor to the aerospace and finally to the traditional ceramics industry. The broad scope of industrial responsibilities handled by ceramic and materials engineers requires knowledge in mathematics, science, engineering, and the social sciences, skills in problem solving, engineering analysis, design, and written and oral communication. The baccalaureate program integrates laboratory with classroom experiences to prepare students for life-long learning. Courses covering thermodynamics, kinetics, mechanical behavior, processing and characterization of materials prepare students for careers in industry and/or ...

2007-01-01

308

Advanced Industrial Materials (AIM) Program: Compilation of project summaries and significant accomplishments, FY 1995  

Energy Technology Data Exchange (ETDEWEB)

In many ways, the Advanced Industrial Materials (AIM) Program underwent a major transformation in Fiscal Year 1995 and these changes have continued to the present. When the Program was established in 1990 as the Advanced Industrial Concepts (AIC) Materials Program, the mission was to conduct applied research and development to bring materials and processing technologies from the knowledge derived from basic research to the maturity required for the end use sectors for commercialization. In 1995, the Office of Industrial Technologies (OIT) made radical changes in structure and procedures. All technology development was directed toward the seven ``Vision Industries`` that use about 80% of industrial energy and generated about 90% of industrial wastes. The mission of AIM has, therefore, changed to ``Support development and commercialization of new or improved materials to improve productivity, product ...

1996-04-01

309

Regulatory quality assurance requirements for the operation of nuclear R and D facilities in Korea  

International Nuclear Information System (INIS)

Full text: Korea Atomic Energy Research Institute (KAERI) has many R and D facilities in operation. including HANARO research reactor, radioactive waste treatment facility (RWTF), post-irradiation examination facility (PIEF) and irradiated material test facility (IMEF). Recently. nation-wide interest is focused on the safety and security of major industrial facilities. Safe operation of nuclear facilities is imperative because of the consequence of public disaster by radiological release/contamination, in case of an accident. Recently, Ministry of Science and Technology (MOST) of the Korean government announced amendments of Atomic Energy laws to enforce requirements of the physical protection and radiological emergency. All provisions on nuclear safety regulation and radiation protection are entrusted to the Atomic Energy Act(AEA). The Act is enacted as the main law concerning the safety regulation of ...

2006-10-15

310

Micromechanical characterization tools for highly-filled polymers  

Energy Technology Data Exchange (ETDEWEB)

We are attempting to characterize and model the micromechanical response of highly-filled polymers. In this class of materials, the continuous plastic binder used to bond the highly-filled material dominates the observed viscoelastic response. As a result, realistic lifetime analysis of these materials will require a thorough understanding of the contribution of the plastic binder. Laboratory applications of these materials include plastic bonded explosives, propellants, a variety of specialized filled organic materials for stockpile systems, and highly filled epoxy dielectric materials for the National Ignition Facility. We have explored numerous techniques to characterize the local microstructure of plastic bonded explosives. However, insufficient funding was obtained to bring these technologies to maturity, nevertheless our present tool ...

2000-02-16

311

Materials choices for the advanced LWR steam generators  

International Nuclear Information System (INIS)

Current light water reactor (LWR) steam generators have been affected by a variety of corrosion and mechanical damage degradation mechanisms. Included are wear caused by tube vibration, intergranular corrosion, pitting, and thinning or wastage of the steam generator tubing and accelerated corrosion of carbon steel supports (denting). The Electric Power Research Institute (EPRI) and the Steam Generator Owners Groups (I, II) have sponsored laboratory and field studies to provide ameliorative actions for the majority of the damage forms experienced to date. Some of the current corrosion mechanisms are aggravated or caused by unique materials choices or materials interactions. New materials have been proposed and at least partially qualified for use in replacement model steam generators, including an advanced LWR design. In so far as possible, the materials choices for the advanced LWR ...

1987-11-15

312

A constitutive model for layered wire mesh and aramid cloth fabric  

Energy Technology Data Exchange (ETDEWEB)

A new package for the air transport of hazardous materials is currently being developed in the Transportation Systems Department at Sandia National Laboratories. The baseline design has a unique impact limiter which uses layers of aluminum screen wire and aramid cloth fabric. A primary motivation for selecting this unusual combination of materials is the need for the impact limiter to not only limit the amount of load transmitted to the primary container but also remain in place during impact events so that it provides a thermal barrier during a subsequent fire. A series of uniaxial and confined compression tests indicated that the layered material does not behave like other well characterized materials. No existing constitutive models were able to satisfactorily capture the behavior of the layered material; thus, a new plasticity model was developed. The new ...

1993-09-01

313

Nuclear research institutes in NEA countries  

Energy Technology Data Exchange (ETDEWEB)

The paper is based on a NEA study entitled `Past Trends and Current State of Nuclear Research Institutes`, which has been published in 1996. The evolution of nuclear research institutes (NRIs) in NEA countries is described from their establishment in the early fifties to present. The objectives, missions, purposes, and competences of NRIs are highlighted. Further, the resources (budget, qualified manpower, equipment such as research reactors and laboratories) are analysed, emphasising the role of the government. Country specific examples are given to illustrate different aspects of the historic evolution, present status and trends of NRIs. It is expected that the future role of NRIs will reflect the progress in nuclear science and technology and the evolving requirements of the nuclear industry with regard to safety enhancement, fuel cycle optimisation, plant life time management ...

1996-12-31

314

Nuclear research institutes in NEA countries  

International Nuclear Information System (INIS)

The paper is based on a NEA study entitled 'Past Trends and Current State of Nuclear Research Institutes', which has been published in 1996. The evolution of nuclear research institutes (NRIs) in NEA countries is described from their establishment in the early fifties to present. The objectives, missions, purposes, and competences of NRIs are highlighted. Further, the resources (budget, qualified manpower, equipment such as research reactors and laboratories) are analysed, emphasising the role of the government. Country specific examples are given to illustrate different aspects of the historic evolution, present status and trends of NRIs. It is expected that the future role of NRIs will reflect the progress in nuclear science and technology and the evolving requirements of the nuclear industry with regard to safety enhancement, fuel cycle optimisation, plant life time management ...

1996-06-04

315

Vulnerability Analysis of Physical Protection System at Wolsung Nuclear Power Plant  

Energy Technology Data Exchange (ETDEWEB)

The 9/11 event in the U.S.A has increased international terror possibilities against nuclear facilities including nuclear power plants(NPPs). It is necessary to assess the performance of an existing physical protection system(PPS) at nuclear facilities based on such malevolent acts. A PPS is a complex configuration of detection, delay, and response elements. Several methods are available to analyze a PPS and evaluate its effectiveness. Sandia National Laboratory(SNL) in the USA was developed a System Analysis of Vulnerability to Intrusion (SAVI) computer code for this purpose. It is powerful software for evaluating the effectiveness of PPS against outsider threats. This study presents the performance assessment of the PPS at Wolsung NPP using SAVI code. First, the site-specific Adversary Sequence Diagrams(ASDs) of the PPS is constructed. It helps to understand the functions of the existing PPS composed ...

2006-07-01

316

Vulnerability Analysis of Physical Protection System at Wolsung Nuclear Power Plant  

International Nuclear Information System (INIS)

The 9/11 event in the U.S.A has increased international terror possibilities against nuclear facilities including nuclear power plants(NPPs). It is necessary to assess the performance of an existing physical protection system(PPS) at nuclear facilities based on such malevolent acts. A PPS is a complex configuration of detection, delay, and response elements. Several methods are available to analyze a PPS and evaluate its effectiveness. Sandia National Laboratory(SNL) in the USA was developed a System Analysis of Vulnerability to Intrusion (SAVI) computer code for this purpose. It is powerful software for evaluating the effectiveness of PPS against outsider threats. This study presents the performance assessment of the PPS at Wolsung NPP using SAVI code. First, the site-specific Adversary Sequence Diagrams(ASDs) of the PPS is constructed. It helps to understand the functions of the existing PPS composed ...

2006-05-25

317

Performance Assessment of Physical Protection System at Wolsong Nuclear Power Plant using SAVI code  

Energy Technology Data Exchange (ETDEWEB)

The 9/11 event in the U.S.A has increased international terror possibilities against nuclear facilities including nuclear power plants(NPPs). It is necessary to assess the performance of existing physical protection system(PPS) at nuclear facilities based on such malevolent acts. A PPS is a complex configuration of detection, delay, and response elements. Several techniques are available to analyze a PPS and evaluate its effectiveness. Sandia National Laboratory(SNL) in the USA was developed a System Analysis of Vulnerability to Intrusion (SAVI) computer code for this purpose. It is powerful software for evaluating the effectiveness of PPS against outsider threats. This study presents the performance assessment of the PPS at Wolsong NPP using SAVI code. The first is that the SAVI constructs the site-specific Adversary Sequence Diagram (ASD) of the PPS. This provides a methods of graphically representing ...

2005-07-01

318

New neutron simulation capabilities provided by the Sandia Pulse Reactor (SPR-III) and the Upgraded Annular Core Pulse Reactor (ACPR)  

Science.gov (United States)

The paper briefly describes the nuclear reactor facilities at Sandia Laboratories which are used for simulating nuclear weapon produced neutron environments. These reactor facilities are used principally in support of continuing R and D programs for the Department of Energy/Office of Military Application (DOE/OMA) in studying the effects of radiation on nuclear weapon systems and components. As such, the reactors are available to DOE and DOD agencies and their contractors responsible for the radiation hardening of advanced nuclear weapon systems. Emphasis is placed upon two new reactor simulation sources; the Sandia Pulse Reactor-III (SPR-III) Facility which enhances the neutron exposure volume capabilities over those presently available with the existing SPR-II Facility, and the Upgraded Annular Core Pulse Reactor (ACPR) Facility which enhances the neutron exposure capabilities ...

1978-07-01

319

A value message is worth a thousand words: Impact of management framework on public perceptions of nuclear waste  

International Nuclear Information System (INIS)

Until recent years, those involved in the design, operation and regulation of nuclear power systems devoted more resources to forward movement than to the back end of the fuel cycle. Now, though, concerted thought and international cooperation have been devoted to the question of nuclear waste management. The expert consensus is that sufficient knowledge exists to make e.g. disposal decisions with an acceptable level of confidence. In the first phases of research, decision processes were adapted to the tasks at hand. However, at some point in each nuclearized country, there came a time when waste management implied finding repository sites. At that time management abruptly entered the social sphere - where unfortunate experience has shown time and time again that classical decision processes are not adapted to facilitating societal acceptance of management solutions. This paper recounts the various management frameworks ...

1999-12-01

320

Proceedings of the 2. international conference on accelerator-driven transmutation technologies and applications  

International Nuclear Information System (INIS)

Technical developments in the construction of high power accelerators have created new research activities on accelerator-driven transmutation technologies (ADTT) with main applications for energy production and nuclear waste transmutation. The on-going research was reported and discussed at the conference. The studies of energy production based on ADTT indicate possible important advantages compared to the present nuclear power reactors. Natural Uranium or Thorium is burned in a subcritical reactor with or without simultaneous incineration and transmutation of nuclear waste. High level radioactive wastes and weapons Plutonium constitute an environmental and proliferation problem. Studies were reported on the possibilities to use ADTT to considerably shorten the life-time and reduce the amount of long-lived radioactive waste in order to decrease the volumes needed for long-term geologic deposition. A panel discussed the ...

1996-06-03

321

Establishment of Database Program for In-service Test Management in Nuclear Power Plants  

International Nuclear Information System (INIS)

In-service Test (IST) of the nuclear power plant is very important to maintain the safety of the plants. The safety features of nuclear power plant are based on the operation of pumps and valves. Therefore, it is an essential basis for the safety of nuclear power plant to keep operational readiness of pumps and valves. Because of the importance of the IST, most of nuclear power plants should designate the IST department and personnel. Because the nuclear power plants of Korea have several types and the designs and operations are different from each other, the methods and experiences are various for the management of the IST program. However, there are no medium to communicate with each other and exchange the tips and information about IST program and education and discussion would be required to apply a consistent code. The nature of the IST Standardization Management Data Base ...

2010-10-01

322

A critical survey of experimental cross section data, comparison with nuclear model calculations and estimation of production yields of "7"7Br and "7"7Kr in no-carrier-added form via various nuclear processes  

International Nuclear Information System (INIS)

Experimentally investigated nuclear reactions for production of no-carrier-added "7"7Br and "7"7Kr were critically surveyed. The survey covered nine reactions for the formation of "7"7Br and six reactions for "7"7Kr. Both radionuclides are simultaneously produced in many of the studied nuclear processes. The experimental data were compared with the results of nuclear model calculations based on the computer code ALICE-IPPE and the third version of TALYS-based Evaluated Nuclear Data Library, TENDL-2010. Good agreement was found over extended energy regions for the p-, "3He- and #alpha#-particle induced reactions on several target materials. In case of d-induced reactions, however, considerable discrepancies were noted between the experimental and theoretical data. The concordant sets of experimental cross section data for each reaction were fitted by a polynomial function to obtain a ...

2011-05-15

323

Synchrotron SAXS Studies of Nanostructured Materials and Colloidal Solutions: A Review  

Scientific Electronic Library Online (English)

Abstract in english Structural characterisations using the SAXS technique in a number of nanoheterogeneous materials and liquid solutions are reviewed. The studied systems are protein (lysozyme)/water solutions, colloidal ZnO particles/water sols, nanoporous NiO-based xerogels, hybrid organic-inorganic siloxane-PEG and PPG nanocomposites and PbTe semiconductor nanocrystals embedded in a glass matrix. These investigations also focus on the transformations of time-varying structures and on str (more) uctural changes related to variations in temperature and composition. The reviewed investigations aim at explaining the unusual and often interesting properties of nanostructured materials and solutions. Most of the reported studies were carried out using the SAXS beamline at the National Synchrotron Light Laboratory (LNLS), Campinas, Brazil.

2002-03-01

324

Advanced power conversion based on the Aerocapacitor{trademark}  

Science.gov (United States)

The authors report here, for the first time, high frequency testing of a new type of electrochemical double layer capacitor (EDLC), based on carbon aerogels: the Aerocapacitor. Carbon aerogels, are a novel type of carbon foam developed by Lawrence Livermore National Laboratory for military applications. The unique properties of carbon aerogels, high surface area (700 m{sup 2}/g), high density (1g/cc), well controlled pore diameter and high material conductivity (25 S/cm) made it an ideal EDLC electrode material. Using carbon aerogel as the electrode material, the authors have developed Aerocapacitors. These new EDLC`s have a frequency response comparable to that of aluminum electrolytic capacitors and are thus ideally suited to power conversion applications.

1997-10-01

325

Status of PACTEL facility  

Energy Technology Data Exchange (ETDEWEB)

Since 1976, the Nuclear Engineering Laboratory of the Technical Research Centre of Finland and Lappeenranta University of Technology have cooperated in the field of nuclear reactor thermal-hydraulics. During these years, a series of experimental facilities (REWET-I, -II, -III, VEERA) simulating pressurized water reactors (PWRs) have been built. The newest facility, PACTEL (Parallel Channel Test Loop), is an experimental out-of-pile facility designed to simulate the major components and system behaviour of a commercial PWR during postulated small and medium size break loss-of-coolant accidents (LOCAs), natural circulation and operational transients. A PACTEL natural circulation experiment has been carried out as an OECD/NEA international standard problem ISP 33. (2 refs., 3 figs., 2 tabs.).

1993-12-31

326

Science & Technology Review July/August 2005  

Energy Technology Data Exchange (ETDEWEB)

This journal contains the following articles (1) The Grand Challenge of Thermonuclear Ignition--Commentary by Edward I. Moses; (2) Orchestrating the World's Most Powerful Laser--The computer control system for the National Ignition Facility will soon have about 1.4-million lines of code running on more than 750 computers; (3) A Randon Walk through Time and Space--Albert einstein's 1905 papers on Brownian motion, random fluctuations, and statistical mechanics are fundamental to many Livermore research projects; (4) The Search for Methane in Earth's Mantle--Scientists are discovering that Earth's mantle may have untapped reserves of methane; and (5) Testing the Physics of Nuclear Isomers--Results from a tri-laboratory project contradict claims of accelerated release of energy from the nuclear isomer hafnium-178.

2005-06-14

327

Reliability analysis of stiff versus flexible piping. Status report  

Energy Technology Data Exchange (ETDEWEB)

Conservative design procedures adopted for nuclear piping systems usually result in stiff piping designs that use excessive support devices such as rigid supports and snubbers. Use of these piping support devices has created safety concerns. This report describes the interim result for a piping research project conducted at Lawrence Livermore National Laboratory (LLNL) for the US Nuclear Regulatory Commission (NRC). The overall objective of this research project is to develop modified design requirements and criteria which will improve piping reliability and minimize the use of pipe supports, snubbers, and pipe whip restraints. The current study was conducted to establish the necessary groundwork for this work based on the piping reliability analysis.

1984-04-01

328

Quality control and evaluation for environmental radiological baseline study of Guangdong Daya Bay nuclear power station  

International Nuclear Information System (INIS)

The main points of quality control methods and technique of environmental radiological baseline study of Guangdong Daya Bay Nuclear Power Station are reported. Results of intercalibration of international and inland laboratories are given. The random chosen samples are checked and compared with two measurement methods. The data obtained in Daya Bay environment are put to the correlation statistics test using the linear regression analysis method between the correlative items such as "4"0K activity by gamma spectrum measurement and potassium content by chemical analysis, total #alpha#(#beta#) activity and nuclide content, as well as environmental gamma radiation dose rate and TLD accumulation dose. The data of Daya Bay environmental radioactivity baseline level show good concordance and reliability.

329

Positive safety features of US nuclear reactors: technical lessons confirmed at Chernobyl. Hearing before the Subcommittee on Energy Research and Production of the Committee on Science and Technology, US House of Representatives, Ninety-Ninth Congress, Second Session, May 14, 1986, No. 138  

Science.gov (United States)

Dr. Rudolf Schulten of West Germany and expert witnesses from national laboratories, utilities, and the nuclear industry testified on reactor safety issues as they relate to the Chernobyl accident and public concern that modern technology has not paid enough attention to public safety. Each of the witnesses contributed safety-related information based on what has been learned from the Soviet incident. Particular focus went to similarities and differences between the Chernobyl and US reactors in safety design and engineering and to the environmental effects of the accident. The N reactor near Richland and a commercial reactor at Fort St. Vrain, Colorado are the only two operating graphite reactors, but neither is a boiling water reactor.

1986-01-01

330

Positive safety features of US nuclear reactors: technical lessons confirmed at Chernobyl. Hearing before the Subcommittee on Energy Research and Production of the Committee on Science and Technology, US House of Representatives, Ninety-Ninth Congress, Second Session, May 14, 1986, No. 138  

International Nuclear Information System (INIS)

Dr. Rudolf Schulten of West Germany and expert witnesses from national laboratories, utilities, and the nuclear industry testified on reactor safety issues as they relate to the Chernobyl accident and public concern that modern technology has not paid enough attention to public safety. Each of the witnesses contributed safety-related information based on what has been learned from the Soviet incident. Particular focus went to similarities and differences between the Chernobyl and US reactors in safety design and engineering and to the environmental effects of the accident. The N reactor near Richland and a commercial reactor at Fort St. Vrain, Colorado are the only two operating graphite reactors, but neither is a boiling water reactor.

331

Operable Unit 3-13, Group 3, Other Surface Soils Remediation Sets 4-6 (Phase II) Waste Management Plan  

Energy Technology Data Exchange (ETDEWEB)

This Waste Management Plan describes waste management and waste minimization activities for Group 3, Other Surface Soils Remediation Sets 4-6 (Phase II) at the Idaho Nuclear Technology and Engineering Center located within the Idaho National Laboratory. The waste management activities described in this plan support the selected response action presented in the Final Record of Decision for Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. This plan identifies the waste streams that will be generated during implementation of the remedial action and presents plans for waste minimization, waste management strategies, and waste disposition.

2006-07-01

332

Class 1E digital systems studies  

International Nuclear Information System (INIS)

This document is furnished as part of the effort to develop NRC Class 1E Digital Computer Systems Guidelines which is Task 8 of USAF Rome Laboratories Contract F30602-89-D-0100. The report addresses four major topics, namely, computer programming languages, software design and development, software testing and fault tolerance and fault avoidance. The topics are intended as stepping stones leading to a Draft Regulatory Guide document. As part of this task a small scale survey of software fault avoidance and fault tolerance practices was conducted among vendors of nuclear safety related systems and among agencies that develop software for other applications demanding very high reliability. The findings of the present report are in part based on the survey and in part on review of software literature relating to nuclear and other critical installations, as well as on the authors' experience in these areas.

333

Assurance and assessment techniques for nuclear weapon related software  

Energy Technology Data Exchange (ETDEWEB)

Sandia National Laboratories has the qualification evaluation responsibility for the design of certain components intended for use in nuclear weapons. Specific techniques in assurance and assessment have been developed to provide the quality evidence that the software has been properly qualified for use. Qualification Evaluation is a process for assessing the suitability of either a process used to develop or manufacture the product, or the product itself The qualification process uses a team approach to evaluating a product or process, chaired by a Quality Assurance professional, with other members representing the design organization, the systems organization, and the production agency. Suitable for use implies that adequate and appropriate definition and documentation has been produced and formally released, adequate verification and validation activities have taken place to ensure proper operation, and the software product meets all ...

1993-12-31

334

Systems Analysis of Safeguards Effectiveness in a Uranium Conversion Facility  

Energy Technology Data Exchange (ETDEWEB)

The U.S. Department of Energy (DOE) is interested in developing tools and methods for potential U.S. use in designing and evaluating safeguards systems. For this goal several DOE National Laboratories are defining the characteristics of typical facilities of several size scales, and the safeguards measures and instrumentation that could be applied. Lawrence Livermore National Laboratory is providing systems modeling and analysis of facility and safeguards operations, diversion path generation, and safeguards system effectiveness. The constituent elements of diversion scenarios are structured using directed graphs (digraphs) and fault trees. Safeguards indicator probabilities are based on sampling statistics and/or measurement accuracies. Scenarios are ranked based on value and quantity of material removed and the estimated probability of non-detection. Significant scenarios, especially those involving timeliness or randomly ...

2004-06-16

335

US Department of Energy Nuclear Energy University program in robotics for advanced reactors: Program plan, FY 1987-1991  

International Nuclear Information System (INIS)

The US Department of Energy has provided support to four universities and the Oak Ridge National Laboratory in order to pursue research leading to the development and deployment of an advanced robotic system capable of performing tasks that are hazardous to humans, that generate significant occupational radiation exposure, and/or whose execution times can be reduced if performed by an automated system. The goal is to develop a generation of advanced robotic systems capable of performing surveillance, maintenance, and repair tasks in nuclear facilities and other hazardous environments. This goal will be achieved through a team effort among the Universities of Florida, Michigan, Tennessee, Texas, and the Oak Ridge National Laboratory, and their industrial partners, Combustion Engineering, Martin Marietta Baltimore Aerospace, Odetics, Remotec, and Telerobotics International. Each of the universities and ORNL have ongoing ...

336

Tokamak and laboratory modeling of hydrocarbon film deposition on metallic mirrors  

International Nuclear Information System (INIS)

In this work, amorphous hydrocarbon (a-C:H) film deposition on metallic mirrors was studied during working shots in tokamak T-10 and at exposure in Ar/CHD3/D2 dc magnetron discharge in a special laboratory high vacuum setup. Analysis of film composition (including hydrogen content) was carried out using nuclear physical methods. Thickness and optical parameters (refractive and extinction coefficients) of the films were estimated by ellipsometry. Laboratory films can be characterized as soft a-C:H films in comparison with hard tokamak films (? = 1.2 and 1.8 g/cm3, respectively). For the first one, a linear dependence of deposition rate on mirror temperature was observed in a wide temperature range. The addition of methane into initial Ar/D2 magnetron gas mixture leads to an increase of deposition rate. The data obtained should be taken into account to prevent hydrocarbon film formation on the surface of first mirrors in ...

2009-06-15

337

The Los Alamos National Laboratory Environmental Restoration Program  

Energy Technology Data Exchange (ETDEWEB)

The LANL Environmental Restoration (ER) Program Office, established in October 1989, is faced with the challenge of assessing and cleaning up nearly 1,8000 potentially hazardous waste sites according to an aggressive corrective action schedule that the Environmental Protection Agency (EPA) mandated on May 23, 1990, in a Resource, Conservation, and Recovery Act (RCRA) Part B Permit. To maximize program efficiency, the ER Program Office will implement a unique management approach designed to maximize the use of laboratory technical expertise. The Installation Work Plan, which provides a blueprint for the program, has been submitted to EPA for review and approval. A work plan for characterization of Technical Area 21, an early plutonium processing facility, is also nearing completion. The feasibility of an expedited cleanup of the Laboratory's worst hazardous waste release has been modelled using a computer code originally developed by ...

1990-01-01

338

Uncertainties of radionuclide migration parameter values obtained from in-situ tracer experiments  

International Nuclear Information System (INIS)

One of the key issues in safety assessment of high-level nuclear waste disposal is evaluating the effects of uncertainty inherent in radionuclide migration parameter values. In this paper, radionuclide transport parameter values and error variances (uncertainties) from in-situ tracer experiments, carried out in a single fracture at the Aespoe Hard Rock Laboratory (HRL) in Sweden, are identified by solving the inverse problem in a framework of the maximum likelihood theory. From the results, it is found that the parameter value uncertainty caused by a conceptual model of radionuclide migration is greater than that caused by a fluctuation in the observed breakthrough curve data. (author)

2005-10-03

339

Neon-20 depth-dose relations in water  

Energy Technology Data Exchange (ETDEWEB)

The dose from heavy ion beams has been calculated using a one-dimensional transport theory and evaluated for 670 MeV/amu /sup 20/Ne beams in water. The result is presented so as to be applicable to arbitrary ions for which the necessary interaction data are known. The present evaluation is based on the Silberberg-Tsao fragmentation parameters augmented with light fragment production from intranuclear cascades, recently calculated nuclear absorption cross sections, and evaluated stopping power data. Comparison with recent experimental data obtained at the Lawrence Berkeley Laboratory reveals the need for more accurate fragmentation data.

1984-05-01

340

Los Alamos DP West Plutonium Facility decontamination project  

Energy Technology Data Exchange (ETDEWEB)

The DP West Plutonium Facility operated by the Los Alamos National Laboratory, Los Alamos, New Mexico, was decontaminated between April 1978 and April 1981. The facility was constructed in 1944 to 1945 to produce plutonium metal and fabricate parts for nuclear weapons. It was continually used as a plutonium processing and research facility until mid-1978. Decontamination operations included dismantling and removing gloveboxes and conveyor tunnels; removing process systems, utilities, and exhaust ducts; and decontaminating all remaining surfaces. This report describes glovebox and conveyor tunnel separations, decontamination techniques, health and safety considerations, waste management procedures, and costs of the operation.

1982-01-01

341

Full-length fuel rod behavior under severe accident conditions  

Energy Technology Data Exchange (ETDEWEB)

This document presents an assessment of the severe accident phenomena observed from four Full-Length High-Temperature (FLHT) tests that were performed by the Pacific Northwest Laboratory (PNL) in the National Research Universal (NRU) reactor at Chalk River, Ontario, Canada. These tests were conducted for the US Nuclear Regulatory Commission (NRC) as part of the Severe Accident Research Program. The objectives of the test were to simulate conditions and provide information on the behavior of full-length fuel rods during hypothetical, small-break, loss-of-coolant severe accidents, in commercial light water reactors.

1992-12-01

342

A dependence of cumulative pion production cross sections in proton-nuclear interactions at high energies  

International Nuclear Information System (INIS)

The A dependence of cumulative pion production yield cross sections on the basis of the comparison of the data on relative pion yields on Be,C,Al,Ti,Mo and W nuclei at the 159 deg angle laboratory system for the incident proton energy E_0 from 25 to 62 GeV is considered. The regular A dependence on cumulative variable X is noted. The results are compared with the data at E_0< 10 GeV. A possible interpretation of the observed behaviour on the basis of the hypothesis of the flucton mechanism of the pion production in the cumulative region is discussed. 15 refs.; 4 figs.

343

Oak Ridge National Laboratory Core Competencies  

Energy Technology Data Exchange (ETDEWEB)

A core competency is a distinguishing integration of capabilities which enables an organization to deliver mission results. Core competencies represent the collective learning of an organization and provide the capacity to perform present and future missions. Core competencies are distinguishing characteristics which offer comparative advantage and are difficult to reproduce. They exhibit customer focus, mission relevance, and vertical integration from research through applications. They are demonstrable by metrics such as level of investment, uniqueness of facilities and expertise, and national impact. The Oak Ridge National Laboratory (ORNL) has identified four core competencies which satisfy the above criteria. Each core competency represents an annual investment of at least $100M and is characterized by an integration of Laboratory technical foundations in physical, chemical, and materials sciences; biological, ...

1994-12-01

344

Phase Formation and Transformations in Transmutation Fuel Materials for the LIFE Engine Part I - Path Forward  

Energy Technology Data Exchange (ETDEWEB)

The current specifications of the LLNL fusion-fission hybrid proposal, namely LIFE, impose severe constraints on materials, and in particular on the nuclear fissile or fertile nuclear fuel and its immediate environment. This constitutes the focus of the present report with special emphasis on phase formation and phase transformations of the transmutation fuel and their consequences on particle and pebble thermal, chemical and mechanical integrities. We first review the work that has been done in recent years to improve materials properties under the Gen-IV project, and with in particular applications to HTGR and MSR, and also under GNEP and AFCI in the USA. Our goal is to assess the nuclear fuel options that currently exist together with their issues. Among the options, it is worth mentioning TRISO, IMF, and molten salts. The later option will not be discussed in details since an ...

2008-11-10

345

Quality-control materials in the USDA National Food and Nutrient Analysis Program (NFNAP)  

British Library Electronic Table of Contents (United Kingdom)

The US Department of Agriculture (USDA) Nutrient Data Laboratory (NDL) develops and maintains the USDA National Nutrient Databank System (NDBS). Data are released from the NDBS for scientific and public use through the USDA National Nutrient Database for Standard Reference (SR) ( http://www.ars.usda.gov/ba/bhnrc/ndl ). In 1997 the NDL initiated the National Food and Nutrient Analysis Program (NFNAP) to update and expand its food-composition data. The program included: 1) nationwide probability-based sampling of foods; 2) central processing and archiving of food samples; 3) analysis of food components at commercial, government, and university laboratories; 4) incorporation of new analytical data into the NDBS; and 5) dissemination of these data to the scientific community. A key feature and...

2006-01-01

346

Photovoltaics: Contract lists, fiscal year 1992  

Energy Technology Data Exchange (ETDEWEB)

US DOE`s Photovoltaics Program has helped photovoltaic technologies evolve from materials and concepts in laboratories to competitive products rolling off automated assembly lines. The program is working to expand industrial capacity while continuing basic and applied technology R and D. This document is a tabulation of photovoltaics R and D that were begun, continued, or completed during this period. National laboratories or industrial, academic, and nonprofit research institutions perform the RR and D activities. The document is organized first by directing organization, then by project title and individual task. Each listing provides the name of contractor, period of performance, funding, objectives, accoplishments, and FY 1993 milestones. An index of contractors is included. (DLC)

1993-03-01

347

Effect of material aging on parachute pack life: a synopsis of Sandia National Laboratories studies  

Energy Technology Data Exchange (ETDEWEB)

A systematic study of the effects of environmental factors on nylon 66 and Kevlar 29 strength degradation in parachute components is being conducted at Sandia National Laboratories. It includes: (1) accelerated aging studies in air, inert environments, humidity, ozone, and smog; (2) a 25-year surveillance program of parachutes in a variety of natural climatic environments; (3) moisture absorption as a function of humidity; (4) effects of surface coatings normally applied to parachutes; and (5) development of nondestructive evaluation techniques which can be used to map mechanical properties over the entire parachute surface. The accelerated aging and moisture absorption studies show that air, humidity, and smog contribute to degradation. Chemiluminescence, gas chromatographic pyrograms, and uv spectroscopy show promise as nondestructive evaluation techniques.

1984-01-01

348

Contingency plan for the Lawrence Livermore National Laboratory's hazardous-waste operations  

Energy Technology Data Exchange (ETDEWEB)

The Lawrence Livermore National Laboratory (LLNL) has the necessary equipment and trained personnel to respond to a large number of hazardous material spills and fires or other emergencies resulting from these spills including injured personnel. This response capability is further expanded by the agreements that LLNL has with a number of outside response agencies. The Hazards Control Department at LLNL functions as the central point for coordinating the response of the equipment and personnel. Emergencies involving hazardous waste are also coordinated through the Hazards Control Department, but the equipment and personnel in the Toxic Waste Control Group would be activated for large volume waste pumpouts. Descriptions of response equipment, hazardous waste locations communication systems, and procedures for personnel involved in the emergency are provided.

1981-03-20

349

Asphalt emulsion sealing of uranium mill tailings. 1980 annual report  

International Nuclear Information System (INIS)

Studies of asphalt emulsion sealants conducted by the Pacific Northwest Laboratory have demonstrated that the sealants are effective in containing radon and other potentially hazardous material within uranium tailings. The laboratory and field studies have further demonstrated that radon exhalation from uranium tailings piles can be reduced by greater than 99% to near background levels. Field tests at the tailings pile in Grand Junction, Colorado, confirmed that an 8-cm admix seal containing 22 wt% asphalt could be effectively applied with a cold-mix paver. Other techniques were successfully tested, including a soil stabilizer and a hot, rubberized asphalt seal that was applied with a distributor truck. After the seals were applied and compacted, overburden was applied over the seal to protect the seal from ultraviolet degradation.

350

SSAC at Your Service: Promoting Co-operation Between IAEA and Finnish SSAC for Safeguards Implementation (Within the EU)  

International Nuclear Information System (INIS)

As the nuclear world is changing, the non-proliferation and safeguard systems have to change along the global development. Nuclear security as well as safety must be involved in all phases. Thus, modernization of thinking is a must. State system of accounting for and control of nuclear material (SSAC) is a basis, but now it is time to move ahead. Safeguards is not any more only to verify the declared nuclear materials but it is to inform the international safeguards society transparently but confidentially about the nuclear fuel cycle related activities and trade, and to confirm that there are no undeclared activities related to the nuclear fuel cycle in the states. Only strong SSAC with enhanced capabilities, activities and rights can meet the demand. The proliferation of nuclear weapons is a threat ...

2010-11-01

351

Integrated design environment for human performance and human reliability analysis  

Energy Technology Data Exchange (ETDEWEB)

Work over the last few years at the Idaho National Engineering and Environmental Laboratory (INEEL) has included a major focus on applying human performance and human reliability knowledge and methods as an integral element of system design and development. This work has been pursued in programs in a wide variety of technical domains, beginning with nuclear power plant operations. Since the mid-1980`s the laboratory has transferred the methods and tools developed in the nuclear domain to military weapons systems and aircraft, offshore oil and shipping operations, and commercial aviation operations and aircraft design. Through these diverse applications the laboratory has developed an integrated approach and framework for application of human performance analysis, human reliability analysis (HRA), operational data analysis, and simulation studies of human performance to the design ...

1997-05-01

352

University of Central Lancashire - Facilities  

Wastenet

...specialised laboratories for pharmaceutics, tissue culture and molecular biology Excellent Laboratory Facilities Tissue Culture Facilities Molecular Biology Laboratory ...

353

The upgrade of nuclear material accounting system at KAERI  

International Nuclear Information System (INIS)

The agreement between the government of Republic Of Korea (ROK) and the IAEA for the application of safeguards was signed and entered into force in 1975. The Additional Protocol (AP) to the Safeguards Agreement between the ROK and the IAEA was signed in 1999 and entered into force on 19 February 2004. Also, Implementation of Integrated Safeguards (IS) was started on 1 July, 2008 after a draw of the broader conclusion. The IAEA provides 2 hours notification for Random Interim Inspection (RII) under IS. For RII, the facility has to prepare the inspection documents in a short time. Therefore, KAERI (Korea Atomic Energy Research Institute) developed a new computerized nuclear material accounting system named KASIS (KAERI Safeguards Information treatment System) to treat the data by on-line for RII. For the efficient IS implementation, KAERI has a plan to upgrade the system to reflect the accounting approaches or reporting procedure according to ...

2010-10-01

354

Overview of the FRG waste package materials corrosion test program  

International Nuclear Information System (INIS)

Presently in the FRG there are essentially three institutions involved in corrosion experiments related to high level waste package materials, namely KfK-INE, Nukem and Bayer Leverkusen. In 1981 KfK-INE started a corrosion test program aiming at the selection of suitable canister materials for vitrified high level waste. The program encompassed electrochemical investigations, which were concluded in 1984. Moreover field corrosion tests and laboratory experiments were initiated, and are still ongoing. Several possible canister materials such as mild steel, Ti-Pd-alloy, Hastelloy C4 and others were investigated under the influence of varying parameters such as temperature, and radiation. Both Nukem Company and DWK were assigned the responsibility to conceive and develop a cask for the direct final disposal of spent fuel assemblies. Two solution turned out as most promising for corrosion protection of ...

1988-03-08

355

Activation of Polymethyl-Methacrylate by Proton Beam  

International Nuclear Information System (INIS)

Activation has been used for many kinds of useful applications, such as use of the radioisotopes for diagnosis and treatment of cancer, and wear (or corrosion) investigation for using thin layer activation (TLA) technique, etc. But activation also has severe problems for the post-processing of the samples; such as time-loss, inconvenience of sample handling, personal radiation safety, etc. For in-vitro experiments, we observed death of tumor cells by proton irradiation. The use of large activated container material can cause erroneous results in this case. To solve these problems, we studied why the samples were activated and how the level of the activation could be reduced. In proton beam irradiation experiments, the target materials could be defined as the container and sample itself. We could easily reduce activation of container material comparing to activation of sample itself. Therefore, we tried to find less ...

2010-10-01

356

State and prospects of the experimental and stand base for fundamental investigations of the RF Ministry for Atomic Energy  

International Nuclear Information System (INIS)

The aim of the report is to describe the state and prospects of the experimental and stand base (ESB) for fundamental investigations in the RF Ministry for Atomic Energy. The ESB includes the following scientific directions: high energy physics, nuclear physics, solid state physics (including superconductivity), plasma physics and controlled thermonuclear synthesis, nuclear reactors and reactor materials testing, lasers, energy conversion and others. Main economical, scientific and technical data on the ESB as a whole and on its most large scientific centers are presented

2003-06-03

357

Replacement of bearing journals on heat transport pumps at the Wolsung nuclear generating station  

International Nuclear Information System (INIS)

The major details of the inspection and replacement of the bearing journals on each of the four heat transport pumps (HTPs) at Wolsung nuclear generating station in Korea are presented in this paper. Investigation following fracture of one of the journals in 1985 revealed that it was excessively hard. The journal material (ASTM A296 CA 40) is considered to be prone to stress corrosion fatigue if the hardness exceeds Rc 40. In 1986 May, during a planned outage, the HTPs were disassembled, the journals were inspected, found to be excessively hard, and all were replaced. At the same time, the pump to motor couplings were all refurbished to ensure proper alignment.

1987-11-22

358

Passive dosimetry of radon and its daughters using solid state nuclear track detectors (SSNTDs)  

Energy Technology Data Exchange (ETDEWEB)

Indoor radon is a potential health hazard for the general public, especially in buildings with poor ventilation. A variety of dosemeters have been developed and used in surveys of radon concentration measurements. In this article the passive dosemeters which are based on solid state nuclear track detectors are reviewed. The principle of passive dosimetry and the factors affecting their performance are discussed. The characteristics of SSNTD materials in relation to their behaviour under different environmental conditions are tabulated and discussed. Results of radon surveys from selected studies are also presented. (Author).

1993-01-01

359

Nuclear fuel behavior at an atomic scale: the contributions of the ab initio calculations and the synchrotron radiation; Comportement du combustible nucleaire a l'echelle atomique: les apports des calculs ab initio et du rayonnement synchrotron  

Energy Technology Data Exchange (ETDEWEB)

This paper presents fundamental researches based on the electronic structure calculations and X absorption spectroscopy, allowing the knowledge on nuclear fuels at an atomic scale. They bring a better understanding of these material behavior to accurate the macroscopic simulation. The calculation methods, the experimental techniques of validation and the ab initio calculations results are detailed. (A.L.B.)

2000-07-01

360

Evaluation of aged concrete structures for continued service in nuclear power plants  

International Nuclear Information System (INIS)

Results are summarized of a study on concrete component aging and its significance relative to continued service of nuclear power plants (NPPs) beyond the initial period for which they were granted operating licenses. Progress is presented of a second study being conducted to identify and provide acceptance criteria for structural safety issues which the USNRC staff will need to address when applications are submitted for continued service of NPPs. Major activities under this program include: development of a materials property data base, establishment of structural component assessment and repair procedures, and development of a methodology for determination of structural reliability. 19 refs., 5 figs., 3 tabs.

1988-10-24

361

Behavior of the cooling towers as a function of the time  

International Nuclear Information System (INIS)

In the scope of the nuclear plants lifetime study, the behavior of the cooling towers is discussed. The main geometrical characteristics of the cooling towers in the French nuclear power plants, are presented. The surveyance program, the risks of accident, the research and development actions are considered. The results of the investigations of the cooling tower structure show that it is a multidiciplinary problem and needs the development of experimental and theoretical methods. Concerning the regenerators, the surveyance actions under operating conditions, the accelerated aging tests, and some aspects of the mechanical resistance, are underlined. It is shown that mainly the creep tests will allow the lifetime estimation of the materials developed for the regenerators.

1988-12-01

365

Shielding options for the ITER conceptual design  

Energy Technology Data Exchange (ETDEWEB)

Several shield options were analyzed for the ITER conceptual design to minimize the nuclear responses in the toroidal field (TF) coils. The total nuclear heating in the physics phase and the insulator dose in the technology phase are the most critical parameters in the design process. The first shield option has type 316 stainless steel and water shielding material. Steel and water also serve as structural material and coolant, respectively. The second option is similar to the first except that borated water is used instead of ordinary water. The other two options include a small layer of lead or boron carbide (B{sub 4}C) at the back of the shield. The last three shield options were considered to reduce the nuclear heating in the toroidal field coils relative to the steel/water shield. An optimization process was performed taking into consideration the thermal-hydraulics and the ...

1989-10-01

366

Transmutation of nuclear waste. Transmutatie van kernafval; Statusrapport programma Recyclage van Actiniden en Splijtingsprodukten (RAS)  

Energy Technology Data Exchange (ETDEWEB)

The most important aim of the title program is to investigate the possibility to convert long-lived actinides and mobile fission products in short-lived and stable isotopes by means of nuclear transmutation and recycling. First, an overview is given of the present situation regarding fission material waste, the origin of such waste in light water reactors and the options for interim and ultimate storage. Next, attention is paid to the aim of the the RAS program, the working method and the results so far of national and international research on the transmutation of actinides and fission products. Speculative expectations for the future are briefly outlined. The report also contains four appendices with technical aspects of the title subject: the RAS program of ECN, chemical aspects of reprocessing fission material, transmutation in fission reactors and in accelerators. 12 figs., 7 tabs., 4 appendices, 57 refs.

1993-07-01

367

Road maps on research and development plans for water chemistry of nuclear power systems  

International Nuclear Information System (INIS)

Water chemistry of nuclear power plants has played an important role in reduction of personnel doses, structural materials and fuel integrity assurance, and reduction of radioactive wastes production. Further contributions are requested for advanced utilization of the LWR, advanced fuels and aging management of plants. Since water chemistry has an effect on all structure and materials immersed and at the same time affected by them, the optimum control not sticking to specific issues and covering the whole plant is required for these requests. Taking account of roles and activities of the industry, governmental institutes and academia, road maps on research and development plans for water chemistry were compiled into identified eleven items with targets and counter measures taken, such as common basic technologies, dose reduction, SCC mitigation, fuel cans corrosion/hydrogen absorption mitigation, condition based maintenance ...

2008-05-01

368

Process for preparing inorganic particulate adsorbent and process for treating nuclear reactor core-circulating water  

Energy Technology Data Exchange (ETDEWEB)

An inorganic particulate adsorbent of a titania-alumina is described for treating a superheated water containing radioactive materials such as cobalt ions, which is free from release of corrosive impruities, and which has a high adsorption capacity of radioactive materials and a high mechanical strength is prepared by hydrolyzing a titanium alkoxide and an aluminum alkoxide, thereby forming a hydrous titanium oxide and a hydrous aluminum oxide, respectively; precalcining the hydrous titanium oxide and aluminum oxide, mixing and molding the resulting titania and alumina into a particulate mixture thereof having a titania mole fraction of 0.2 to 0.9, and calcining the particulate mixture at 500/sup 0/-700/sup 0/C. This absorbent is effectively used in treat boiling water-type nuclear reactor core-circulating water to remove radioactive substances therefrom.

1981-08-04

369

National waste terminal storage program. Supplementary quality-assurance requirements  

International Nuclear Information System (INIS)

The basic Quality Assurance Program Requirements standard for the National Waste Terminal Storage Program has been developed primarily for nuclear reactors and other fairly well established nuclear facilities. In the case of waste isolation, however, there are many ongoing investigations for which quality assurance practices and requirements have not been well defined. This paper points out these problems which require supplementary requirements. Briefly these are: (1) the language barrier, that is geologists and scientists are not familiar with quality assurance (QA) terminology; (2) earth sciences deal with materials that cannot be characterized as easily as metals or other materials that are reasonably homogeneous; (3) development and control of mathematical models and associated computer programs; (4) research and development.

370

Increased capability of Strassy: the decision making aid for the inspection of nuclear materials; Prolongement des capacites de Strassy: systeme d`aide a la decision pour le controle des matieres nucleaires  

Energy Technology Data Exchange (ETDEWEB)

The paper describes the latest developments in STRASSY (Strategy Assistance System), the strategy assistance system for the inspection of nuclear materials. The user can now select the fuel cycle he wishes to investigate from an initial range of 19 facilities. An inspection interface has been developed to enable the details and dates of inspections to be modified. One of the special features of the application of STRASSY in international safeguards is the taking into account of timeliness of detection; certain aspects of the time manager algorithms are presented and analysed, including the guaranteed existence of a solution. The results of a study of diversion paths in a simplified cycle consisting of our facilities are presented. Finally, the modifications necessary to enable STRASSY to be used for a posterior analysis of inspection results are discussed. (authors). 7 refs., 3 figs.

1994-12-31

371

Behavior of Stress-Relaxation phenomena in Zr-1.1Nb-0.05Cu  

International Nuclear Information System (INIS)

Zirconium alloys have anisotropic mechanical properties depending on their physical orientations and are widely used as nuclear materials such as cladding tube material. An operation condition of the nuclear reactor requires a high creep resistance, because it is subjected to long period operations, high temperature and high pressure. Generally, it takes a few days or months to do the creep experiment, so it is difficult to get a data in short period. However, there is a way to predict a creep property by using the stress-relaxation in the short term. These studies realized the stress-relaxation through a compressive test of HANA-6 (Zr-1.1Nb-0.05Cu) alloy that was developed by KAERI (Korea Atomic Energy Research Institute), and then predicted the creep property

2010-10-01

372

An integrated high-performance beam optics-nuclear processes framework with hybrid transfer map-Monte Carlo particle transport and optimization  

International Nuclear Information System (INIS)

An integrated beam optics-nuclear processes framework is essential for accurate simulation of fragment separator beam dynamics. The code COSY INFINITY provides powerful differential algebraic methods for modeling and beam dynamics simulations in absence of beam-material interactions. However, these interactions are key for accurately simulating the dynamics of heavy ion fragmentation and fission. We have developed an extended version of the code that includes these interactions, and a set of new tools that allow efficient and accurate particle transport: by transfer map in vacuum and by Monte Carlo methods in materials. The new framework is presented, along with several examples from a preliminary layout of a fragment separator for a facility for rare isotope beams.

2010-12-01

373

Propagation of an alkaline wave with a short contact time through an argilite sample from the Meuse-Haute Marne underground laboratory; Propagation d'une onde alcaline a temps de contact court a travers un echantillon d'argilite de l'est  

Energy Technology Data Exchange (ETDEWEB)

In the framework of the feasibility study of radioactive waste disposal in deep geologic formations, a clay formation (named 'argilite de l'Est') has been selected in the Meuse-Haute Marne region (France) for the construction of an underground laboratory. The percolation of alkaline solutions through the argilite has been studied using column experiments with short residence times (30 min). These experiments simulate the leaching of a cement which could be used in the building materials of the laboratory. The alkaline solutions used are mono-cationic solutions of calcium, sodium and strontium. The behaviour of calcium is differentiated from the other cations. For all alkaline solutions (NaOH, Ca(OH){sub 2} or Sr(OH){sub 2}) chemical reactions consuming both hydroxide ions and their associated cations have been evidenced. These reactions are heterogenous reactions of surface adsorption by site ...

2001-07-01

374

Production of radiopharmaceuticals for positron emission tomography via laboratory robotics  

International Nuclear Information System (INIS)

The production of radiopharmaceuticals used in positron emission tomography (PET) can require large amounts of activity at the start of synthesis in order to yield sufficient labeled material for clinical studies. Several investigators have developed remote and automated systems for the routine production of PET radiopharmaceuticals in order to reduce radiation exposure to personnel. Such devices, however, suffer from limited flexibility and can be relatively complicated in design. These systems are also limited to the production of a single or a few closely related compounds. Furthermore, changes in chemistry would require considerable modifications in hardware and/or software in order to bring the device back into operation. To circumvent the above limitations associated with the remote production of PET radiopharmaceuticals, the authors have investigated the use of laboratory robotics as a flexible alternative to the synthesis of several ...

1987-11-15

375

Laboratory development of +- 600 kVdc pipe type cable systems  

Energy Technology Data Exchange (ETDEWEB)

In 1976, the US Department of Energy and New York State - ERDA granted a contract for the development of a +-600 kV dc underground transmission cable system looking to inevitable future requirements in the US for economic, high-capacity, long-distance underground transmission linking remote generating stations to metropolitan load centers. This project was comprehensive and dealt with three separate system components, i.e., cable, splice, and terminals. In each instance, for each component, development required an intensive R and D effort, focused on the following categories: insulating materials, model testing, design of full-scale prototype, manufacturer of prototype, and laboratory development testing. Insulating papers and oils were selected, and model studies performed, for both self-contained type and pipe type oil-filled cables. However, only the pipe cable design was finally designated for full-size cable manufacture and EHV ...

1982-07-01

376

Facility Effluent Monitoring Plan for Pacific Northwest National Laboratory Balance-of-Plant Facilities  

Energy Technology Data Exchange (ETDEWEB)

The Pacific Northwest National Laboratory (PNNL) operates a number of research and development (R and D) facilities for the Department of Energy on the Hanford Site. According to DOE Order 5400.1, a Facility Effluent Monitoring Plan is required for each site, facility, or process that uses, generates, releases, or manages significant pollutants or hazardous materials. Three of the R and D facilities: the 325, 331, and 3720 Buildings, are considered major emission points for radionuclide air sampling and thus individual Facility Effluent Monitoring Plans (FEMPs) have been developed for them. Because no definition of ''significant'' is provided in DOE Order 5400.1 or the accompanying regulatory guide DOE/EH-0173T, this FEMP was developed to describe monitoring requirements in the DOE-owned, PNNL-operated facilities that do not have individual FEMPs. The remainder of the DOE-owned, PNNL-operated facilities are ...

1999-04-02

377

Cleanup at Los Alamos National Laboratory - the challenges - 9493  

Energy Technology Data Exchange (ETDEWEB)

This paper provides an overview of environmental cleanup at the Los Alamos National Laboratory (LANL) and some of the unique aspects and challenges. Cleanup of the 65-year old Department of Energy Laboratory is being conducted under a RCRA Consent Order with the State of New Mexico. This agreement is one of the most recent cleanup agreements signed in the DOE complex and was based on lessons learned at other DOE sites. A number of attributes create unique challenges for LANL cleanup -- the proximity to the community and pueblos, the site's topography and geology, and the nature of LANL's on-going missions. This overview paper will set the stage for other papers in this session, including papers that present: Plans to retrieve buried waste at Material Disposal Area B, across the street from oen of Los Alamos' commercial districts and the local newspaper; Progress to date and joint plans with WIPP ...

2008-01-01

378

Assessment of degradation processes in corrosion resistant steels in nuclear power engineering  

International Nuclear Information System (INIS)

The possible corrosion damage is discussed of the CrNi and CrNiMo types steels used as structural materials in WWER type nuclear power plants. It includes point and slot corrosion, corrosion cracking and corrosion fatigue as well as corrosion denting. Also discussed are test procedures that simulate operating conditions and are used for assessing the properties of metallurgical products (sheets and tubes) used in nuclear power engineering. Briefly described is a system for testing the said products in an aqueous medium while keeping the test parameters in a narrow range for a long time. Under the defined temperature, pressure and corrosion medium composition, the test specimens in this system can mechanically be loaded, both statically and dynamically or a temperature gradient can be produced at the tube-tube plate joint. (Z.M.). 1 fig., 1 tab., 10 refs.

1987-12-01

379

Apparatus for in situ determination of burnup cooling time and fissile content of an irradiated nuclear fuel assembly in a fuel storage pond  

Energy Technology Data Exchange (ETDEWEB)

A detector head for in situ inspection of irradiated nuclear fuel assemblies submerged in a water-filled nuclear fuel storage pond. The detector head includes two parallel arms which extend from a housing and which are spaced apart so as to be positionable on opposite sides of a submerged fuel assembly. Each arm includes an ionization chamber and two fission chambers. One fission chamber in each arm is enclosed in a cadmium shield and the other fission chamber is unshielded. The ratio of the outputs of the shielded and unshielded fission chambers is used to determine the boron content of the pond water. Correcting for the boron content, the neutron flux and gamma ray intensity are then used to verify the declared exposure, cooling time and fissile material content of the irradiated fuel assembly.

1985-04-09

380

American National Standard ANSI/ANS-8.15-1983: Nuclear criticality control of special actinide elements  

Energy Technology Data Exchange (ETDEWEB)

The American National Standard, `Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors` ANSI/ANS-8.1- 1983 provides guidance for the nuclides [sup 233]U, [sup 235]U, and [sup 239]Pu These three nuclides are of primary interest in out-of-reactor criticality safety since they are the most commonly encountered in the vast majority of operations. However, some operations can involve nuclides other than `U, `U, and `Pu in sufficient quantities that their effect on criticality safety could be of concern. The American National Standard, `Nuclear Criticality Control of Special Actinide Elements` ANSI/ANS-8.`15-1983 (Ref 2), provides guidance for fifteen such nuclides.

1996-12-31

381

12th Symposium on Space Nuclear Power and Propulsion. Conference on Alternative Power from Space (APFS),Conference on Accelerator-Driven Transmutation Technologies and Applications (A-DTTA)  

International Nuclear Information System (INIS)

These proceedings represent papers presented at the 12th symposium on Space Nuclear Power and Propulsion held in Albuquerque, New Mexico. The symposium theme was ''commercialization and technology transfer''. The topics discussed include: wireless power transmission, solar power from space next generation spacecraft, space power electronics and power management, flight testing of components, manufacturing and processing of materials, nuclear propulsion, reactors and shielding and many others of interest to the scientific community representing industry, government and academic institutions. There were 163 papers presented at the conference and 60 have been abstracted for the Energy Science and Technology database.

1995-01-08

382

Law project adopted by the Senate and authorizing the ratification of the additional protocol to the agreement between France, the European atomic energy community and the international atomic energy agency relative to the application of warranties in France; Projet de loi adopte par le Senat autorisant la ratification du protocole additionnel a l'accord entre la France, la Communaute europeenne de l'energie atomique et l'Agence internationale de l'energie atomique relatif a l'application de garanties en Franc  

Energy Technology Data Exchange (ETDEWEB)

This project of law concerns an additional protocol to the agreement of warranties signed on September 22, 1998 between France, the European atomic energy community and the IAEA. This agreement concerns the declaration of all information relative to the R and D activities linked with the fuel cycle and involving the cooperation with a foreign country non endowed with nuclear weapons. These information include the trade and processing of nuclear and non-nuclear materials and equipments devoted to nuclear reactors (pressure vessels, fuel loading/unloading systems, control rods, force and zirconium tubes, primary coolant pumps, deuterium and heavy water, nuclear-grade graphite), to fuel reprocessing plants, to isotope separation plants (gaseous diffusion, laser enrichment, plasma separation, electromagnetic enrichment), to heavy water and deuterium production ...

2002-10-01

383

Irradiation characteristics examination technology development of irradiated nuclear material and high burn-up fuels  

Energy Technology Data Exchange (ETDEWEB)

The research and development for the first year of the project are performed through specialization of researchers, information from aborad and international cooperation, securement of advanced nuclear technology, development and installation of test equipment, application of external man-power, establishment of advanced test techniques, and certified test method. 1. Absolute efficiency measurement examination technology development of gamma scanning system 2. Sample preparation technology development of SEM and EPMA for micro-structural observation and chemical composition analysis 3. Irradiated high burn-up nuclear fuel transportation and test for PWR 4. Development of hot cell examination techniques and equipment 5. Acquirement of KOLAS system. In addition to the project, the following activities are carried out as follows; - PIE of Hanaro fuel(KH99H-001) - PIE of U-Mo advanced nuclear fuel irradiated at Hanaro - PIE of ...

2002-12-01

384

Displacement damage cross sections for neutron-irradiated silicon carbide  

International Nuclear Information System (INIS)

Displacements per atom (DPA) is a widely used damage unit for displacement damage in nuclear materials. Calculating the DPA for SiC irradiated in a particular facility requires a knowledge of the neutron spectrum as well as specific information about displacement damage in that material. In recent years significant improvements in displacement damage information for SiC have been generated, especially the energy required to displace an atom in an irradiation event and the models used to describe electronic and nuclear stopping. Using this information, numerical solutions for the displacement functions in SiC have been determined from coupled integro-differential equations for displacements in polyatomic materials and applied in calculations of spectral-averaged displacement cross sections for SiC. This procedure has been used to generate spectrally averaged displacement cross ...

2002-12-01

385

Displacement Damage Cross Sections for Neutron-irradiated Silicon Carbide  

Energy Technology Data Exchange (ETDEWEB)

Displacements per atom (DPA) is a widely used damage unit for displacement damage in nuclear materials. Calculating the DPA for SiC irradiated in a particular facility requires a knowledge of the neutron spectrum as well as specific information about displacement damage in that material. In recent years significant improvements in displacement damage information for SiC have been generated, especially the energy required to displace an atom in an irradiation event and the models used to describe electronic and nuclear stopping. Using this information, numerical solutions for the displacement functions in SiC have been determined from coupled integro-differential equations for displacements in polyatomic materials and applied in calculations of spectral-averaged displacement cross sections for SiC. This procedure has been used to generate spectrally averaged displacement cross ...

2002-12-01

386

Annual report on heavy water reactor fuel fabrication  

Energy Technology Data Exchange (ETDEWEB)

The CANDU-type nuclear fuel localization project started in 1981, and mass-production system completed in 1987 through the pilot scale demonstration of fuel manufacturing. Since the completion of the mass-production system, about 24,000 fuel bundles (450 ton-U) had been delivered to Wolsung Nuclear Power Plant by the end of 1992, according to the fuel supply contracts with KEPCO. The superiority of KAERI-made nuclear fuel has been demonstrated by having achieved the highest utilization factor in the world in 1992. In 1993, as contracted, 4,824 fuel bundles well fabricated and delivered to Wolsung Nuclear Power Plant. The process improvement, quality control, safety management, safeguards of nuclear materials and various kinds of audits have also been performed in the course for fuel manufacturing. Especially in 1993, the difficulties of the reduction of ...

1994-03-01

387

Status of the surry low power and shutdown PRA  

International Nuclear Information System (INIS)

Traditionally, probabilistic risk analyses [PRA] of severe accidents in nuclear power plants have limited themselves to consideration of the set of initiating events occurring during full power operation. However, some analyses of accident initiators during low power, shutdown, and other modes of plant operation other than full power have been performed. These studies as well as the Chernobyl accident and recent operating experience at U.S. pressurized water reactors suggested that risks during low power and shutdown could be significant. As such, the analysis of the frequencies, consequences, and risks of these accidents was identified as one task in the Nuclear Regulatory Commission staff's study of the implications of the Chernobyl accident to U.S. commercial nuclear power plants. The surry PRA project is an ongoing high priority effort at BNL [Brookhaven National Laboratory] that is expected to ...

1990-10-01

388

Radionuclide release rates from spent fuel for performance assessment modeling  

Energy Technology Data Exchange (ETDEWEB)

In a scenario of aqueous transport from a high-level radioactive waste repository, the concentration of radionuclides in water in contact with the waste constitutes the source term for transport models, and as such represents a fundamental component of all performance assessment models. Many laboratory experiments have been done to characterize release rates and understand processes influencing radionuclide release rates from irradiated nuclear fuel. Natural analogues of these waste forms have been studied to obtain information regarding the long-term stability of potential waste forms in complex natural systems. This information from diverse sources must be brought together to develop and defend methods used to define source terms for performance assessment models. In this manuscript examples of measures of radionuclide release rates from spent nuclear fuel or analogues of nuclear fuel are presented. ...

1994-11-01

389

Probability of failure in BWR reactor coolant piping: Guillotine break indirectly induced by earthquakes  

Energy Technology Data Exchange (ETDEWEB)

The requirements to design nuclear power plants for the effects of an instantaneous double-ended guillotine break (DEGB) of the reactor coolant piping have led to excessive design costs, interference with normal plant operation and maintenance, and unnecessary radiation exposure of plant maintenance personnel. This report describes an aspect of the NRC/Lawrence Livermore National laboratory-sponsored research program aimed at investigating whether the probability of DEGB in Reactor Coolant Loop Piping of nuclear power plants is acceptably small such that the requirements to design for the DEGB effects (e.g., provision of pipe whip restraints) may be removed. This study estimates the probability of indirect DEGB in Reactor Coolant piping as a consequence of seismic-induced structural failures within the containment of the GE supplied boiling water reactor at the Brunswick nuclear power plant. The median ...

1986-12-01

390

ENDF-102 DATA FORMATS AND PROCEDURES FOR THE EVALUATION NUCLEAR DATA FILE ENDF-6.  

Energy Technology Data Exchange (ETDEWEB)

The Evaluated Nuclear Data File (ENDF) formats and libraries are decided by the Cross Section Evaluation Working Group (CSEWG), a cooperative effort of national laboratories, industry, and universities in the U.S. and Canada, and are maintained by the National Nuclear Data Center (NNDC). Earlier versions of the ENDF format provided representations for neutron cross sections and distributions, photon production from neutron reactions, a limited amount of charged-particle production from neutron reactions, photo-atomic interaction data, thermal neutron scattering data, and radionuclide production and decay data (including fission products). Version 6 (ENDF-6) allows higher incident energies, adds more complete descriptions of the distributions of emitted particles, and provides for incident charged particles and photonuclear data by partitioning the ENDF library into sub-libraries. Decay data, fission product yield data, ...

2001-05-15

391

Development of PHWR fuel fabrication in Korea  

Energy Technology Data Exchange (ETDEWEB)

Korea Advanced Energy Research Institute (KAERI) started a research project to develop the PHWR (CANDU) nuclear fuel fabrication technology in 1981. Based on the results of the intensive developmental work, several prototype fuel bundles were fabricated and tested in the Hot Test Loop at KAERI continuously in 1983 and 1984. After that, irradiation test and post-irradiation examination were carried out for two KAERI-made fuel bundles at Chalk River Nuclear Laboratories in Canada in 1984. Since the results of in-pile and out-of-pile tests with prototype fuel bundles proved to be satisfactory, 48 additional fuel bundles were loaded in Wolsung reactor (CANDU) in 1984 and 1985, and all of them were discharged without a defect after excellent performance in the power reactor. In 1985, the Korean government decided that KAERI supplies all the fuel necessary for the Wolsung reactor. For the mass production of ...

1988-01-01

392

Characterization system for Germanium detectors dedicated to gamma spectroscopy applied to nuclear waste  

International Nuclear Information System (INIS)

CEA-Valduc produces some radioactive waste (mainly alpha emitters). Legislation requires producers to sort their waste by activity and type of isotopes, and to package them in order to forward them to the appropriate reprocessing or storage facility. Our lab LMDE (laboratory for measurements on nuclear wastes and valuation) is in charge of the characterization of the majority of waste produced by CEA-Valduc. Among non-destructive methods to characterize a radioactive object, gamma-spectroscopy is one of the most efficient. We present to this conference the method we use to characterize nuclear waste and the system we developed to characterize our germanium detectors. The goal of this system is to obtain reliable numerical models of our detectors and calculate their efficiency curves. Measurements are necessary to checks models and improve them. These measurements are made on a bench using pinpoint sources ("1"3"3Ba, ...

2009-06-07

393

BWR stability analysis at Brookhaven National Laboratory  

Energy Technology Data Exchange (ETDEWEB)

Following the unexpected, but safely terminated, power and flow oscillations in the LaSalle-2 Boiling Water Reactor (BWR) on March 9, 1988, the Nuclear Regulatory Commission (NRC) Offices of Nuclear Reactor Regulation (NRR) and of Analysis and Evaluation of Operational Data (AEOD) requested that the Office of Nuclear Regulatory Research (RES) carry out BWR stability analyses, centered around fourteen specific questions. Ten of the fourteen questions address BWR stability issues in general and are dealt with in this paper. The other four questions address local, out-of-phase oscillations and matters of instrumentation; they fall outside the scope of the work reported here. It was the purpose of the work documented in this report to answer ten of the fourteen NRC-stipulated questions. Nine questions are answered by analyzing the LaSalle-2 instability and related BWR transients with the BNL Engineering Plant Analyzer (EPA) and ...

1991-12-31

394

Assessment of RELAP5 model for the University of Massachusetts Lowell research reactor  

International Nuclear Information System (INIS)

RELAP5 (Reactor Excursion and Leak Analysis Program) is a system code developed at the Idaho National Environmental and Engineering Laboratory for thermal hydraulic analysis of nuclear reactors. The code RELAP5 is widely used for safety analysis studies of commercial nuclear power plants. However, recent released version of RELAP5/3.2 and over present significant capabilities for analysis of nuclear reactor research systems. As a contribution to the assessment of RELAP5/3.3 for research reactor safety analysis, experimental data from the University of Massachusetts Lowell Research Reactor UMLRR are used. The UMLRR is a 1 MW, light water moderated and cooled, graphite-reflected, open-pool type research reactor. This paper presents the development and the validation of a UMLRR-RELAP model using experimental data. For this purpose, a series of experiments were performed for benchmarking RELAP5 calculations ...

395

Accelerator driven assembly  

Energy Technology Data Exchange (ETDEWEB)

This report addresses a Los Alamos National Laboratory (LANL) proposal to build a pulsed neutron source for simulating nuclear-weapons effects. A point design for the pulsed neutron facility was initiated early in FY94 after hosting a Defense Nuclear Agency (DNA) panel review and after subsequently visiting several potential clients and users. The technical and facility designs contained herein fulfill the Statement of Work (SOW) agreed upon by LANL and DNA. However, our point designs and parametric studies identify a unique, cost-effective, above-ground capability for neutron nuclear-weapons-effects studies at threat levels. This capability builds on existing capital installations and infrastructure at LANL. We believe that it is appropriate for us, together with the DNA, to return to the user community and ask for their comments and critiques. We also realize that the requirements of last year have ...

1997-01-01

396

Summary on performance study of corrosion resistance of zirconium alloys  

International Nuclear Information System (INIS)

Zirconium-base alloys are used primarily as fuel cladding material and other core structure material in water cooled nuclear power reactors. Main research achievements and problems about corrosion of zirconium alloys are reviewed; the present theories and challenge are summarized. In the 1980s, great progress had been made towards correlating alloy composition, microstructure and irradiation with corrosion resistance. In the 1990s, main researches are focused on exploring actual mechanism of corrosion, optimizing both alloy composition and microstructure in order to minimize the fuel cycle costs through burnup optimization.

397

Study on reactor building structures using ultrahigh strength materials - Part 8: Results of mixed structure tests  

International Nuclear Information System (INIS)

The mixed structure of a nuclear reactor building is composed of SC-columns, S-beams, S-joints and PCa-panels. Following the last report (Part 7)[1], the main test results of the mixed structure, that is, the deformation mode, strain distribution and shear strength, are described. The S-joints using ultrahigh strength materials had no buckling nor shear slipping. The proposed mixed structure resisted the external horizontal forces under integrated uniformity among SC-columns, S-joints and PCa-panels. It could be confirmed that the mixed structure can be established. (author)

1993-08-15

398

Study on reactor building structure using ultrahigh strength materials - Part 7: Outline of mixed structure tests  

International Nuclear Information System (INIS)

The objective of this study is to comprehend the basic structural characteristics of box shaped mixed structures proposed for a future nuclear reactor building structure. Specimens of reinforced concrete precast panel walls of the mixed structures were prepared using ultrahigh strength materials. Two bending shear tests were conducted with a parameter of the quantity of reinforcement bars. The results include: (1) Relationship of shear stress and the angle of the structure, and (2) Failure mode. (author)

1993-08-15

399

Solid state and materials research  

International Nuclear Information System (INIS)

Within about 10 years, microelectronic devices will be made with more than a billion (10"9) electronic components per chip. To implement such a sophisticated technology it will be essential to have a fundamental understanding of the solid state interaction between the different materials in thin film semiconductor structures. This is the main purpose of this research program. Characterization and analysis is carried out mainly by Rutherford backscattering spectrometry and channelling using accelerated nuclear particles from the Van de Graaff accelerator, while radioactive isotopes provide information about interaction mechanisms. 6 figs., 1 ref.

400

Simulation of High Power Deposition on Target Materials: Applications in Magnetic, Inertial Fusion, and High Power Plasma Lithography Devices  

International Nuclear Information System (INIS)

High power and particle deposition on target materials are encountered in many applications including magnetic and inertial fusion devices, nuclear and high energy physics applications, and laser and discharge produced plasma devices. Surface and structural damage to plasma-facing components due to the frequent loss of plasma confinement remains a serious problem for the Tokamak reactor concept. The deposited plasma energy causes significant surface erosion, possible structural failure, and frequent plasma contamination.

2006-01-01

401

Radiation-induced chemical modification of wood  

International Nuclear Information System (INIS)

The results of theoretical and experimental investigations, describing the effect of ionizing radiation on wood and its main components and methods for production of wood-plastic composites by means of radiation-induced chemical modification are generalized. Domestic and foreign experience in their production is systematized; physico-mechanical characteristics of new material, simulation and calculation of irradiating devices, as well as calculation and experimental study of #gamma#-radiation attenuation both by wood material and by wood of different species are given. Gamma sources ("6"0Co isotope, a hot loop of a nuclear reactor) as well as electron accelerators are considered as ionizing radiation sources.

1985-01-01

402

Dry aerosol resuspension after a hydrogen deflagration in the containment  

International Nuclear Information System (INIS)

During a hypothetical severe incident in a nuclear power plant with core meltdown a large part of radioactive material is present as aerosol particles in the reactor containment. In current severe accident containment codes the potential influences of hydrogen combustions on the behaviour of aerosols are not considered. Among other effects dry resuspension can increase the aerosol concentration in the atmosphere. Already deposited aerosol material can be re-released into the containment atmosphere by atmospheric currents induced by hydrogen deflagrations or by other phenomena like steam explosions. The objective is to assess the possible influence of this dry resuspension effect on the radioactive source term. (author)

2007-09-10

403

Corrosion cracking of rotor steels of steam turbines  

International Nuclear Information System (INIS)

Results of investigation of stress corrosion cracking of steam turbine materials in nuclear, fossil and geothermal power plants have been analysed. The role of factors that cause damage to rotor discs, mono block and welding rotors of steam turbines has been shown. These are yield stress and steel composition, stress intensity coefficient and crack growth rate, composition and temperature of the condensed steam and water, electrochemical conditions. The conclusion has been made about the state of stress corrosion cracking of the rotors materials, and main investigation trends which are necessary to solve this problem have been listed.

404

Conceptual design of a nuclear reactor facility for medical and biological purposes  

Energy Technology Data Exchange (ETDEWEB)

Optimal neutron energy for boron neutron capture therapy (BNCT) has been studied. Epithermal neutron is superior to thermal neutrons in treating deep-seated tumors. Design of the epithermal neutron column for BNCT has been performed by using a two-dimensional transport calculation code. Aluminum and heavy water are used as moderation materials. A thermal neutron column is also designed using heavy water as thermalization material. The configuration of the facility for treatment and research of BNCT and also for basic radio-biological studies of neutrons has been presented.

1981-09-01

405

Conceptual design of a nuclear reactor facility for medical and biological purposes  

International Nuclear Information System (INIS)

Optimal neutron energy for boron neutron capture therapy (BNCT) has been studied. Epithermal neutron is superior to thermal neutrons in treating deep-seated tumors. Design of the epithermal neutron column for BNCT has been performed by using a two-dimensional transport calculation code. Aluminum and heavy water are used as moderation materials. A thermal neutron column is also designed using heavy water as thermalization material. The configuration of the facility for treatment and research of BNCT and also for basic radio-biological studies of neutrons has been presented. (author).

406

The prospects for polarized target materials with pure carbon background  

Science.gov (United States)

None of the materials presently in common use for polarized proton targets has a pure carbon nuclear background. The alcohols and diols contain some oxygen, and the ammonia and amine-based materials contain nitrogen and/or other noncarbon species. In the latter cases the noncarbon nuclei are measurably polarized as a concomitant of the process used to polarize the hydrogen nuclei. The relative simplicity of a pure carbon background would be advantageous for most types of scattering experiments and perhaps crucial for some. In addition to simplifying the kinematics of background events, pure carbon is relatively easy to prepare as a dummy'' target for background subtraction. Also, in such a target material, [sup 13]C-enrichment would yield a clean polarized [sup 13]C material. In this note I explore the possibilities for such materials, ...

1992-10-06

407

Different purification methods and quality of sunflower biodiesel  

Energy Technology Data Exchange (ETDEWEB)

Biodiesel is derived from triacylglycerides and is produced primarily through transesterification, a chemical reaction of vegetable oils with alcohol, methanol or ethanol. The cost of raw material should be considered since 85 per cent of production cost is related to vegetable oil. The purpose of this study was to evaluate oil expression of sunflower seed. It also examined the sunflower crude oil as a raw material for biodiesel by transesterification in both laboratory and pilot scale studies. Three different biodiesel purification methods were examined. The best result for oil expelling (68.4 per cent) at the experimental stage was obtained for seeds with a moisture content of 6.9 per cent at 25 degrees C and at a screw speed of 114 rpm. For biodiesel production at the laboratory scale, the best result for oil expelling was 87.5 per cent. It was obtained with an ethanol:oil molar ratio of 4.7:1 and ...

2010-07-01

408

The GERDA experiment: status and perspectives  

British Library Electronic Table of Contents (United Kingdom)

The GERDA experiment is located in the underground Gran Sasso laboratory. The experiment aims at studying the neutrinoless ?? decay of 76Ge. The implementation of the experiment is divided in two consecutive phases. Phase I will allow within one year of data taking to reach a sensitivity limit for the half life of the process of the order of Formula Not Shown years. Phase II, with an increased amount of active material and a background index lower by one order of magnitude than in Phase I, will allow to reach a half life limit of about Formula Not Shown years. In the present paper a brief review of the status of the experiment and its perspectives is given.

2011-01-01

409

State-of-the-art in photovoltaic research and application (except for use in concentrators)  

Energy Technology Data Exchange (ETDEWEB)

A review is given of the state-of-the-art of single and polycrystalline solar cells, which includes a short theoretical review, laboratory achievements, and production methods. The Si single and polycrystalline cell and the amorphous Si cell are described, including material preparation, crystal and sheet growth, and cell and panel production. Promising second generation thin film solar cells including GaAs, CdS(CuInSe/sub 2/), and CdTe are briefly described. Economical aspects are discussed.

1987-01-01

410

Smart Acquisition EELS  

Energy Technology Data Exchange (ETDEWEB)

Electron energy loss (EEL) spectroscopy and high angle annular dark field (HAADF) imaging in aberration-corrected electron microscopes are powerful techniques to determine the chemical composition and structure of materials at atomic resolution. We have implemented Smart Acquisition, a flexible system of scanning transmission electron microsocpy (STEM) beam position control and EELS collection, on two aberration-corrected dedicated cold field emission gun (FEG) STEMs located at SuperSTEM, Daresbury Laboratory. This allows the collection of EEL spectra from spatially defined areas with a much lower electron dose possible than existing techniques such as spectrum imaging.

2010-07-01

411

Refractometry of organosilica microspheres  

CERN Document Server

The refractive index of novel organosilica (nano/micro)material is determined using two methods. The first method is based on analysis of optical extinction efficiency of organosilica beads versus wavelength, which is obtained by a standard laboratory spectrometer. The second method relies on the measurable trapping potential of these beads in the focused light beam (laser tweezers). Polystyrene beads were used to test these methods, and the determined dispersion curves of refractive index values have been found accurate. The refractive index of organosilica beads has been determined to range from 1.60-1.51 over the wavelength range of 300-1100 nm.

2007-01-01

412

Ion exchange resins for water purification : properties and characterisation  

International Nuclear Information System (INIS)

The report is divided into three sections. The first section contains a general introduction to ion exchange resins used in various processes, the second section describes characteristic properties of the polymer materials and the inter relation between them. This will, in turn, be useful to interpret the data obtained from the various tests carried out on the resins in the laboratory. In the third section of the report, are given the details of each method used for a particular test to be carried out on a routine basis. Each method describes the principle involved, the reagents and apparatus used in the experiment, the actual procedure and calculations and recording of the data. 3 refs. (author).

2005-03-14

413

IRSL characteristics of NaCl and KCl relative to dosimeter  

Energy Technology Data Exchange (ETDEWEB)

The aim of this work is to determine and compare the dosimetric properties of NaCl and KCl samples using infrared-stimulated luminescence (IRSL) technique. For a material to be used as dosimeter, both the IRSL temperature dependence and the radiation dose response have critical importance. In this work the IRSL characteristics from NaCl and KCl samples were experimentally investigated as a function of temperature and laboratory radiation doses. Dosimetric properties of NaCl and KCl samples were found significantly different. The IRSL signals displayed by NaCl were found to be more stable, reliable and agreeable than those of KCl.

2007-01-15

414

Geothermal well cost sensitivity analysis: current status  

Energy Technology Data Exchange (ETDEWEB)

The geothermal well-cost model developed by Sandia National Laboratories is being used to analyze the sensitivity of well costs to improvements in geothermal drilling technology. Three interim results from this modeling effort are discussed. The sensitivity of well costs to bit parameters, rig parameters, and material costs; an analysis of the cost reduction potential of an advanced bit; and a consideration of breakeven costs for new cementing technology. All three results illustrate that the well-cost savings arising from any new technology will be highly site-dependent but that in specific wells the advances considered can result in significant cost reductions.

1980-01-01

415

Gamma Radiation Detectors of the TA-55 Waste Line Monitoring System  

Energy Technology Data Exchange (ETDEWEB)

This report covers the gamma detectors, measurement instrumentation, and testing results of a system developed at Los Alamos National Laboratory. This system monitors the process liquid waste streams at the Plutonium Facility (TA-55) for the presence of radioactive contamination. The detectors are at various points on the acid, caustic, and industrial waste lines. Two of the detectors are on the sanitary sewer lines from the facility. A custom interface unit associated with these two detectors furnishes the facility operation center with a notification of the detection of material. All of the detectors furnish measurement information to a central computer system for storage and trending.

1999-06-01

416

A personal computer based system to evaluate J-integral by a single specimen unloading compliance method  

International Nuclear Information System (INIS)

The single specimen unloading compliance technique has become the preferred method for evaluating J-integrals. It involves data acquisition and analysis using a computer. This paper describes in detail the development of a simple experimental system and related software that can be used in a laboratory equipped with a microcomputer and with access to a minicomputer. The effects of loading rate, test temperature, specimen geometry and material composition can be readily evaluated using this system. The results on a pressure vessel steel and an #alpha#-#beta# titanium alloy are discussed in Part II. (author).

417

Utilization of microwaves in processing of polymer composites - past, present, and future  

Energy Technology Data Exchange (ETDEWEB)

Utilization of microwaves for heating purposes began in the 1940`s. This new form of energy transfer offers many distinct advantages over conventional heating, such as volumetric, fast, direct, selective, instantaneous, and controllable heating. Studies of microwave processing of polymeric materials in the early 1960`s led to a successful industrial application in the rubber industry. Since the mid-1980`s, there has been a great deal of interest in microwave processing of polymeric materials. Technical issues, such as temperature uniformity and control of thermal runaway during processing, were investigated and many successful laboratory scale results were obtained from both fundamental and processing studies. This paper presents a historical perspective of microwave heating in the processing of polymer composites and discusses possible future directions for technology commercialization.

1995-12-01

418

Transuranic material recovery in the Integral Fast Reactor fuel cycle demonstration  

Energy Technology Data Exchange (ETDEWEB)

The Integral Fast Reactor is an innovative liquid metal reactor concept that is being developed by Argonne National Laboratory. It takes advantage of the properties of metallic fuel and liquid metal cooling to offer significant improvements in reactor safety, operation, fuel cycle economics, environmental protection, and safeguards. The plans for demonstrating the IFR fuel cycle, including its waste processing options, by processing irradiated fuel from the Experimental Breeder Reactor-II fuel in its associated Fuel Cycle Facility have been developed for the first refining series. This series has been designed to provide the data needed for the further development of the IFR program. An important piece of the data needed is the recovery of TRU material during the reprocessing and waste operations.

1993-01-01

419

Transuranic material recovery in the Integral Fast Reactor fuel cycle demonstration  

Energy Technology Data Exchange (ETDEWEB)

The Integral Fast Reactor is an innovative liquid metal reactor concept that is being developed by Argonne National Laboratory. It takes advantage of the properties of metallic fuel and liquid metal cooling to offer significant improvements in reactor safety, operation, fuel cycle economics, environmental protection, and safeguards. The plans for demonstrating the IFR fuel cycle, including its waste processing options, by processing irradiated fuel from the Experimental Breeder Reactor-II fuel in its associated Fuel Cycle Facility have been developed for the first refining series. This series has been designed to provide the data needed for the further development of the IFR program. An important piece of the data needed is the recovery of TRU material during the reprocessing and waste operations.

1993-03-01

420

Results of laboratory studies to investigate new gel-forming composites for temporary capping of beds  

Energy Technology Data Exchange (ETDEWEB)

Formulas were developed based on an aqueous solution of hydrolyzed polyacrylonitrile widely used in the oil industry. The additive used consisted of products of industrial production: synthetic resin TEG-1 with hardening agent PEPA (polyehtylene polyamine) and technical formalin. The mixtures containing about 80-85% by volume 5% hydrolyzed polyacrylonitrile, 10-15% by volume of resin TEG-1 with hardening agent PEPA and 3-5% by volume formalin satisfy the requirements made for the plugging materials. The initial mixtures are distinguished by technological efficiency of preparation and have controllable hardening periods. Physical-chemical properties are given for the gel polymers. In the set of properties, the mixtures based on hydrolyzed polyacrylonitrile, resin TEG-1 with hardening agent PEPA and formalin can be recommended as plugging materials of temporary action with complex treatment of the heterogeneous beds.

1982-01-01

421

Quantitative measurements of injections into porous media with contrast based MRI  

British Library Electronic Table of Contents (United Kingdom)

Porous flow occurs in a wide range of materials and applies to many commercially relevant applications such as oil recovery, chemical reactors and contaminant transport in soils. Typically, breakthrough and pressure curves of column floods are used in the laboratory characterization of these materials. These characterization methods lack the detail to easily and unambiguously resolve flow mechanisms with similar effects at the core scale that can dominate at the aquifer or oil field scale, as well as the effects of geometry that control the flow at interfaces as in a perforated well or the inlet of an improperly designed column. Non-invasive imaging techniques such as MRI have been shown to provide a far more detailed characterization of the properties of the solid matrix and flow, but usu...

2011-01-01

422

Properties of molecular solids and fluids at high pressure and temperatures  

Energy Technology Data Exchange (ETDEWEB)

This renewal request for DOE grant DE-FG02-86ER45238, is dedicated to providing a complete thermodynamic profile of solids fluids, and fluid mixtures, over a wide range of temperatures and pressures. We are partially motivated by technological interest in detonation, combustion, superhard high pressure materials, and high temperature superconductors, which are important components of interest of various DOE laboratories. Our work on fluids and solids, composed of simple molecules, involves the determination of structures, phase transitions, pressure-volume relations, phonon, vibron, and libron modes of excitation, sound velocities, specific heats, thermal expansion, virial coefficients, sublimation energies, and orientational translational, and magnetic correlations. We hope that the study of these systems under extreme thermodynamic conditions will lead to exotic new materials of value, as well as enhanced fundamental ...

1992-03-01

423

Petroleum storage tank cleaning using commercial microbial culture products  

Energy Technology Data Exchange (ETDEWEB)

The removal of paraffinic bottom accumulations from refinery storage tanks represents an increasingly costly area of petroleum storage management. Microorganisms can be used to reduce paraffinic bottoms by increasing the solubility of bottom material and by increasing the wax-carrying capacity of carrier oil used in the cleaning process. The economic savings of such treatments are considerable. The process is also intrinsically safer than alternative methods, as it reduces and even eliminates the need for personnel to enter the tank during the cleaning process. Both laboratory and field sample analyses can be used to document changes in tank material during the treatment process. These changes include increases in volatile content and changes in wax distribution. Several case histories illustrating these physical and chemical changes are presented along with the economics of treatment.

1995-12-31

424

Membrane barriers for radon gas flow restrictions  

International Nuclear Information System (INIS)

Research was performed to assess the feasibility of barrier membrane substances, for use within mining or associated high risk environments, in restricting the diffusion transport of radon gas quantities. Specific tests were conducted to determine permeability parameters of a variety of membrane materials with reference to radon flow capabilities. Tests were conducted both within laboratory and in-situ emanation environments where concentrations and diffusion flows of radon gas were known to exist. Equilibrium radon gas concentrations were monitored in initially radon-free chambers adjacent to gas sources, but separated by specified membrane substances. Membrane barrier effectiveness was demonstrated to result in reduced emanation concentrations of radon gas within the sampling chamber atmosphere. Minimum gas concentrations were evidenced where the barrier membrane material was shown to exhibit lowest radon permeability ...

425

Integrated optoelectronic materials and circuits for optical interconnects  

International Nuclear Information System (INIS)

Conventional interconnect and switching technology is rapidly becoming a critical issue in the realization of systems using high speed silicon and GaAs based technologies. In recent years clock speeds and on-chip density for VLSI/VHSIC technology has made packaging these high speed chips extremely difficult. A strong case can be made for using optical interconnects for on-chip/on-wafer, chip-to-chip and board-to-board high speed communications. GaAs integrated optoelectronic circuits (IOC's) are being developed in a number of laboratories for performing Input/Output functions at all levels. In this paper integrated optoelectronic materials, electronics and optoelectronic devices are presented. IOC's are examined from the standpoint of what it takes to fabricate the devices and what performance can be expected.

426

Influence of silica fume on the desiccation cracks of compacted clayey soils  

British Library Electronic Table of Contents (United Kingdom)

Clayey soils containing smectites are widely used for construction of liner and cover systems to reduce the hydraulic conductivity in geotechnical applications because of their low permeability and high cation exchange capacity. However, the compacted clayey soils crack on drying because of their high swelling potential, and their hydraulic conductivities increase. To solve this problem, it is essential to stabilize the clayey soils using additive materials. The aim of this study is to examine the suitability of silica fume as a stabilization material to reduce the development of desiccation cracks in compacted clayey liner and cover systems. Natural clayey soil and clayey soil?silica fume mixtures were compacted at the optimum moisture content and subjected to laboratory tests. The result...

2009-01-01

427

Indoor climate seminar; Sisaeilmastoseminaari  

Energy Technology Data Exchange (ETDEWEB)

The national energy research programme LVIS-2000: Future Building Services is concerned with the control of energy use and indoor climate in buildings of the future. The projects were presented at a one day seminar arranged by the Laboratory of Heating and Ventilation of the Technical Research Centre in Finland which is coordinating the programme. The presentations at the seminar were: Impurity emission from materials, Building materials and indoor air quality, analysis of organic compounds in indoor air, effect of the return air, effect of the return air on health and comfort, electric heating as an indoor climate factor, calculations of air flows in ventilated rooms, effect of energy saving measures on hospital hygiene, application of modern aerosol measurement technique on indoor climate research.

1989-12-31

428

Eluates from pyrolysed refuse. Eluate aus pyrolysiertem Hausmuell  

Energy Technology Data Exchange (ETDEWEB)

The solubility behavior of solid residues from the heat treatment of domestic rubbish was examined by simulated precipitation in laboratory lysimeters. The precipitation corresponded to the average amount of rain in West Germany and was applied at different time periods. Specific soil characteristics, the value of k/sub f/ and the water retention capacity was determined in this way. In parallel with the lysimeter flood ions, extraction (by batch process) was done, in order to find the maximum solubility of the materials used. It was found that for pyrolysis residues from reactor temperatures of 450/sup 0/ to 1000/sup 0/C, a greater solubility was measured than for slag from combustion. The eluates from these residues gave information about the degree of contamination or on the solubility of the measured parameters and materials in organoleptic, physical, organic and inorganic examinations. The concentrations of harmful ...

1981-01-01

429

Compression molded energy storage flywheels  

Energy Technology Data Exchange (ETDEWEB)

Flywheels containing fiber-reinforced composite materials have attributes suitable for vehicular propulsion, indicating the need for rotor designs which are easily manufactured and low in cost. This development goal was pursued in a cooperative effort between Owens-Corning Fiberglas and Lawrence Livermore Laboratory which investigated flywheels made from compression-molded sheet molding compound (SMC). The design resulted from a Lawrence Livermore analysis, with successful fabrication achieved using a procedure developed by Owens-Corning. Details concerning materials selection, rotor fabrication, and testing are discussed. Owens-Corning subsequently initiated a technical/marketing survey to determine current industrial interests in a low-cost flywheel design; precursory information, pertaining to composite flywheels in particular, is described.

1982-08-01

430

Ceramic injection molding  

International Nuclear Information System (INIS)

Interest in making complex net-shape ceramic parts with good surface finishing and sharp tolerances without machining is a driving force for studying the injection molding technique. This method consists of softhening the ceramic material by means of adding some plastic and heating in order to inject the mixture under pressure into a relatively cold mold where solidification takes place. Essentially, it is the same process used in thermoplastic industry but, in the present case, the ceramic powder load ranges between 80 to 90 wt.%. This work shows results obtained from the fabrication of pieces of different ceramic materials (alumina, barium titanate ferrites, etc.) in a small scale, using equipments developed and constructed in the laboratory. (Author).

1988-11-01

431

Capturing recrystallization of metals with a multi-scale materials model  

Energy Technology Data Exchange (ETDEWEB)

The final report for a Laboratory Directed Research and Development project entitled, ``Capturing Recrystallization of Metals in a Multiscale Materials Model'' is presented. In this project, deformation and recrystallization processes have been followed experimentally and theoretically in order to incorporate essential mechanisms from the defect (dislocation) and grain size length scales. A nonlinear rotational gradient theory has been developed which enables the incorporation of microstructural parameters. The evolution of these parameters during deformation and recrystallization has been characterized qualitatively and quantitatively, applying various electron optic techniques ranging over several length scales. The theoretical and experimental framework developed is general. It has been exemplified by an application to recrystallization in single crystals and bicrystals of aluminum. The recrystallization process has been ...

2000-04-01

432

Brief laboratory report: surgical drape flammability.  

Science.gov (United States)

Fires in the operating room continue to present a hazard to patients, at times with catastrophic and debilitating results. Recent data from closed claim files reveal oxygen, electrosurgical unit (ESU), and surgical drapes are common components of the fire triangle in the operating room. In this era of biotechnological sophistication, why are surgical drapes flammable? The purpose of this study was to test the flammability of different surgical drape materials and to determine the time to ignition using a bipolar ESU device in 21%, 35%, and 100% oxygen concentrations. Results show that regardless of oxygen concentration surgical drapes, when exposed to close contact with the ESU, are flammable. Time to ignition decreases with increasing concentrations of oxygen as expected. One of the surgical drapes tested was advertised to the hospital as nonflammable. Future research should focus on surgical drape materials and aim to reduce the flammability ...

2006-10-01

433

Report on the project on the researcher dispatch type international joint research survey. Feasibility study for digging up the seeds for international joint research; Kenkyusha hakengata kokusai kyodo kenkyu chosa jigyo hokokusho. Kokusai kyodokenkyu sizu hakkutsu no tameno FS chosa  

Energy Technology Data Exchange (ETDEWEB)

For the purpose of digging up themes of the joint research which develop the R and D in the industrial technology field in Japan to a new stage, researchers were sent to the world representing research institutes to conduct the research survey of 'Nano-structured carbon and hydrogen absorption' and 'Development of the creation technology of nano-porous materials.' As to the former, an experiment on electrochemical hydrogen absorption of carbon materials including nanotubes was conducted by researchers dispatched, but the large absorption amount was not observed. As to the latter, visits were paid to Fraunhofer Institute and the related facilities in Germany, Princeton University, MIT, GIT and Naval Research Laboratories in the U.S., Orleans University in France, AO Research Institute (bone repair study) in Switzerland, Cambridge University and University of Bristol in the U.K., etc., and ...

2001-03-01

434

Cryocycling of energetic materials: Status report for FY94  

Energy Technology Data Exchange (ETDEWEB)

The Cryocycling of Energetic Materials Project is sponsored by the Memorandum of Understanding (MOU) on advanced munition technologies. This MOU is an agreement between the Department of Energy and the Department of Defense (Office of Munitions) that facilitates the development of technologies of mutual interest to the two Departments. The cryocycling project is one of several that focus on demilitarization aspects of conventional weapons and weapon systems. During FY94 the project pursued the development of analytical and numerical models that can be used to describe and optimize the cryocycling process for preparing energetic materials for recycle and reuse. In addition, the demilitarization stockpile of the Department of Defense was analyzed to identify candidate munitions for the process, and pilot scale cryocycling operations were begun at an industrial contractor. When a material is cryocycled, it is repeatedly ...

1995-07-01

435

Problems occurring while carrying out cost-benefit analysis for "3H, "1"4C, "8"5Kr, iodine and aerosols in nuclear facilities  

International Nuclear Information System (INIS)

Up to now the retention of radioactive material for nuclear facilities has been based on the maximum individual dose. The maximum individual dose can locally be lowered considerably by higher dissolution. In general, the collective doses are not lowered by this. In order to set up regulations concerning collective doses, the new recommmendations of the ICRP are very welcome. However, the costs of detriment and the period to be considered have not yet been defined. Therefore there are no fixed methods for carrying out a cost-benefit analysis. Furthermore, for nuclear technology the costs and the effectiveness of the retention of radioactive material for non-realized facilities can only be quoted roughly, which makes a cost-benefit analysis more difficult. A cost-benefit analysis for the retention of radioactive material in nuclear power plants with LWRs and ...

436

Environmental monitoring as an important tool for safeguards of nuclear material and nuclear forensics  

International Nuclear Information System (INIS)

The use of environmental monitoring as a technique to identify activities related to the nuclear fuel cycle has been proposed by international safeguards organizations. The elements specific for each kind of nuclear activity, or 'nuclear signatures', inserted in the ecosystem can be intercepted by different live organisms. This work demonstrates the technical viability of using pine needles as bioindicators of nuclear signatures associated with uranium enrichment activities. Additionally, it proposes the use of HR-ICP-MS to identify the signature corresponding to that kind of activities in the ecosystem. Nitric acid solutions, used to wash pine needles sampled near nuclear facilities and containing only 0.1 #mu#g x kg"-"1 of uranium, exhibit a n("2"3"5U)/n("2"3"8U) isotopic abundance ratio of 0.0092#+-#0.0002, while solutions originated from samples collected at places located more ...

2006-11-01

437

Review of the corrosion resistance properties of Alloy 800 in high-temperature steam  

International Nuclear Information System (INIS)

The investigations carried out on Alloy 800 in aqueous high-temperature environments in France as well as in other countries are reviewed. These studies are mainly concerned with nuclear industry where Alloy 800 can be used as structural material for steam generators of PWR, breeders or HTR. As results referred to in the literature on cracking in caustic environmens do not always agree, a discussion is presented on the matter. The behaviour of Alloy 800 in superheated steam is examined. (Auth.).

438

Radioisotope imaging of brain tumors in two rhesus monkeys. Final report  

Energy Technology Data Exchange (ETDEWEB)

Two geriatic male rhesus monkeys were used for the radioisotope imaging in this research. Discussion of the radionuclide, materials, and method used to accomplish the neurologic examination and the results obtained, both during the procedure and confirmation of the results by necropsies were accompanied by color photos of scan images. Results were that the nuclear images provided accurate images of intracranial neoplasia.

1988-04-01

439

Fusion technology  

International Nuclear Information System (INIS)

The Fusion Technology task performs analyses and systems studies of conceptual fusion reactors based upon inertial and high-#beta# magnetic confinement schemes. Progress in the areas of theoretical analysis (plasma and neutral-gas blanket models), specific reactor studies (toroidal and linear theta pinches, Z pinches, laser fusion) neutronic and nuclear data assessments, materials (metals and insulators) evaluation, and general engineering design is reported.

1976-12-01

440

Evaluations of half-bead weld repair procedures with thick-wall pressure vessels  

Science.gov (United States)

The results of research on the evaluation of the half-bead weld repair method for use on nuclear reactor components are reviewed from data obtained on thick-section test pieces and intermediate-size pressure vessels. Material properties, the magnitude of residual stresses and the structural behavior of flawed pressure vessels are being obtained to determine the adequacy of the weld repair method for application in thick-section components.

1978-01-01

441

Environmental interactions working group report  

Energy Technology Data Exchange (ETDEWEB)

Interactions between spacecraft systems and the space charged particle environment are reviewed and recommendations are presented for both near-term and far-term research considerations. Transient environment models, large space structures, solar and nuclear power systems/environment interactions, single event upsets, material degradation, and planetary missions are addressed.

1984-04-01

442

Container for the long-term storage of radioactive substances with a lid tightening device  

International Nuclear Information System (INIS)

The invention concerns a container for the long term storage of irradiated nuclear reactor fuel elements, which consists mainly of a basic body, at least one lid and an outside ring shaped lid tightening device, which acts on the basic body and the lid and holds the contact surface of the lid tight against the contact surface of the basic body, where the basic body, lid and the lid tightening device consist of corrosion-proof materials. (orig./HP).

1983-09-24

443

CEA and the Saclay center  

International Nuclear Information System (INIS)

CEA is a public body devoted to technological research with 9 research centers throughout France. The activities of its 16,000 scientists, engineers, and technicians deal with new technologies for nuclear energy and alternative energies (fuel batteries, solar energy, energy storage) as well as technologies related to the new economy, in particular in the fields of microelectronics, bio-technologies, and materials. (author)

2000-10-01

444

An initial survey of nuclear material safeguards requirements applicable to the civilian waste management program  

Science.gov (United States)

This report provides an initial survey of the domestic and international safeguards requirements and provides a general framework on which future studies may be based. Additional studies are needed to evaluate the activities required to implement effective safeguards within the civilian waste management system and to ensure compliance with all safeguards requirements. 16 refs.

445

Amarillo National Resource Center for Plutonium quarterly technical progress report, August 1, 1997--October 31, 1997  

Energy Technology Data Exchange (ETDEWEB)

This report summarizes activities of the Amarillo National Resource Center for Plutonium during the quarter. The report describes the Electronic Resource Library; DOE support activities; current and future environmental health and safety programs; pollution prevention and pollution avoidance; communication, education, training, and community involvement programs; and nuclear and other material studies, including plutonium storage and disposition studies.

1997-12-31

446

Accelerated aging speeds test of instrument reliability  

International Nuclear Information System (INIS)

Safety-related instrument in nuclear power plants must be checked for reliability over their projected operating life. A method of conducting accelerated aging tests is presentd. It uses the Arrhenius activation energy concept and manipulation of the parameters of the test e.g. by raising test temperature, by relying on a model characterizing the chemical-related reactions of materials.

1982-01-01

447

AGB (asymptotic giant branch): Star evolution  

Energy Technology Data Exchange (ETDEWEB)

Asymptotic giant branch stars are red supergiant stars of low-to-intermediate mass. This class of stars is of particular interest because many of these stars can have nuclear processed material brought up repeatedly from the deep interior to the surface where it can be observed. A review of recent theoretical and observational work on stars undergoing the asymptotic giant branch phase is presented. 41 refs.

1987-01-01

448

Final Environmental Impact Statement to construct and operate a facility to receive, store, and dispose of 11e.(2) byproduct material near Clive, Utah (Docket No. 40-8989)  

Energy Technology Data Exchange (ETDEWEB)

A Final Environmental Impact Statement (FEIS) related to the licensing of Envirocare of Utah, Inc.`s proposed disposal facility in Tooele county, Utah (Docket No. 40-8989) for byproduct material as defined in Section 11e.(2) of the Atomic Energy Act, as amended, has been prepared by the Office of Nuclear Material Safety and Safeguards. This statement describes and evaluates the purpose of and need for the proposed action, the alternatives considered, and the environmental consequences of the proposed action. The NRC has concluded that the proposed action evaluated under the National Environmental Policy Act of 1969 (NEPA) and 10 CFR Part 51, is to permit the applicant to proceed with the project as described in this Statement.

1993-08-01

449

Accelerated aging speeds test of instrument reliability  

International Nuclear Information System (INIS)

This paper shows how molecular theory paves the way for accelerated aging tests of safety-related equipment in nuclear power plants, as required by NRC qualification programs. Arrhenius' model, based on an equation, provides useful information regarding the extent of molecular change as a function of time and temperature. Critical to determining the aging characteristics and qualified life of organic materials is the activation energy concept, which is derived from information gathered when the molecular reaction of the material is documented over the entire life cycle. In accelerated-aging applications, the importance of the model lies in characterizing the chemical related reactions of materials. The problem with the Arrhenius approach is that, in generating a testing period of reasonable duration, a rather high test temperature must be selected which may lead to an added and unrelated environmental ...

1982-01-01

450

Development of American National Standard on External Event PRA Methodology  

International Nuclear Information System (INIS)

During the last ten years, the U.S. Nuclear Regulatory Commission and the U.S. nuclear utilities have been developing methods and requirements for risk-informed applications making use of probabilistic risk assessments (PRA) of nuclear power plants. Early in this process, it became clear that the existing PRAs were done with different objectives and methodologies by different analysts. For uniformity and consistency in future risk-informed applications, industry consensus standards on probabilistic risk assessments were deemed to be essential. Currently, the following standards have been published or under preparation: - ASME RA-S-2002: 'Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications', Addendum C, March 2005. - ANSI/ANS-58.21-2003 'External-Events PRA Methodology' March 2003. - ANS-58.22 'Low Power and Shutdown PRA Standard'. - ANS-58.23 'Fire PRA Methodology Standard'. ...

2007-11-14

451

Mass Production of 64Cu with 64Ni(p,n)64Cu Nuclear Reaction and Target Material Recycling  

International Nuclear Information System (INIS)

64Cu (T1/2=12.7h, ?- decay: 40%, ?+ decay: 19%, E.C. decay: 41%) is one of the most useful radioisotope in the nuclear medicine due to its multiple decay mode and the intermediate half-life. Several nuclear reaction, i.e., 64Ni(p,n)64Cu, 68Zn(p,?n)64Cu and 64Ni(d,2n)64Cu have been investigated for production. The highest could be obtained with proton irradiation on the enriched 64Ni target. For mass and routine production, the 64Ni target fabrication using electroplating, the reliable chemical separation of 64Cu from the irradiated 64Ni target and the effective recovery process for the recycling of very expensive enriched material ($20,000/g) and so forth are absolutely necessary to be established. In this work, we report our mass production method of 64Cu with 64Ni and Cyclone-30 accelerator

2009-05-01

452

On the integration of technology readiness levels at Sandia National Laboratories.  

Energy Technology Data Exchange (ETDEWEB)

Integrating technology readiness levels (TRL) into the management of engineering projects is critical to the mitigation of risk and improved customer/supplier communications. TRLs provide a common framework and language with which consistent comparisons of different technologies and approaches can be made. At Sandia National Laboratories, where technologies are developed, integrated and deployed into high consequence systems, the use of TRLs may be transformational. They are technology independent and span the full range of technology development including scientific and applied research, identification of customer requirements, modeling and simulation, identification of environments, testing and integration. With this report, we provide a reference set of definitions for TRLs and a brief history of TRLs at Sandia National Laboratories. We then propose and describe two approaches that may be used to integrate TRLs into the NW SMU business ...

2006-09-01

453

Occupational dose reduction at Department of Energy contractor facilities: Bibliography of selected readings in radiation protection and ALARA; Volume 5  

Energy Technology Data Exchange (ETDEWEB)

Promoting the exchange of information related to implementation of the As Low as Reasonably Achievable (ALARA) philosophy is a continuing objective for the Department of Energy (DOE). This report was prepared by the Brookhaven National Laboratory (BNL) ALARA Center for the DOE Office of Health. It contains the fifth in a series of bibliographies on dose reduction at DOE facilities. The BNL ALARA Center was originally established in 1983 under the sponsorship of the Nuclear Regulatory Commission to monitor dose-reduction research and ALARA activities at nuclear power plants. This effort was expanded in 1988 by the DOE`s Office of Environment, Safety and Health, to include DOE nuclear facilities. This bibliography contains abstracts relating to various aspects of ALARA program implementation and dose-reduction activities, with a specific focus on DOE facilities. Abstracts included in this bibliography ...

1994-01-01

454

Waste sampling and characterization facility (WSCF)  

Energy Technology Data Exchange (ETDEWEB)

The Waste Sampling and Characterization Facility (WSCF) complex consists of the main structure (WSCF) and four support structures located in the 600 Area of the Hanford site east of the 200 West area and south of the Hanford Meterology Station. WSCF is to be used for low level sample analysis, less than 2 mRem. The Laboratory features state-of-the-art analytical and low level radiological counting equipment for gaseous, soil, and liquid sample analysis. In particular, this facility is to be used to perform Resource Conservation and Recovery Act (RCRA) of 1976 and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 sample analysis in accordance with U.S. Environmental Protection Agency Protocols, room air and stack monitoring sample analysis, waste water treatment process support, and contractor laboratory quality assurance checks. The samples to be analyzed contain very low concentrations of radioisotopes. The ...

1994-10-01

455

Theoretical and experimental investigation of thermohydrologic processes in a partially saturated, fractured porous medium  

Energy Technology Data Exchange (ETDEWEB)

The performance of a geologic repository for high-level nuclear waste will be influenced to a large degree by thermohydrologic phenomena created by the emplacement of heat-generating radioactive waste. The importance of these phenomena is manifest in that they can greatly affect the movement of moisture and the resulting transport of radionuclides from the repository. Thus, these phenomena must be well understood prior to a definitive assessment of a potential repository site. An investigation has been undertaken along three separate avenues of analysis: (i) laboratory experiments, (ii) mathematical models, and (iii) similitude analysis. A summary of accomplishments to date is as follows. (1) A review of the literature on the theory of heat and mass transfer in partially saturated porous medium. (2) A development of the governing conservation and constitutive equations. (3) A development of a dimensionless form of the governing equations. (4) A ...

1993-07-01

456

Surface physics with cold and thermal neutron reflectometry. Progress report, April 1, 1991--September 30, 1993  

Energy Technology Data Exchange (ETDEWEB)

Within the past two and one half years of the project ``Surface Physics With Cold and Thermal Neutron Reflectometry`` a new thermal neutron reflectometer was constructed at the Rhode Island Nuclear Science Center (RINSC). It was used to study various liquid and solid surfaces. Furthermore, neutron reflection experiments were be un at different laboratories in collaboration with Dr. G.P. Fetcher (at Argonne National Laboratory), Dr. T. Russell (IBM Almaden) and Drs. S.K. Satija and A. Karim (at the National Institute for Standards and Technology). The available resources allowed partial construction of an imaging system for ultracold neutrons. It is expected to provide an extremely high resolution in momentum and energy transfer in surface studies using neutron reflectometry. Much of the work reported here was motivated by the possibility of later implementation at the planned Advanced Neutron Source at Oak Ridge. In a ...

1993-09-01

457

Radiant{trademark} Liquid Radioisotope Intravascular Radiation Therapy System  

Energy Technology Data Exchange (ETDEWEB)

RADIANT{trademark} is manufactured by United States Surgical Corporation, Vascular Therapies Division, (formerly Progressive Angioplasty Systems). The system comprises a liquid {beta}-radiation source, a shielded isolation/transfer device (ISAT), modified over-the-wire or rapid exchange delivery balloons, and accessory kits. The liquid {beta}-source is Rhenium-188 in the form of sodium perrhenate (NaReO{sub 4}), Rhenium-188 is primarily a {beta}-emitter with a physical half-life of 17.0 hours. The maximum energy of the {beta}-particles is 2.1 MeV. The source is produced daily in the nuclear pharmacy hot lab by eluting a Tungsten-188/Rhenium-188 generator manufactured by Oak Ridge National Laboratory (ORNL). Using anion exchange columns and Millipore filters the effluent is concentrated to approximately 100 mCi/ml, calibrated, and loaded into the (ISAT) which is subsequently transported to the cardiac catheterization ...

1998-01-16

458

Laser eye protection. Interim report, July 1989-January 1990  

Energy Technology Data Exchange (ETDEWEB)

Laser applications have proliferated in recent years and, as to be expected, their presence is no longer confined to the laboratory or places where access to their radiation can be easily controlled. One obvious application where this is so is in military operations where various devices such as laser range finders, target designators, and secure communications equipment elevate the risk of exposure, specifically eye exposure, to unacceptable levels. Although the need for eye protection in the laboratory and other controlled areas has been appreciated since the invention of the laser, the use of lasers in circumstances where safety or the risk of temporary loss of vision, which can not always be ensured by administrative procedures, has made adequate eye protection essential. It is the critical nature of many military operations that has driven the search for eye protection against both nuclear and laser radiation. At the ...

1990-01-01

459

Construction of a open-quotes black neutron detectorclose quotes at the University of Massachusetts-Lowell Accelerator Laboratory  

International Nuclear Information System (INIS)

In many experiments involving fast neutrons generated in nuclear reactions initiated by accelerator produced charged particle beams, it is important to be able to determine accurately the neutron yield from the target. A detector suitable for such applications should have: a constant efficiency over a large energy range; a fast time response; and the ability to discriminate between gamma rays and neutrons. The authors have constructed a open-quotes black neutron detectorclose quotes based on the design of Poenitz that has these characteristics. At the Lowell Van de Graaff accelerator laboratory neutrons are produced via the "7Li(p,n)"7Be reaction using a pulsed proton beam which impinges on metallic lithium targets. The pulsed beam enables the detector to be used in a time-of-flight spectrometer. Use of BC501 liquid scintillator permits neutron-gamma discrimination. The scintillator is viewed by five RCA 48796 photo tubes. The detector is ...

1992-03-16

460

A CANDU utility perspective on using world experience to manage Alloy 800 SG tube degradation  

Energy Technology Data Exchange (ETDEWEB)

In response to European operating experience regarding Alloy 800 steam generator (SG) tube cracking, New Brunswick Power Nuclear (NBPN) recognized two important shortcomings in the industry SG technical support framework. First, information exchange networks between utilities with Alloy 800 SG tubing should be strengthened. Second and more importantly, there is a need for consistent industry guidance for Alloy 800 SG tubing degradation management, supported by clear technical bases. It is NBPN's perspective that this guidance can be improved immediately using the extensive amount of laboratory and field data that is available for Alloys 600, 690, and 800, and EPRI methodology developed to predict the performance of Alloy 690. NBPN has initiated the development of a performance-based inspection plan. This effort is based on demonstrated improvement factors for Alloy 800, defined by the EPRI approach, and described in this paper. This ...

2007-07-01

461

A CANDU utility perspective on using world experience to manage Alloy 800 SG tube degradation  

International Nuclear Information System (INIS)

In response to European operating experience regarding Alloy 800 steam generator (SG) tube cracking, New Brunswick Power Nuclear (NBPN) recognized two important shortcomings in the industry SG technical support framework. First, information exchange networks between utilities with Alloy 800 SG tubing should be strengthened. Second and more importantly, there is a need for consistent industry guidance for Alloy 800 SG tubing degradation management, supported by clear technical bases. It is NBPN's perspective that this guidance can be improved immediately using the extensive amount of laboratory and field data that is available for Alloys 600, 690, and 800, and EPRI methodology developed to predict the performance of Alloy 690. NBPN has initiated the development of a performance-based inspection plan. This effort is based on demonstrated improvement factors for Alloy 800, defined by the EPRI approach, and described in this paper. This approach is ...

2007-08-19

462

{sup 99m}Tc generator preparation using (n, {gamma}){sup 99}Mo produced ex-natural molybdenum  

Energy Technology Data Exchange (ETDEWEB)

Theoretical assessment on the chromatographic {sup 99m}Tc generator preparation using (n, {gamma}) {sup 99}Mo produced ex-natural molybdenum was carried out. The relationship between the neutron flux for MoO{sub 3} target activation, Mo-content or Mo adsorption capacity of column packing material, {sup 99m}Tc pertechnetate concentration and/or {sup 99m}Tc radioactivity of eluate was established. The reasonably lower limit of neutron flux of reactor and Molybdenum content of column packing material were found out to estimate the production of portable chromatographic generators available for nuclear medicine application. The concentration of {sup 99m}Tc pertechnetate eluate of low {sup 99m}Tc concentration using the column elution technique was also evaluate theoretically and conducted successfully in practice. Three options of {sup 99m}Tc generator using Titanium-Molybdate, Zirconium-Molybdate and Zirconium Oxide as ...

2003-03-01

463

INTRINSIC DOSIMETRY: A POTENTIAL NEW TOOL FOR NUCLEAR FORENSICS INVESTIGATIONS  

International Nuclear Information System (INIS)

Thermoluminescence (TL) dosimetry was used to measure dose effects on the raw stock material of borosilicate container glass from different geographical locations. Effects were studied at times up to 60 days post-irradiation at doses from 0.15 to 20 Gy. The minimum detectable dose using this technique was estimated to be 0.15 Gy which is roughly equivalent to a 24 hr irradiation 1 cm from a 50 ng source of 60Co. Two peaks were identified in the TL glow curve, a relatively unstable peak around 125 C and a more stable peak around 225 C. Differences in TL glow curve shape and intensity were also observed for the glasses from different geographical origins. We investigate radiation induced defects in glass to further develop the technique of intrinsic dosimetry - the measurement of the total absorbed dose received by the walls of a container holding radioactive material. Intrinsic dosimetry is intended to be used as an interrogation tool to provide ...

2010-07-11

464

Determination of americium in plutonium based nuclear fuel materials: An assessment of different methodologies  

International Nuclear Information System (INIS)

Determination of americium (Am) is one of the requirements of chemical quality assurance of plutonium (Pu) bearing fuel materials. Though many methods are published for determining Am at picogram to femtogram levels in environmental and biological matrices, yet a few of them are used routinely for Pu based nuclear fuel samples. This paper gives a brief summary of the different analytical methods available and presents results of our experiments on the determination of Am in Pu bearing fuels using gamma spectroscopy. The methods utilizing gamma emissions from "2"4"1Am and Pu isotopes are fast as they do not involve chemical separation of Pu and Am, do not require an accurate knowledge of the efficiency values of the detector systems and are not dependent on the availability of a radiometric standard for "2"4"1Am. In addition, for aged Pu samples containing large amounts of "2"4"1Am, there is no need for dilution and this reduces the volume of ...

2010-11-15

465

Control of population dose equivalent from naturally occurring radionuclides in building materials  

International Nuclear Information System (INIS)

Naturally occurring radionuclides in building materials are a source of external and interal radiation exposure to essentially the entire US population. Although detailed data are not available, estimates are that the average contribution from such sources to the external dose equilvaent rate in brick and masonry houses is about 5 to 10 mrem/year. For critical population groups, values reported in the literature for the contribution from such sources range up to a hundred mrem/year or more. Dose equivalent rates to the lungs are even higher and, for abnormal situations, it would appear that control measures, either on a voluntary or mandatory (legislative) basis should be considered. Such measures include: (1) material substitution; (2) improved manufacturing standards; (3) changes in basic building designs; (4) application of surface sealants; and (5) increased ventilation accompanied by processes for the adsorption and/or filtration of ...

466

On important matters (fire protection) related to No. 3 plant in the Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., No. 2 plant in the Tsuruga Power Station, Japan Atomic Power Co., and No. 2 plant in the Sendai Nuclear Power Station, Kyushu Electric Power Co., Inc  

International Nuclear Information System (INIS)

The Nuclear Safety Commission acknowledged the policy of the Agency of Natural Resources and Energy to cope with these important matters on August 8, 1984. The main contents of the investigation and deliberation were as follows, As to the prevention of the occurrence of fires, the prevention of the leak and spread of inflammable liquid and gas, the installation of protective relays and so on, the use of incombustible materials and aseismatic design and the installation of lightning arresters. As to the detection of fires and fire fighting, the proper selection and arrangement of fire detectors and extinguishers, the extinguishers which do not harm the safety function of structures and equipment, and the extinguishers which are not affected by natural phenomena. As to the reduction of the effect of fires, the proper installation of fire walls and extinguishers, and the high temperature shut off of nuclear reactors which is ...

1985-01-01

467

Nuclear incident monitor criticality alarm instrument for the Savannah River Site: Technical manual  

Energy Technology Data Exchange (ETDEWEB)

The Savannah River Site is a Department of Energy facility. The facility stores, processes, and works with fissionable material at a number of locations. Technical standards and US Department of Energy orders, require these locations to be monitored by criticality alarm systems under certain circumstances. The Savannah River Site calls such instruments Nuclear Incident Monitors or NIMs. The Sole purpose of the Nuclear Incident Monitor is to provide an immediate evacuation signal in the case of an accidental criticality in order to minimize personnel exposure to radiation. The new unit is the third generation Nuclear Incident Monitor at the Savannah River Site. The second generation unit was developed in 1979. It was designed to eliminate vacuum-tube circuits, and was the first solid state NIM at SRS. The major design objectives of the second generation NIM were to improve reliability and reduce ...

1996-05-21

468

Leak-Before-Break: Further developments in regulatory policies and supporting research  

Energy Technology Data Exchange (ETDEWEB)

The fourth in a series of international Leak-Before-Break (LBB) Seminars supported in part by the US Nuclear Regulatory Commission was held at the National Central Library in Taipei, Taiwan on May 11 and 12, 1989. The seminar updated the international polices and supporting research on LBB. Attendees included representatives from regulatory agencies, electric utilities, nuclear power plant fabricators, research organizations, and academic institutions. Regulatory policy was the subject of presentations by Mr. G. Arlotto (US NRC, USA) Dr. B. Jarman (AECB, Canada), Dr.P. Milella (ENEA-DISP, Italy), Dr. C. Faidy (EDF/Septen, France ), and Dr. K. Takumi (NUPEC, Japan). A paper by Mr. K. Wichman and Mr. A. Lee of the US NRC Office of Nuclear Reactor Regulation is included as background material to these proceedings; it discusses the history and status of LBB applications in US nuclear ...

1990-02-01

469

Institutt for Energiteknikk - Annual Report 1994  

Energy Technology Data Exchange (ETDEWEB)

Work at Institutt for energiteknikk (IFE) comprises both nuclear and non-nuclear activities. The main nuclear program is centered on the Halden Reactor Project. In 1958, the first Halden Reactor Project Agreement was signed by organisations representing 12 European countries. During 1994 France became a full member and associate membership was established with Russia. Accordingly, 16 countries were participating in the Project by the end of the year. The objectives have evolved from being simply a demonstration of the operation of a boiling heavy-water reactor to becoming a substantial research and development programme covering the domains of human-machine interaction, fuel behaviour, materials testing, water chemistry, and instrumentation. In 1994, significant progress was achieved in all of the areas addressed by the project, including the re-instrumentation of irradiated fuel rods, fission gas ...

1995-12-01

470

Environmental impacts of nuclear and coal-fired power plants  

International Nuclear Information System (INIS)

The current situation in the development of nuclear power in the world and in Czechoslovakia is briefly outlined and the possibilities are discussed of alternative energy resources. The environmental impact is described of conventional power plants firing coal; sulphur and nitrogen oxides are mentioned and their environmental impacts shown. Their quantities and the quantities of other gaseous, liquid and soid wastes produced by coal power plants are given. Annual estimates are presented of radioactive material emissions; trace amount emissions of toxic metals and their ecological risks are shown. Concern over the increasing concentration of CO_2 in the atmosphere is voiced. For nuclear power plants, the amount of radionuclides in stack emission and of those released into water flows is tabulated. Their effect on the aqueous ecosystem is characterized as is thermal pollution of water flows and the environmental impact of ...

1984-01-01

471

Application of a finite element method to leak before break (LBB) of a heat exchanger  

International Nuclear Information System (INIS)

The leak before break (LBB) concept is difficult to apply to a structure with a thin tube that is immersed in a water environment. A heat exchanger in a nuclear power plant is such a structure. The present paper addresses an application of the LBB concept to a heat exchanger in a nuclear power plant. The minimum leaked coolant amount containing the radioactive material which can activate the radiation detector device installed near the heat exchanger is assumed. The postulated initial flaw size that cannot grow to the critical flaw size within the time period to activate the radiation detector is justified. In this case, the radiation detector can activate the warning signal caused by coolant leakage from initially postulated flaws of the heat exchanger. The nuclear plant can safely shutdown when this occurs. Since the postulated initial flaw size can not grow to the critical flaw size, the structural ...

2003-08-17

472

Advanced nuclear data for radiation-damage calculations  

Energy Technology Data Exchange (ETDEWEB)

Accurate calculations of atomic displacement damage in materials exposed to neutrons require detailed spectra for primary recoil nuclei. Such data are not available from direct experimental measurements. Moreover, they cannot always be computed accurately starting from evaluated nuclear data libraries such as ENDF/B-V that were developed primarily for neutron transport applications, because these libraries lack detailed energy-and-angle distributions for outgoing charged particles. Fortunately, a new generation of nuclear model codes is now available that can be used to fill in the missing spectra. One example is the preequilibrium statistical-model code GNASH. For heating and damage applications, a supplementary code called RECOIL has been developed. RECOIL uses detailed reaction data from GNASH, together with angular distributions based on Kalbach-Mann systematics to compute the energy and angle distributions of recoil ...

1983-01-01

473

Adaptation of COSYMA and assessment of accident consequences for Daya Bay nuclear power plant in China  

International Nuclear Information System (INIS)

The program package COSYMA for assessing the radiological and economic consequences of nuclear accidents, developed with the support of the European Commission, was applied to investigate the health effects and risks from accidental releases of radioactive material from the Daya Bay nuclear power plant. Population distribution data in the range of 80 km around the site and hourly meteorological data for the year 1985 representative of accident consequence analysis were used. The results showed that early effects are more important at distances closer to the site, while the number of fatal cancers is closely related to the population density and the late effects are still important at distances larger than 50 km from the site. The mean annual expected values for early mortality and late mortality estimated for the population within a circle of 80 km around the Daya Bay nuclear power plant are 4.5x10"-"3 ...

2000-05-01

474

Hydrogen storage in nano-structured carbon materials  

Energy Technology Data Exchange (ETDEWEB)

Full text of publication follows: Energy and environment are two major concerns in our modern society due to the coming shortage in fossil energy sources and the growing of greenhouse gas emissions. The challenge for the coming years is to discover new energy resources and to develop devices that are compatible with a sustainable development and generate few (or zero) emission. One of these devices is the fuel cell feed by hydrogen, whose application fields are very large. In particular, the proton exchange membrane fuel cell (PEMFC) is the most realistic device for automotive application. However, hydrogen storage remains one of the most important challenges regarding its development. Although different techniques are available for storing hydrogen, no ideal solution has been found yet. Compression needs elaborated tanks in shape for supporting high pressures, liquefaction requires an expensive hydrogen cooling and adapted tanks. Chemical storage by hydrides imposes heavy devices. A ...

2005-07-01

475

Hydrogen storage in nano-structured carbon materials  

Energy Technology Data Exchange (ETDEWEB)

Full text of publication follows: Energy and environment are two major concerns in our modern society due to the coming shortage in fossil energy sources and the growing of greenhouse gas emissions. The challenge for the coming years is to discover new energy resources and to develop devices that are compatible with a sustainable development and generate few (or zero) emission. One of these devices is the fuel cell feed by hydrogen, whose application fields are very large. In particular, the proton exchange membrane fuel cell (PEMFC) is the most realistic device for automotive application. However, hydrogen storage remains one of the most important challenges regarding its development. Although different techniques are available for storing hydrogen, no ideal solution has been found yet. Compression needs elaborated tanks in shape for supporting high pressures, liquefaction requires an expensive hydrogen cooling and adapted tanks. Chemical storage by hydrides imposes heavy devices. A ...

2005-07-01

476

Radioactive targets for neutron-induced cross section measurements  

Science.gov (United States)

Measurements using radioactive targets are important for the determination of key reaction path ways associated with the synthesis of the elements in nuclear astrophysics (sprocess), advanced fuel cycle initiative (transmutation of radioactive waste), and stockpile stewardship. High precision capture cross-section measurements are needed to interpret observations, predict elemental or isotopical ratios, and unobserved abundances. There are two new detector systems that are presently being commissioned at Los Alamos National Laboratory for very precise measurements of (n,{gamma}) and (n,f) cross-sections using small quantities of radioactive samples. DANCE (Detector for Advanced Neutron-Capture Experiments), a 4 {pi} gamma array made up of 160 BaF{sub 2} detectors, is designed to measure neutron capture cross-sections of unstable nuclei in the low-energy range (thermal to {approx}500 keV). The high granularity and high detection efficiency of ...

2004-01-01

478

Nuclear moments and changes in rms-radii of neutron-deficient silver isotopes  

International Nuclear Information System (INIS)

... nuclear electric moments nuclear magnetic moments nuclear radii quadrupole

1987-03-23

480

Packaging materials for use in radiation processing of foods  

International Nuclear Information System (INIS)

In radiation processing of food, the product often has to be prepackaged to prevent microbial recontamination during and after irradiation. The packaging material is exposed to radiation during radiation processing and radiation stability is a key consideration in the selection of packaging materials. The effects of ionizing radiation on many food packaging materials at the dose levels recommended for food precessing can be minimized by selecting appropriate radiation resistant materials. It is important to select materials in which chemicals formed as a result of the radiation treatment do not migrate and interact with the food, affecting its organoleptic and toxicological aspects. It is also important to select materials in which the physical properties are not altered to the extent they cannot resist damage during commercial production, shipment and storage. ...

481

Calibration curves of a PGNAA system for cement raw material analysis using the MCNP code  

Energy Technology Data Exchange (ETDEWEB)

In large samples, the {gamma}-ray count rate of a prompt gamma neutron activation analysis system is a multi-variable function of the elemental dry composition, density, water content and thickness of the material. The experimental calibration curves require tremendous laboratory work, using a great number of standards with well-known compositions. Although a Monte Carlo simulation study does not avoid the experimental calibration work, it reduces the number of experimental calibration standards. This paper is part of a feasibility study for a PGNAA system for on-line continuous characterisation of cement raw material conveyed on a belt (Oliveira, C., Salgado, J. and Carvalho, F. G. (1997) Optimisation of PGNAA instrument design for cement raw materials using the MCNP code. J. Radioanal. Nucl. Chem. 216(2), 191-198; Oliveira, C., Salgado, J., Goncalves, I. F., Carvalho, F. G. and Leitao, F. (1997a) A ...

1998-12-01