The effect of repeated measurements and working memory on the most comfortable level in the ANL test.

Science.gov (United States)

Brännström, K Jonas; Olsen, Steen Østergaard; Holm, Lucas; Kastberg, Tobias; Ibertsson, Tina

2014-11-01

To study the effect of a large number of repetitions on the most comfortable level (MCL) when doing the acceptable noise level (ANL) test, and explore if MCL variability is related to central cognitive processes. Twelve MCL repetitions were measured within the ANL test using interleaved methodology during one session using a non-semantic version. Phonological (PWM) and visuospatial working memory (VSWM) was measured. Thirty-two normal-hearing adults. Repeated measures ANOVA, intraclass correlations, and the coefficient of repeatability (CR) were used to assess the repeatability. Repeated measures ANOVA and CR indicated poor agreement between the two first repetitions. After excluding the first repetition, analyses showed that the MCL in the ANL test is reliable. A negative association was found between PWM and MCL variability indicating that subjects with higher PWM show less variability. The findings suggest that, after excluding the first repetition, the MCL in the ANL test is reliable. A single repetition of the MCL in the ANL test should be avoided. If an interleaved methodology is used, a single ANL repetition should be added prior to the actual testing. The findings also suggest that MCL variability is associated to PWM but not VSWM.

Recommended documentation for computer users at ANL

Energy Technology Data Exchange (ETDEWEB)

Heiberger, A.A.

1992-04-01

Recommended Documentation for Computer Users at ANL is for all users of the services available from the Argonne National Laboratory (ANL) Computing and Telecommunications Division (CTD). This document will guide you in selecting available documentation that will best fill your particular needs. Chapter 1 explains how to use this document to select documents and how to obtain them from the CTD Document Distribution Counter. Chapter 2 contains a table that categorizes available publications. Chapter 3 gives descriptions of the online DOCUMENT command for CMS, and VAX, and the Sun workstation. DOCUMENT allows you to scan for and order documentation that interests you. Chapter 4 lists publications by subject. Categories I and IX cover publications of a general nature and publications on telecommunications and networks respectively. Categories II, III, IV, V, VI, VII, VIII, and X cover publications on specific computer systems. Category XI covers publications on advanced scientific computing at Argonne. Chapter 5 contains abstracts for each publication, all arranged alphabetically. Chapter 6 describes additional publications containing bibliographies and master indexes that the user may find useful. The appendix identifies available computer systems, applications, languages, and libraries.

DOE/ANL/HTRI heat exchanger tube vibration data bank

Energy Technology Data Exchange (ETDEWEB)

Halle, H.; Chenoweth, J.M.; Wambsganss, M.W.

1981-01-01

This addendum to the DOE/ANL/HTRI Heat Exchanger Tube Vibration Data Bank includes 16 new case histories of field experiences. The cases include several exchangers that did not experience vibration problems and several for which acoustic vibration was reported.

Verification of WIMS-ANL to be used as supporting code for WIMS-CANDU development

Energy Technology Data Exchange (ETDEWEB)

Chung, Dai Hai; Kim, Won Young; Park, Joo Hwan

2007-08-15

The lattice code WIMS-ANL has been tested in order to assess it for the qualification to be used as a supporting code to aide the WIMS-CANDU development. A series of calculations have been performed to determine lattice physics parameters such as multiplication factors, isotopic number densities and coolant void reactivity. The WIMS-ANL results are compared with the predictions of WIMS-AECL/D4/D5 and PPV (POWDERPUFS-V), and the comparisons indicate that WIMS-ANL can be used not only as a supporting code to aide the WIMS-CANDU development, but also as a starting source for the study of developing detailed model that could delineate the realistic situations as it might occur during LOCA such as the asymmetric flux distribution across lattice cell.

Survey of ANL organization plans for word processors, personal computers, workstations, and associated software. Revision 3

Energy Technology Data Exchange (ETDEWEB)

Fenske, K.R.

1991-11-01

The Computing and Telecommunications Division (CTD) has compiled this Survey of ANL Organization Plans for Word Processors, Personal Computers, Workstations, and Associated Software to provide DOE and Argonne with a record of recent growth in the acquisition and use of personal computers, microcomputers, and word processors at ANL. Laboratory planners, service providers, and people involved in office automation may find the Survey useful. It is for internal use only, and any unauthorized use is prohibited. Readers of the Survey should use it as a reference that documents the plans of each organization for office automation, identifies appropriate planners and other contact people in those organizations, and encourages the sharing of this information among those people making plans for organizations and decisions about office automation. The Survey supplements information in both the ANL Statement of Site Strategy for Computing Workstations and the ANL Site Response for the DOE Information Technology Resources Long-Range Plan.

VIM: a continuous energy Monte Carlo code at ANL

International Nuclear Information System (INIS)

Blomquist, R.N.; Lell, R.M.; Gelbard, E.M.

1980-01-01

The continuous-energy Monte Carlo neutron transport code VIM and its auxiliaries are briefly described. The ENDF/B cross section data processing procedure is summarized and its benchmarking against MC 2 -2 is reviewed. Several representative applications at ANL are described, including fast critical assembly benchmark calculations and STF and TREAT Upgrade benchmark calculations. 2 figures

Superfund record of decision (EPA Region 10): Idaho National Engineering Lab (USDOE) (ANL-W), Operable Unit 9-04, Idaho Falls, ID, September 29, 1998

International Nuclear Information System (INIS)

1998-10-01

The Argonne National Laboratory-West (ANL-W) Waste Area Group 9 (WAG 9) is one of the ten Idaho National Engineering and Environmental Laboratory (INEEL) WAGs identified in the Federal Facility Agreement and Consent Order (FFA/CO). The eight affected areas at ANL-W include the Sanitary Sewage Lagoons (ANL-04), Industrial Waste Pond, Ditches A, Ditch B, (all from ANL-01), Main Cooling Tower Blowdown Ditch (ANL-01A), Interceptor Canal-Canal and-Mound (sub-portions of ANL-09), and the Industrial Waste Lift Station Discharge Ditch (ANL-35). The major components of the selected remedy for ANL-W are: Completion of phytoremediation workplan for the field-scale testing; Conducting a field-scale phytoremediation test of selected plant species at the sites that pose unacceptable risks; Determining the effectiveness and implementability of phytoremediation based on results of field-scale testing; Collecting soil and plant samples after a two-year field season to be used to determine the effectiveness of phytoremediation on the ANL-W soils; Harvesting, compacting, incinerating, and disposing of the above- and below-ground plant matter that will be sent to a permitted landfill; Continuing the planting, harvesting process for phytoremediation only if completion of the two-year field-scale testing is successful; Installing access restrictions consisting of fences, bird netting, and posting warning signs; Review of the remedy no less than every five years after the RAOs have been met until the year 2098; and Implementing DOE controls which limit residential land use for at least 100 years from now (2098)

Recommended documentation for computer users at ANL. Revision 3

Energy Technology Data Exchange (ETDEWEB)

Heiberger, A.A.

1992-04-01

Recommended Documentation for Computer Users at ANL is for all users of the services available from the Argonne National Laboratory (ANL) Computing and Telecommunications Division (CTD). This document will guide you in selecting available documentation that will best fill your particular needs. Chapter 1 explains how to use this document to select documents and how to obtain them from the CTD Document Distribution Counter. Chapter 2 contains a table that categorizes available publications. Chapter 3 gives descriptions of the online DOCUMENT command for CMS, and VAX, and the Sun workstation. DOCUMENT allows you to scan for and order documentation that interests you. Chapter 4 lists publications by subject. Categories I and IX cover publications of a general nature and publications on telecommunications and networks respectively. Categories II, III, IV, V, VI, VII, VIII, and X cover publications on specific computer systems. Category XI covers publications on advanced scientific computing at Argonne. Chapter 5 contains abstracts for each publication, all arranged alphabetically. Chapter 6 describes additional publications containing bibliographies and master indexes that the user may find useful. The appendix identifies available computer systems, applications, languages, and libraries.

[Forest lighting fire forecasting for Daxing'anling Mountains based on MAXENT model].

Science.gov (United States)

Sun, Yu; Shi, Ming-Chang; Peng, Huan; Zhu, Pei-Lin; Liu, Si-Lin; Wu, Shi-Lei; He, Cheng; Chen, Feng

2014-04-01

Daxing'anling Mountains is one of the areas with the highest occurrence of forest lighting fire in Heilongjiang Province, and developing a lightning fire forecast model to accurately predict the forest fires in this area is of importance. Based on the data of forest lightning fires and environment variables, the MAXENT model was used to predict the lightning fire in Daxing' anling region. Firstly, we studied the collinear diagnostic of each environment variable, evaluated the importance of the environmental variables using training gain and the Jackknife method, and then evaluated the prediction accuracy of the MAXENT model using the max Kappa value and the AUC value. The results showed that the variance inflation factor (VIF) values of lightning energy and neutralized charge were 5.012 and 6.230, respectively. They were collinear with the other variables, so the model could not be used for training. Daily rainfall, the number of cloud-to-ground lightning, and current intensity of cloud-to-ground lightning were the three most important factors affecting the lightning fires in the forest, while the daily average wind speed and the slope was of less importance. With the increase of the proportion of test data, the max Kappa and AUC values were increased. The max Kappa values were above 0.75 and the average value was 0.772, while all of the AUC values were above 0.5 and the average value was 0. 859. With a moderate level of prediction accuracy being achieved, the MAXENT model could be used to predict forest lightning fire in Daxing'anling Mountains.

ANL results for LMFR reactivity coefficients benchmark

International Nuclear Information System (INIS)

Hill, Robert

2000-01-01

The fast reactor analysis methods developed at ANL were extensively tested in ZPR and ZPPR experiments, applied to EBR-2 and FFTF test reactors. The basic nuclear data library used was ENDF/B-V.2 with the ETOE-2 data processing code and the ENDF/B-VI. Multigroup constants were generated by Monte Carlo code MCNP 2 -2. Neutron flux calculation were done by DIF3D code applying neutron diffusion theory and finite difference method. The results obtained include basic parameters; fuel and structure regional Doppler coefficients; geometry expansion fuel coefficients; kinetics parameters. In general, agreement between phase 1 and 2 results were excellent

The effect of extending high-frequency bandwidth on the acceptable noise level (ANL) of hearing-impaired listeners.

Science.gov (United States)

Johnson, Earl; Ricketts, Todd; Hornsby, Benjamin

2009-01-01

This study examined the effects of extending high-frequency bandwidth, for both a speech signal and a background noise, on the acceptable signal-to-noise ratio (SNR) of listeners with mild sensorineural hearing loss through utilization of the Acceptable Noise Level (ANL) procedure. In addition to extending high-frequency bandwidth, the effects of reverberation time and background noise type and shape were also examined. The study results showed a significant increase in the mean ANL (i.e. participants requested a better SNR for an acceptable listening situation) when high-frequency bandwidth was extended from 3 to 9 kHz and from 6 to 9 kHz. No change in the ANL of study participants was observed as a result of isolated modification to reverberation time or background noise stimulus. An interaction effect, however, of reverberation time and background noise stimulus was demonstrated. These findings may have implications for future design of hearing aid memory programs for listening to speech in the presence of broadband background noise.

Disposal criticality analysis for the ceramic waste form from the ANL electrometallurgical treatment process - Internal configurations

International Nuclear Information System (INIS)

Lell, R. M.; Agrawal, R.; Morris, E. E.

2000-01-01

Criticality safety issues for disposal of the ANL ceramic waste were examined for configurations within the waste package. Co-disposal of ceramic waste and DOE spent fuel is discussed briefly; co-disposal of ANL ceramic and metal wastes is examined in detail. Calculations indicate that no significant potential for criticality exists until essentially all of the important neutron absorbers are flushed from the degraded ceramic waste. Even if all of the neutron absorbers are removed from the ceramic waste rubble, the package remains far subcritical if the blended salts used in ceramic waste production have an initial U-235 enrichment below 40%

Permanent Closure of MFC Biodiesel Underground Storage Tank 99ANL00013

Energy Technology Data Exchange (ETDEWEB)

Kerry L. Nisson

2012-10-01

This closure package documents the site assessment and permanent closure of the Materials and Fuels Complex biodiesel underground storage tank 99ANL00013 in accordance with the regulatory requirements established in 40 CFR 280.71, “Technical Standards and Corrective Action Requirements for Owners and Operators of Underground Storage Tanks: Out-of-Service UST Systems and Closure.”

ANL/CANTIA code for steam generator tube integrity assessment

International Nuclear Information System (INIS)

Revankar, S.T.; Wolf, B.; Majumdar, S.; Riznic, J.R.

2009-01-01

Steam generator (SG) tubes have an important safety role in CANDU type reactors and Pressurized Water Reactors (PWR) because they constitute one of the primary barriers between the radioactive and non-radioactive sides of the nuclear plant. The SG tubes are susceptible to corrosion and damage. A failure of a single steam generator tube, or even a few tubes, would not be a serious safety-related event in a CANDU reactor. The leakage from a ruptured tube is within makeup capacity of the primary heat transport system, so that as long as the operator takes the correct actions, the off-site consequences will be negligible. A sufficient safety margin against tube rupture used to be the basis for a variety of maintenance strategies developed to maintain a suitable level of plant safety and reliability. Several through-wall flaws may remain in operation and potentially contribute to the total primary-to-secondary leak rate. Assessment of the conditional probabilities of tube failures, leak rates, and ultimately risk of exceeding licensing dose limits has been used for steam generator tube fitness-for-service assessment. The advantage of this type of analysis is that it avoids the excessive conservatism typically present in deterministic methodologies. However, it requires considerable effort and expense to develop all of the failure, leakage, probability of detection, and flaw growth distributions and models necessary to obtain meaningful results from a probabilistic model. The Canadian Nuclear Safety Commission (CNSC) recently developed the CANTIA methodology for probabilistic assessment of inspection strategies for steam generator tubes as a direct effect on the probability of tube failure and primary-to-secondary leak rate Recently Argonne National Laboratory has developed tube integrity and leak rate models under Integrated Steam Generator Tube Integrity Program (ISGTIP-2). These models have been incorporated in the ANL/CANTIA code. This paper presents the ANL

ANL site response for the DOE FY1994 information resources management long-range plan

Energy Technology Data Exchange (ETDEWEB)

Boxberger, L.M.

1992-03-01

Argonne National Laboratory's ANL Site Response for the DOE FY1994 Information Resources Management (IRM) Long-Range Plan (ANL/TM 500) is one of many contributions to the DOE information resources management long-range planning process and, as such, is an integral part of the DOE policy and program planning system. The Laboratory has constructed this response according to instructions in a Call issued in September 1991 by the DOE Office of IRM Policy, Plans and Oversight. As one of a continuing series, this Site Response is an update and extension of the Laboratory's previous submissions. The response contains both narrative and tabular material. It covers an eight-year period consisting of the base year (FY1991), the current year (FY1992), the budget year (FY1993), the plan year (FY1994), and the out years (FY1995-FY1998). This Site Response was compiled by Argonne National Laboratory's Computing and Telecommunications Division (CTD), which has the responsibility to provide leadership in optimizing computing and information services and disseminating computer-related technologies throughout the Laboratory. The Site Response consists of 5 parts: (1) a site overview, describes the ANL mission, overall organization structure, the strategic approach to meet information resource needs, the planning process, major issues and points of contact. (2) a software plan for DOE contractors, Part 2B, Software Plan FMS plan for DOE organizations, (3) computing resources telecommunications, (4) telecommunications, (5) printing and publishing.

ANL site response for the DOE FY1994 information resources management long-range plan

Energy Technology Data Exchange (ETDEWEB)

Boxberger, L.M.

1992-03-01

Argonne National Laboratory`s ANL Site Response for the DOE FY1994 Information Resources Management (IRM) Long-Range Plan (ANL/TM 500) is one of many contributions to the DOE information resources management long-range planning process and, as such, is an integral part of the DOE policy and program planning system. The Laboratory has constructed this response according to instructions in a Call issued in September 1991 by the DOE Office of IRM Policy, Plans and Oversight. As one of a continuing series, this Site Response is an update and extension of the Laboratory`s previous submissions. The response contains both narrative and tabular material. It covers an eight-year period consisting of the base year (FY1991), the current year (FY1992), the budget year (FY1993), the plan year (FY1994), and the out years (FY1995-FY1998). This Site Response was compiled by Argonne National Laboratory`s Computing and Telecommunications Division (CTD), which has the responsibility to provide leadership in optimizing computing and information services and disseminating computer-related technologies throughout the Laboratory. The Site Response consists of 5 parts: (1) a site overview, describes the ANL mission, overall organization structure, the strategic approach to meet information resource needs, the planning process, major issues and points of contact. (2) a software plan for DOE contractors, Part 2B, ``Software Plan FMS plan for DOE organizations, (3) computing resources telecommunications, (4) telecommunications, (5) printing and publishing.

ANL progress in developing an LEU target and process for Mo-99 production: Cooperation with CNEA

International Nuclear Information System (INIS)

Gelis, A.V.; Vandegrift, G.F.; Aase, S.B.; Bakel, A.J.; Falkenberg, J.R.; Regalbuto, M.C.; Quigley, K.J.

2003-01-01

The primary mission of the Reduced Enrichment in Research and Test Reactors (RERTR) Program is to facilitate the conversion of research and test-reactor fuel and targets from high-enriched uranium (HEU) to low-enriched uranium (LEU). One of the current goals at Argonne National Laboratory (ANL) is to assist the Argentine Comision Nacional de Energia Atomica (CNEA) in developing an LEU foil target and a process for 99 Mo production. Specifically addressed in this paper is ANL R and D related to this conversion: (1) designing a prototype production vessel for digesting irradiated LEU foils in alkaline solutions and (2) developing a new digestion method to address all issues related to HEU to LEU conversion. (author)

MATCH package for the ANL three-view geometry program

International Nuclear Information System (INIS)

Gieraltowski, G.F.

1976-02-01

The ANL MATCH package consists of a set of 13 subroutines which are linked to the current 12-foot and 15-foot versions of the ANL TVGP program. Their purpose is to match the tracks from the various measured views to obtain a proper matched set of tracks to be processed by TVGP. The MATCH package can effectively handle up to 20 tracks per event measured in 2 or 3 views and, in cases of ambiguous match solutions, allow up to 10 match ambiguities. A basic assumption made is that the same number of tracks is measured in each view. MATCH can work in either two or three measured views with the assumption that, if only two views are measured, the last point measured on each track is a good representation of the true end-point of the track. This is not to say that, if this assumption is false, that MATCH cannot obtain a match solution. It is true, however, that the probability of obtaining a match solution is inversely proportional both to the number of tracks per vertex and to the momentum of the tracks. Current uses of MATCH are in obtaining match solutions for two-view K - p (6.5 GeV/c) events measured on POLLY III and in obtaining match solutions for events with large numbers of tracks (3 to 10) produced by an anti ν p interaction in the FNAL 15-foot bubble chamber with a spectrum of momentum values ranging from 5 to 25 Gev/c

A user's guide to the PLTEMP/ANL code

International Nuclear Information System (INIS)

Kalimullah, M.

2011-01-01

PLTEMP/ANL V4.1 is a FORTRAN program that obtains a steady-state flow and temperature solution for a nuclear reactor core, or for a single fuel assembly. It is based on an evolutionary sequence of ''PLTEMP'' codes in use at ANL for the past 20 years. Fueled and non-fueled regions are modeled. Each fuel assembly consists of one or more plates or tubes separated by coolant channels. The fuel plates may have one to five layers of different materials, each with heat generation. The width of a fuel plate may be divided into multiple longitudinal stripes, each with its own axial power shape. The temperature solution is effectively 2-dimensional. It begins with a one-dimensional solution across all coolant channels and fuel plates/tubes within a given fuel assembly, at the entrance to the assembly. The temperature solution is repeated for each axial node along the length of the fuel assembly. The geometry may be either slab or radial, corresponding to fuel assemblies made of a series of flat (or slightly curved) plates, or of nested tubes. A variety of thermal-hydraulic correlations are available with which to determine safety margins such as Onset-of-Nucleate boiling (ONB), departure from nucleate boiling (DNB), and onset of flow instability (FI). Coolant properties for either light or heavy water are obtained from FORTRAN functions rather than from tables. The code is intended for thermal-hydraulic analysis of research reactor performance in the sub-cooled boiling regime. Both turbulent and laminar flow regimes can be modeled. Options to calculate both forced flow and natural circulation are available. A general search capability is available (Appendix XII) to greatly reduce the reactor analyst's time.

Assessment Using ANL Experiments on Void Fraction in a Vertical Tube

Energy Technology Data Exchange (ETDEWEB)

Han, KyuHyun; Bang, YoungSeok [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2015-05-15

A licensing application of a safety analysis code, SPACE, was submitted and is currently under KINS' review. This code was developed to consider three fluid fields, i.e. liquid, vapor and droplet, for a realistic simulation of accident phenomena. Therefore, there may be a concern that this code could predict different behavior compared to the existing codes. To assess the important performance independently and to compare with prediction results of SPACE might be helpful to regulatory review for identifying validity of the code. The interfacial friction could largely affect prediction of thermal hydraulic phenomena during LOCA or non- LOCA. This paper provides MARS-KS prediction of void fraction experiments in a vertical tube by ANL and compares with SPACE prediction results. It was found that the similar interfacial friction model adopting the drift flux correlations were implemented in both codes. Experimental void fractions of the ANL test presented in this paper correspond to bubbly, slug and churn flow regions. Agreements in general sense between the experiment and the predicted values were identified through calculations. Thus, similar accuracy for this experiment can be expected in SPACE and MARS-KS. It was also shown that drift flux interfacial friction model for intermediate flow channel (diameter of 7cm) is valid.

ANL progress in developing a target and process for converting CNEA Mo-99 production to LEU

International Nuclear Information System (INIS)

Vandegrift, G.F.; Gelis, A.; Aase, S.; Bakel, A.; Freiberg, E.; Conner, C.

2002-01-01

The primary mission of the Reduced Enrichment in Research and Test Reactors (RERTR) Program is to facilitate the conversion of research and test reactor fuel and targets from high-enriched uranium (HEU) to low-enriched uranium (LEU). One of the current goals at Argonne National Laboratory (ANL) is to convert 99 Mo production at Argentine Commission Nacional de Energia Atomica (CNEA) from HEU to LEU targets. Specifically addressed in this paper is ANL R and D related to this conversion: (1) designing a prototype production vessel for digesting irradiated LEU foils in alkaline solutions, (2) developing means to improve digestion efficiency, and (3) modifying ion-exchange processes used in the CNEA recovery and purification of 99 Mo to deal with the lower volumes generated from LEU-foil digestion. (author)

The ANL X6B beamline at NSLS: A versatile facility

International Nuclear Information System (INIS)

Huang, K.G.; Ramanathan, M.; Montano, P.A.; Illinois Univ., Chicago, IL

1994-07-01

We have described the x-ray optics and beamline performance of the ANL X6B beam line at the NSLS. Considerable flexibility has been built into the beam line to accommodate a wide range of x-ray diffraction, scattering, and spectroscopy experiments with various requirements. We presented selected examples of experimental results and showed that with the high intensity, high energy resolution, high-q resolution, and energy tunability, the X6B beam line has become a versatile facility

Status of Striped Hyaena (Hyaena hyaena in Hatay and Şanlıurfa-Turkey

Directory of Open Access Journals (Sweden)

Erol Atay

2017-10-01

Full Text Available In the present work, an 18 month survey, involving face to face interviews with the local people and deployment camera-traps, was carried out on about 600 km2 areas in Turkey. Field surveys and camera-trapping resulted in strong evidences that striped hyenas travel and live around Hatay (Syria border and Şanlıurfa Provinces in Turkey. However, a comprehensive study was not carried out about the status of striped hyenas in this region. Our results showed that striped hyenas were frequently observed around the wasteland and the chicken farm in Hatay Province. Alternatively, they live in small groups in Şanlıurfa Province. Several caves suitable for striped hyenas were identified by footprints, feces and other animal remnants observed in and before those caves. We performed molecular characterization of striped hyenas in Turkey for the first time using Cytb mitochondrial DNA isolated from hair, ear and carcass tissues. Sequences of Cytb DNA sequences from10 different striped hyena samples from Turkey were found to be identical to each other. Comparison of the sequences with the previously reported Cytb sequences, including prehistoric ones, showed that Ctyb gene was highly conserved among the Hyaena hyaena species. During the field surveys we also observed that habitat destruction and fragmentation are detected on high level in the studied regions due to the intensive agricultural areas, settlements and quarries. Illegal hunting, frequent cave usage by shepherds, extensive porcupines hunting, water pollution from olive oil production facilities and highway crashes have been negatively affecting striped hyena population in Hatay and Şanlıurfa regions. It appears that a comprehensive study and protection plan should be exerted to preserve the habitat of striped hyenas.

Development and Validation of the Persian Version of the Acceptable Noise Level (ANL Test in Normal Children Aged 5-8 Years

Directory of Open Access Journals (Sweden)

Abdollah Moossavi

2016-06-01

Full Text Available Background: The goal of the present study was to develop and validate the Persian version of the Acceptable Noise Level (ANL test in normal, Persianspeaking children aged 5-8 years. Methods: This tool-making and non-experimental research was conducted in two stages. In the first stage the proper story was selected and recorded after evaluation of its content validity. In the second stage this test material was administered to a total 181 normal children (97 girls and 84 boys randomly chosen from the population of preschool and primary school children of Tehran (District 5, aged 5-8 years in four age groups to evaluate the reliability of test in order to develop the Persian version of the ANL test and assess its changes during the growth. Lawshe’s method and Cronbach’s alpha coefficient were used to assess the content validity and reliability of the test, respectively. Mann– Whitney U test was used to examine gender differences, and Kruskal-Wallis test was to examine age differences. Results: Test-retest correlation of 0.74 indicated acceptable reliability of the test. Significant differences were found between most of different age groups for the ANL mean scores (P0.05. Conclusion: The study results indicated good validity and reliability of the Persian version of the ANL test in children. Therefore this test can be useful in designing classrooms suitable for 5-8 year-old children of both genders.

ENPEP model enhancements at ANL

International Nuclear Information System (INIS)

Guziel, K.A.

1997-01-01

Argonne National Laboratory (ANL) has been involved in energy and electricity planning analyses for almost 20 years. Their activities include the development of analytical tools and methodologies along with their application to a wide variety of national energy planning studies. The methodologies cover all aspects of energy planning. In response to a request by the US Department of Energy (USDOE) to integrate existing tools into a package that could be distributed to developing countries for their own use, the ENergy and Power Evaluation Program (ENPEP) was developed. The USDOE wanted an all purpose tool that would allow the user to do a complete energy analysis, from demand forecast through primary energy resources allocation to electricity generation system expansion plan and environmental analysis. Since its original development, the ENPEP modules have been improved and enhanced to incorporate advancements in computer hardware and software technology, as well as to correct bugs that were identified in the programs. In cooperation with other organizations (e.g. The World Bank - IBRD - and the International Atomic Energy Agency - IAEA -), the ENPEP package has been used at national, regional and inter-regional training courses, as well as in the conduct of national energy/electricity planning studies. This paper reviews the development of the ENPEP package and the proposed enhancements to the package. (author). 1 fig., 2 tabs

ENPEP model enhancements at ANL

Energy Technology Data Exchange (ETDEWEB)

Guziel, K A [Decision and Information Sciences Div., Argonne National Lab., Argonne, IL (United States)

1997-09-01

Argonne National Laboratory (ANL) has been involved in energy and electricity planning analyses for almost 20 years. Their activities include the development of analytical tools and methodologies along with their application to a wide variety of national energy planning studies. The methodologies cover all aspects of energy planning. In response to a request by the US Department of Energy (USDOE) to integrate existing tools into a package that could be distributed to developing countries for their own use, the ENergy and Power Evaluation Program (ENPEP) was developed. The USDOE wanted an all purpose tool that would allow the user to do a complete energy analysis, from demand forecast through primary energy resources allocation to electricity generation system expansion plan and environmental analysis. Since its original development, the ENPEP modules have been improved and enhanced to incorporate advancements in computer hardware and software technology, as well as to correct bugs that were identified in the programs. In cooperation with other organizations (e.g. The World Bank - IBRD - and the International Atomic Energy Agency - IAEA -), the ENPEP package has been used at national, regional and inter-regional training courses, as well as in the conduct of national energy/electricity planning studies. This paper reviews the development of the ENPEP package and the proposed enhancements to the package. (author). 1 fig., 2 tabs.

Power transients of Ghana research reactor-1 using PARET/ANL thermal hydraulic code

International Nuclear Information System (INIS)

Ampomah-Amoaka, E.; Akaho, E.H.K.; Anim-Sampong, S.; Nyarko, B.J.B.

2010-01-01

PARET/ANL(Version 7.3 of 2007) thermal-hydraulic code was used to perform transient analysis of the Ghana Research Reactor-1.The reactivities inserted were 2.1mk and 4mk.The peak power of 5.81kW was obtained for 2.1 mk insertion whereas the peak power for 4mk insertion of reactivity was 92.32kW.These results compare closely with experiments and theoretical studies conducted previously.

Genes involved in the astrocyte-neuron lactate shuttle (ANLS) are specifically regulated in cortical astrocytes following sleep deprivation in mice.

Science.gov (United States)

Petit, Jean-Marie; Gyger, Joël; Burlet-Godinot, Sophie; Fiumelli, Hubert; Martin, Jean-Luc; Magistretti, Pierre J

2013-10-01

There is growing evidence indicating that in order to meet the neuronal energy demands, astrocytes provide lactate as an energy substrate for neurons through a mechanism called "astrocyte-neuron lactate shuttle" (ANLS). Since neuronal activity changes dramatically during vigilance states, we hypothesized that the ANLS may be regulated during the sleep-wake cycle. To test this hypothesis we investigated the expression of genes associated with the ANLS specifically in astrocytes following sleep deprivation. Astrocytes were purified by fluorescence-activated cell sorting from transgenic mice expressing the green fluorescent protein (GFP) under the control of the human astrocytic GFAP-promoter. 6-hour instrumental sleep deprivation (TSD). Animal sleep research laboratory. Young (P23-P27) FVB/N-Tg (GFAP-GFP) 14Mes/J (Tg) mice of both sexes and 7-8 week male Tg and FVB/Nj mice. Basal sleep recordings and sleep deprivation achieved using a modified cage where animals were gently forced to move. Since Tg and FVB/Nj mice displayed a similar sleep-wake pattern, we performed a TSD in young Tg mice. Total RNA was extracted from the GFP-positive and GFP-negative cells sorted from cerebral cortex. Quantitative RT-PCR analysis showed that levels of Glut1, α-2-Na/K pump, Glt1, and Ldha mRNAs were significantly increased following TSD in GFP-positive cells. In GFP-negative cells, a tendency to increase, although not significant, was observed for Ldha, Mct2, and α-3-Na/K pump mRNAs. This study shows that TSD induces the expression of genes associated with ANLS specifically in astrocytes, underlying the important role of astrocytes in the maintenance of the neuro-metabolic coupling across the sleep-wake cycle.

Genes involved in the astrocyte-neuron lactate shuttle (ANLS) are specifcally regulated in cortical astrocytes following sleep deprivation in mice

KAUST Repository

Petit, Jean Marie

2013-10-01

Study Objectives: There is growing evidence indicating that in order to meet the neuronal energy demands, astrocytes provide lactate as an energy substrate for neurons through a mechanism called "astrocyte-neuron lactate shuttle" (ANLS). Since neuronal activity changes dramatically during vigilance states, we hypothesized that the ANLS may be regulated during the sleep-wake cycle. To test this hypothesis we investigated the expression of genes associated with the ANLS specifcally in astrocytes following sleep deprivation. Astrocytes were purifed by fuorescence-activated cell sorting from transgenic mice expressing the green fuorescent protein (GFP) under the control of the human astrocytic GFAP-promoter. Design: 6-hour instrumental sleep deprivation (TSD). Setting: Animal sleep research laboratory. Participants: Young (P23-P27) FVB/N-Tg (GFAP-GFP) 14Mes/J (Tg) mice of both sexes and 7-8 week male Tg and FVB/Nj mice. Interventions: Basal sleep recordings and sleep deprivation achieved using a modifed cage where animals were gently forced to move. Measurements and Results: Since Tg and FVB/Nj mice displayed a similar sleep-wake pattern, we performed a TSD in young Tg mice. Total RNA was extracted from the GFP-positive and GFP-negative cells sorted from cerebral cortex. Quantitative RT-PCR analysis showed that levels of Glut1, a-2-Na/K pump, Glt1, and Ldha mRNAs were signifcantly increased following TSD in GFP-positive cells. In GFP-negative cells, a tendency to increase, although not signifcant, was observed for Ldha, Mct2, and α-3-Na/K pump mRNAs. Conclusions: This study shows that TSD induces the expression of genes associated with ANLS specifcally in astrocytes, underlying the important role of astrocytes in the maintenance of the neuro-metabolic coupling across the sleep-wake cycle.

A user's guide to the PLTEMP/ANL code.

Energy Technology Data Exchange (ETDEWEB)

Kalimullah, M. (Nuclear Engineering Division)

2011-07-05

PLTEMP/ANL V4.1 is a FORTRAN program that obtains a steady-state flow and temperature solution for a nuclear reactor core, or for a single fuel assembly. It is based on an evolutionary sequence of ''PLTEMP'' codes in use at ANL for the past 20 years. Fueled and non-fueled regions are modeled. Each fuel assembly consists of one or more plates or tubes separated by coolant channels. The fuel plates may have one to five layers of different materials, each with heat generation. The width of a fuel plate may be divided into multiple longitudinal stripes, each with its own axial power shape. The temperature solution is effectively 2-dimensional. It begins with a one-dimensional solution across all coolant channels and fuel plates/tubes within a given fuel assembly, at the entrance to the assembly. The temperature solution is repeated for each axial node along the length of the fuel assembly. The geometry may be either slab or radial, corresponding to fuel assemblies made of a series of flat (or slightly curved) plates, or of nested tubes. A variety of thermal-hydraulic correlations are available with which to determine safety margins such as Onset-of-Nucleate boiling (ONB), departure from nucleate boiling (DNB), and onset of flow instability (FI). Coolant properties for either light or heavy water are obtained from FORTRAN functions rather than from tables. The code is intended for thermal-hydraulic analysis of research reactor performance in the sub-cooled boiling regime. Both turbulent and laminar flow regimes can be modeled. Options to calculate both forced flow and natural circulation are available. A general search capability is available (Appendix XII) to greatly reduce the reactor analyst's time.

A User's Guide to the PLTEMP/ANL Code

Energy Technology Data Exchange (ETDEWEB)

Olson, Arne P. [Argonne National Lab. (ANL), Argonne, IL (United States); Kalimullah, M. [Argonne National Lab. (ANL), Argonne, IL (United States)

2015-07-07

PLTEMP/ANL V4.2 is a FORTRAN program that obtains a steady-state flow and temperature solution for a nuclear reactor core, or for a single fuel assembly. It is based on an evolutionary sequence of ''PLTEMP'' codes in use at ANL for the past 20 years. Fueled and non-fueled regions are modeled. Each fuel assembly consists of one or more plates or tubes separated by coolant channels. The fuel plates may have one to five layers of different materials, each with heat generation. The width of a fuel plate may be divided into multiple longitudinal stripes, each with its own axial power shape. The temperature solution is effectively 2-dimensional. It begins with a one-dimensional solution across all coolant channels and fuel plates/tubes within a given fuel assembly, at the entrance to the assembly. The temperature solution is repeated for each axial node along the length of the fuel assembly. The geometry may be either slab or radial, corresponding to fuel assemblies made of a series of flat (or slightly curved) plates, or of nested tubes. A variety of thermal-hydraulic correlations are available with which to determine safety margins such as Onset-of- Nucleate boiling (ONB), departure from nucleate boiling (DNB), and onset of flow instability (FI). Coolant properties for either light or heavy water are obtained from FORTRAN functions rather than from tables. The code is intended for thermal-hydraulic analysis of research reactor performance in the sub-cooled boiling regime. Both turbulent and laminar flow regimes can be modeled. Options to calculate both forced flow and natural circulation are available. A general search capability is available (Appendix XII) to greatly reduce the reactor analyst’s time.

A User's Guide to the PLTEMP/ANL Code

International Nuclear Information System (INIS)

Olson, Arne P.; Kalimullah, M.

2015-01-01

PLTEMP/ANL V4.2 is a FORTRAN program that obtains a steady-state flow and temperature solution for a nuclear reactor core, or for a single fuel assembly. It is based on an evolutionary sequence of ''PLTEMP'' codes in use at ANL for the past 20 years. Fueled and non-fueled regions are modeled. Each fuel assembly consists of one or more plates or tubes separated by coolant channels. The fuel plates may have one to five layers of different materials, each with heat generation. The width of a fuel plate may be divided into multiple longitudinal stripes, each with its own axial power shape. The temperature solution is effectively 2-dimensional. It begins with a one-dimensional solution across all coolant channels and fuel plates/tubes within a given fuel assembly, at the entrance to the assembly. The temperature solution is repeated for each axial node along the length of the fuel assembly. The geometry may be either slab or radial, corresponding to fuel assemblies made of a series of flat (or slightly curved) plates, or of nested tubes. A variety of thermal-hydraulic correlations are available with which to determine safety margins such as Onset-of- Nucleate boiling (ONB), departure from nucleate boiling (DNB), and onset of flow instability (FI). Coolant properties for either light or heavy water are obtained from FORTRAN functions rather than from tables. The code is intended for thermal-hydraulic analysis of research reactor performance in the sub-cooled boiling regime. Both turbulent and laminar flow regimes can be modeled. Options to calculate both forced flow and natural circulation are available. A general search capability is available (Appendix XII) to greatly reduce the reactor analyst's time.

A review of ANL base technology studies in support of the U.S. LMFBR vibration program

International Nuclear Information System (INIS)

Wambsganss, M.W.; Chen, S.S.; Mulcahy, T.M.; Shin, Y.S.

1977-01-01

Argonne National Laboratory (ANL) is the center for base technology studies of flow induced vibration for the U.S. LMFBR Program. This paper reviews and summarizes published results, reports on the status of ongoing programs, and discusses future needs as outlined in the U.S. LMFBR Vibrations Program Plan. (author)

A review of ANL base technology studies in support of the U.S. LMFBR vibration program

Energy Technology Data Exchange (ETDEWEB)

Wambsganss, M W; Chen, S S [Components Technology Division, Argonne National Laboratory, Argonne, IL (United States); Mulcahy, T M; Shin, Y S

1977-12-01

Argonne National Laboratory (ANL) is the center for base technology studies of flow induced vibration for the U.S. LMFBR Program. This paper reviews and summarizes published results, reports on the status of ongoing programs, and discusses future needs as outlined in the U.S. LMFBR Vibrations Program Plan. (author)

ANL experimental program for pulsed superconducting coils

International Nuclear Information System (INIS)

Wang, S.T.; Kim, S.H.; Praeg, W.F.; Krieger, C.I.

1978-01-01

Argonne National Laboratory (ANL) had recognized the clear advantage of a superconducting ohmic-heating (OH) coil and started in aggressive development program in FY 1977. The main objectives for FY 1977 are to develop cryostable basic cable configurations with reasonably low ac losses, to develop 12 kA cryostable cable, using it to design and build a 1.5 MJ pulsed coil, and to develop a rather inexpensive large fiberglass reinforced helium cryostat for the 1.5 MJ pulsed coil. The principal objective in building the 1.5 MJ ac coil is to demonstrate ac cryostability of a large coil ranging from 2 T/s up to 12 T/s. Another objective in the pulsed coil program is to determine the feasibility of parallel coil operation in order to avoid excessive voltage and current requirements and to minimize the number of turns for the equilibrium field (EF) coils, should the EF coils be connected in parallel with the OH coils. A two-coil section model using the 11 kA cable will be built and tested

ANL experimental program for pulsed superconducting coils

International Nuclear Information System (INIS)

Wang, S.T.; Kim, S.H.; Praeg, W.F.; Krieger, C.I.

1977-01-01

Argonne National Laboratory (ANL) had recognized the clear advantage of a superconducting ohmic-heating (OH) coil and started an aggressive development program in FY 1977. The main objectives for FY 1977 are to develop cryostable basic cable configurations with reasonably low ac losses, to develop 12 kA cryostable cable, using it to design and build a 1.5 MJ pulsed coil, and to develop a rather inexpensive large fiberglass reinforced helium cryostat for the 1.5 MJ pulsed coil. The principal objective in building the 1.5 MJ ac coil is to demonstrate ac cryostability of a large coil ranging from 2 T/s up to 12 T/s. Another objective in the pusled coil program is to determine the feasibility of parallel coil operation in order to avoid excessive voltage and current requirements and to minimize the number of turns for the equilibrium field (EF) coils, should the EF coils be connected in parallel with the OH coils. A two-coil section model using the 11 kA cable will be built and tested

Tritium handling trade studies and design options for the GA/ANL TNS

International Nuclear Information System (INIS)

Mintz, J.M.; Clemmer, R.G.; Maroni, V.A.

1978-01-01

A comprehensive effort involving members of both the General Atomic Company (GA) and the Argonne National Laboratory (ANL) has been undertaken to define the objectives, criteria and potential systems design solutions that accrue to the tritium handling systems for the next logical step in tokamak reactor development (TNS). A primary focus of these activities has been a systematic analysis of fuel cycle parameters and trade studies on the sensitivity of these parameters to reactor design and operating conditions. Principal results of these analyses and an assembly of potentially useful design concepts for various subsystems of the fuel cycle are presented

The ANL 50 MeV H- Injector: 35 year anniversary

International Nuclear Information System (INIS)

Stipp, V.; Brumwell, F.; McMichael, G.

1996-01-01

The H - Injector at ANL consists of a 750 keV Cockcroft-Walton preaccelerator and an Alvarez type 50 MeV Linac. The accelerator was originally constructed as the source of protons for the Zero Gradient Synchrotron (ZGS). The first proton beam was extracted from the preaccelerator in 1961. The accelerator is presently used as the injector for the Intense Pulsed Neutron Source (IPNS), a 500 MeV rapid cycling synchrotron with a spallation-neutron target. During most of the time since turn-on over 15 years ago, the IPNS facility availability has rarely dropped below 90% and has averaged 95% over the last ten years. During the same period, the 50 MeV injector availability has averaged 99%. Performance and improvements over the 35 year period is discussed

ANL statement of site strategy for computing workstations

Energy Technology Data Exchange (ETDEWEB)

Fenske, K.R. (ed.); Boxberger, L.M.; Amiot, L.W.; Bretscher, M.E.; Engert, D.E.; Moszur, F.M.; Mueller, C.J.; O' Brien, D.E.; Schlesselman, C.G.; Troyer, L.J.

1991-11-01

This Statement of Site Strategy describes the procedure at Argonne National Laboratory for defining, acquiring, using, and evaluating scientific and office workstations and related equipment and software in accord with DOE Order 1360.1A (5-30-85), and Laboratory policy. It is Laboratory policy to promote the installation and use of computing workstations to improve productivity and communications for both programmatic and support personnel, to ensure that computing workstations acquisitions meet the expressed need in a cost-effective manner, and to ensure that acquisitions of computing workstations are in accord with Laboratory and DOE policies. The overall computing site strategy at ANL is to develop a hierarchy of integrated computing system resources to address the current and future computing needs of the laboratory. The major system components of this hierarchical strategy are: Supercomputers, Parallel computers, Centralized general purpose computers, Distributed multipurpose minicomputers, and Computing workstations and office automation support systems. Computing workstations include personal computers, scientific and engineering workstations, computer terminals, microcomputers, word processing and office automation electronic workstations, and associated software and peripheral devices costing less than $25,000 per item.

Overview of the ANL advanced LMR system thermal-hydraulic test program supporting both GE/PRISM and RI/SAFR

International Nuclear Information System (INIS)

Oras, J.J.; Kuzay, T.M.; Kasza, K.E.

1988-01-01

Descriptions of the ANL thermal-hydraulic water models of both the PRISM and SAFR reactors are presented, together with results from Phases I and II of the thermal-hydraulic test program. Phenomena discovered during these tests and modeling results are presented. Overall, these efforts demonstrate the acceptable thermal-hydraulic performance of both the PRISM and SAFR concepts

Acquisition of the ANL 4-MeV electrostatic accelerator. Progress report, September 1, 1975--August, 1976

International Nuclear Information System (INIS)

Dixon, D.R.

1976-01-01

The operation of the ANL 4-MeV accelerator for the reporting period September 1, 1975 through August 31, 1976 is described. Some improvements and modifications to the accelerator and associated equipment, as well as maintenance problems are reported. Activities on the three research projects and a subsequent modification are summarized. Progress on the shift of research activities from the BYU 2-MeV accelerator to the 4-MeV accelerator is described

Colloid-Associated Radionuclide Concentration Limits: ANL

International Nuclear Information System (INIS)

Mertz, C.

2000-01-01

The purpose and scope of this report is to describe the analysis of available colloidal data from waste form corrosion tests at Argonne National Laboratory (ANL) to extract characteristics of these colloids that can be used in modeling their contribution to the source term for sparingly soluble radioelements (e.g., Pu). Specifically, the focus is on developing a useful description of the following waste form colloid characteristics: (1) composition, (2) size distribution, and (3) quantification of the rate of waste form colloid generation. The composition and size distribution information are intended to support analysis of the potential transport of the sparingly soluble radionuclides associated with the waste form colloids. The rate of colloid generation is intended to support analysis of the waste form colloid-associated radionuclide concentrations. In addressing the above characteristics, available data are interpreted to address mechanisms controlling colloid formation and stability. This report was developed in accordance with the ''Technical Work Plan for Waste Form Degradation Process Model Report for SR'' (CRWMS M and O 2000). Because the end objective is to support the source term modeling we have organized the conclusions into two categories: (1) data analysis conclusions and (2) recommendations for colloid source term modeling. The second category is included to facilitate use of the conclusions from the data analysis in the abstraction of a colloid source term model. The data analyses and conclusions that are presented in this report are based on small-scale laboratory tests conducted on a limited number of waste glass compositions and spent fuel types

Steady-state thermal-hydraulic analysis of the Moroccan TRIGA MARK II reactor by using PARET/ANL and COOLOD-N2 codes

International Nuclear Information System (INIS)

Boulaich, Y.; Nacir, B.; El Bardouni, T.; Zoubair, M.; El Bakkari, B.; Merroun, O.; El Younoussi, C.; Htet, A.; Boukhal, H.; Chakir, E.

2011-01-01

Research highlights: → The COOLOD/N2 and PARET/ANL codes were used for a steady-state thermal-hydraulic and safety analysis of the 2 MW TRIGA MARK II reactor located at the Nuclear Studies Center of Maamora (CENM), Morocco. → The main objective of this study is to ensure the safety margins of different safety related parameters by steady-state calculations at full power level (2 MW). → The most important conclusion is that all obtained values of DNBR, fuel center and surface temperature, cladding surface temperature and coolant temperature across the hottest channel are largely far to compromise safety of the reactor. - Abstract: The COOLOD/N2 and PARET/ANL codes were used for a steady-state thermal-hydraulic and safety analysis of the 2 MW TRIGA MARK II reactor located at the Nuclear Studies Center of Maamora (CENM), Morocco. In order to validate our PARET/ANL and COOLOD-N2 models, the fuel center temperature as function of core power was calculated and compared with the corresponding experimental values. The comparison indicates that the calculated values are in satisfactory agreement with the measurement. The main objective of this study is to ensure the safety margins of different safety related parameters by steady-state calculations at full power level (2 MW). Therefore, we have calculated the departure from nucleate boiling ratio (DNBR), fuel center and surface temperature, cladding surface temperature and coolant temperature profiles across the hottest channel. The most important conclusion is that all obtained values are largely far to compromise safety of the reactor.

Analysis of the KUCA MEU experiments using the ANL code system

Energy Technology Data Exchange (ETDEWEB)

Shiroya, S.; Hayashi, M.; Kanda, K.; Shibata, T.; Woodruff, W.L.; Matos, J.E.

1982-01-01

This paper provides some preliminary results on the analysis of the KUCA critical experiments using the ANL code system. Since this system was employed in the earlier neutronics calculations for the KUHFR, it is important to assess its capabilities for the KUHFR. The KUHFR has a unique core configuration which is difficult to model precisely with current diffusion theory codes. This paper also provides some results from a finite-element diffusion code (2D-FEM-KUR), which was developed in a cooperative research program between KURRI and JAERI. This code provides the capability for mockup of a complex core configuration as the KUHFR. Using the same group constants generated by the EPRI-CELL code, the results of the 2D-FEM-KUR code are compared with the finite difference diffusion code (DIF3D(2D) which is mainly employed in this analysis.

Analysis of the KUCA MEU experiments using the ANL code system

International Nuclear Information System (INIS)

Shiroya, S.; Hayashi, M.; Kanda, K.; Shibata, T.; Woodruff, W.L.; Matos, J.E.

1982-01-01

This paper provides some preliminary results on the analysis of the KUCA critical experiments using the ANL code system. Since this system was employed in the earlier neutronics calculations for the KUHFR, it is important to assess its capabilities for the KUHFR. The KUHFR has a unique core configuration which is difficult to model precisely with current diffusion theory codes. This paper also provides some results from a finite-element diffusion code (2D-FEM-KUR), which was developed in a cooperative research program between KURRI and JAERI. This code provides the capability for mockup of a complex core configuration as the KUHFR. Using the same group constants generated by the EPRI-CELL code, the results of the 2D-FEM-KUR code are compared with the finite difference diffusion code (DIF3D(2D) which is mainly employed in this analysis

Status of ANL out-of-pile investigations of severe accident phenomena for liquid metal reactors

International Nuclear Information System (INIS)

Spencer, B.W.; Marchaterre, J.F.; Anderson, R.P.

1986-01-01

Research addressing LMFBR whole core accidents has been terminated, and there is now emphasis on quantifying reactivity feedbacks, and in particular enhancing negative feedback, so that advanced LMR designs will provide inherently safe operation. The status of recent HCDA-related laboratory research performed at ANL, up to the time that such activities were no longer needed to support CRBR licensing, is described. Included are descriptions of programs addressing sodium channel voiding, fuel sweepout, fuel dispersal and plugging, boiled-up pool, UO 2 /sodium FCI, and debris coolability. Descriptions of recent investigations involving the metal fuel/sodium system are also included

ANL Technical Support Program for DOE Environmental Restoration and Waste Management

International Nuclear Information System (INIS)

Bates, J.K.; Bradley, C.R.; Buck, E.C.; Cunnane, J.C.; Dietz, N.L.; Ebert, W.L.; Emery, J.W.; Feng, X.; Gerding, T.J.; Gong, M.; Hoh, J.C.; Mazer, J.J.; Wronkiewicz, D.J.; Bourcier, W.L.; Morgan, L.E.; Nielsen, J.K.; Steward, S.A.; Ewing, R.C.; Wang, L.M.; Han, W.T.; Tomozawa, M.

1992-03-01

This report provides an overview of progress during FY 1991 for the Technical Support Program that is part of the ANL Technology Support Activity for DOE, Environmental Restoration and Waste Management (EM). The purpose is to evaluate, before hot start-up of the Defenses Waste Processing Facility (DWPF) and the West Valley Demonstration Project (WVDP), factors that are likely to affect glass reaction in an unsaturated environment typical of what may be expected for the candidate Yucca Mountain repository site. Specific goals for the testing program include the following: (1) to review and evaluate available information on parameters that will be important in establishing the long-term performance of glass in a repository environment; (2) to perform testing to further quantify the effects of important variables where there are deficiencies in the available data; and (3) to initiate long-term testing that will bound glass performance under a range of conditions applicable to repository disposal

Recent development in analytical methodology on the ANL 300 kV instrument

International Nuclear Information System (INIS)

Zaluzec, N.J.

2003-01-01

Full text: The advantages of field emission gun (FEG) based medium voltage instruments has been described for many years in terms of the increased spatial and image 'resolution' that can be obtained. Many laboratories have pressed the instruments to reach their highest resolution capabilities, but in doing so at a sacrifice of other parameters and/or capabilities which are equally important to solving real world problems. We have instead chosen to use the ANL instrument as an electron-optical bench to explore novel imaging and analysis modes, which in a conventional machine are not always readily achievable. These include operation in Lorentz and Stem, Position Resolved Diffraction, Scanning Confocal, and most recently high count rate XEDS mode using a new design of SDD EDS system. The results from these studies will be presented and then extended to their application in typical materials problems. Copyright (2003) Australian Microbeam Analysis Society

A comparative study of the systems for neutronics calculations used in Los Alamos Scientific Laboratory (LASL) and Argonne National Laboratory (ANL)

International Nuclear Information System (INIS)

Amorim, E.S. do; D'Oliveira, A.B.; Oliveira, E.C. de.

1980-11-01

A comparative study of the systems for neutronics calculations used in Los Alamos Scientific Laboratory (LASL) and Argonne National Laboratory (ANL) has been performed using benchmark results available in the literature, in order to analyse tghe convenience of using the respective codes MINX/NJOY and ETOE/MC 2 -2 for performing neutronics calculations in course at the Divisao de Estudos Avancados. (Author) [pt

SPECTER-ANL, Neutron Damage for Material Irradiation

International Nuclear Information System (INIS)

1989-01-01

1 - Description of program or function: SPECTER calculates spectral- averaged displacements, recoil spectra, gas production, and total damage energy (Kerma) for 41 pure elements using ENDF/B-V derived cross sections. The user need only specify a neutron energy spectrum. Because SPECTER does not handle compounds, SPECOMP was developed to determine displacement damage for alloys, insulators, and breeder materials. 2 - Method of solution: In SPECTER elastic scattering is treated exactly including angular distributions from ENDF/B-V. Inelastic scattering calculations consider both discrete and continuous nuclear level distributions. Multiple (n,xn) reactions use a Monte Carlo technique to derive the recoil distributions. The (n,d) and (n,t) reactions are treated as (n,p) and (n, 3 He) as (n, 4 He). The neutron-gamma reaction and subsequent beta-decay are also included, using a new treatment of gamma-gamma coincidences, angular correlations, beta-neutrino correlations and the incident neutron energy. The Lindhard model was used to compute the energy available for nuclear displacement at each recoil energy. SPECOMP reads the required files from SPECTER, computes secondary displacement functions for each combination of recoil and matrix atom, and then integrates over recoil energy to find the net displacement cross section at each neutron energy. Damage due to neutron, gamma-ray and beta decay events is then added in and the results are summed to obtain the total dpa cross section. 3 - Restrictions on the complexity of the problem: The DISCS computer code was used to process ENDF/B-V data for 41 pure elements for use with SPECTER-ANL. SPECOMP can use any combination of four elements in a single run

Modelling thermodynamic properties of lanthanide (LnL)3+ and actinide (AnL)3+ complexes with tridentate planar nitrogen ligands (L)

International Nuclear Information System (INIS)

Ionova, G.; Rabbe, C.; Charbonnel, M.C.; Hill, C.; Guillaumont, D.; Guillaumont, R.; Ionov, S.; Madic, C.

2004-01-01

We report here the results obtained from a systematic theoretical study on the thermodynamic properties of trivalent lanthanide (Ln) and actinide (An) complexes with chelating nitrogen tridentate ligands. The mechanism of chelation has been investigated and the role of cation dissolution is investigated through a comparison of the thermodynamic properties of solvated cations and complexes. The difference in thermodynamic properties of LnL and AnL complexes is analyzed. (authors)

Revised ANL-reported tensile data for V-Ti and V-Cr-Ti alloys

Energy Technology Data Exchange (ETDEWEB)

Billone, M.C. [Argonne National Lab., IL (United States)

1997-08-01

The tensile for all irradiated vanadium alloy samples and several unirradiated vanadium alloys tested at Argonne National Laboratory (ANL) have been critically reviewed and revised, as necessary. The review and revision are based on re-analyzing the original load-displacement strip-chart recording using a methodology consistent with current ASTM standards. No significant difference has been found between the newly-revised and previously-reported values of yield strength (YS) and ultimate tensile strength (UTS). However, by correctly subtracting the non-gauge-length displacement and linear gauge-length displacement from the total cross-head displacement, the uniform elongation (UE) of the gauge length decreases by 4-9% strain and the total elongation (TE) of the gauge length decreases by 1-7% strain. These differences are more significant for lower-ductility irradiated alloys than for higher-ductility alloys.

Revised ANL-reported tensile data for V-Ti and V-Cr-Ti alloys

International Nuclear Information System (INIS)

Billone, M.C.

1997-01-01

The tensile for all irradiated vanadium alloy samples and several unirradiated vanadium alloys tested at Argonne National Laboratory (ANL) have been critically reviewed and revised, as necessary. The review and revision are based on re-analyzing the original load-displacement strip-chart recording using a methodology consistent with current ASTM standards. No significant difference has been found between the newly-revised and previously-reported values of yield strength (YS) and ultimate tensile strength (UTS). However, by correctly subtracting the non-gauge-length displacement and linear gauge-length displacement from the total cross-head displacement, the uniform elongation (UE) of the gauge length decreases by 4-9% strain and the total elongation (TE) of the gauge length decreases by 1-7% strain. These differences are more significant for lower-ductility irradiated alloys than for higher-ductility alloys

Demonstration personnel and material tracking system at ANL-W

International Nuclear Information System (INIS)

Roybal, J.A.; Ortiz, S.; Henslee, S.P.

1988-01-01

A Personnel and Material Tracking System (PMTS) was demonstrated in the Fuel Manufacturing Facility (FMF) at Argonne National Laboratories-West (ANL-W) in July, 1987. The PMTS is intended to aid in the transfer of inventory materials from area to area within a facility such as FMF. It is also intended to assure that only those personnel who are authorized to do so may conduct these transfer operations. The PMTS Personnel Movement (PM) subsystem uses portals installed between areas to alert the system to the movement of personnel between areas. The portals are composed to two sensors, one on either side of a proximity badge reader, to detect the presence of personnel entering the portal area. However, a restricted area can be assigned to any badge holder which will cause the system to issue an alert if the badge holder passes into his/her restricted area. The PM subsystem is intended to be transparent when in use. The PMTS Inventory Material Access (IMA) subsystem provides two functions: material control and material access. The material control is provided by the Wireless Alarm Transmission of Container Handling (WATCH) system which is a sensor rf transmitter system that detects item movements. Material access is provided by the Mobile Accountability Verification Inventory Station (MAVIS) system which is a self-powered smart barcode reader

Stibine/arsine monitoring during EV operation: summary report on preliminary tests at ANL and at LILCO

Energy Technology Data Exchange (ETDEWEB)

Loutfy, R.O.; Graczyk, D.G.; Varma, R.; Hayes, E.R.; Williams, F.L.; Yao, N.P.

1981-02-01

A series of tests was performed to monitor the evolution and dispersal of stibine and arsine from the lead-acid propulsion batteries in three different Electra-Van Model 600 vehicles operated by Argonne National Laboratory (ANL) and by the Long Island Lighting Company (LILCO). Ambient air was sampled at several locations inside the vehicles and in the garages where testing was done during charge, equalization charge, and on-the-road discharge operations. In addition, direct sampling of cell off-gases was performed with the ANL van. Interpretation of the individual test results was carried out in the context of vehicle characteristics, sampling protocol, and operating conditions. The test results demonstrated that under the test conditions only small concentrations of stibine and arsine accumulated in occupiable work areas. Measured concentrations in the vehicles and in the garages never exceeded 25% of the Threshold Limit Value-Time Weighted Average (TLV-TWA) standards. A threshold voltage for hydride production, at about 2.45 V per cell, was reflected in the results of the experiments performed during charging of the batteries. Hydride evolution rates were lower during equalization charge than during the overcharge portion of a charge cycle when the on-board charger was used in a normal operating mode. A delayed release of the metal hydrides from the battery cells was observed during on-the-road operation of the vehicles. The implications of these observations for electric vehicle (EV) operation are discussed. An engineering analysis of the generation and dispersal of the metal hydrides is presented, and equations are derived for estimating minimum ventilation requirements for the EV battery compartment and for garages housing EV operations. Recommendations are made regarding safe handling procedures for battery off-gases, procedures for conducting stibine/arsine monitoring tests and future work.

ANL progress on the cooperation with CNEA for the MO-99 production: Base-side digestion process

International Nuclear Information System (INIS)

Gelis, A.V.; Quigley, K.J.; Aase, S.B.; Bakel, A.J.; Leyva, A.; Regalbuto, M.C.; Vandergrift, G.F.

2005-01-01

Conversion from high-enriched uranium (HEU) to low-enriched uranium (LEU) targets for the Mo-99 production requires certain modifications of the target design, the digestion and the purification processes. ANL and the Argentine Comision Nacional de Energia Atomica (CNEA) are collaborating to overcome all the concerns caused by the conversion of the CNEA process to use LEU foil targets. A new digester with stirring system has been successfully applied for the digestion of the low burn-up U foil targets in KMnO 4 alkaline media. In this paper, we report the progress on the development of the digestion procedure utilizing effective stirring and focusing on minimization of the liquid radioactive waste. (author)

Mathematical modeling and evaluation of radionuclide transport parameters from the ANL Laboratory Analog Program

International Nuclear Information System (INIS)

Chen, B.C.J.; Hull, J.R.; Seitz, M.G.; Sha, W.T.; Shah, V.L.; Soo, S.L.

1984-07-01

Computer model simulation is required to evaluate the performance of proposed or future high-level radioactive waste geological repositories. However, the accuracy of a model in predicting the real situation depends on how well the values of the transport properties are prescribed as input parameters. Knowledge of transport parameters is therefore essential. We have modeled ANL's Experiment Analog Program which was designed to simulate long-term radwaste migration process by groundwater flowing through a high-level radioactive waste repository. Using this model and experimental measurements, we have evaluated neptunium (actinide) deposition velocity and analyzed the complex phenomena of simultaneous deposition, erosion, and reentrainment of bentonite when groundwater is flowing through a narrow crack in a basalt rock. The present modeling demonstrates that we can obtain the values of transport parameters, as added information without any additional cost, from the available measurements of laboratory analog experiments. 8 figures, 3 tables

A Study on Living Conditions of the Seasonal Agricultural Workers: Hilvan County (Şanlıurfa Sample

Directory of Open Access Journals (Sweden)

Sedat Benek

2011-12-01

Full Text Available This study is carried out to identify living standards of seasonal agricultural workers in Hilvan County of Şanlıurfa that largely rely on agriculture and have sufficient or little cultivable lands. Study sample is composed of families of the students who attend schools affiliated to Hilvan County Directorate of National Education and are involved in temporary migration before the school term ends in a year. “Face to face” interviews were held with and questionnaires were applied to heads of 523 families which live on seasonal agricultural labor. The results were assessed by using SPSS (Statistical Package for Social Science through various statistical techniques required for the study purpose. Majority of the children of families who

Verification and validation of the PLTEMP/ANL code for thermal hydraulic analysis of experimental and test reactors

International Nuclear Information System (INIS)

Kalimullah, M.; Olson, A.O.; Feldman, E.E.; Hanan, N.; Dionne, B.

2012-01-01

The document compiles in a single volume several verification and validation works done for the PLTEMP/ANL code during the years of its development and improvement. Some works that are available in the open literature are simply referenced at the outset, and are not included in the document. PLTEMP has been used in conversion safety analysis reports of several US and foreign research reactors that have been licensed and converted. A list of such reactors is given. Each chapter of the document deals with the verification or validation of a specific model. The model verification is usually done by comparing the code with hand calculation, Microsoft spreadsheet calculation, or Mathematica calculation. The model validation is done by comparing the code with experimental data or a more validated code like the RELAP5 code.

Verification and Validation of the PLTEMP/ANL Code for Thermal-Hydraulic Analysis of Experimental and Test Reactors

Energy Technology Data Exchange (ETDEWEB)

Kalimullah, M. [Argonne National Lab. (ANL), Argonne, IL (United States); Olson, Arne P. [Argonne National Lab. (ANL), Argonne, IL (United States); Feldman, E. E. [Argonne National Lab. (ANL), Argonne, IL (United States); Hanan, N. [Argonne National Lab. (ANL), Argonne, IL (United States); Dionne, B. [Argonne National Lab. (ANL), Argonne, IL (United States)

2015-04-07

The document compiles in a single volume several verification and validation works done for the PLTEMP/ANL code during the years of its development and improvement. Some works that are available in the open literature are simply referenced at the outset, and are not included in the document. PLTEMP has been used in conversion safety analysis reports of several US and foreign research reactors that have been licensed and converted. A list of such reactors is given. Each chapter of the document deals with the verification or validation of a specific model. The model verification is usually done by comparing the code with hand calculation, Microsoft spreadsheet calculation, or Mathematica calculation. The model validation is done by comparing the code with experimental data or a more validated code like the RELAP5 code.

A User’s Guide to the PLTEMP/ANL Code

Energy Technology Data Exchange (ETDEWEB)

Olson, A. P. [Argonne National Lab. (ANL), Argonne, IL (United States); Kalimullah, M. [Argonne National Lab. (ANL), Argonne, IL (United States); Feldman, E. E. [Argonne National Lab. (ANL), Argonne, IL (United States)

2016-07-25

PLTEMP/ANL V4.2 is a program that obtains a steady-state flow and temperature solution for a nuclear reactor core, or for a single fuel assembly. It is based on an evolutionary sequence of codes originally used for plate temperatures, hence “PLTEMP”, developed at Argonne National Laboratory over several decades. Fueled and non-fueled regions are modeled. Each fuel assembly consists of one or more plates or tubes separated by coolant channels. The fuel plates may have one to five layers of different materials, each with heat generation. The width of a fuel plate may be divided into multiple longitudinal stripes, each with its own axial power shape. The temperature solution is effectively 2-dimensional. It begins with a one-dimensional solution across all coolant channels and fuel plates or tubes within a given fuel assembly, at the entrance to the assembly. The temperature solution is repeated for each axial node along the length of the fuel assembly. The geometry may be either slab or radial, corresponding to fuel assemblies made of a series of flat (or slightly curved) plates, or of nested tubes. A variety of thermal-hydraulic correlations are available with which to determine safety margins such as onset-of-nucleate boiling ratio(ONBR), departure from nucleate boiling ratio (DNBR), and onset of flow instability ratio (OFIR). Coolant properties for either light or heavy water are obtained from FORTRAN functions rather than from tables. The code is intended for thermal-hydraulic analysis of research reactor performance in the sub-cooled boiling regime. Both turbulent and laminar flow regimes can be modeled. Options to calculate both forced flow and natural circulation are available. A general search capability is available (Appendix XII) to greatly reduce the reactor analyst’s time.

Relation of Market Where Gold Supply And Demand is Intensive With Finance Sector and Analyze Of Present Market Structure in Terms Of Socio-Economic: A Study Based On Survey in Şanlıurfa and in the Region

Directory of Open Access Journals (Sweden)

Mehmet Cihangir

2010-03-01

Full Text Available One of the provinces where gold is purchased and sold mostly is Şanlıurfa. Especially trading of gold mostly in some special days following İstanbul and Ankara has made necessary that jewelry sector in this province where gold is purchased and sold is put under the scope and thereby examination of the contribution of gold to region economy as well as its other aspects. Within this scope a detailed questionnaire study to search gold and jewelry sector in Şanlıurfa in point of social, cultural and economical effects have been carried out and it has been aimed to explain these effectsdirectly from explanations of parties of incident. Considering the inevitability of emergence of some problems in a region where such extensive sale and purchase is made, the problems seen mostly have been determined and proposals regarding the solution of these have been made. In addition it has also been aimed to observe perception manner of gold and its contribution to region economy as a investment vehicle in the region. Especially the damage of misleading of credit card in sector has been tried to determine and made solution recommendations to the problem. It has been pointed out on the benefits in case the gold called mattress and considered its effect to economy is little is gained to Şanlıurfa economy.

ANL Technical Support Program for DOE Environmental Restoration and Waste Management. Annual report, October 1992--September 1993

International Nuclear Information System (INIS)

Bates, J.K.; Bourcier, W.L.; Bradley, C.R.

1994-06-01

This report is an overview of the progress during FY 1993 for the Technical Support Program that is part of the ANL Technology Support Activity for DOE Environmental Restoration and Waste Management (EM). The purpose is to evaluate, before hot start-up of the Defense Waste Processing Facility (DWPF) and the West Valley Demonstration Project (WVDP), factors that are anticipated to affect glass reaction in an unsaturated environment typical of what may be expected for the candidate Yucca Mountain repository site. Specific goals for the testing program include the following: reviewing and evaluating available data on parameters that will be important in establishing the long-term performance of glass in a repository environment; performing tests to further quantify the effects of important variables where there are deficiencies in the available data; and initiating long-term tests to determine glass performance under a range of conditions applicable to repository disposal

Analysis of Moderator Temperature Reactivity Coefficient of the PWR Core Using WIMS-ANL

International Nuclear Information System (INIS)

Tukiran; Rokhmadi

2007-01-01

The Moderator Temperature Reactivity Coefficient (MTRC) is an important parameter in design, control and safety, particularly in PWR reactor. It is then very important to validate any new processed library for an accurate prediction of this parameter. The objective of this work is to validate the newly WIMS library based on ENDF/B-VI nuclear data files, especially for the prediction of the MTRC parameter. For this purpose, it is used a set of light water moderated lattice experiments as the NORA experiment and R1-100H critical reactors, both of reactors using UO 2 fuel pellet. Analysis is used with WIMSD/4 lattice code with original cross section libraries and WIMS-ANL with ENDF/B-VI cross section libraries. The results showed that the moderator temperatures reactivity coefficients for the NORA reactor using original libraries is - 5.039E-04 %Δk/k/℃ but for ENDF/B-VI libraries is - 2.925E-03 %Δk/k/℃. Compared to the designed value of the reactor core, the difference is in the range of 1.8 - 3.8 % for ENDF/B-IV libraries. It can be concluded that for reactor safety and control analysis, it has to be used ENDF/B- VI libraries because the original libraries is not accurate any more. (author)

A plan for administrative computing at ANL FY1991 through FY1993

Energy Technology Data Exchange (ETDEWEB)

Caruthers, L.E. (ed.); O' Brien, D.E.; Bretscher, M.E.; Hischier, R.C.; Moore, N.J.; Slade, R.G.

1990-10-01

In July of 1988, Argonne National Laboratory management approved the restructuring of Computing Services into the Computing and Telecommunications Division, part of the Physical Research area of the Laboratory. One major area of the Computing and Telecommunications Division is Management Information Systems (MIS). A significant aspect of Management Information Systems' work is the development of proposals for new and enhanced administrative computing systems based on an analysis of informational needs. This document represent the outcome of the planning process for FY1991 through FY1993. The introduction of the FY1991 through FY1993 Long-Range Plan assesses the state of administrative computing at ANL and the implications of FY1991 funding recommendations. It includes a history of MIS planning for administrative data processing. This document discusses the strategy and goals which are an important part of administrative data processing plans for the Laboratory. It also describes the management guidelines established by the Administrative Data Processing Oversight Committee for the proposal and implementation of administrative computing systems. Summaries of the proposals for new or enhanced administrative computing systems presented by individual divisions or departments with assistance of Management Information Systems, to the Administrative Data Processing Oversight Committee are given. The detailed tables in this paper give information on how much the resources to develop and implement a given systems will cost its users. The tables include development costs, computing/operations costs, software and hardware costs, and efforts costs. They include both systems funded by Laboratory General Expense and systems funded by the users themselves.

Characterization of mixed CH-TRU waste for the WIPP Experimental Test Program conducted at ANL-W

International Nuclear Information System (INIS)

Dwight, C.C.; McClellan, G.C.; Guay, K.P.; Courtney, J.C.; Duff, M.J.

1992-01-01

Argonne National Laboratory is participating in the Department of Energy's Waste Isolation Pilot Plant (WIPP) Experimental Test Program by characterizing and repackaging mixed contact-handled transuranic waste. Characterization activities include gas sampling the waste containers, visually examining the waste contents, categorizing the contents according to their gas generation potentials, and weighing the contents. The waste is repackaged from 0.21m 3 (55 gallon) drums into instrumented steel test bins which can hold up to six drum-equivalents in volume. Eventually the loaded test bins will be shipped to WIPP where they will be evaluated during a five-year test program. Three test bins of inorganic solids (primarily glass) were prepared between March and September 1991 and are ready for shipment to WIPP. The characterization activities confirmed process knowledge of the waste and verified the nondestructive examinations; the gas sample analyses showed the target constituents to be within allowable regulatory limits. A new waste characterization chamber is being developed at ANL-W which will improve worker safety, decrease the potential for contamination spread, and increase the waste characterization throughput. The new facility is expected to begin operations by Fall 1992. A comprehensive summary of the project is contained herein

Characterization of mixed CH-TRU waste for the WIPP Experimental Test Program conducted at ANL-W

Energy Technology Data Exchange (ETDEWEB)

Dwight, C.C.; McClellan, G.C.; Guay, K.P. [Argonne National Lab., Idaho Falls, ID (United States); Courtney, J.C. [Louisiana State Univ., Baton Rouge, LA (United States); Duff, M.J. [Consolidated Technical Services, Inc., Walkersville, MD (United States)

1992-02-01

Argonne National Laboratory is participating in the Department of Energy`s Waste Isolation Pilot Plant (WIPP) Experimental Test Program by characterizing and repackaging mixed contact-handled transuranic waste. Characterization activities include gas sampling the waste containers, visually examining the waste contents, categorizing the contents according to their gas generation potentials, and weighing the contents. The waste is repackaged from 0.21m{sup 3} (55 gallon) drums into instrumented steel test bins which can hold up to six drum-equivalents in volume. Eventually the loaded test bins will be shipped to WIPP where they will be evaluated during a five-year test program. Three test bins of inorganic solids (primarily glass) were prepared between March and September 1991 and are ready for shipment to WIPP. The characterization activities confirmed process knowledge of the waste and verified the nondestructive examinations; the gas sample analyses showed the target constituents to be within allowable regulatory limits. A new waste characterization chamber is being developed at ANL-W which will improve worker safety, decrease the potential for contamination spread, and increase the waste characterization throughput. The new facility is expected to begin operations by Fall 1992. A comprehensive summary of the project is contained herein.

Characterization of mixed CH-TRU waste for the WIPP Experimental Test Program conducted at ANL-W

Energy Technology Data Exchange (ETDEWEB)

Dwight, C.C.; McClellan, G.C.; Guay, K.P. (Argonne National Lab., Idaho Falls, ID (United States)); Courtney, J.C. (Louisiana State Univ., Baton Rouge, LA (United States)); Duff, M.J. (Consolidated Technical Services, Inc., Walkersville, MD (United States))

1992-01-01

Argonne National Laboratory is participating in the Department of Energy's Waste Isolation Pilot Plant (WIPP) Experimental Test Program by characterizing and repackaging mixed contact-handled transuranic waste. Characterization activities include gas sampling the waste containers, visually examining the waste contents, categorizing the contents according to their gas generation potentials, and weighing the contents. The waste is repackaged from 0.21m{sup 3} (55 gallon) drums into instrumented steel test bins which can hold up to six drum-equivalents in volume. Eventually the loaded test bins will be shipped to WIPP where they will be evaluated during a five-year test program. Three test bins of inorganic solids (primarily glass) were prepared between March and September 1991 and are ready for shipment to WIPP. The characterization activities confirmed process knowledge of the waste and verified the nondestructive examinations; the gas sample analyses showed the target constituents to be within allowable regulatory limits. A new waste characterization chamber is being developed at ANL-W which will improve worker safety, decrease the potential for contamination spread, and increase the waste characterization throughput. The new facility is expected to begin operations by Fall 1992. A comprehensive summary of the project is contained herein.

Beretning for undersøgelse af bopladsområde med værkstedsaktivitet fra yngre jernalder/vikingetid, neolitiske anlæg fortrinsvis fra MN A III og en grav fra MN B II. Kalmergården (KU) 2000

DEFF Research Database (Denmark)

Bican, Josefine Franck

2001-01-01

anlæggelse er omtalt nedenfor i en separat beretning ved Lone Gebauer Thomsen (se bilag 2). Yngre jernalder/vikingetid er den periode, der var bedst repræsenteret på pladsen. Her var spor efter en markeds-/produktionsplads, der er registreret vha. 3735 detektorfund, hvor især sølvskatten (KU 2337) skal...

Simulation of IST Turbomachinery Power-Neutral Tests with the ANL Plant Dynamics Code

Energy Technology Data Exchange (ETDEWEB)

Moisseytsev, A. [Argonne National Lab. (ANL), Argonne, IL (United States); Sienicki, J. J. [Argonne National Lab. (ANL), Argonne, IL (United States)

2016-12-13

The validation of the Plant Dynamics Code (PDC) developed at Argonne National Laboratory (ANL) for the steady-state and transient analysis of supercritical carbon dioxide (sCO2) systems has been continued with new test data from the Naval Nuclear Laboratory (operated by Bechtel Marine Propulsion Corporation) Integrated System Test (IST). Although data from three runs were provided to ANL, only two of the data sets were analyzed and described in this report. The common feature of these tests is the power-neutral operation of the turbine-compressor shaft, where no external power through the alternator was provided during the tests. Instead, the shaft speed was allowed to change dictated by the power balance between the turbine, the compressor, and the power losses in the shaft. The new test data turned out to be important for code validation for several reasons. First, the power-neutral operation of the shaft allows validation of the shaft dynamics equations in asynchronous mode, when the shaft is disconnected from the grid. Second, the shaft speed control with the compressor recirculation (CR) valve not only allows for testing the code control logic itself, but it also serves as a good test for validation of both the compressor surge control and the turbine bypass control actions, since the effect of the CR action on the loop conditions is similar for both of these controls. Third, the varying compressor-inlet temperature change test allows validation of the transient response of the precooler, a shell-and-tube heat exchanger. The first transient simulation of the compressor-inlet temperature variation Test 64661 showed a much slower calculated response of the precooler in the calculations than the test data. Further investigation revealed an error in calculating the heat exchanger tube mass for the PDC dynamic equations that resulted in a slower change in the tube wall temperature than measured. The transient calculations for both tests were done in two steps. The

The Impact of Geographical Environment on Urban Place Names: Case of Şanlıurfa City

Directory of Open Access Journals (Sweden)

Veysi GÜNAL

2011-06-01

Full Text Available This study which holds Şanlıurfa city’s place names consists of three chapters. First, the factors that impact streets and district names are being held. Also, development of names is examined and classified. The purpose of this study is to understand the impact of geographical environment on naming of streets and districts. Natural environment characteristics have an impact on urban naming. City’s areal extension and an increase in population, national and local historical events, social and economic structure have an impact on urban place names too. While naming, the political party which includes mayor and councilors has an important mission. In this concept, there are a lot of places which have been named after person’s names, sites and historical-political events. Out of 149 names, 78 of it have taken its names after human activities. In the human activities based names (78, person’s names have an outstanding place (60. And in those names, governmental-military-political names (24 and religious person’s names come into prominence. In the city there are 22 natural environment names, 6 streets and 14 districts. There are a lot of urban places’ names which have been named after economic activities. These activities have given names to 36 districts and streets. Names which unknown the origin and others are 13

Transient behavior during reactivity insertion in the Moroccan TRIGA Mark II reactor using the PARET/ANL code

International Nuclear Information System (INIS)

Boulaich, Y.; Nacir, B.; El Bardouni, T.; Boukhal, H.; Chakir, E.; El Bakkari, B.; El Younoussi, C.

2015-01-01

Highlights: • PARET model for the Moroccan TRIGA MARK II reactor has been developed. • Transient behavior under reactivity insertion has been studied based on PARET code. • Power factors required by PARET code have been calculated by using MCNP5 code. • The dependence on time of the main thermal-hydraulic parameters was calculated. • Results are largely far to compromise the thermal design limits. - Abstract: A three dimensional model for the Moroccan 2 MW TRIGA MARK II reactor has been developed for thermal-hydraulic and safety analysis by using the PARET/ANL and MCNP5 codes. This reactor is located at the nuclear studies center of Mâamora (CENM), Morocco. The model has been validated through temperature measurements inside two instrumented fuel elements located near the center of the core, at various power levels, and also through the power and fuel temperature evolution after the reactor shutdown (SCRAM). The axial distributions of power factors required by the PARET code have been calculated in each fuel element rod by using MCNP5 code. Based on this thermal-hydraulic model, a safety analysis under the reactivity insertion phenomenon has been carried out and the dependence on time of the main thermal-hydraulic parameters was calculated. Results were compared to the thermal design limits imposed to maintain the integrity of the clad

Determination of Yield and Yield Components as a Second Crop of Some Sesame Genotypes Collected from Şanlıurfa Region

Directory of Open Access Journals (Sweden)

Hüseyin ARSLAN

2014-09-01

Full Text Available This research, was carried out to determine the performance of some sesame (Sesamum indicum L. lines/genotype (15 and Arslanbey, Özberk-82, Muganlı-57, Gölmarmara and Baydar-2001 standard varieties in the Southeastern Anatolia Region. The studies were conducted at two locations (GAP Agricultural Research Institute-Gündaş Research Station and Talat Demirören Research Station during the growing season in 2010 (13 lines/genotype and 2011 (15 lines/genotype. Trials randomized complete block design as three replications. Plots length were 6 m, each plot formed 4 rows, row spacing was 70 cm and row distance was 15 cm. In the experiments was taken plant height, number of lateral branches per plant, number of capsules per plant, seed yield and 1000-grain weight as the herbal properties of the observations. According to research results; Arslanbey sesame variety with amounts ranging from 1112 kg ha-1 to 548 kg ha- 1 seed yield, in Şanlıurfa climate and soil conditions as the second product compared to other prominent varieties and lines is easily recommended.

Measurement of Acceptable Noise Level with Background Music.

Science.gov (United States)

Ahn, Hyun-Jung; Bahng, Junghwa; Lee, Jae Hee

2015-09-01

Acceptable noise level (ANL) is a measure of the maximum background noise level (BNL) that a person is willing to tolerate while following a target story. Although researchers have used various sources of target sound in ANL measures, a limited type of background noise has been used. Extending the previous study of Gordon-Hickey & Moore (2007), the current study determined the effect of music genre and tempo on ANLs as possible factors affecting ANLs. We also investigated the relationships between individual ANLs and the familiarity of music samples and between music ANLs and subjective preference. Forty-one participants were seperated into two groups according to their ANLs, 29 low-ANL listeners and 12 high-ANL listeners. Using Korean ANL material, the individual ANLs were measured based on the listeners' most comfortable listening level and BNL. The ANLs were measured in six conditions, with different music tempo (fast, slow) and genre (K-pop, pop, classical) in a counterbalanced order. Overall, ANLs did not differ by the tempo of background music, but music genre significantly affected individual ANLs. We observed relatively higher ANLs with K-pop music and relatively lower ANLs with classical music. This tendency was similar in both low-ANL and high-ANL groups. However, the subjective ratings of music familiarity and preference affected ANLs differently for low-ANL and high-ANL groups. In contrast to the low-ANL listeners, the ANLs of the high-ANL listeners were significantly affected by music familiarity and preference. The genre of background music affected ANLs obtained using background music. The degree of music familiarity and preference appears to be associated with individual susceptibility to background music only for listeners who are greatly annoyed by background noise (high-ANL listeners).

Analysis of IFR samples at ANL-E

International Nuclear Information System (INIS)

Bowers, D.L.; Sabau, C.S.

1993-01-01

The Analytical Chemistry Laboratory analyzes a variety of samples submitted by the different research groups within IFR. This talk describes the analytical work on samples generated by the Plutonium Electrorefiner, Large Scale Electrorefiner and Waste Treatment Studies. The majority of these samples contain Transuranics and necessitate facilities that safely contain these radioisotopes. Details such as: sample receiving, dissolution techniques, chemical separations, Instrumentation used, reporting of results are discussed. The Importance of Interactions between customer and analytical personnel Is also demonstrated

Argonne National Laboratory-East site environmental report for calendar year 1999

International Nuclear Information System (INIS)

Golchert, N. W.; Kolzow, R. G.

2000-01-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL-E) for 1999. To evaluate the effects of ANL-E operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL-E site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL-E effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, ANL-E, and other) and are compared with applicable environmental quality standards. A US Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the US Environmental Protection Agency's CAP-88 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report. The status of ANL-E environmental protection activities with respect to the various laws and regulations that govern waste handling and disposal is discussed, along with the progress of environmental corrective actions and restoration projects

Argonne National Laboratory-East site environmental report for calendar year 1998

International Nuclear Information System (INIS)

Golchert, N.W.; Kolzow, R.G.

1999-01-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL-E) for 1998. To evaluate the effects of ANL-E operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL-E site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL-E effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, ANL-E, and other) and are compared with applicable environmental quality standards. A US Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the US Environmental Protection Agency's CAP-88 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report. The status of ANL-E environmental protection activities with respect to the various laws and regulations that govern waste handling and disposal is discussed, along with the progress of environmental corrective actions and restoration projects

Argonne National Laboratory-East site environmental report for calendar year 1996

International Nuclear Information System (INIS)

Golchert, N.W.; Kolzow, R.G.

1997-09-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL-E) for 1996. To evaluate the effects of ANL-E operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL-E site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL-E effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL-E, and other) and are compared with applicable environmental quality standards. A US Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL-E environmental protection activities with respect to the various laws and regulations that govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects

Argonne National Laboratory-East site environmental report for calendar year 1996

Energy Technology Data Exchange (ETDEWEB)

Golchert, N.W.; Kolzow, R.G.

1997-09-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL-E) for 1996. To evaluate the effects of ANL-E operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL-E site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL-E effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL-E, and other) and are compared with applicable environmental quality standards. A US Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL-E environmental protection activities with respect to the various laws and regulations that govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects.

Taxonomic and phylogenetic diversity of vascular plants at Ma'anling volcano urban park in tropical Haikou, China: Reponses to soil properties.

Science.gov (United States)

Cheng, Xia-Lan; Yuan, Lang-Xing; Nizamani, Mir Mohammad; Zhu, Zhi-Xin; Friedman, Cynthia Ross; Wang, Hua-Feng

2018-01-01

Anthropogenic processes and socio-economic factors play important roles in shaping plant diversity in urban parks. To investigate how plant diversity of Ma' anling urban volcano park in Hainan Province, China respond to these factors, we carried out a field investigation on the taxonomic and phylogenetic diversity of vascular plants and soil properties in this area. We found 284 species of vascular plants belonging to 88 families and 241 genera, which included 194 native species, 23 invasive species, 31 naturalized species, 40 cultivars, and 4 rare / endangered plant species. Tree composition and richness significantly varied between different vegetation formations (plantation, secondary forest, and abandoned land). Plant species richness and community composition were significantly affected by elevation (El), soil water content (WC), total soil nitrogen (TN) and soil organic matter (SOM). There were significant diversity differences between plantations and abandoned lands, but not between the plantations and secondary forests. The flora in the study site was tropical in nature, characterized by pantropic distributions. Compared to adjacent areas, floristic composition in the study site was most similar to that of Guangdong, followed by that of Vietnam. Our study revealed the diversity patterns of volcanic plants and provided the basis for future planning of plant conservation, such as preserving plant species, maintaining plant habitats, and coordinating plant management in this region.

Argonne National Laboratory 1986 publications

International Nuclear Information System (INIS)

Kopta, J.A.; Springer, C.J.

1987-12-01

This report is a bibliography of scientific and technical 1986 publications of Argonne National Laboratory. Some are ANL contributions to outside organizations' reports published in 1986. This compilation, prepared by the Technical Information Services Technical Publications Section (TPS), lists all nonrestricted 1986 publications submitted to TPS by the Laboratory's Divisions. Author indexes list ANL authors only. If a first author is not an ANL employee, an asterisk in the bibliographic citation indicates the first ANL author. The report is divided into seven parts: Journal Articles -- Listed by first author; ANL Reports -- Listed by report number; ANL and non-ANL Unnumbered Reports -- Listed by report number; Non-ANL Numbered Reports -- Listed by report number; Books and Book Chapters -- Listed by first author; Conference Papers -- Listed by first author; and Complete Author Index

Argonne National Laboratory 1986 publications

Energy Technology Data Exchange (ETDEWEB)

Kopta, J.A.; Springer, C.J.

1987-12-01

This report is a bibliography of scientific and technical 1986 publications of Argonne National Laboratory. Some are ANL contributions to outside organizations' reports published in 1986. This compilation, prepared by the Technical Information Services Technical Publications Section (TPS), lists all nonrestricted 1986 publications submitted to TPS by the Laboratory's Divisions. Author indexes list ANL authors only. If a first author is not an ANL employee, an asterisk in the bibliographic citation indicates the first ANL author. The report is divided into seven parts: Journal Articles -- Listed by first author; ANL Reports -- Listed by report number; ANL and non-ANL Unnumbered Reports -- Listed by report number; Non-ANL Numbered Reports -- Listed by report number; Books and Book Chapters -- Listed by first author; Conference Papers -- Listed by first author; and Complete Author Index.

Revised ANL-reported tensile data for unirradiated and irradiated (FFTF, HFIR) V-Ti and V-Cr-Ti alloys

International Nuclear Information System (INIS)

Billone, M.C.

1998-01-01

The tensile data for all unirradiated and irradiated vanadium alloys samples tested at Argonne National Laboratory (ANL) have been critically reviewed and, when necessary, revised. The review and revision are based on reanalyzing the original load-displacement strip chart recordings by a methodology consistent with current ASTM standards. For unirradiated alloys (162 samples), the revised values differ from the previous values as follows: -11±19 MPa (-4±6%) for yield strength (YS), -3±15 MPa (-1±3%) for ultimate tensile strength (UTS), -5±2% strain for uniform elongation (UE), and -4±2% strain for total elongation (TE). Of these changes, the decrease in -1±6 MPa (0±1%) for UTS, -5±2% for UE, and -4±2% for TE. Of these changes, the decrease in UE values for alloys irradiated and tested at 400--435 C is the most significant. This decrease results from the proper subtraction of nongauge-length deformation from measured crosshead deformation. In previous analysis of the tensile curves, the nongauge-length deformation was not correctly determined and subtracted from the crosshead displacement. The previously reported and revised tensile values for unirradiated alloys (20--700 C) are tabulated in Appendix A. The revised tensile values for the FFTF-irradiated (400--600 C) and HFIR-irradiated (400 C) alloys are tabulated in Appendix B, along with the neutron damage and helium levels. Appendix C compares the revised values to the previously reported values for irradiated alloys. Appendix D contains previous and revised values for the tensile properties of unirradiated V-5Cr-5Ti (BL-63) alloy exposed to oxygen

Plutonium working group report on environmental, safety and health vulnerabilities associated with the Department's plutonium storage. Volume II, part 8: Argonne National Laboratory - East and New Brunswick Laboratory working group assessment team report

International Nuclear Information System (INIS)

1994-09-01

The Plutonium Vulnerability Working Group Assessment Team No. 1 (WGAT-1) visited Argonne National Laboratory-East (ANL-E) and New Brunswick Laboratory (NBL), located at the ANL-Illinois site, from May 23 through May 27 and June 6 through June 10, 1994. The objective of the WGAT-1, the ANL-E Site Assessment Team (SAT), and the NBL SAT was to conduct a comprehensive assessment of the environment, safety, and health (ES ampersand H) vulnerabilities arising at ANL-E and NBL from the storage and handling of the Department's current plutonium holdings. During the first visit to the site (May 23-27), WGAT-1 toured various site facilities and, after each tour, met with SAT members to conduct 'table-top' discussions. In addition, various briefings were given to ANL-E management, NBL management, and DOE management. During the second visit (June 6-10), WGAT-1 completed their assessment report, and met with various site technical representatives

Advantages of binaural amplification to acceptable noise level of directional hearing aid users.

Science.gov (United States)

Kim, Ja-Hee; Lee, Jae Hee; Lee, Ho-Ki

2014-06-01

The goal of the present study was to examine whether Acceptable Noise Levels (ANLs) would be lower (greater acceptance of noise) in binaural listening than in monaural listening condition and also whether meaningfulness of background speech noise would affect ANLs for directional microphone hearing aid users. In addition, any relationships between the individual binaural benefits on ANLs and the individuals' demographic information were investigated. Fourteen hearing aid users (mean age, 64 years) participated for experimental testing. For the ANL calculation, listeners' most comfortable listening levels and background noise level were measured. Using Korean ANL material, ANLs of all participants were evaluated under monaural and binaural amplification with a counterbalanced order. The ANLs were also compared across five types of competing speech noises, consisting of 1- through 8-talker background speech maskers. Seven young normal-hearing listeners (mean age, 27 years) participated for the same measurements as a pilot testing. The results demonstrated that directional hearing aid users accepted more noise (lower ANLs) with binaural amplification than with monaural amplification, regardless of the type of competing speech. When the background speech noise became more meaningful, hearing-impaired listeners accepted less amount of noise (higher ANLs), revealing that ANL is dependent on the intelligibility of the competing speech. The individuals' binaural advantages in ANLs were significantly greater for the listeners with longer experience of hearing aids, yet not related to their age or hearing thresholds. Binaural directional microphone processing allowed hearing aid users to accept a greater amount of background noise, which may in turn improve listeners' hearing aid success. Informational masking substantially influenced background noise acceptance. Given a significant association between ANLs and duration of hearing aid usage, ANL measurement can be useful for

The effect of hearing aid signal-processing schemes on acceptable noise levels: perception and prediction.

Science.gov (United States)

Wu, Yu-Hsiang; Stangl, Elizabeth

2013-01-01

The acceptable noise level (ANL) test determines the maximum noise level that an individual is willing to accept while listening to speech. The first objective of the present study was to systematically investigate the effect of wide dynamic range compression processing (WDRC), and its combined effect with digital noise reduction (DNR) and directional processing (DIR), on ANL. Because ANL represents the lowest signal-to-noise ratio (SNR) that a listener is willing to accept, the second objective was to examine whether the hearing aid output SNR could predict aided ANL across different combinations of hearing aid signal-processing schemes. Twenty-five adults with sensorineural hearing loss participated in the study. ANL was measured monaurally in two unaided and seven aided conditions, in which the status of the hearing aid processing schemes (enabled or disabled) and the location of noise (front or rear) were manipulated. The hearing aid output SNR was measured for each listener in each condition using a phase-inversion technique. The aided ANL was predicted by unaided ANL and hearing aid output SNR, under the assumption that the lowest acceptable SNR at the listener's eardrum is a constant across different ANL test conditions. Study results revealed that, on average, WDRC increased (worsened) ANL by 1.5 dB, while DNR and DIR decreased (improved) ANL by 1.1 and 2.8 dB, respectively. Because the effects of WDRC and DNR on ANL were opposite in direction but similar in magnitude, the ANL of linear/DNR-off was not significantly different from that of WDRC/DNR-on. The results further indicated that the pattern of ANL change across different aided conditions was consistent with the pattern of hearing aid output SNR change created by processing schemes. Compared with linear processing, WDRC creates a noisier sound image and makes listeners less willing to accept noise. However, this negative effect on noise acceptance can be offset by DNR, regardless of microphone mode

Development and pilot demonstration program of a waste minimization plan at Argonne National Laboratory

International Nuclear Information System (INIS)

Peters, R.W.; Wentz, C.A.; Thuot, J.R.

1991-01-01

In response to US Department of Energy directives, Argonne National Laboratory (ANL) has developed a waste minimization plan aimed at reducing the amount of wastes at this national research and development laboratory. Activities at ANL are primarily research- oriented and as such affect the amount and type of source reduction that can be achieved at this facility. The objective of ANL's waste minimization program is to cost-effectively reduce all types of wastes, including hazardous, mixed, radioactive, and nonhazardous wastes. The ANL Waste Minimization Plan uses a waste minimization audit as a systematic procedure to determine opportunities to reduce or eliminate waste. To facilitate these audits, a computerized bar-coding procedure is being implemented at ANL to track hazardous wastes from where they are generated to their ultimate disposal. This paper describes the development of the ANL Waste Minimization Plan and a pilot demonstration of the how the ANL Plan audited the hazardous waste generated within a selected divisions of ANL. It includes quantitative data on the generation and disposal of hazardous waste at ANL and describes potential ways to minimize hazardous wastes. 2 refs., 5 figs., 8 tabs

The Acceptance of Background Noise in Adult Cochlear Implant Users

Science.gov (United States)

Plyler, Patrick N.; Bahng, Junghwa; von Hapsburg, Deborah

2008-01-01

Purpose: The purpose of this study was to determine (a) if acceptable noise levels (ANLs) are different in cochlear implant (CI) users than in listeners with normal hearing, (b) if ANLs are related to sentence reception thresholds in noise in CI users, and (c) if ANLs and subjective outcome measures are related in CI users. Method: ANLs and the…

Acceptance noise level: effects of the speech signal, babble, and listener language.

Science.gov (United States)

Shi, Lu-Feng; Azcona, Gabrielly; Buten, Lupe

2015-04-01

The acceptable noise level (ANL) measure has gained much research/clinical interest in recent years. The present study examined how the characteristics of the speech signal and the babble used in the measure may affect the ANL in listeners with different native languages. Fifteen English monolingual, 16 Russian-English bilingual, and 24 Spanish-English bilingual listeners participated. The ANL was obtained in eight conditions varying in the language of the signal (English and Spanish), language of the babble (English and Spanish), and number of talkers in the babble (4 and 12). Test conditions were randomized across listeners. The ANL for each condition was based on a minimum of two trials. Russian-English bilinguals yielded higher ANLs than other listeners; the intergroup difference of 4-5 dB was statistically and clinically significant. Spanish signals yielded significantly higher ANLs than English signals, but this difference of 0.5 dB was clinically negligible. The language and composition of the babble had a significant effect on Russian-English bilinguals, who yielded higher ANLs with the Spanish than English 12-talker babble. The above findings do not fully support the notion that the ANL is language- and population-independent. Clinicians should be aware of possible effects on ANL measures due to listeners' linguistic/cultural background.

Argonne National Laboratory, east hazardous waste shipment data validation

International Nuclear Information System (INIS)

Casey, C.; Graden, C.; Coveleskie, A.

1995-09-01

At the request of EM-331, the Radioactive Waste Technical Support Program (TSP) is conducting an evaluation of data regarding past hazardous waste shipments from DOE sites to commercial TSDFs. The intent of the evaluation is to find out if, from 1984 to 1991, DOE sites could have shipped hazardous waste contaminated with DOE-added radioactivity to commercial TSDFs not licensed to receive radioactive material. A team visited Argonne National Laboratory, East (ANL-E) to find out if any data existed that would help to make such a determination at ANL-E. The team was unable to find any relevant data. The team interviewed personnel who worked in waste management at the time. All stated that ANL-E did not sample and analyze hazardous waste shipments for radioactivity. Waste generators at ANL-E relied on process knowledge to decide that their waste was not radioactive. Also, any item leaving a building where radioisotopes were used was surveyed using hand-held instrumentation. If radioactivity above the criteria in DOE Order 5400.5 was found, the item was considered radioactive. The only documentation still available is the paperwork filled out by the waste generator and initialed by a health physics technician to show no contamination was found. The team concludes that, since all waste shipped offsite was subjected at least once to health physics instrumentation scans, the waste shipped from ANL-E from 1984 to 1991 may be considered clean

Structure of the d-alanylgriseoluteic acid biosynthetic protein EhpF, an atypical member of the ANL superfamily of adenylating enzymes

International Nuclear Information System (INIS)

Bera, Asim K.; Atanasova, Vesna; Gamage, Swarna; Robinson, Howard; Parsons, James F.

2010-01-01

The structure of EhpF from P. agglomerans has been solved alone and in complex with phenazine-1,6-dicarboxylate. Apo EhpF was solved and refined in two different space groups at 1.95 and 2.3 Å resolution and the EhpF–phenazine-1,6-dicarboxylate complex structure was determined at 2.8 Å resolution. The structure of EhpF, a 41 kDa protein that functions in the biosynthetic pathway leading to the broad-spectrum antimicrobial compound d-alanylgriseoluteic acid (AGA), is reported. A cluster of approximately 16 genes, including ehpF, located on a 200 kbp plasmid native to certain strains of Pantoea agglomerans encodes the proteins that are required for the conversion of chorismic acid to AGA. Phenazine-1,6-dicarboxylate has been identified as an intermediate in AGA biosynthesis and deletion of ehpF results in accumulation of this compound in vivo. The crystallographic data presented here reveal that EhpF is an atypical member of the acyl-CoA synthase or ANL superfamily of adenylating enzymes. These enzymes typically catalyze two-step reactions involving adenylation of a carboxylate substrate followed by transfer of the substrate from AMP to coenzyme A or another phosphopantetheine. EhpF is distinguished by the absence of the C-terminal domain that is characteristic of enzymes from this family and is involved in phosphopantetheine binding and in the second half of the canonical two-step reaction that is typically observed. Based on the structure of EhpF and a bioinformatic analysis, it is proposed that EhpF and EhpG convert phenazine-1,6-dicarboxylate to 6-formylphenazine-1-carboxylate via an adenylyl intermediate

Argonne National Laboratory 1985 publications

International Nuclear Information System (INIS)

Kopta, J.A.; Hale, M.R.

1987-08-01

This report is a bibliography of scientific and technical 1985 publications of Argonne National Laboratory. Some are ANL contributions to outside organizations' reports published in 1985. This compilation, prepared by the Technical Information Services Technical Publications Section (TPB), lists all nonrestricted 1985 publications submitted to TPS by Laboratory's Divisions. The report is divided into seven parts: Journal Articles - Listed by first author, ANL Reports - Listed by report number, ANL and non-ANL Unnumbered Reports - Listed by report number, Non-ANL Numbered Reports - Listed by report number, Books and Book Chapters - Listed by first author, Conference Papers - Listed by first author, Complete Author Index

[Relationship between the Mandarin acceptable noise level and the personality traits in normal hearing adults].

Science.gov (United States)

Wu, Dan; Chen, Jian-yong; Wang, Shuo; Zhang, Man-hua; Chen, Jing; Li, Yu-ling; Zhang, Hua

2013-03-01

To evaluate the relationship between the Mandarin acceptable noise level (ANL) and the personality trait for normal-hearing adults. Eighty-five Mandarin speakers, aged from 21 to 27, participated in this study. ANL materials and the Eysenck Personality Questionnaire (EPQ) questionnaire were used to test the acceptable noise level and the personality trait for normal-hearing subjects. SPSS 17.0 was used to analyze the results. ANL were (7.8 ± 2.9) dB in normal hearing participants. The P and N scores in EPQ were significantly correlated with ANL (r = 0.284 and 0.318, P 0.05). Listeners with higher ANL were more likely to be eccentric, hostile, aggressive, and instabe, no ANL differences were found in listeners who were different in introvert-extravert or lying.

Argonne National Laboratory 1985 publications

Energy Technology Data Exchange (ETDEWEB)

Kopta, J.A. (ED.); Hale, M.R. (comp.)

1987-08-01

This report is a bibliography of scientific and technical 1985 publications of Argonne National Laboratory. Some are ANL contributions to outside organizations' reports published in 1985. This compilation, prepared by the Technical Information Services Technical Publications Section (TPB), lists all nonrestricted 1985 publications submitted to TPS by Laboratory's Divisions. The report is divided into seven parts: Journal Articles - Listed by first author, ANL Reports - Listed by report number, ANL and non-ANL Unnumbered Reports - Listed by report number, Non-ANL Numbered Reports - Listed by report number, Books and Book Chapters - Listed by first author, Conference Papers - Listed by first author, Complete Author Index.

The effects of noise reduction technologies on the acceptance of background noise.

Science.gov (United States)

Lowery, Kristy Jones; Plyler, Patrick N

2013-09-01

Directional microphones (D-Mics) and digital noise reduction (DNR) algorithms are used in hearing aids to reduce the negative effects of background noise on performance. Directional microphones attenuate sounds arriving from anywhere other than the front of the listener while DNR attenuates sounds with physical characteristics of noise. Although both noise reduction technologies are currently available in hearing aids, it is unclear if the use of these technologies in isolation or together affects acceptance of noise and/or preference for the end user when used in various types of background noise. The purpose of the research was to determine the effects of D-Mic, DNR, or the combination of D-Mic and DNR on acceptance of noise and preference when listening in various types of background noise. An experimental study in which subjects were exposed to a repeated measures design was utilized. Thirty adult listeners with mild sloping to moderately severe sensorineural hearing loss participated (mean age 67 yr). Acceptable noise levels (ANLs) were obtained using no noise reduction technologies, D-Mic only, DNR only, and the combination of the two technologies (Combo) for three different background noises (single-talker speech, speech-shaped noise, and multitalker babble) for each listener. In addition, preference rankings of the noise reduction technologies were obtained within each background noise (1 = best, 3 = worst). ANL values were significantly better for each noise reduction technology than baseline; and benefit increased significantly from DNR to D-Mic to Combo. Listeners with higher (worse) baseline ANLs received more benefit from noise reduction technologies than listeners with lower (better) baseline ANLs. Neither ANL values nor ANL benefit values were significantly affected by background noise type; however, ANL benefit with D-Mic and Combo was similar when speech-like noise was present while ANL benefit was greatest for Combo when speech spectrum noise was

Argonne National Laboratory's photo-oxidation organic mixed waste treatment system - installation and startup testing

International Nuclear Information System (INIS)

Shearer, T.L.; Nelson, R.A.; Torres, T.; Conner, C.; Wygmans, D.

1997-01-01

This paper describes the installation and startup testing of the Argonne National Laboratory (ANL-E) Photo-Oxidation Organic Mixed Waste Treatment System. This system will treat organic mixed (i.e., radioactive and hazardous) waste by oxidizing the organics to carbon dioxide and inorganic salts in an aqueous media. The residue will be treated in the existing radwaste evaporators. The system is installed in the Waste Management Facility at the ANL-E site in Argonne, Illinois. 1 fig

Tiger team assessment of the Argonne Illinois site

International Nuclear Information System (INIS)

1990-01-01

This report documents the results of the Department of Energy's (DOE) Tiger Team Assessment of the Argonne Illinois Site (AIS) (including the DOE Chicago Operations Office, DOE Argonne Area Office, Argonne National Laboratory-East, and New Brunswick Laboratory) and Site A and Plot M, Argonne, Illinois, conducted from September 17 through October 19, 1990. The Tiger Team Assessment was conducted by a team comprised of professionals from DOE, contractors, consultants. The purpose of the assessment was to provide the Secretary of Energy with the status of Environment, Safety, and Health (ES ampersand H) Programs at AIS. Argonne National Laboratory-East (ANL-E) is the principal tenant at AIS. ANL-E is a multiprogram laboratory operated by the University of Chicago for DOE. The mission of ANL-E is to perform basic and applied research that supports the development of energy-related technologies. There are a significant number of ES ampersand H findings and concerns identified in the report that require prompt management attention. A significant change in culture is required before ANL-E can attain consistent and verifiable compliance with statutes, regulations and DOE Orders. ES ampersand H activities are informal, fragmented, and inconsistently implemented. Communication is seriously lacking, both vertically and horizontally. Management expectations are not known or commondated adequately, support is not consistent, and oversight is not effective

Tiger team assessment of the Argonne Illinois site

Energy Technology Data Exchange (ETDEWEB)

1990-10-19

This report documents the results of the Department of Energy's (DOE) Tiger Team Assessment of the Argonne Illinois Site (AIS) (including the DOE Chicago Operations Office, DOE Argonne Area Office, Argonne National Laboratory-East, and New Brunswick Laboratory) and Site A and Plot M, Argonne, Illinois, conducted from September 17 through October 19, 1990. The Tiger Team Assessment was conducted by a team comprised of professionals from DOE, contractors, consultants. The purpose of the assessment was to provide the Secretary of Energy with the status of Environment, Safety, and Health (ES H) Programs at AIS. Argonne National Laboratory-East (ANL-E) is the principal tenant at AIS. ANL-E is a multiprogram laboratory operated by the University of Chicago for DOE. The mission of ANL-E is to perform basic and applied research that supports the development of energy-related technologies. There are a significant number of ES H findings and concerns identified in the report that require prompt management attention. A significant change in culture is required before ANL-E can attain consistent and verifiable compliance with statutes, regulations and DOE Orders. ES H activities are informal, fragmented, and inconsistently implemented. Communication is seriously lacking, both vertically and horizontally. Management expectations are not known or commondated adequately, support is not consistent, and oversight is not effective.

The Relationship between Personality Type and Acceptable Noise Levels: A Pilot Study.

Science.gov (United States)

Franklin, Cliff; Johnson, Laura V; White, Letitia; Franklin, Clay; Smith-Olinde, Laura

2013-01-01

Objectives. This study examined the relationship between acceptable noise level (ANL) and personality. ANL is the difference between a person's most comfortable level for speech and the loudest level of background noise they are willing to accept while listening to speech. Design. Forty young adults with normal hearing participated. ANLs were measured and two personality tests (Big Five Inventory, Myers-Briggs Type Indicator) were administered. Results. The analysis revealed a correlation between ANL and the openness and conscientious personality dimensions from the Big Five Inventory; no correlation emerged between ANL and the Myers-Briggs personality types. Conclusions. Lower ANLs are correlated with full-time hearing aid use and the openness personality dimension; higher ANLs are correlated with part-time or hearing aid nonuse and the conscientious personality dimension. Current data suggest that those more open to new experiences may accept more noise and possibly be good hearing aid candidates, while those more conscientious may accept less noise and reject hearing aids, based on their unwillingness to accept background noise. Knowing something about a person's personality type may help audiologists determine if their patients will likely be good candidates for hearing aids.

Decontamination and decommissioning of 61 plutonium gloveboxes in D-Wing, Building 212 Argonne National Laboratory-East: Final project report

International Nuclear Information System (INIS)

Cheever, C.L.; Rose, R.W.

1996-09-01

Argonne National Laboratory-East (ANL-E) is a government-owned, contractor operated, multipurpose research facility located 25 miles southwest of downtown Chicago on 689 hectares (1,700 acres) in DuPage County, Illinois, as shown in Figure 1.1. Building 212 is located in the central area of ANL-E, as shown in Figure 1.2. The purpose of this project was to eliminate the risk of radioactive material release from the contaminated glovebox systems and to make the laboratories available for unrestricted use. The following work objectives were established: (1) Identify and remove radioactive materials for return to ANL-E Special Materials control. (2) Remove and package the radioactively contaminated materials and equipment from the gloveboxes. (3) Decontaminate the gloveboxes to nontransuranic (non-TRU) levels. (4) Size-reduce and package the gloveboxes and support systems. (5) Document and dispose of the radioactive and mixed waste. (6) Decontaminate, survey, and release the nine laboratories and corridor areas for unrestricted use

Low-level radioactive waste management at Argonne National Laboratory-East

International Nuclear Information System (INIS)

Rock, C.M.; Shearer, T.L.; Nelson, R.A.

1997-01-01

This paper is an overview of the low-level radioactive waste management practices and treatment systems at Argonne National Laboratory - East (ANL-E). It addresses the systems, processes, types of waste treated, and the status and performance of the systems. ANL-E is a Department of Energy laboratory that is engaged in a variety of research projects, some of which generate radioactive waste, in addition a significant amount of radioactive waste remains from previous projects and decontamination and decommissioning of facilities where this work was performed

Acceptable noise level with Danish, Swedish, and non-semantic speech materials

DEFF Research Database (Denmark)

Brännström, K Jonas; Lantz, Johannes; Nielsen, Lars Holme

2012-01-01

reported results from American studies. Generally, significant differences were seen between test conditions using different types of noise within ears in each population. Significant differences were seen for ANL across populations, also when the non-semantic ISTS was used as speech signal. Conclusions......Abstract Objective: Acceptable noise level (ANL) has been established as a method to quantify the acceptance of background noise while listening to speech presented at the most comfortable level. The aim of the present study was to generate Danish, Swedish, and a non-semantic version of the ANL...... test and investigate normal-hearing Danish and Swedish subjects' performance on these tests. Design: ANL was measured using Danish and Swedish running speech with two different noises: Speech-weighted amplitude-modulated noise, and multitalker speech babble. ANL was also measured using the non...

Dicty_cDB: VSC691 [Dicty_cDB

Lifescience Database Archive (English)

Full Text Available no Acid sequence ---snefptftfvpvdlgkvnthpivkei*sxptfyfyvngakvsefrgaxeatxgstfe anl...kkkkkkkkkkkkkkk Frame B: ---snefptftfvpvdlgkvnthpivkei*sxptfyfyvngakvsefrgaxeatxgstfe anl*ffvkliiaqkmpqik*II

Immobilization of fission products in phosphate ceramic waste forms

International Nuclear Information System (INIS)

Singh, D.; Wagh, A.

1997-01-01

Argonne National Laboratory (ANL) is developing chemically bonded phosphate ceramics (CBPCs) to treat low-level mixed wastes, particularly those containing volatiles and pyrophorics that cannot be treated by conventional thermal processes. This work was begun under ANL''s Laboratory Directed Research and Development funds, followed by further development with support from EM-50''s Mixed Waste Focus Area

Evidence of a treatment dose response in acute nonlymphocytic leukemias which occur after therapy of non-Hodgkin's lymphoma

International Nuclear Information System (INIS)

Greene, M.H.; Young, R.C.; Merrill, J.M.; DeVita, V.T.

1983-01-01

We evaluated the occurrence of second cancers among 517 patients with non-Hodgkin's lymphoma (NHL) treated at the National Cancer Institute. Nine cases of acute nonlymphocytic leukemia (ANL) were observed compared to 0.08 cases expected (ratio of observed to expected cases, 105; 95% confidence limits, 48; 199). The excess risk of ANL was 4.1 cases per 1000 patients per year; the cumulative risk of ANL at 10 years was 7.9 +/- 3.2% (S.E.). A case-control study within the NHL cohort revealed that patients treated with both radiation and chemotherapy were at greater risk of ANL than were patients who received single-modality therapy (relative risk, 6.0; p less than 0.05), especially if the therapy included total-body or hemibody radiation. A positive correlation between cumulative radiation dose to the bone marrow and risk of ANL was demonstrated, independent of chemotherapy duration. A similar correlation between chemotherapy dose and risk of ANL was suggested but could not be proven with the available data. An apparent association between ANL risk and indolent NHL histological subtypes was due to the significantly larger amounts of potentially leukemogenic therapy to which these patients were repeatedly exposed. Only one case of ANL occurred among NHL patients whose initial therapy produced a durable complete remission. Our data are compatible with a multistep model of leukemogenesis and also underscore the need for curative NHL treatment regimens which minimize the duration and quantity of therapy required for optimum patient management

Argonne National Laboratory-East site environmental report for calendar year 1992

International Nuclear Information System (INIS)

Golchert, N.W.; Kolzow, R.G.

1993-05-01

This report discusses the results of the Environmental Protection Program at Argonne National Laboratory-East (ANL) for 1992. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed

Argonne National Laboratory-East site environmental report for calendar year 1992

Energy Technology Data Exchange (ETDEWEB)

Golchert, N.W.; Kolzow, R.G.

1993-05-01

This report discusses the results of the Environmental Protection Program at Argonne National Laboratory-East (ANL) for 1992. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed.

A Mechanical Musculo-Skeletal System for a Human-Shaped Robot Arm

Directory of Open Access Journals (Sweden)

Koichi Koganezawa

2014-06-01

Full Text Available This paper presents a mechanical system with a similar configuration to a human musculo-skeletal system for use in anthropomorphic robots or as artificial limbs for disabled persons. First, a mechanical module called ANLES (Actuator with Non-Linear Elasticity System is introduced. There are two types of ANLES: the linear-type ANLES and rotary-type ANLES. They can be used as a voluntary muscle in a wide-range of musculo-skeletal structures in which at least double actuators work in an antagonistic setup via some elastic elements. Next, an application of the two types of ANLES to a two-degree-of-freedom (DOF manipulator that has a similar configuration to the human elbow joint is shown. The experimental results of the joint stiffness and joint angle control elucidate that the developed mechanism effectively regulates joint stiffness in the same way as a musculo-skeletal system.

Improvements in the fabrication of metallic fuels

International Nuclear Information System (INIS)

Tracy, D.B.; Henslee, S.P.; Dodds, N.E.; Longua, K.J.

1989-01-01

Argonne National Laboratory (ANL) is currently developing a new liquid-metal-cooled breeder reactor known as the Integral Fast Reactor (IFR). The IFR represents the state of the art in metal-fueled reactor technology. Improvements in the fabrication of metal fuel, discussed in this paper, will support ANL-West's (ANL-W) fully remote fuel cycle facility, which is an integral part of the IFR concept

Geochemistry of Hydrothermal Alteration Associated with Cenozoic Intrusion-Hosted Cu-Pb-Zn Mineralization at Tavşanlı Area, Kütahya, NW Turkey

Directory of Open Access Journals (Sweden)

Mustafa Kumral

2016-02-01

Full Text Available The Miocene magmatic intrusion in the Tavşanlı zone of the Kütahya-Bolkardağ Belt (KBB in the northwestern region of Turkey is represented by the Eğrigöz granitoids. This paper studies the petrology and geochemistry of hydrothermal alterations associated with the vein-type Cu-Pb-Zn mineralization hosted by this pluton, focusing on the determination of the mass gains and losses of chemical components, which reflect the chemical exchanges between the host rocks and hydrothermal fluids. Vein-type Cu-Pb-Zn mineralization is closely associated with intense hydrothermal alterations within the brecciation, quartz stockwork veining, and brittle fracture zones that are controlled by NW-SE trending faults cutting through the Eğrigöz granitoids. Paragenetic relationships reveal three stages of mineralization: pre-ore, ore, and supergene. The ore mineralogy typically includes hypogene chalcopyrite, sphalerite, galena, and pyrite, with locally supergene covellite, malachite, and azurite. Wall-rock hypogene hydrothermal alterations include pervasive silicification, sulfidation, sericitization, and selective carbonatization and albitization. These are distributed in three main alteration zones (zone 1: silicified/iron carbonatized alterations ± albite, zone 2: argillic-silicic alterations, and zone 3: phyllic alterations. Based on the gains and losses of mass and volume (calculated by the GEOISO-Windows™ program, zone 1 has a higher mass and volume gain than zones 2 and 3. Non-systematic zonal distributions of alterations are observed in which the silicic-carbonate alterations +/− albitization appeared in zone 1 in the center and the phyllic-argillic alterations appeared in zones 2 and 3, with an increase in base metals (Cu-Pb-Zn in the zone from Cu, Cu-Pb, to Cu-Pb-Zn moving outwards.

Risk Factors and Relationship Between Intestinal Parasites and the Growth Retardation and Psychomotor Development Delays of Children in Şanlıurfa, Turkey.

Science.gov (United States)

Yentur Doni, Nebiye; Yildiz Zeyrek, Fadile; Simsek, Zeynep; Gurses, Gulcan; Sahin, İbrahim

2015-12-01

The objective of this study was to determine the risk factors for and relationship among parasitic infections, growth retardation, and psychomotor developmental delays in children aged 6 years and below. This case-control study was performed in Şanlıurfa in southeastern Turkey between October and December 2007. Data were collected using a structured questionnaire, anthropometry, Ankara Development Screening Inventory, and laboratory analysis of stool specimens. The most common parasite was Giardia intestinalis (42.53%) followed by Enterobius vermicularis (27.58%), Ascaris lumbricoides (18.39%), Hymenolepis nana (5.75%), Trichuris trichiura (3.45%), Escherichia coli (1.15%), and Blastocystis spp. (1.15%). Fifty-eight percent of all children were infected with intestinal parasites; 55.2% had only one parasite, whereas 44.8% had multiple parasites. The children infected with G. intestinalis and other intestinal parasites had significantly higher levels of growth retardation and psychomotor development delay than non-infected children. Children with parasitic infections had growth delay up to 2.9 times, general development delay up to 1.9 times, language-cognitive development delay up to 2.2 times, and fine motor development delay up to 2.9 times higher than children without any parasitic infections. However, no significant relationship among intestinal parasites, gross motor development, social-self skills, and development delay was identified. The education level of parents, poor economic situation, number of households, not washing hands, playing with soil, family history of parasitic infection were the significant risk factors for intestinal parasites. Our study indicates that the presence of either malnutrition or intestinal parasites may put a child in a high-risk group for developmental delays and growth retardation. Therefore, public health interventions can embrace nationwide deworming in children.

Acceptable noise level with Danish, Swedish, and non-semantic speech materials

DEFF Research Database (Denmark)

Brännström, K Jonas; Lantz, Johannes; Nielsen, Lars Holme

2012-01-01

: The present findings indicate that there are extrinsic factors, such as instructions, affecting the ANL results. Summario Objetivo: Se ha establecido el Nivel de Ruido Aceptable (ANL) como un método para cuantifi car la aceptación de ruido de fondo mientras se escucha lenguaje presentado al nivel más...... confortable. El objetivo de este estudio fue generar las versiones sueca, danesa y una no-semántica de la prueba ANL e investigar el desempeño de sujetos normoyentes daneses y suecos en estas pruebas. Diseño: Se midió el ANL utilizando un discurso continuo en danés y sueco con dos diferentes ruidos: ruido con...

LLNL contributions to ANL Report ANL/NE-16/6 'Sharp User Manual'

International Nuclear Information System (INIS)

Solberg, J. M.

2016-01-01

Diablo is a Multiphysics implicit finite element code with an emphasis on coupled structural/thermal analysis. In the SHARP framework, it is used as the structural solver, and may also be used as the mesh smoother.

Argonne National Laboratory-East site environmental report for calendar year 1993

International Nuclear Information System (INIS)

Golchert, N.W.; Kolzow, R.G.

1994-05-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1993. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects from past activities

Argonne National Laboratory-East site environmental report for calendar year 1994

International Nuclear Information System (INIS)

Golchert, N.W.; Kolzow, R.G.

1995-05-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1994. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK COMPUTER CODE, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects

Argonne National Laboratory-East site environmental report for calendar year 1994

Energy Technology Data Exchange (ETDEWEB)

Golchert, N.W.; Kolzow, R.G.

1995-05-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1994. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK COMPUTER CODE, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects.

Argonne National Laboratory--East site environmental report for calendar year 1990

International Nuclear Information System (INIS)

Golchert, N.W.; Duffy, T.L.; Moos, L.P.

1991-07-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1990. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, bottom sediment, and milk samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects from past activities

Argonne National Laboratory-East site environmental report for calendar year 1991

International Nuclear Information System (INIS)

Golchert, N.W.; Duffy, T.L.; Moos, L.P.

1992-05-01

This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1991. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. Chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects from past activities

Argonne National Laboratory site environmental report for calendar year 2004.

Energy Technology Data Exchange (ETDEWEB)

Golchert, N. W.; Kolzow, R. G.

2005-09-02

This report discusses the accomplishments of the environmental protection program at Argonne National Laboratory (ANL) for calendar year 2004. The status of ANL environmental protection activities with respect to compliance with the various laws and regulations is discussed, along with the progress of environmental corrective actions and restoration projects. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A U.S. Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the U.S. Environmental Protection Agency's CAP-88 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report.

JANUS reactor d and d project

International Nuclear Information System (INIS)

Fellhauer, C. R.

1998-01-01

Argonne National Laboratory (ANL-E) has recently completed the decontamination and decommissioning (D and D) of the JANUS Reactor Facility located in Building 202. The 200 KW reactor operated from August 1963 to March 1992. The facility was used to study the effects of both high and low doses of fission neutrons in animals. There were two exposure rooms on opposite sides of the reactor and the reactor was therefore named after the two-faced Roman god. The High Dose Room was capable of specimen exposure at a dose rate of 3,600 rads per hour. During calendar year 1996 a detailed characterization of the facility was performed by ANL-E Health Physics personnel. ANL-E Analytical Services performed the required sample analysis. An Auditable Safety Analysis and an Environmental Assessment were completed. D and D plans, procedures and procurement documents were prepared and approved. A D and D subcontractor was selected and a firm, fixed price contract awarded for the field work and final survey effort. The D and D subcontractor was mobilized to ANL-E in January 1997. Electrical isolation of all reactor equipment and control panels was accomplished and the equipment removed. A total of 207,230 pounds (94,082 Kg) of lead shielding was removed, surveyed and sampled, and free-released for recycle. All primary and secondary piping was removed, size reduced and packaged for disposal or recycled as appropriate. The reactor vessel was removed, sized reduced and packaged as radioactive waste in April. The activated graphite block reflector was removed next, followed by the bioshield concrete and steel. All of this material was packaged as low level waste. Total low level radioactive waste generation was 4002.1 cubic feet (113.3 cubic meters). Mixed waste generation was 538 cubic feet (15.2 cubic meters). The Final Release Survey was completed in September. The project field work was completed in 38 weeks without any lost-time accidents, personnel contaminations or unplanned

Acceptance of background noise, working memory capacity, and auditory evoked potentials in subjects with normal hearing.

Science.gov (United States)

Brännström, K Jonas; Zunic, Edita; Borovac, Aida; Ibertsson, Tina

2012-01-01

The acceptable noise level (ANL) test is a method for quantifying the amount of background noise that subjects accept when listening to speech. Large variations in ANL have been seen between normal-hearing subjects and between studies of normal-hearing subjects, but few explanatory variables have been identified. To explore a possible relationship between a Swedish version of the ANL test, working memory capacity (WMC), and auditory evoked potentials (AEPs). ANL, WMC, and AEP were tested in a counterbalanced order across subjects. Twenty-one normal-hearing subjects participated in the study (14 females and 7 males; aged 20-39 yr with an average of 25.7 yr). Reported data consists of age, pure-tone average (PTA), most comfortable level (MCL), background noise level (BNL), ANL (i.e., MCL - BNL), AEP latencies, AEP amplitudes, and WMC. Spearman's rank correlation coefficient was calculated between the collected variables to investigate associations. A principal component analysis (PCA) with Varimax rotation was conducted on the collected variables to explore underlying factors and estimate interactions between the tested variables. Subjects were also pooled into two groups depending on their results on the WMC test, one group with a score lower than the average and one with a score higher than the average. Comparisons between these two groups were made using the Mann-Whitney U-test with Bonferroni correction for multiple comparisons. A negative association was found between ANL and WMC but not between AEP and ANL or WMC. Furthermore, ANL is derived from MCL and BNL, and a significant positive association was found between BNL and WMC. However, no significant associations were seen between AEP latencies and amplitudes and the demographic variables, MCL, and BNL. The PCA identified two underlying factors: One that contained MCL, BNL, ANL, and WMC and another that contained latency for wave Na and amplitudes for waves V and Na-Pa. Using the variables in the first factor

The Relationship between Personality Type and Acceptable Noise Levels: A Pilot Study

OpenAIRE

Franklin, Cliff; Johnson, Laura V.; White, Letitia; Franklin, Clay; Smith-Olinde, Laura

2013-01-01

Objectives. This study examined the relationship between acceptable noise level (ANL) and personality. ANL is the difference between a person’s most comfortable level for speech and the loudest level of background noise they are willing to accept while listening to speech. Design. Forty young adults with normal hearing participated. ANLs were measured and two personality tests (Big Five Inventory, Myers-Briggs Type Indicator) were administered. Results. The analysis revealed a correlation bet...

Argonne National Laboratory-East site environmental report for calendar year 1989

International Nuclear Information System (INIS)

Golchert, N.W.; Duffy, T.L.

1990-04-01

This report discusses the results of the environmental monitoring program at Argonne National Laboratory (ANL) for 1989. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared. A variety of radionuclides were measured in air, surface water, groundwater, soil, grass, bottom sediment, and milk samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the monitoring program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations, is used in this report. This report also discusses progress being made on corrective actions and restoration projects from past activities. 27 refs., 7 figs., 75 tabs

Marrow, ovary, and breast doses delivered by CHR diagnostic x-ray examinations: an update

International Nuclear Information System (INIS)

Schlenker, R.A.; Oltman, B.G.

1977-01-01

The mean absorbed dose averaged over the marrow volume in a RANDO phantom is 232 +- 14 mrad and 175 +- 26 mrad when the ANL examination is made using 1 mm Al and 3 mm Al added filtration, respectively; it is 606 +- 69 mrad when the MIT examination is made. The absorbed dose averaged over the ovaries is 243 +- 25 mrad and 162 +- 38 mrad for 1 mm Al and 3 mm Al at ANL and 606 +- 40 mrad for the MIT examination. Breast doses are 388 +- 35 mrad, 226 +- 9 mrad, and 333 +- 103 mrad. Dose reduction could be achieved by using a faster film-screen combination for the MIT examination, by routinely using 3 mm Al added filtration at ANL and by improving the collimation at ANL

Radiological Characterization Methodology for INEEL-Stored Remote-Handled Transuranic (RH TRU) Waste from Argonne National Laboratory-East

International Nuclear Information System (INIS)

Kuan, P.; Bhatt, R.N.

2003-01-01

An Acceptable Knowledge (AK)-based radiological characterization methodology is being developed for RH TRU waste generated from ANL-E hot cell operations performed on fuel elements irradiated in the EBR-II reactor. The methodology relies on AK for composition of the fresh fuel elements, their irradiation history, and the waste generation and collection processes. Radiological characterization of the waste involves the estimates of the quantities of significant fission products and transuranic isotopes in the waste. Methods based on reactor and physics principles are used to achieve these estimates. Because of the availability of AK and the robustness of the calculation methods, the AK-based characterization methodology offers a superior alternative to traditional waste assay techniques. Using the methodology, it is shown that the radiological parameters of a test batch of ANL-E waste is well within the proposed WIPP Waste Acceptance Criteria limits

Major results on the development of high density U-Mo fuel and pin-type fuel elements executed under the Russian RERTR program and in cooperation with ANL (USA)

International Nuclear Information System (INIS)

Vatulin, A.; Morozov, A.; Stetsky, Y.; Suprun, V.; Dobrikova, I.; Trifonov, Y.; Mishunin, V.; Sorokin, V.

2003-01-01

VNIINM is active participant of 'Russian program on Reduced Enrichment for Research and Test Reactors'. Institute Works in two main directions: 1) development of new high-density fuels (HDF) and 2) development of new design of fuel elements with LEU. The development of the new type fuel element is carried out both for existing reactors, and for developing new advanced reactors. The 'TVEL' concern is coordinator of works of this program. The majority enterprises of branch (NIIAR, PIYaF, RRC KI, NZChK) take part in this work. Since 2000 these works are being conducted in cooperation with Argonne National Laboratory (USA) within the RERTR program under VNIINM with ANL contract. At the present, a large set of pre-pile investigations has been completed. All necessary fabrication procedures have been developed for utilization of U-Mo dispersion fuel in Russian-designed research reactors. For irradiation tests the pin-type mini-fuel elements with HDF dispersion fuel with LEU and the uranium density equaled to 4,0 and 6,0 g/cm 3 (up to 40 vol.%) have been manufactured. Their irradiation began in August 2003 in the MIR reactor (NIIAR, Dimitrovgrad). A large set of works for preparation of lifetime tests (WWR-M reactor in Gatchina) of two full-scale fuel assemblies with new pin-type fuel elements on basis LEU UO 2 -Al and UMo-Al fuels has been completed. The in-pile tests of fuel assemblies began in September 2003. The summary of important results of performed works and their near-term future are presented in paper. (author)

Kongernes Jelling

DEFF Research Database (Denmark)

Høyer, Steen

2001-01-01

Nyt udstillingsbyggeri opført vest for kirken i Jelling. Anlægget rummet udover udstillingslokaler kontorer, bibliotek, multimediesal og cafe.......Nyt udstillingsbyggeri opført vest for kirken i Jelling. Anlægget rummet udover udstillingslokaler kontorer, bibliotek, multimediesal og cafe....

The Effect of Material Variability on Fatigue Behaviors of Low Alloy Steels in 310 .deg. C Deoxygenated Water

International Nuclear Information System (INIS)

Jang, Hun; Jang, Changheui; Kim, Insup; Cho, Hyunchul

2008-01-01

As environmental fatigue damage is one of the main crack initiation mechanisms in nuclear power plants (NPPs), it is most important factor to assess the integrity and safety of NPPs. So, based on extensive researches, argon nation laboratory (ANL) suggested the statistical model to predict fatigue life of low alloy steels (LASs) which are widely used as structural material in NPPs. Also, we reported the environmental fatigue behaviors of SA508 Gr.1a LAS. However, from comparison between our experimental fatigue data and ANL's statistical model, our fatigue life data showed poor agreement with the ANL's statistical model. In this regard, the additional low cycle fatigue (LCF) tests were performed in 310 .deg. C deoxygenated water, and compared with ANL's statistical model to evaluate reliability of the data. And then, the effect of material variability on the fatigue life of LASs was investigated through microstructure analysis

The Effects of Audiovisual Stimulation on the Acceptance of Background Noise.

Science.gov (United States)

Plyler, Patrick N; Lang, Rowan; Monroe, Amy L; Gaudiano, Paul

2015-05-01

Previous examinations of noise acceptance have been conducted using an auditory stimulus only; however, the effect of visual speech supplementation of the auditory stimulus on acceptance of noise remains limited. The purpose of the present study was to determine the effect of audiovisual stimulation on the acceptance of noise in listeners with normal and impaired hearing. A repeated measures design was utilized. A total of 92 adult participants were recruited for this experiment. Of these participants, 54 were listeners with normal hearing and 38 were listeners with sensorineural hearing impairment. Most comfortable levels and acceptable noise levels (ANL) were obtained using auditory and auditory-visual stimulation modes for the unaided listening condition for each participant and for the aided listening condition for 35 of the participants with impaired hearing that owned hearing aids. Speech reading ability was assessed using the Utley test for each participant. The addition of visual input did not impact the most comfortable level values for listeners in either group; however, visual input improved unaided ANL values for listeners with normal hearing and aided ANL values in listeners with impaired hearing. ANL benefit received from visual speech input was related to the auditory ANL in listeners in each group; however, it was not related to speech reading ability for either listener group in any experimental condition. Visual speech input can significantly impact measures of noise acceptance. The current ANL measure may not accurately reflect acceptance of noise values when in more realistic environments, where the signal of interest is both audible and visible to the listener. American Academy of Audiology.

Historic preservation requirements and the evaluation of cold war era nuclear facilities at Argonne National Laboratory-East

International Nuclear Information System (INIS)

Wescott, K. L.

1999-01-01

Project design for the decontamination and decommissioning (D and D) of federal facilities must address the requirements of the National Environmental Policy Act which includes compliance with the National Historic Preservation Act (NHPA). Section 106 of the NHPA requires that Federal agencies consider any effect their activities may have on historic properties. While a cultural property is not usually considered historic until it has reached an age of 50 years or older, special consideration is given to younger properties if they are of exceptional importance in demonstrating unique development in American history, architecture, archaeology, engineering, or culture. As part of the U.S. Department of Energy's (DOE's) D and D program at Argonne National Laboratory-East (ANL-E), site properties are evaluated within the context of the Cold War Era and within themes associated with nuclear technology. Under this program, ANL-E staff have conducted archival research on three nuclear reactor facilities, one accelerator, and one laboratory building. DOE and ANL-E have been working closely with the Illinois Historic Preservation Agency (IHPA) to determine the eligibility of these properties for listing on the National Register of Historic Places. In 1998, in consultation with the IHPA, the DOE determined that the reactor facilities were eligible. Memoranda of Agreement were signed between the DOE and the IHPA stipulating mitigation requirements for the recordation of two of these properties. The laboratory building was recently determined eligible and will likely undergo similar documentation procedures. The accelerator was determined not eligible. Similar studies and determinations will be required for all future D and D projects

Institutional plan. Fiscal year, 1997--2002

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-10-01

The Institutional Plan is the culmination of Argonne`s annual planning cycle. The document outlines what Argonne National Laboratory (ANL) regards as the optimal development of programs and resources in the context of national research and development needs, the missions of the Department of Energy and Argonne National Laboratory, and pertinent resource constraints. It is the product of ANL`s internal planning process and extensive discussions with DOE managers. Strategic planning is important for all of Argonne`s programs, and coordination of planning for the entire institution is crucial. This Institutional Plan will increasingly reflect the planning initiatives that have recently been implemented.

Preliminary Engineering Report contaminated groundwater seeps 317/319/ENE area

International Nuclear Information System (INIS)

1996-01-01

When the Resource Conservation and Recovery Act Facility Investigation (RFI) in the 317/319/ENE Area of Argonne National Laboratory-East (ANL-E) was being completed, groundwater was discovered moving to the surface through a series of seeps. The seeps are located approximately 600 ft south of the ANL fence line in Waterfall Glen Forest Preserve. Samples of this water were collected and analyzed for selected parameters. Two of five seeps sampled were found to contain detectable levels of organic contaminants. Three chemical species were identified: chloroform (14-25 μg/L), carbon tetrachloride (56-340 μg/L), and tetrachloroethylene (3-6 μg/L). The other seeps did not contain detectable levels of volatile organic compounds (VOCs). The water issuing from these two contaminated seeps flows into a narrow ravine, where it is visible as a trickle of water flowing through sand and gravel deposits on the floor of the ravine. Approximately 100-ft downstream of the seep area, the contaminated water is no longer visible, having drained back into the soil in the bed of the ravine. Figure 1 shows the location of the 317/319/ENE Area in relation to the ANL-E site and the Waterfall Glen Forest Preserve

Analytical Chemistry Laboratory. Progress report for FY 1996

Energy Technology Data Exchange (ETDEWEB)

Green, D.W.; Boparai, A.S.; Bowers, D.L.

1996-12-01

The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year (FY) 1996. This annual report is the thirteenth for the ACL. It describes effort on continuing and new projects and contributions of the ACL staff to various programs at ANL. The ACL operates in the ANL system as a full-cost-recovery service center, but has a mission that includes a complementary research and development component: The Analytical Chemistry Laboratory will provide high-quality, cost-effective chemical analysis and related technical support to solve research problems of our clients -- Argonne National Laboratory, the Department of Energy, and others -- and will conduct world-class research and development in analytical chemistry and its applications. Because of the diversity of research and development work at ANL, the ACL handles a wide range of analytical chemistry problems. Some routine or standard analyses are done, but the ACL usually works with commercial laboratories if our clients require high-volume, production-type analyses. It is common for ANL programs to generate unique problems that require significant development of methods and adaption of techniques to obtain useful analytical data. Thus, much of the support work done by the ACL is very similar to our applied analytical chemistry research.

LANL Activities Supporting Electron Accelerator Production of 99Mo for NorthStar Medical Radioisotopes, LLC

International Nuclear Information System (INIS)

Dale, Gregory E.; Kelsey, Charles T. IV; Woloshun, Keith A.; Holloway, Michael A.; Olivas, Eric R.; Dalmas, Dale A.; Romero, Frank P.; Hurtle, Kenneth P.

2012-01-01

Summary of LANL FY12 Activities are: (1) Preparation, performance, and data analysis for the FY12 accelerator tests at ANL - (a) LANL designed and installed a closed-loop helium target cooling system at ANL for the FY12 accelerator tests, (b) Thermal test was performed on March 27, (c) 24 h production test to follow the accelerator upgrade at ANL; (2) Local target shielding design and OTR/IR recommendations - (a) Target dose rate and activation products were calculated with MCNPX, (b) 206 Pb(γ,2n) 204m Pb vs 204g Pb branching ratio unpublished, will measure using the LANL microtron, (c) OTR system nearing final configuration, (d) IR prototype system demonstrated during the recent thermal test at ANL; (3) Target housing lifetime estimation - Target housing material specifications and design to be finalized following the thermal test, lifetime not believed to be an issue; and (4) Target cooling system reliability - Long duration system characterizations will begin following the thermal test.

Decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East. Project final report

International Nuclear Information System (INIS)

Fellhauer, C.R.; Clark, F.R.

1997-10-01

The decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East (ANL-E) was completed in October 1997. Descriptions and evaluations of the activities performed and analyses of the results obtained during the JANUS D and D Project are provided in this Final Report. The following information is included: objective of the JANUS D and D Project; history of the JANUS Reactor facility; description of the ANL-E site and the JANUS Reactor facility; overview of the D and D activities performed; description of the project planning and engineering; description of the D and D operations; summary of the final status of the JANUS Reactor facility based upon the final survey results; description of the health and safety aspects of the project, including personnel exposure and OSHA reporting; summary of the waste minimization techniques utilized and total waste generated by the project; and summary of the final cost and schedule for the JANUS D and D Project

Status report on the Experimental Boiling Water Reactor (EBWR) Decontamination and Decommissioning (D ampersand D) Project

International Nuclear Information System (INIS)

Sears, L.; Garlock, G.; Mencarelli, R.; Fellhauer, C.

1994-01-01

ALARON Corporation is under contract, to Argonne National Laboratory - East (ANL-E), to complete the decontamination and decommissioning of the Experimental Boiling Water Reactor (EBWR). The project, begun, in 1986 by ANL-E personnel, is projected to be completed by the end of 1994. The final phase of work was awarded to ALARON in December 1993 with the scope of work including the disassembly and removal of all remaining reactor internals, the reactor vessel, the lead bio-shield, the core liner, and the activated portion of the concrete bio-shield. This paper discusses the work undertaken beginning in January 1994 and continuing through July 1994. During this period the required pre-mobilization documentation was prepared and approved, mobilization was completed, and the reactor internals, reactor vessel, lead bio-shield and core liner were removed. The paper will compare the planned schedule to the actual schedule, discuss problems encountered, review volume reduction techniques and health and safety issues including radiological aspects of the project

Fiscal year 1996 decontamination and decommissioning activities photobriefing book for the Argonne National Laboratory-East Site, Technology Development Division, Waste Management Program, Decontamination and Decommissioning Projects Department

International Nuclear Information System (INIS)

1996-01-01

The Photobriefing Book describes the Decontamination and Decommissioning (D and D) Program at the Argonne National Laboratory-East Site (ANL-E) near Lemont, Illinois. This book summarizes current D and D projects, reviews fiscal year (FY) 1996 accomplishments, and outlines FY 1997 goals. A section on D and D Technology Development provides insight on new technologies for D and D developed or demonstrated at ANL-E. Past projects are recapped and upcoming projects are described as Argonne works to accomplish its commitment to, ''Close the Circle on the Splitting of the Atom.'' Finally, a comprehensive review of the status and goals of the D and D Program is provided to give a snap-shot view of the program and the direction it's taking as it moves into FY 1997. The D and D projects completed to date include: Plutonium Fuel Fabrication Facility; East Area Surplus Facilities; Experimental Boiling Water Reactor; M-Wing Hot Cell Facilities; Plutonium Gloveboxes; and Fast Neutron Generator

Plutonium working group report on environmental, safety and health vulnerabilities associated with the Department's plutonium storage. Volume II, Appendix B, Part 8: Argonne National Laboratory - East and New Brunswick Laboratory site assessment team report

International Nuclear Information System (INIS)

1994-09-01

The objective of the Plutonium ES ampersand H Vulnerability Assessment Project is to conduct a comprehensive assessment of the environmental, safety and health (ES ampersand H) vulnerabilities arising from the Department's storage and handling of Its current plutonium holdings. The term open-quote ES ampersand H vulnerabilitiesclose quotes is defined for the purpose of this project to mean conditions or weaknesses that could lead to unnecessary or increased radiation exposure of workers, release of radioactive materials to the environment, or radiation exposure of the public. The assessment will identify and prioritize ES ampersand H vulnerabilities, and will serve as an information base for identifying corrective actions and options for the safe management of fissile materials. The Argonne National Laboratory-East (ANL-E) Site Assessment Team (SAT) was formed from Department of Energy (DOE) Chicago Operations Office-Argonne Area Office Personnel, to conduct a self-assessment of the plutonium holdings and any associated ES ampersand H vulnerabilities at the ANL-E site

Verification Survey of the Building 315 Zero Power Reactor-6 Facility, Argonne National Laboratory-East, Argonne, Illinois

International Nuclear Information System (INIS)

W. C. Adams

2007-01-01

Oak Ridge Institute for Science and Education (ORISE) conducted independent verification radiological survey activities at Argonne National Laboratory's Building 315, Zero Power Reactor-6 facility in Argonne, Illinois. Independent verification survey activities included document and data reviews, alpha plus beta and gamma surface scans, alpha and beta surface activity measurements, and instrumentation comparisons. An interim letter report and a draft report, documenting the verification survey findings, were submitted to the DOE on November 8, 2006 and February 22, 2007, respectively (ORISE 2006b and 2007). Argonne National Laboratory-East (ANL-E) is owned by the U.S. Department of Energy (DOE) and is operated under a contract with the University of Chicago. Fundamental and applied research in the physical, biomedical, and environmental sciences are conducted at ANL-E and the laboratory serves as a major center of energy research and development. Building 315, which was completed in 1962, contained two cells, Cells 5 and 4, for holding Zero Power Reactor (ZPR)-6 and ZPR-9, respectively. These reactors were built to increase the knowledge and understanding of fast reactor technology. ZPR-6 was also referred to as the Fast Critical Facility and focused on fast reactor studies for civilian power production. ZPR-9 was used for nuclear rocket and fast reactor studies. In 1967, the reactors were converted for plutonium use. The reactors operated from the mid-1960's until 1982 when they were both shut down. Low levels of radioactivity were expected to be present due to the operating power levels of the ZPR's being restricted to well below 1,000 watts. To evaluate the presence of radiological contamination, DOE characterized the ZPRs in 2001. Currently, the Melt Attack and Coolability Experiments (MACE) and Melt Coolability and Concrete Interaction (MCCI) Experiments are being conducted in Cell 4 where the ZPR-9 is located (ANL 2002 and 2006). ANL has performed final

TEMP-STRESS analysis of a reinforced concrete vessel under internal pressure

International Nuclear Information System (INIS)

Marchertas, A.H.; Kennedy, J.M.; Pfeiffer, P.A.

1987-01-01

Prediction of the response of the Sandia National laboratory 1/6-scale reinforced concrete containment model test was obtained by Argonne National Laboratory (ANL) employing a computer program developed by ANL. The test model was internally pressurized to failure. The two-dimensional code TEMP-STRESS [1-5] has been developed at ANL for stress analysis of plane and axisymmetric 2-D reinforced structures under various thermal conditions. The program is applicable to a wide variety of nonlinear problems, and is utilized in the present study. The comparison of these pretest computations with test data on the containment model should be a good indication of the state of the code

An evaluation of alternative reactor vessel cutting technologies for the experimental boiling water reactor at Argonne National Laboratory

International Nuclear Information System (INIS)

Boing, L.E.; Henley, D.R.; Manion, W.J.; Gordon, J.W.

1989-12-01

Metal cutting techniques that can be used to segment the reactor pressure vessel of the Experimental Boiling Water Reactor (EBWR) at Argonne National Laboratory (ANL) have been evaluated by Nuclear Energy Services. Twelve cutting technologies are described in terms of their ability to perform the required task, their performance characteristics, environmental and radiological impacts, and cost and schedule considerations. Specific recommendations regarding which technology should ultimately be used by ANL are included. The selection of a cutting method was the responsibility of the decommissioning staff at ANL, who included a relative weighting of the parameters described in this document in their evaluation process. 73 refs., 26 figs., 69 tabs

An evaluation of alternative reactor vessel cutting technologies for the experimental boiling water reactor at Argonne National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Boing, L.E.; Henley, D.R. (Argonne National Lab., IL (USA)); Manion, W.J.; Gordon, J.W. (Nuclear Energy Services, Inc., Danbury, CT (USA))

1989-12-01

Metal cutting techniques that can be used to segment the reactor pressure vessel of the Experimental Boiling Water Reactor (EBWR) at Argonne National Laboratory (ANL) have been evaluated by Nuclear Energy Services. Twelve cutting technologies are described in terms of their ability to perform the required task, their performance characteristics, environmental and radiological impacts, and cost and schedule considerations. Specific recommendations regarding which technology should ultimately be used by ANL are included. The selection of a cutting method was the responsibility of the decommissioning staff at ANL, who included a relative weighting of the parameters described in this document in their evaluation process. 73 refs., 26 figs., 69 tabs.

Cooperative Threat Reduction for a New Era

Science.gov (United States)

2004-09-01

Reactor From Inr-Pitesti,” Institute for Nuclear Research (Romania), Papers Presented by ANL at the RERTR Meeting, 1997 <http://www.td.anl.gov/Programs... RERTR /Analysis97/CToma-abs.html> as of 30 July 2004. 51 This program often works in conjunction with the second proposal above. Although the

The decommissioning of a research reactor in the USA: A case study from planning to site release

International Nuclear Information System (INIS)

Boing, L.E.

1997-01-01

Argonne National Laboratory (ANL) has completed the D ampersand D of the Experimental Boiling Water Reactor (EBWR). The project consisted of the decontamination and/or packaging as radioactive waste the reactor vessel and internals, contaminated piping systems, miscellaneous tanks, pumps, and associated equipment. The dismantling process involved the removal and size reduction of equipment and associated plumbing, ductwork, drain lines, etc. Size reduction of reactor vessel internals was performed in the fuel pool. All radioactive and mixed waste was packaged and manifested. A thorough survey of the facility was performed after the removal of contaminated and activated material. Non-radioactive waste was disposed of in the ANL landfill or recycled as appropriate. The EBWR D ampersand D project was divided into four phases. Phases I and II were completed by ANL personnel, while Phases III and IV were done by a contractor under ANL management. The final survey was performed by the contractor, while the verification survey was performed by ANL. The project lasted 118 months. Phase I was initiated in April 1986 and the final report was issued February 1996. The duration of the project was driven by the availability of funding for decommissioning. Total exposure to project personnel was 208.7 person-mSv (20.87 person-rem), with no personnel exceeding the EBWR project dose limit of 15 mSv (1.5 rem)

Are the noise levels acceptable in a built environment like Hong Kong?

Science.gov (United States)

To, Wai Ming; Mak, Cheuk Ming; Chung, Wai Leung

2015-01-01

Governments all over the world have enacted environmental noise directives and noise control ordinances/acts to protect tranquility in residential areas. However, there is a lack of literature on the evaluation of whether the Acceptable Noise Levels (ANLs) stipulated in the directive/ordinance/act are actually achievable. The study aimed at measuring outdoor environmental noise levels in Hong Kong and identifying whether the measured noise levels are lower than the stipulated ANLs at 20 categories of residential areas. Data were gathered from a territory-wide noise survey. Outdoor noise measurements were conducted at 203 residential premises in urban areas, low-density residential areas, rural areas, and other areas. In total, 366 daytime hourly Leq outdoor noise levels, 362 nighttime hourly Leq outdoor noise levels, and 20 sets of daily, that is, 24 Leq,1-h outdoor noise levels were recorded. The mean daytime Leq,1-h values ranged 54.4-70.8 dBA, while the mean nighttime Leq,1-h values ranged 52.6-67.9 dBA. When the measured noise levels were compared with the stipulated ANLs, only three out of the 20 categories of areas had outdoor noise levels below ANLs during daytime. All other areas (and all areas during nighttime) were found to have outdoor noise levels at or above ANLs. PMID:26572703

Analytical Chemistry Laboratory, progress report for FY 1993

Energy Technology Data Exchange (ETDEWEB)

1993-12-01

The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year (FY) 1993 (October 1992 through September 1993). This annual report is the tenth for the ACL and describes continuing effort on projects, work on new projects, and contributions of the ACL staff to various programs at ANL. The Analytical Chemistry Laboratory is a full-cost-recovery service center, with the primary mission of providing a broad range of analytical chemistry support services to the scientific and engineering programs at ANL. The ACL also has research programs in analytical chemistry, conducts instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL handles a wide range of analytical problems. Some routine or standard analyses are done, but it is common for the Argonne programs to generate unique problems that require development or modification of methods and adaption of techniques to obtain useful analytical data. The ACL is administratively within the Chemical Technology Division (CMT), its principal ANL client, but provides technical support for many of the technical divisions and programs at ANL. The ACL has four technical groups--Chemical Analysis, Instrumental Analysis, Organic Analysis, and Environmental Analysis--which together include about 45 technical staff members. Talents and interests of staff members cross the group lines, as do many projects within the ACL.

Klimaregnskab og Carbon Footprint beregning for Kommunekemi a/s

DEFF Research Database (Denmark)

Leinikka Dall, Ole; Wenzel, Henrik

2009-01-01

Klimaregnskab for anlægget i Nyborg og carbon footprint for: -forbrænding -uorganisk behandling -halmaskeanlæg Afrapporteret på tryk og indtastet i Simapro......Klimaregnskab for anlægget i Nyborg og carbon footprint for: -forbrænding -uorganisk behandling -halmaskeanlæg Afrapporteret på tryk og indtastet i Simapro...

Argonne Code Center: compilation of program abstracts

Energy Technology Data Exchange (ETDEWEB)

Butler, M.K.; DeBruler, M.; Edwards, H.S.; Harrison, C. Jr.; Hughes, C.E.; Jorgensen, R.; Legan, M.; Menozzi, T.; Ranzini, L.; Strecok, A.J.

1977-08-01

This publication is the eleventh supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the complete document ANL-7411 are as follows: preface, history and acknowledgements, abstract format, recommended program package contents, program classification guide and thesaurus, and the abstract collection. (RWR)

Argonne Code Center: compilation of program abstracts

International Nuclear Information System (INIS)

Butler, M.K.; DeBruler, M.; Edwards, H.S.; Harrison, C. Jr.; Hughes, C.E.; Jorgensen, R.; Legan, M.; Menozzi, T.; Ranzini, L.; Strecok, A.J.

1977-08-01

This publication is the eleventh supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the complete document ANL-7411 are as follows: preface, history and acknowledgements, abstract format, recommended program package contents, program classification guide and thesaurus, and the abstract collection

Guide to computing at ANL

Energy Technology Data Exchange (ETDEWEB)

Peavler, J. (ed.)

1979-06-01

This publication gives details about hardware, software, procedures, and services of the Central Computing Facility, as well as information about how to become an authorized user. Languages, compilers' libraries, and applications packages available are described. 17 tables. (RWR)

ANL/WSU radiation damage studies

International Nuclear Information System (INIS)

Jankowski, D.; Lopiano, D.; Proudfoot, J.; Underwood, D.; Miles, L.; Neidiger, J.; Tripard, G.

1993-01-01

We report preliminary results for the radiation hardness of (polystryrene) plastic scintillator stacks using a spectrum of energy hardened neutrons from a MARK-III TRIGA reactor. The total dose ranged from 100 KRad to 3MRad. The corresponding fluence was 3.8 x 10 13 to 3.8 x 10 14 (n/cm/cm) with the gamma contribution on the order 2--3% (of fluence). The measurements used Li-6, Li-7 Thermo-luminescence dosimeters. Radiochromic/GaF- Chromic film, and activated foils simultaneously allowing an inter-comparison of these various methods of dosimetry

Proposed environmental remediation at Argonne National Laboratory, Argonne, Illinois

International Nuclear Information System (INIS)

1997-05-01

The Department of Energy (DOE) has prepared an Environmental Assessment evaluating proposed environmental remediation activity at Argonne National Laboratory-East (ANL-E), Argonne, Illinois. The environmental remediation work would (1) reduce, eliminate, or prevent the release of contaminants from a number of Resource Conservation and Recovery Act (RCRA) Solid Waste Management Units (SWMUs) and two radiologically contaminated sites located in areas contiguous with SWMUs, and (2) decrease the potential for exposure of the public, ANL-E employees, and wildlife to such contaminants. The actions proposed for SWMUs are required to comply with the RCRA corrective action process and corrective action requirements of the Illinois Environmental Protection Agency; the actions proposed are also required to reduce the potential for continued contaminant release. Based on the analysis in the EA, the DOE has determined that the proposed action does not constitute a major federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (NEPA). Therefore, the preparation of an Environmental Impact Statement is not required

Physiologic correlates to background noise acceptance

Science.gov (United States)

Tampas, Joanna; Harkrider, Ashley; Nabelek, Anna

2004-05-01

Acceptance of background noise can be evaluated by having listeners indicate the highest background noise level (BNL) they are willing to accept while following the words of a story presented at their most comfortable listening level (MCL). The difference between the selected MCL and BNL is termed the acceptable noise level (ANL). One of the consistent findings in previous studies of ANL is large intersubject variability in acceptance of background noise. This variability is not related to age, gender, hearing sensitivity, personality, type of background noise, or speech perception in noise performance. The purpose of the current experiment was to determine if individual differences in physiological activity measured from the peripheral and central auditory systems of young female adults with normal hearing can account for the variability observed in ANL. Correlations between ANL and various physiological responses, including spontaneous, click-evoked, and distortion-product otoacoustic emissions, auditory brainstem and middle latency evoked potentials, and electroencephalography will be presented. Results may increase understanding of the regions of the auditory system that contribute to individual noise acceptance.

Metabolic gene expression changes in astrocytes in Multiple Sclerosis cerebral cortex are indicative of immune-mediated signaling

KAUST Repository

Zeis, T.

2015-04-01

Emerging as an important correlate of neurological dysfunction in Multiple Sclerosis (MS), extended focal and diffuse gray matter abnormalities have been found and linked to clinical manifestations such as seizures, fatigue and cognitive dysfunction. To investigate possible underlying mechanisms we analyzed the molecular alterations in histopathological normal appearing cortical gray matter (NAGM) in MS. By performing a differential gene expression analysis of NAGM of control and MS cases we identified reduced transcription of astrocyte specific genes involved in the astrocyte–neuron lactate shuttle (ANLS) and the glutamate–glutamine cycle (GGC). Additional quantitative immunohistochemical analysis demonstrating a CX43 loss in MS NAGM confirmed a crucial involvement of astrocytes and emphasizes their importance in MS pathogenesis. Concurrently, a Toll-like/IL-1β signaling expression signature was detected in MS NAGM, indicating that immune-related signaling might be responsible for the downregulation of ANLS and GGC gene expression in MS NAGM. Indeed, challenging astrocytes with immune stimuli such as IL-1β and LPS reduced their ANLS and GGC gene expression in vitro. The detected upregulation of IL1B in MS NAGM suggests inflammasome priming. For this reason, astrocyte cultures were treated with ATP and ATP/LPS as for inflammasome activation. This treatment led to a reduction of ANLS and GGC gene expression in a comparable manner. To investigate potential sources for ANLS and GGC downregulation in MS NAGM, we first performed an adjuvant-driven stimulation of the peripheral immune system in C57Bl/6 mice in vivo. This led to similar gene expression changes in spinal cord demonstrating that peripheral immune signals might be one source for astrocytic gene expression changes in the brain. IL1B upregulation in MS NAGM itself points to a possible endogenous signaling process leading to ANLS and GGC downregulation. This is supported by our findings that, among others

Analytical Chemistry Laboratory progress report for FY 1999

Energy Technology Data Exchange (ETDEWEB)

Green, D. W.; Boparai, A. S.; Bowers, D. L.; Graczyk, D. G.

2000-06-15

This report summarizes the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year (FY) 1999 (October 1998 through September 1999). This annual progress report, which is the sixteenth in this series for the ACL, describes effort on continuing projects, work on new projects, and contributions of the ACL staff to various programs at ANL.

Analytical Chemistry Laboratory progress report for FY 1998.

Energy Technology Data Exchange (ETDEWEB)

Boparai, A. S.; Bowers, D. L.; Graczyk, D. G.; Green, D. W.; Lindahl, P. C.

1999-03-29

This report summarizes the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year (FY) 1998 (October 1997 through September 1998). This annual progress report, which is the fifteenth in this series for the ACL, describes effort on continuing projects, work on new projects, and contributions of the ACL staff to various programs at ANL.

Software documentation and user's manual for fish-impingement sampling design and estimation method computer programs

International Nuclear Information System (INIS)

Murarka, I.P.; Bodeau, D.J.

1977-11-01

This report contains a description of three computer programs that implement the theory of sampling designs and the methods for estimating fish-impingement at the cooling-water intakes of nuclear power plants as described in companion report ANL/ES-60. Complete FORTRAN listings of these programs, named SAMPLE, ESTIMA, and SIZECO, are given and augmented with examples of how they are used

Analytical Chemistry Laboratory progress report for FY 1998

International Nuclear Information System (INIS)

Boparai, A. S.; Bowers, D. L.; Graczyk, D. G.; Green, D. W.; Lindahl, P. C.

1999-01-01

This report summarizes the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year (FY) 1998 (October 1997 through September 1998). This annual progress report, which is the fifteenth in this series for the ACL, describes effort on continuing projects, work on new projects, and contributions of the ACL staff to various programs at ANL

Memory of a myth

DEFF Research Database (Denmark)

Odgaard, Ulla

2012-01-01

I 1954 fandt arkæolog fra Nationalmuseet i Danmark, Jørgen Meldgaard, et unikt anlæg fra den sene dorset kultur (ca. 500-1200 e.Kr.) på bopladsen Alarnerk i Igloolik området ved Foxe Basin i det nordøstlige Canada. Anlægget indeholdt menneskeknogler (fra et barn), og Meldgaard mente, at der var t...

Wave Star

DEFF Research Database (Denmark)

Kramer, Morten; Frigaard, Peter

Nærværende rapport beskriver modelforsøg udført på Aalborg Universitet, Institut for Byggeri og Anlæg med bølgeenergianlæget Wave Star.......Nærværende rapport beskriver modelforsøg udført på Aalborg Universitet, Institut for Byggeri og Anlæg med bølgeenergianlæget Wave Star....

Project plan for the decontamination and decommissioning of the Argonne National Laboratory Experimental Boiling Water Reactor

International Nuclear Information System (INIS)

Boing, L.E.

1989-12-01

In 1956, the Experimental Boiling Water Reactor (EBWR) Facility was first operated at Argonne National Laboratory (ANL) as a test reactor to demonstrate the feasibility of operating an integrated power plant using a direct cycle boiling water reactor as a heat source. In 1967, ANL permanently shut down the EBWR and placed it in dry lay-up. This project plan presents the schedule and organization for the decontamination and decommissioning of the EBWR Facility which will allow it to be reused by other ANL scientific research programs. The project total estimated cost is $14.3M and is projected to generate 22,000 cubic feet of low-level radioactive waste which will be disposed of at an approved DOE burial ground. 18 figs., 3 tabs

Project plan for the decontamination and decommissioning of the Argonne National Laboratory Experimental Boiling Water Reactor

Energy Technology Data Exchange (ETDEWEB)

Boing, L.E.

1989-12-01

In 1956, the Experimental Boiling Water Reactor (EBWR) Facility was first operated at Argonne National Laboratory (ANL) as a test reactor to demonstrate the feasibility of operating an integrated power plant using a direct cycle boiling water reactor as a heat source. In 1967, ANL permanently shut down the EBWR and placed it in dry lay-up. This project plan presents the schedule and organization for the decontamination and decommissioning of the EBWR Facility which will allow it to be reused by other ANL scientific research programs. The project total estimated cost is $14.3M and is projected to generate 22,000 cubic feet of low-level radioactive waste which will be disposed of at an approved DOE burial ground. 18 figs., 3 tabs.

Design/build/mockup of the Waste Isolation Pilot Plant gas generation experiment glovebox

International Nuclear Information System (INIS)

Rosenberg, K.E.; Benjamin, W.W.; Knight, C.J.; Michelbacher, J.A.

1996-01-01

A glovebox was designed, fabricated, and mocked-up for the WIPP Gas Generation Experiments (GGE) being conducted at ANL-W. GGE will determine the gas generation rates from materials in contact handled transuranic waste at likely long term repository temperature and pressure conditions. Since the customer's schedule did not permit time for performing R ampersand D of the support systems, designing the glovebox, and fabricating the glovebox in a serial fashion, a parallel approach was undertaken. As R ampersand D of the sampling system and other support systems was initiated, a specification was written concurrently for contracting a manufacturer to design and build the glovebox and support equipment. The contractor understood that the R ampersand D being performed at ANL-W would add additional functional requirements to the glovebox design. Initially, the contractor had sufficient information to design the glovebox shell. Once the shell design was approved, ANL-W built a full scale mockup of the shell out of plywood and metal framing; support systems were mocked up and resultant information was forwarded to the glovebox contractor to incorporate into the design. This approach resulted in a glovebox being delivered to ANL-W on schedule and within budget

Decontamination and dismantlement of the building 200/205 pneumatic transfer tube at Argonne National Laboratory-East project final report

International Nuclear Information System (INIS)

Wiese, E. C.

1998-01-01

The Building 200/205 Pneumatic Transfer Tube D and D Project was directed toward the following goals: Remove any radioactive and hazardous materials associated with the transfer tube; Survey the transfer tube to identify any external contamination; Remove the transfer tube and package for disposal; Survey the soil and sand surrounding the transfer tube for any contamination; and Backfill the trench in which the tube sat and restore the area to its original condition. These goals had been set in order to eliminate the radiological and hazardous safety concerns inherent in the buried transfer tube and to allow, upon completion of the project, the removal of this project from the ANL-E action item list. The physical condition of the transfer tube and possible nuclear fuel samples lost in the tube were the primary areas of concern, while the exact location of the transfer tube was of secondary concern. ANL-E health physics technicians collected characterization data from the ends of the Building 200/205 pneumatic transfer tube in January 1998. The characterization surveys identified contamination to a level of 67,000 dpm (1,117 Bq) (β/γ) and 20,000 dpm (333 Bq) α smearable at the opening

Implementation of Waste Minimization at a complex R ampersand D site

International Nuclear Information System (INIS)

Lang, R.E.; Thuot, J.R.; Devgun, J.S.

1995-01-01

Under the 1994 Waste Minimization/Pollution Prevention Crosscut Plan, the Department of Energy (DOE) has set a goal of 50% reduction in waste at its facilities by the end of 1999. Each DOE site is required to set site-specific goals to reduce generation of all types of waste including hazardous, radioactive, and mixed. To meet these goals, Argonne National Laboratory (ANL), Argonne, IL, has developed and implemented a comprehensive Pollution Prevention/Waste Minimization (PP/WMin) Program. The facilities and activities at the site vary from research into basic sciences and research into nuclear fuel cycle to high energy physics and decontamination and decommissioning projects. As a multidisciplinary R ampersand D facility and a multiactivity site, ANL generates waste streams that are varied, in physical form as well as in chemical constituents. This in turn presents a significant challenge to put a cohesive site-wide PP/WMin Program into action. In this paper, we will describe ANL's key activities and waste streams, the regulatory drivers for waste minimization, and the DOE goals in this area, and we will discuss ANL's strategy for waste minimization and it's implementation across the site

Management of wildlife causing damage at Argonne National Laboratory-East, DuPage County, Illinois

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-01

The DOE, after an independent review, has adopted an Environmental Assessment (EA) prepared by the US Department of Agriculture (USDA) which evaluates use of an Integrated Wildlife Damage Management approach at Argonne National Laboratory-East (ANL-E) in DuPage County, Illinois (April 1995). In 1994, the USDA issued a programmatic Environmental Impact Statement (EIS) that covers nationwide animal damage control activities. The EA for Management of Wildlife Causing Damage at ANL-E tiers off this programmatic EIS. The USDA wrote the EA as a result of DOE`s request to USDA to prepare and implement a comprehensive Wildlife Management Damage Plan; the USDA has authority for animal damage control under the Animal Damage Control Act of 1931, as amended, and the Rural Development, Agriculture and Related Agencies Appropriations Act of 1988. DOE has determined, based on the analysis in the EA, that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (NEPA). Therefore, the preparation of an EIS is not required. This report contains the Environmental Assessment, as well as the Finding of No Significant Impact (FONSI).

317/319 phytoremediation site monitoring report - 2003 growing season.

Energy Technology Data Exchange (ETDEWEB)

Negri, M. C.; Gopalakrishnan, G.; Hamilton, C.; Energy Systems

2004-02-20

In 1999, Argonne National Laboratory-East (ANL-E) designed and installed a series of engineered plantings consisting of a vegetative cover system and approximately 800 hybrid poplars and willows rooting at various predetermined depths. The plants were installed using various methods including Applied Natural Science's TreeWell{reg_sign} system. The goal of the installation was to protect downgradient surface and groundwater by hydraulic control of the contaminated plume by intercepting the contaminated groundwater with the tree roots, removing moisture from the upgradient soil area, reducing water infiltration, preventing soil erosion, degrading and/or transpiring the residual volatile organic compounds (VOCs), and removing tritium from the subsoil and groundwater. This report presents the results of the monitoring activities conducted by Argonne's Energy Systems Division (ES) in the growing season of 2003. ES was tasked with the biomonitoring of the plantation to determine contaminant uptake and groundwater contact. VOCs were found in plant tissue both at the French Drain and the Hydraulic Control locations in varying concentrations, and tritium levels in transpirate was found to continue a trend of higher concentrations compared to the background in the ANL-E area.

Hydrogen meter prooftesting

International Nuclear Information System (INIS)

McCown, J.J.; Mettler, G.W.

1976-04-01

Two diffusion type hydrogen meters have been tested on the Prototype Applications Loop (PAL). The ANL designed unit was used to monitor hydrogen in sodium during FFTF startup and over a wide range of hydrogen concentrations resulting from chemical additions to the sodium and cover gas. A commercially available meter was added and its performance compared with the ANL unit. Details of the test work are described

Analytical chemistry laboratory. Progress report for FY 1997

Energy Technology Data Exchange (ETDEWEB)

Green, D.W.; Boparai, A.S.; Bowers, D.L. [and others

1997-12-01

The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year (FY) 1997 (October 1996 through September 1997). This annual progress report is the fourteenth in this series for the ACL, and it describes continuing effort on projects, work on new projects, and contributions of the ACL staff to various programs at ANL.

The restoration of an Argonne National Laboratory foundry

International Nuclear Information System (INIS)

Shearer, T.; Pancake, D.; Shelton, B.

1997-01-01

The Environmental Management Operations' Waste Management Department (WMD) at Argonne National Laboratory-East (ANL-E) undertook the restoration of an unused foundry with the goal of restoring the area for general use. The foundry was used in the fabrication of reactor components for ANL's research and development programs; many of the items fabricated in the facility were radioactive, thereby contaminating the foundry equipment. This paper very briefly describes the dismantling and decontamination of the facility. The major challenges associated with the safe removal of the foundry equipment included the sheer size of the equipment, a limited overhead crane capability (4.5 tonne), the minimization of radioactive and hazardous wastes, and the cost-effective completion of the project, the hazardous and radioactive wastes present, and limited process knowledge (the facility was unused for many years)

Alpha-Gamma Hot-Cell Facility at Argonne National Laboratory East

International Nuclear Information System (INIS)

Neimark, L.A.; Jackson, W.D.; Donahue, D.A.

1979-01-01

The Alpha-Gamma Hot-Cell Facility has been in operation at Argonne National Laboratory East (ANL-E) for 15 years. The facility was designed for plutonium research in support of ANL's LMFBR program. The facility consists of a kilocurie, nitrogen-atmosphere alpha-gamma hot cell and supporting laboratories. Modifications to the facility and its equipment have been made over the years as the workload and nature of the work changed. These modifications included inerting the entire hot cell, adding four work stations, modifying in-loading procedures and examination equipment to handle longer test articles, and changing to a new sodium-vapor lighting system. Future upgrading includes the addition of a decontamination and repair facility, use of radio-controlled transfer carts, refurbishment of the zinc bromide windows, and the installation of an Auger microprobe

Using electrochemical separation to reduce the volume of high-level nuclear waste

International Nuclear Information System (INIS)

Slater, S.A.; Gay, E.C.

1998-01-01

Argonne National Laboratory (ANL) has developed an electrochemical separation technique called electrorefining that will treat a variety of metallic spent nuclear fuel and reduce the volume of high-level nuclear waste that requires disposal. As part of that effort, ANL has developed a high throughput electrorefiner (HTER) that has a transport rate approximately three times faster than electrorefiners previously developed at ANL. This higher rate is due to the higher electrode surface area, a shorter transport path, and more efficient mixing, which leads to smaller boundary layers about the electrodes. This higher throughput makes electrorefining an attractive option in treating Department of Energy spent nuclear fuels. Experiments have been done to characterize the HTER, and a simulant metallic fuel has been successfully treated. The HTER design and experimental results is discussed

Fugemateriale til belægningssten og fliser

DEFF Research Database (Denmark)

Larsen, Kristian

2004-01-01

Der anlægges ca. 9 millioner kvadratmeter belægning i betonsten og fliser om året i Danmark. Fugearealet udgør gennemsnitlig 4 %, svarende til et areal på ca. 36 ha.......Der anlægges ca. 9 millioner kvadratmeter belægning i betonsten og fliser om året i Danmark. Fugearealet udgør gennemsnitlig 4 %, svarende til et areal på ca. 36 ha....

Reactor D and D at Argonne National Laboratory - lessons learned

International Nuclear Information System (INIS)

Fellhauer, C. R.

1998-01-01

This paper focuses on the lessons learned during the decontamination and decommissioning (D and D) of two reactors at Argonne National Laboratory-East (ANL-E). The Experimental Boiling Water Reactor (EBWR) was a 100 MW(t), 5 MSV(e) proof-of-concept facility. The Janus Reactor was a 200 kW(t) reactor located at the Biological Irradiation Facility and was used to study the effects of neutron radiation on animals

Antenatal Maternity Leave and Childbirth Using the First Baby Study: A Propensity Score Analysis.

Science.gov (United States)

Goodman, Julia M; Guendelman, Sylvia; Kjerulff, Kristen H

Most employed American women work during pregnancy and continue working through the month they deliver. Yet, few studies estimate the relationship between maternity leave taken during pregnancy and maternal health. We evaluate the association of antenatal leave (ANL) uptake with obstetric outcomes, assessing the potential role of protective and adverse selection pathways on this relationship. We sample 1,740 employed women who delivered at term from the First Baby Study, a prospective cohort of nulliparous women in Pennsylvania. We use propensity scores to estimate the relationship between ANL and negative delivery outcomes (labor induction, long labor duration, unplanned cesarean delivery, and self-reported negative birth experience). We estimated propensity scores using a range of employment, health, and sociodemographic variables. One-half of the sampled women worked until the day before or day of delivery. Women who stopped working at least 2 days before delivery experienced 16% more negative delivery outcomes, on average, than women who worked until delivery, driven largely by a 25% higher predicted probability of unplanned cesarean section deliveries. These robust findings hold up to a range of sensitivity analyses and demonstrate selective mechanisms operating in ANL uptake. Our findings suggest that, even after controlling for an extensive set of observable employment, health, and sociodemographic characteristics, women who take ANL continue to differ in unobserved characteristics that lead to negative delivery outcomes. Like most U.S. states, Pennsylvania does not grant paid maternity leave. In a context of limited maternity leave availability, only relatively unhealthy women take ANL. Copyright © 2016 Jacobs Institute of Women's Health. Published by Elsevier Inc. All rights reserved.

IPNS upgrade: A feasibility study

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-01

Many of Argonne National Laboratory`s (ANL`s) scientific staff members were very active in R&D work related to accelerator-based spoliation sources in the 1970s and early 1980s. In 1984, the Seitz/Eastman Panel of the National Academy of Sciences reviewed U.S. materials science research facilities. One of the recommendations of this panel was that the United States build a reactor-based steady-state source, the Advanced Neutron Source (ANS), at Oak Ridge National Laboratory. Subsequently, R&D activities related to the design of an accelerator-based source assumed a lower priority. The resumption of pulsed-source studies in this country started simultaneously with design activities in Europe aimed at the European Spallation Source (ESS). The European Community funded a workshop in September 1991 to define the parameters of the ESS. Participants in this workshop included both accelerator builders and neutron source users. A consortium of European countries has proposed to build a 5-MW pulsed source, and a feasibility study is currently under way. Soon after the birth of the ESS, a small group at ANL set about bringing themselves up to date on pulsed-source information since 1984 and studied the feasibility of upgrading ANL`s Intense Pulsed Neutron Source (IPNS) to 1 MW by means of a rapidly cycling synchrotron that could be housed, along with its support facilities, in existing buildings. In early 1993, the Kohn panel recommended that (1) design and construction of the ANS should be completed according to the proposed project schedule and (2) development of competitive proposals for cost-effective design and construction of a 1-MW pulsed spallation source should be authorized immediately.

Preparing for radiological assessments in the event of a tornado strike at Argonne National Lab.-East

International Nuclear Information System (INIS)

Goodkind, M.E.; Klimczak, C.A.; Munyon, W.J.

1993-01-01

Argonne National Laboratory-East (ANL) is a Department of Energy (DOE)-owned, contractor-operated national laboratory located 22 miles southwest of downtown Chicago on a wooded, 1700-acre site. The principal nuclear facilities at ANL include a large fast neutron source (Intense Pulse Neutron Source) in which high-energy protons strike a uranium target to produce neutrons for research studies; 60 Co irradiation sources; chemical and metallurgical plutonium laboratories, some of which are currently being decommissioned; several large hot cell facilities designed for work with multicurie quantities of actinide elements and irradiated reactor fuel materials; a few small research reactors currently in different phases of being decommissioned; and a variety of research laboratories handling many different sources in various chemical and physical forms. The hazards analysis for the ANL site shows that tornado strikes are a serious threat. The site has been struck twice in the past 20 yr, receiving only minor building damage and no release of radioactivity to the environment. Although radioactive materials in general are handled in areas that provide good tornado protection, ANL is prepared to address the problems that would occur should there be a loss of control of radioactive materials due to severe building damage

Decontamination and decommissioning of the Experimental Boiling Water Reactor (EBWR): Project final report, Argonne National Laboratory

International Nuclear Information System (INIS)

Fellhauer, C.R.; Boing, L.E.; Aldana, J.

1997-03-01

The Final Report for the Decontamination and Decommissioning (D ampersand D) of the Argonne National Laboratory - East (ANL-E) Experimental Boiling Water Reactor (EBWR) facility contains the descriptions and evaluations of the activities and the results of the EBWR D ampersand D project. It provides the following information: (1) An overall description of the ANL-E site and EBWR facility. (2) The history of the EBWR facility. (3) A description of the D ampersand D activities conducted during the EBWR project. (4) A summary of the final status of the facility, including the final and confirmation surveys. (5) A summary of the final cost, schedule, and personnel exposure associated with the project, including a summary of the total waste generated. This project report covers the entire EBWR D ampersand D project, from the initiation of Phase I activities to final project closeout. After the confirmation survey, the EBWR facility was released as a open-quotes Radiologically Controlled Area,close quotes noting residual elevated activity remains in inaccessible areas. However, exposure levels in accessible areas are at background levels. Personnel working in accessible areas do not need Radiation Work Permits, radiation monitors, or other radiological controls. Planned use for the containment structure is as an interim transuranic waste storage facility (after conversion)

Argonne National Laboratory-east site environmental report for calendar year 1988

International Nuclear Information System (INIS)

Golchert, N.W.; Duffy, T.L.

1989-04-01

The results of the environmental monitoring program at Argonne National Laboratory (ANL) for 1988 are presented and discussed. Sample collections were made on the site, at the site boundary, and off the ANL site for comparison purposes. Measurements were made for a variety of radionuclides in air, surface water, ground water, soil, grass, bottom sediment, and milk. Samples were also analyzed for a variety of chemical constituents in surface water, ground water, and ANL effluent water. External penetrating radiation doses were also measured. The potential for radiation exposure to off-site population groups is estimated. The results of the program are interpreted in terms of the origin of the radioactive and chemical substances and are compared with applicable environmental quality standards. A United States Department of Energy dose calculation methodology, is used in this report. 28 refs., 9 figs., 81 tabs

Progress report for the scintillator plate calorimeter subsystem

International Nuclear Information System (INIS)

1990-01-01

This report covers the work completed in FY90 by ANL staff and those of Westinghouse STC and BICRON Corporation under subcontract to ANL towards the design of a compensating calorimeter based on the use of scintillator plate as the sensitive medium. It is presented as five task sections dealing with respectively mechanical design; simulation studies; optical system design; electronics development; development of rad hard plastic scintillator and wavelength shifter and a summary. The work carried out by the University of Tennessee under a subcontract from ANL is reported separately. Finally, as principal institution with responsibility for the overall management of this subsystem effort, the summary here reports the conclusions resulting from the work of the collaboration and their impact on our proposed direction of effort in FY91. This proposal, for obvious reasons is given separately

Acceptable noise level

DEFF Research Database (Denmark)

Olsen, Steen Østergaard; Nielsen, Lars Holme; Lantz, Johannes

2012-01-01

The acceptable noise level (ANL) is used to quantify the amount of background noise that subjects can accept while listening to speech, and is suggested for prediction of individual hearing-aid use. The aim of this study was to assess the repeatability of the ANL measured in normal-hearing subjects...... using running Danish and non-semantic speech materials as stimuli and modulated speech-spectrum and multi-talker babble noises as competing stimuli....

ELRA: The exposure limiting robotic apparatus

International Nuclear Information System (INIS)

Knighton, G.C.; Rosenberg, K.E.; Henslee, S.P.; Michelbacher, J.A.; Wilkes, C.W.

1992-09-01

A problem situation involving the handling of radioactive material at Argonne National Laboratory -- West (ANL-W) was solved through the use of remote handling techniques, providing significant exposure reduction to personnel. Robotic devices can be useful, but the cost of a robot is often prohibitive for many jobs. A low cost, disposable robot was built which successfully removed a highly radioactive and potentially explosive system from a hot cell at ANL-W

Acceptable noise level

DEFF Research Database (Denmark)

Olsen, Steen Østergaard; Nielsen, Lars Holme; Lantz, Johannes

2012-01-01

The acceptable noise level (ANL) is used to quantify the amount of background noise that subjects can accept while listening to speech, and is suggested for prediction of individual hearing-aid use. The aim of this study was to assess the repeatability of the ANL measured in normal-hearing subjec...... using running Danish and non-semantic speech materials as stimuli and modulated speech-spectrum and multi-talker babble noises as competing stimuli....

A Lifecycle Emissions Model (LEM): Lifecycle Emissions from Transportation Fuels, Motor Vehicles, Transportation Modes, Electricity Use, Heating and Cooking Fuels, and Materials

OpenAIRE

Delucchi, Mark

2003-01-01

This report documents changes to the methods and data in a recently revised version of the greenhouse-gas emissions model originally documented in Emissions of Greenhouse Gases from the Use of Transportation Fuels and Electricity, ANL/ESD/TM-22, Volumes 1 and 2, Center for Transportation Research, Argonne National Laboratory, Argonne (ANL), Illinois (DeLuchi, 1991, 1993). The revised Lifecycle Emissions Model (LEM) calculates energy use, air-pollutant emissions, and CO2-equivalent emissions o...

Upgrades to the WIMS-ANL code

International Nuclear Information System (INIS)

Woodruff, W. L.

1998-01-01

The dusty old source code in WIMS-D4M has been completely rewritten to conform more closely with current FORTRAN coding practices. The revised code contains many improvements in appearance, error checking and in control of the output. The output is now tabulated to fit the typical 80 column window or terminal screen. The Segev method for resonance integral interpolation is now an option. Most of the dimension limitations have been removed and replaced with variable dimensions within a compile-time fixed container. The library is no longer restricted to the 69 energy group structure, and two new libraries have been generated for use with the code. The new libraries are both based on ENDF/B-VI data with one having the original 69 energy group structure and the second with a 172 group structure. The common source code can be used with PCs using both Windows 95 and NT, with a Linux based operating system and with UNIX based workstations. Comparisons of this version of the code to earlier evaluations with ENDF/B-V are provided, as well as, comparisons with the new libraries

Upgrades to the WIMS-ANL code

International Nuclear Information System (INIS)

Woodruff, W.L.; Leopando, L.S.

1998-01-01

The dusty old source code in WIMS-D4M has been completely rewritten to conform more closely with current FORTRAN coding practices. The revised code contains many improvements in appearance, error checking and in control of the output. The output is now tabulated to fit the typical 80 column window or terminal screen. The Segev method for resonance integral interpolation is now an option. Most of the dimension limitations have been removed and replaced with variable dimensions within a compile-time fixed container. The library is no longer restricted to the 69 energy group structure, and two new libraries have been generated for use with the code. The new libraries are both based on ENDF/B-VI data with one having the original 69 energy group structure and the second with a 172 group structure. The common source code can be used with PCs using both Windows 95 and NT, with a Linux based operating system and with UNIX based workstations. Comparisons of this version of the code to earlier evaluations with ENDF/B-V are provided, as well as, comparisons with the new libraries. (author)

The EPRI Laboratory experiments at ANL

International Nuclear Information System (INIS)

Roche, M.F.; Settle, J.L.; Leibowitz, L.; Johnson, C.E.; Ritzman, R.L.

1987-01-01

The vaporization of core-concrete mixtures is being measured using a transpiration method. Mixtures of stainless steel, concrete (limestone or basaltic) and urania (doped with La 2 O 3 , SrO, BaO, and ZrO 2 ) are vaporized at 2150 - 2400 K from a zirconia crucible into flowing He - 6% H 2 gas. Up to 600 ppM H 2 O is added to the gas to fix the partial molar free energy of oxygen in the range -420 kJ to -550 kJ. The fraction of the sample that is vaporized is determined by weight change and by chemical analyses on the condensates that are collected in an Mo condenser tube. The results are being used to test the thermodynemic data base and the underlying assumptions of computer codes used for prediction of release during the severe accident. 13 refs., 2 tabs

Tokamak power system studies at ANL

International Nuclear Information System (INIS)

Baker, C.C.; Ehst, D.A.; Brooks, J.N.; Evans, K. Jr.

1986-06-01

The following features, in particular, have been examined: (a) large aspect ratio (A ≅ 6), which may ease maintenance; (b) high beta (β ≥ 0.20) without indentation, which brings the maximum toroidal field down to about 6 to 7 T; (c) low toroidal current (I ≅ 4MA), which reduces the cost of the current drive and equilibrium field system; and (d) steady state operation with current density control via fast and slow wave current drive. The key to high beta operation with low toroidal current lies in utilizing second stability regime equilibria with the required current distributions produced by an appropriate selection of wave driver frequencies and power spectra. The ray tracing and current drive calculation is self-consistent with the actual magnetic fields they produce in the plasma. The impurity control activities in TPSS have emphasized the self-pumping concept as applied to using the entire first wall or ''slot'' limiters. The blanket design effort has emphasized liquid metal and Flibe concepts. The reference concept is a liquid lithium/vanadium, self-cooled configuration. Overall, there exists a number of major design improvements which will substantially improve the attractiveness of tokamak reactors

Tokamak power systems studies at ANL

International Nuclear Information System (INIS)

Baker, C.C.; Ehst, D.A.; Brooks, J.N.; Evans, K. Jr.

1986-01-01

A number of advances in plasma physics and engineering promise to greatly improve the reactor prospects of tokamaks. The following features, in particular, are examined: (a) large aspect ratio (A ≅ 6), which may ease maintenance; (b) high beta (β ≥ 0.20) without indentation, which brings the maximum toroidal field down to about 7 T; (c) low toroidal current (I ≅ 5MA), which reduces the cost of the current drive and equilibrium field system; and (d) steady state operation with current density control via fast and slow wave current drive. The key to high beta operation with low toroidal current lies in utilizing second stability regime equilibria with the required current distributions produced by an appropriate selection of wave driver frequencies and power spectra. The ray tracing and current drive calculation is self-consistent with the actual magnetic fields produced in the plasma. In addition to matching desirable high-beta equilibria, this method is capable of producing a large variety of new equilibria, many of which look attractive. The impurity control activities in TPSS have emphasized the self-pumping concept as applied to using the entire first wall or ''slot'' limiters. The blanket design effort has emphasized liquid metal and Flibe concepts. The reference concept is a liquid lithium/vanadium, self-cooled configuration. Overall, there exists a number of major design improvements which will substantially improve the attractiveness of tokamak reactors

Investigation of GOSIP technology at ANL

Energy Technology Data Exchange (ETDEWEB)

Winkler, L.

1992-01-01

This document describes testing of OSI products conducted at Argonne National Laboratory. Sun, IBM, and Clsco hardware platforms were used. Various software packages that implement file transfer and gateway applications were evaluated. The OSI model and GOSIP compliance are briefly discussed. Technical details on OSI addressing and routing are presented. The relationship of this testing to other OSI activities at Argonne and to activities of the national networking community is discussed. Mention is also made of the relationship of DECnet Phase V transition issues.

Final Environmental Impact Statement for the Treatment and Management of Sodium-Bonded Spent Nuclear Fuel

International Nuclear Information System (INIS)

2000-01-01

DOE is responsible for the safe and efficient management of its sodium-bonded spent nuclear fuel. This fuel contains metallic sodium, a highly reactive material; metallic uranium, which is also reactive; and in some cases, highly enriched uranium. The presence of reactive materials could complicate the process of qualifying and licensing DOE's sodium-bonded spent nuclear fuel inventory for disposal in a geologic repository. Currently, more than 98 percent of this inventory is located at the Idaho National Engineering and Environmental Laboratory (INEEL), near Idaho Falls, Idaho. In addition, in a 1995 agreement with the State of Idaho, DOE committed to remove all spent nuclear fuel from Idaho by 2035. This EIS evaluates the potential environmental impacts associated with the treatment and management of sodium-bonded spent nuclear fuel in one or more facilities located at Argonne National Laboratory-West (ANL-W) at INEEL and either the F-Canyon or Building 105-L at the Savannah River Site (SRS) near Aiken, South Carolina. DOE has identified and assessed six proposed action alternatives in this EIS. These are: (1) electrometallurgical treatment of all fuel at ANL-W, (2) direct disposal of blanket fuel in high-integrity cans with the sodium removed at ANL-W, (3) plutonium-uranium extraction (PUREX) processing of blanket fuel at SRS, (4) melt and dilute processing of blanket fuel at ANL-W, (5) melt and dilute processing of blanket fuel at SRS, and (6) melt and dilute processing of all fuel at ANL-W. In addition, Alternatives 2 through 5 include the electrometallurgical treatment of driver fuel at ANL-W. Under the No Action Alternative, the EIS evaluates both the continued storage of sodium-bonded spent nuclear fuel until the development of a new treatment technology or direct disposal without treatment. Under all of the alternatives, the affected environment is primarily within 80 kilometers (50 miles) of spent nuclear fuel treatment facilities. Analyses indicate

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

International Nuclear Information System (INIS)

Boing, L.E.; Coffey, M.J.; Ditch, R.W.; Fellhauer, C.R.; Rose, R.W.

1996-01-01

Argonne National Laboratory (ANL) is implementing waste minimization and pollution prevention activities into its conduct of decontamination and decommissioning (D ampersand 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 ampersand D projects at ANL are presented

Brugervejledning TEMPFO 4

DEFF Research Database (Denmark)

Kloch, Søren; Pedersen, Thomas

Denne publikation er en indføring i EDB-kørsel med dataprogrammet TEMPFO 4 beregnet med referenceårets vejrdata. Kørselsvejledningen indeholder dels beskrivelse af jobafviklingen på AUD's anlæg og dels beregningseksempel.......Denne publikation er en indføring i EDB-kørsel med dataprogrammet TEMPFO 4 beregnet med referenceårets vejrdata. Kørselsvejledningen indeholder dels beskrivelse af jobafviklingen på AUD's anlæg og dels beregningseksempel....

Fuel conditioning facility electrorefiner start-up results

International Nuclear Information System (INIS)

Goff, K.M.; Mariani, R.D.; Vaden, D.; Bonomo, N.L.; Cunningham, S.S.

1996-01-01

At ANL-West, there are several thousand kilograms of metallic spent nuclear fuel containing bond sodium. This fuel will be treated in the Fuel Conditioning Facility (FCF) at ANL-West to produce stable waste forms for storage and disposal. The treatment operations will make use of an electrometallurgical process employing molten salts and liquid metals. The treatment equipment is presently undergoing testing with depleted uranium. Operations with irradiated fuel will commence when the environmental evaluation for FCF is complete

Southern Great Plains Safety Orientation

Energy Technology Data Exchange (ETDEWEB)

Schatz, John

2014-05-01

Welcome to the Atmospheric Radiation Measurement (ARM) Climate Research Facility (ARM) Southern Great Plains (SGP) site. This U.S. Department of Energy (DOE) site is managed by Argonne National Laboratory (ANL). It is very important that all visitors comply with all DOE and ANL safety requirements, as well as those of the Occupational Safety and Health Administration (OSHA), the National Fire Protection Association, and the U.S. Environmental Protection Agency, and with other requirements as applicable.

Advanced Numerical Techniques of Performance Evaluation. Volume 1

Science.gov (United States)

1990-06-01

34Speedup": Performance Analysis of Parallel Programs. Technical Report ANL-87-7, Mathematics and Computer Science Division, Argonne National Laboratory...and dequeue- pilicessoms a shared bus, and a write-through cache coherency4 hras anocu i amlc.wih a rotm sig if roocl[ Lvel & hakr 9U.Th Smety a atie...James M. Boyle. Beyond "Speedup": Parlor- mance Analysis of Parallel Progrms. Technical Report ANL-J7-7. Mathematics and Computer Science Division, Aronn

Uranium silicide activities at Babcock and Wilcox

International Nuclear Information System (INIS)

Noel, W.W.; Freim, J.B.

1983-01-01

Babcock and Wilcox, Naval Nuclear Fuel Division (NNFD) in conjunction with Argonne National Laboratory (ANL) is actively involved in the Reduced Enrichment Research Test Reactor (RERTR) Program to produce low enriched fuel elements for research reactors. B and W and ANL have undertaken a joint effort in which NNFD will fabricate two low enriched uranium (LEU), Oak Ridge Reactor (ORR) elements with uranium silicide fuel furnished by ANL. These elements are being fabricated for irradiation testing at Oak Ridge National Laboratory (ORNL). Concurrently with this program, NNFD is developing and implementing the uranium silicide and uranium aluminide fuel fabrication technology. NNFD is fabricating the uranium silicide ORR elements in a two-phase program, Development and Production. To summarize: 1. Full size fuel plates can be made with U 3 SiAl but the fabricator must prevent oxidation of the compact prior to hot roll bonding; 2. Providing the ANL U 3 Si x irradiation results are successful, NNFD plans to provide two ORR elements during February 1983; 3. NNFD is developing and implementing U 3 Si x and UAI x fuel fabrication technology to be operational in 1983; 4. NNFD can supply U 3 O 8 high enriched uranium (HEU) or low enriched uranium (LEU) research reactor elements; 5. NNFD is capable of providing high quality, cost competitive LEU or HEU research reactor elements to meet the needs of the customer

Superconducting TlCa2Ba2Cu3O9 thick films

International Nuclear Information System (INIS)

1994-01-01

GE Corporate Research and Development's (GE-CRD) program to develop the two-zone silver addition (TZSA) process for fabricating superconducting films of TlCa 2 Ba 2 Cu 3 O 9 has activities in the areas of (1) precursor preparation, (2) the thallium oxide vapor process, (3) the effects of post-synthesis annealing ambient and temperature on superconducting properties, (4) the influence of film stoichiometry and composition on superconducting properties, (5) microstructure and film growth mechanism, (6) the preparation of thicker films, (7) the fabrication of films on flexible substrates, and (8) process scale-up. As part of its effort under the ANL Pilot Center Agreement, GE-CRD has supplied to ANL a complete two-zone furnace, has provided consultation on its use and on the planning of experiments, has processed ANL samples in GE's furnaces to help define optimum process conditions, and has provided precursor and finished films as requested. These contributions are described more fully in the descriptions of the work performed at ANL presented elsewhere in this report. Under the Pilot Center Agreement work at GE-CRD has been directed toward the optimization of the TZSA process with emphasis on (A) process improvement, (B) effects of silver content on film properties, (C) the relationship between microstructure and J c , and (D) toward the assessment of the compatibility of silver substrates with the process chemistry

Reduction of patient dose delivered by CHR diagnostic x-ray examinations

International Nuclear Information System (INIS)

Evans, R.D.; Schlenker, R.A.

1978-01-01

Three changes in technique have been made which reduce the x-ray dose delivered by diagnostic examinations of patients of the Center for Human Radiobiology (CHR): Kodak Lanex Regular screens and Kodak Ortho G film have been substituted for DuPont Cronex Parspeed screens and DuPont Cronex 4 film for five projections in the MIT examinations; 3 mm Al added filtration is now used in place of 1 mm Al added filtration in the ANL examination; improvements in collimation for the ANL examination have been made. Use of the new screen-film combination at MIT has reduced the mean dose to the active marrow of the female RANDO phantom from 606 +- 69 mrad to 235 +- 16 mrad; it has reduced the ovary dose from 606 +- 40 mrad to 291 +- 19 mrad and has left the breast dose unchanged at 333 +- 103 mrad. The change from 1 mm Al to 3 mm Al added filtration at ANL, without changes in collimation, would reduce the mean marrow dose in the phantom from 232 +- 14 mrad to 175 +- 26 mrad, reduce the ovary dose from 243 +- 25 mrad to 162 +- 38 mrad and reduce the breast dose from 388 +- 35 mrad to 226 +- 9 mrad. The changes in collimation at ANL should reduce these doses even further but the quantitative effect has not been ascertained

Inspection and monitoring plan, contaminated groundwater seeps 317/319/ENE Area, Argonne National Laboratory

International Nuclear Information System (INIS)

1996-01-01

During the course of completing the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) in the 317/319/East-Northeast (ENE) Area of Argonne National Laboratory-East (ANL-E), groundwater was discovered moving to the surface through a series of groundwater seeps. The seeps are located in a ravine approximately 600 ft south of the ANL-E fence line in Waterfall Glen Forest Preserve. Samples of the seep water were collected and analyzed for selected parameters. Two of the five seeps sampled were found to contain detectable levels of organic contaminants. Three chemical species were identified: chloroform (14--25 microg/L), carbon tetrachloride (56--340 microg/L), and tetrachloroethylene (3--6 microg/L). The other seeps did not contain detectable levels of volatile organics. The nature of the contaminants in the seeps will also be monitored on a regular basis. Samples of surface water flowing through the bottom of the ravine and groundwater emanating from the seeps will be collected and analyzed for chemical and radioactive constituents. The results of the routine sampling will be compared with the concentrations used in the risk assessment. If the concentrations exceed those used in the risk assessment, the risk calculations will be revised by using the higher numbers. This revised analysis will determine if additional actions are warranted

Determination of Energy Use Efficiency of Sesame Production

OpenAIRE

BARAN, Mehmet Firat

2018-01-01

In this research it was aimed to determine an energy use efficiency of sesame production in Şanlıurfa province, during the production season of 2015. In order to determine the energy use efficiency of sesame production, trials and measurement were performed in sesame farm in the Bozova district of Şanlıurfa province. As energy inputs, human labour energy, machinery energy, chemical fertilizers energy, irrigation water energy, chemicals energy, diesel fuel energy and seed energy as were calcul...

Design of Mixed Batch Reactor and Column Studies at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Wu, Weimin; Criddle, Craig S.

2015-01-01

We (the Stanford research team) were invited as external collaborators to contribute expertise in environmental engineering and field research at the ORNL IFRC, Oak Ridge, TN, for projects carried out at the Argonne National Laboratory and funded by US DOE. Specifically, we assisted in the design of batch and column reactors using ORNL IFRC materials to ensure the experiments were relevant to field conditions. During the funded research period, we characterized ORNL IFRC groundwater and sediments in batch microcosm and column experiments conducted at ANL, and we communicated with ANL team members through email and conference calls and face-to-face meetings at the annual ERSP PI meeting and national meetings. Microcosm test results demonstrated that U(VI) in sediments was reduced to U(IV) when amended with ethanol. The reduced products were not uraninite but unknown U(IV) complexes associated with Fe. Fe(III) in solid phase was only partially reduced. Due to budget reductions at ANL, Stanford contributions ended in 2011.

Monitoring Uranium Transformations Determined by the Evolution of Biogeochemical Processes: Design of Mixed Batch Reactor and Column Studies at Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Criddle, Craig S.; Wu, Weimin

2013-04-17

With funds provided by the US DOE, Argonne National Laboratory subcontracted the design of batch and column studies to a Stanford University team with field experience at the ORNL IFRC, Oak Ridge, TN. The contribution of the Stanford group ended in 2011 due to budget reduction in ANL. Over the funded research period, the Stanford research team characterized ORNL IFRC groundwater and sediments and set up microcosm reactors and columns at ANL to ensure that experiments were relevant to field conditions at Oak Ridge. The results of microcosm testing demonstrated that U(VI) in sediments was reduced to U(IV) with the addition of ethanol. The reduced products were not uraninite but were instead U(IV) complexes associated with Fe. Fe(III) in solid phase was only partially reduced. The Stanford team communicated with the ANL team members through email and conference calls and face to face at the annual ERSP PI meeting and national meetings.

Safety assessment of the Indonesian multipurpose reactor RSG-GAS against ATWS and hypothetical accidents

International Nuclear Information System (INIS)

Hastowo, H.; Nabbi, R.; Prayoto; Ismuntoyo, R.P.H.

2004-01-01

Investigation on ATWS and hypothetical accidents for the Indonesian Multipurpose Reactor RSG-GAS have been undertaken by computer simulation technique. Two computer codes, namely RELAP5 and PARET-ANL, were used as the main tools. The RELAP5 was utilized to perform system analysis while the PARET-ANL code was used to perform the reactor core analysis in more detail. Two different models have been applied as a basis of the simulation: Typical Working Core model (IWC-model) consisting of four regions with different radial power factors; and the hot-channel model consisting of two regions with different radial power factors. Both RELAP5 ad PARET-ANL results showed that in the occurrence of ATWS, failure on fuel element or fuel plate was limited to the region with the most highest power factor. The results also indicated that no high pressure development occurs in that region, so that mechanical damage on the fuel element or other core components due to pressure shock did not happen.(author)

Design of Mixed Batch Reactor and Column Studies at Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Wu, Weimin [Stanford Univ., CA (United States); Criddle, Craig S. [Stanford Univ., CA (United States)

2015-11-16

We (the Stanford research team) were invited as external collaborators to contribute expertise in environmental engineering and field research at the ORNL IFRC, Oak Ridge, TN, for projects carried out at the Argonne National Laboratory and funded by US DOE. Specifically, we assisted in the design of batch and column reactors using ORNL IFRC materials to ensure the experiments were relevant to field conditions. During the funded research period, we characterized ORNL IFRC groundwater and sediments in batch microcosm and column experiments conducted at ANL, and we communicated with ANL team members through email and conference calls and face-to-face meetings at the annual ERSP PI meeting and national meetings. Microcosm test results demonstrated that U(VI) in sediments was reduced to U(IV) when amended with ethanol. The reduced products were not uraninite but unknown U(IV) complexes associated with Fe. Fe(III) in solid phase was only partially reduced. Due to budget reductions at ANL, Stanford contributions ended in 2011.

Audit calculation of the limiting CESSAR feedwater-line-break transient with RELAP5/MOD1

International Nuclear Information System (INIS)

Chung, K.S.; Kennedy, M.F.; Guttmann, J.

1983-01-01

Argonne National Laboratory (ANL) performed a series of audit calculations of the limiting FLB transient presented in Appendix 15B to the CESSAR FSAR, supported by a limited number of additional calculations to investigate the sensitivity of the results (in terms of peak primary reactor system pressure) to break area and reactor trip time. The latter calculations were performed to quantify potential benefits in crediting reactor tip on low steam generator downcomer water level, which occurs earlier than the trip shown in the limiting FSAR transient, which tripped on high pressurizer pressure. These calculations were performed to verify the break spectrum results presented by C-E and to insure that C-E did indeed analyze the limiting transient. All of the ANL calculations were performed with RELAP5/MOD1 (cycle 18) using an input deck developed at ANL from CESSAR plant data provided by C-E. In this paper we compare the results and provide insight into the generic behavior of a Feedwater Line Break transient

Fears for Sale from the Owner: The Role of Media in the Construction of Women as the Frightened Subject

Directory of Open Access Journals (Sweden)

Şehriban Şahin Kaya

2012-06-01

Full Text Available Television, which makes people lonely and standardized, is in the business of constructing woman as frightened subject. Women who have been pushed out of job market, prisoned at home where they found shelter and are exposed to televion spreding fears and anxieties. Thus, the real frightened problems remain untouched and replaced by superfluous fears. Society, which sees security as the only way of existence, reveals itself in the relationship between gender and crime. This article aims to examine the construction of woman as frightened subject by analyzing the Müge Anlı ile Tatlı Sert (Sweet and Hard with Müge Anlı, a reality show which is one of the most watched TV program by women. The question this article searches for an answer is why women of media sell fears and anxieties to women. Müge Anlı’s program has the central position to find this anwer

Review of the treat upgrade reactor scram system reliability analysis

International Nuclear Information System (INIS)

Montague, D.F.; Fussell, J.B.; Krois, P.A.; Morelock, T.C.; Knee, H.E.; Manning, J.J.; Haas, P.M.; West, K.W.

1984-10-01

In order to resolve some key LMFBR safety issues, ANL personnel are modifying the TREAT reactor to handle much larger experiments. As a result of these modifications, the upgraded Treat reactor will not always operate in a self-limited mode. During certain experiments in the upgraded TREAT reactor, it is possible that the fuel could be damaged by overheating if, once the computer systems fail, the reactor scram system (RSS) fails on demand. To help ensure that the upgraded TREAT reactor is shut down when required, ANL personnel have designed a triply redundant RSS for the facility. The RSS is designed to meet three reliability goals: (1) a loss of capability failure probability of 10 -9 /demand (independent failures only); (2) an inadvertent shutdown probability of 10 -3 /experiment; and (3) protection agaist any known potential common cause failures. According to ANL's reliability analysis of the RSS, this system substantially meets these goals

Evaluating the environmental impacts of the energy system: The ENPEP [ENergy and Power Evaluation Program] approach

International Nuclear Information System (INIS)

Hamilton, B.P.; Sapinski, P.F.; Cirillo, R.R.; Buehring, W.A.

1990-01-01

Argonne National Laboratory (ANL) has developed the ENergy and Power Evaluation Program (ENPEP), a PC-based energy planning package intended for energy/environmental analysis in developing countries. The IMPACTS module of ENPEP examines environmental implications of overall energy and electricity supply strategies that can be developed with other ENPEP modules, including ELECTRIC, the International Atomic Energy Agency's Wien Automatic System Planning Package (WASP-III). The paper presents the status and characteristics of a new IMPACTS module that is now under development at ANL. 3 figs

Accelerator lyfter forskningen

CERN Multimedia

Frankel, Göran

2004-01-01

"Geologerna i Lund har under hösten byggt upp och testat en ny anläggning för $^{14}$C-datering med s.k. AMS - Acceleratormasspektrometri. AMS - Metodenär inte ny men just den här teknologinär det - det här är den första anläggningen i shitt slag i världen och förvänt-ningarna på vad den ska kunna åstad komma är stora" (1 page)

Methods for removing transuranic elements from waste solutions

International Nuclear Information System (INIS)

Slater, S.A.; Chamberlain, D.B.; Connor, C.; Sedlet, J.; Srinivasan, B.; Vandegrift, G.F.

1994-11-01

This report outlines a treatment scheme for separating and concentrating the transuranic (TRU) elements present in aqueous waste solutions stored at Argonne National Laboratory (ANL). The treatment method selected is carrier precipitation. Potential carriers will be evaluated in future laboratory work, beginning with ferric hydroxide and magnetite. The process will result in a supernatant with alpha activity low enough that it can be treated in the existing evaporator/concentrator at ANL. The separated TRU waste will be packaged for shipment to the Waste Isolation Pilot Plant

Characterization report for Building 301 Hot Cell Facility

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

During the period from October, 1997, through March, 1998, ANL-E Health Physics conducted a pre-D and D characterization of Building 301, referred to as the Hot Cell Facility. While primary emphasis was placed on radiological evaluation, the presence of non-nuclear hazardous and toxic material was also included in the scope of the characterization. This is one of the early buildings on the ANL-E site, and was heavily used in the 1950`s and 1960`s for various nuclear reaction and reactor design studies. Some degree of cleanup and contamination fixation was done in the 1970`s, so that the building could be used with a minimum of risk of personnel contamination. Work records are largely nonexistent for the early history of the building, so that any assumptions about extent and type of contamination had to be kept very open in the survey planning process. The primary contaminant was found to be painted-over Cs-137 embedded in the concrete floors, although a variety of other nuclides consistent with the work said to have been performed were found in smaller quantities. Due to leaks and drips through the floor, a relatively modest amount of soil contamination was found in the service trench under the building, not penetrating deeply. Two contaminated, disconnected drain lines leaving the building could not be traced by site records, and remain a problem for remediation. The D and D Characterization Plan was fulfilled.

Evaluation of the single-pass flow-through test to support a low-activity waste specification

International Nuclear Information System (INIS)

McGrail, B.P.; Peeler, D.K.

1995-09-01

A series of single-pass flow-through (SPFT) tests was performed on five reference low-activity waste glasses and a reference glass from the National Institute of Standards and Technology to support a product specification for low-activity waste (LAW) forms. The results showed that the SPFT test provides a means to quantitatively distinguish among LAW glass forms in terms of their forward reaction rate at a given temperature and solution pH. Two of the test glasses were also subjected to SPFT testing at Argonne National Laboratory (ANL). Forward reaction rate constants calculated from the ANL test data were 100 to over 1,000 times larger than the values obtained from the SPFT tests conducted at PNL. An analysis of the ANL results showed that they were inconsistent with independent measurements done on glasses of similar composition, the known pH-dependence of the forward rate, and with the results from low surface-area-to-volume, short duration product consistency tests. Because the data set obtained from the SPFT tests done at PNL was consistent with each of these same factors, a detailed examination of the test procedures used at both laboratories was performed to determine the cause(s) of the discrepancy. The omission of background subtraction in the data analysis procedure and the short-duration (on the order of hours) of the ANL tests are factors that may have significantly affected the calculated rates

Decontamination and dismantlement of the building 594 waste ion exchange facility at Argonne National Laboratory-East project final report

International Nuclear Information System (INIS)

Wiese, E. C.

1998-01-01

The Building 594 D and D Project was directed toward the following goals: Removal of any radioactive and hazardous materials associated with the Waste Ion Exchange Facility; Decontamination of the Waste Ion Exchange Facility to unrestricted use levels; Demolition of Building 594; and Documentation of all project activities affecting quality (i.e., waste packaging, instrument calibration, audit results, and personnel exposure) These goals had been set in order to eliminate the radiological and hazardous safety concerns inherent in the Waste Ion Exchange Facility and to allow, upon completion of the project, unescorted and unmonitored access to the area. The ion exchange system and the resin contained in the system were the primary areas of concern, while the condition of the building which housed the system was of secondary concern. ANL-E health physics technicians characterized the Building 594 Waste Ion Exchange Facility in September 1996. The characterization identified a total of three radionuclides present in the Waste Ion Exchange Facility with a total activity of less than 5 microCi (175 kBq). The radionuclides of concern were Co 60 , Cs 137 , and Am 241 . The highest dose rates observed during the project were associated with the resin in the exchange vessels. DOE Order 5480.2A establishes the maximum whole body exposure for occupational workers at 5 rem (50 mSv)/yr; the administrative limit at ANL-E is 1 rem/yr (10 mSv/yr)

Characterization report for Building 301 Hot Cell Facility

International Nuclear Information System (INIS)

1998-07-01

During the period from October, 1997, through March, 1998, ANL-E Health Physics conducted a pre-D and D characterization of Building 301, referred to as the Hot Cell Facility. While primary emphasis was placed on radiological evaluation, the presence of non-nuclear hazardous and toxic material was also included in the scope of the characterization. This is one of the early buildings on the ANL-E site, and was heavily used in the 1950's and 1960's for various nuclear reaction and reactor design studies. Some degree of cleanup and contamination fixation was done in the 1970's, so that the building could be used with a minimum of risk of personnel contamination. Work records are largely nonexistent for the early history of the building, so that any assumptions about extent and type of contamination had to be kept very open in the survey planning process. The primary contaminant was found to be painted-over Cs-137 embedded in the concrete floors, although a variety of other nuclides consistent with the work said to have been performed were found in smaller quantities. Due to leaks and drips through the floor, a relatively modest amount of soil contamination was found in the service trench under the building, not penetrating deeply. Two contaminated, disconnected drain lines leaving the building could not be traced by site records, and remain a problem for remediation. The D and D Characterization Plan was fulfilled

Kryogenbehandling: vejen til forståelse

DEFF Research Database (Denmark)

Stojko, Allan; Frandsen, Rasmus Berg; Somers, Marcel A.J.

2003-01-01

De mekaniske egenskaber for visse ståltyper kan påvirkes ved kryogenbehandling, dvs. en nedkøling til -196C efter austenitisering og før anløbning. Kuglelejestål, 100Cr6 (AISI E 52100), er blevet undersøgt med dilatometri, røntgendiffraktion (XRD) og transmissions elektron mikroskopi (TEM...... anløbningen var ca. 20 % mindre i det kryogenbehandlede 100Cr6 end i det konventionelt behandlede materiale. Spændingsmålinger med XRD antyder en mere homogen spændingsfordeling i kryogenbehandlet 100Cr6....

Implementing partnerships in nonreactor facility safety analyses

International Nuclear Information System (INIS)

Courtney, J.C.; Perry, W.H.; Phipps, R.D.

1996-01-01

Faculty and students from LSU have been participating in nuclear safety analyses and radiation protection projects at ANL-W at INEL since 1973. A mutually beneficial relationship has evolved that has resulted in generation of safety-related studies acceptable to Argonne and DOE, NRC, and state regulatory groups. Most of the safety projects have involved the Hot Fuel Examination Facility or the Fuel Conditioning Facility; both are hot cells that receive spent fuel from EBR-II. A table shows some of the major projects at ANL-W that involved LSU students and faculty

Superconductivity Technology Program for electric power systems: Proceedings

Energy Technology Data Exchange (ETDEWEB)

Marriott, K.B.

1993-09-01

Twenty-seven presentations are included in viewgraph form for the wire development panel, applications development panel, and thallium workshop. Authors and affiliations are: (wire development panel) Kreoger/Christen (ORNL), Malozemoff (American Superconductor Corp.), Blaugher (National Renewable Energy Lab.), Haldar (Intermagnetics), Gray/Lanagan/Eror (ANL), Bickel/Voigt/Roth (Sandia), Tkaczyk (GE), Suenaga (BNL), Willis/Korzekwa/Maley (Los Alamos); (applications development panel) Peterson/Stewart (Los Alamos), Iwasa (BNL), Hull/Nieman (ANL), Murphy/DeGregoria (ORNL), Hazelton (Intermagnetics), Dykhuizen (Sandia); (thallium workshop) Goodrich (NIST), Blaugher (NREL), Roth (Sandia), Holstein (DuPont), Paranthaman (ORNL), and Willis (Los Alamos).

Turbulent Dynamo Amplification of Magnetic Fields in Laser-Produced Plasmas: Simulations and Experiments

Science.gov (United States)

Tzeferacos, P.; Rigby, A.; Bott, A.; Bell, A.; Bingham, R.; Casner, A.; Cattaneo, F.; Churazov, E.; Forest, C.; Katz, J.; Koenig, M.; Li, C.-K.; Meinecke, J.; Petrasso, R.; Park, H.-S.; Remington, B.; Ross, J.; Ryutov, D.; Ryu, D.; Reville, B.; Miniati, F.; Schekochihin, A.; Froula, D.; Lamb, D.; Gregori, G.

2017-10-01

The universe is permeated by magnetic fields, with strengths ranging from a femtogauss in the voids between the filaments of galaxy clusters to several teragauss in black holes and neutron stars. The standard model for cosmological magnetic fields is the nonlinear amplification of seed fields via turbulent dynamo. We have conceived experiments to demonstrate and study the turbulent dynamo mechanism in the laboratory. Here, we describe the design of these experiments through large-scale 3D FLASH simulations on the Mira supercomputer at ANL, and the laser-driven experiments we conducted with the OMEGA laser at LLE. Our results indicate that turbulence is capable of rapidly amplifying seed fields to near equipartition with the turbulent fluid motions. This work was supported in part from the ERC (FP7/2007-2013, No. 256973 and 247039), and the U.S. DOE, Contract No. B591485 to LLNL, FWP 57789 to ANL, Grant No. DE-NA0002724 and DE-SC0016566 to the University of Chicago, and DE-AC02-06CH11357 to ANL.

Status of RF superconductivity at Argonne

International Nuclear Information System (INIS)

Shepard, K.W.

1990-01-01

Development of a superconducting slow-wave structures began at Argonne National Laboratory (ANL) in 1971, and led to the first superconducting heavy-ion linac (ATLAS - the Argonne Tandem-Linac Accelerator System). The Physics Division at ANL has continued to develop superconducting RF technology for accelerating heavy-ions, with the result that the linac has been in an almost continuous process of upgrade and expansion. In 1987, the Engineering Physics Division at ANL began developing of superconducting RF components for the acceleration of high-brightness proton and deuterium beams. The two divisions collaborate in work on several applications of RF superconductivity, and also in work to develop the technology generally. The present report briefly describes major features of the superconducting heavy-ion linac (very-low-velocity superconducting linac, positive ion injector), proton accelerating structures (superconducting resonant cavities for acceleration of high-current proton and deuteron beams, RF properties of oxide superconductors), and future work. Both divisions expect to continue a variety of studies, frequently in collaboration, to advance the basic technology of RF superconductivity. (N.K.)

Data Reduction Algorithm Using Nonnegative Matrix Factorization with Nonlinear Constraints

Science.gov (United States)

Sembiring, Pasukat

2017-12-01

Processing ofdata with very large dimensions has been a hot topic in recent decades. Various techniques have been proposed in order to execute the desired information or structure. Non- Negative Matrix Factorization (NMF) based on non-negatives data has become one of the popular methods for shrinking dimensions. The main strength of this method is non-negative object, the object model by a combination of some basic non-negative parts, so as to provide a physical interpretation of the object construction. The NMF is a dimension reduction method thathasbeen used widely for numerous applications including computer vision,text mining, pattern recognitions,and bioinformatics. Mathematical formulation for NMF did not appear as a convex optimization problem and various types of algorithms have been proposed to solve the problem. The Framework of Alternative Nonnegative Least Square(ANLS) are the coordinates of the block formulation approaches that have been proven reliable theoretically and empirically efficient. This paper proposes a new algorithm to solve NMF problem based on the framework of ANLS.This algorithm inherits the convergenceproperty of the ANLS framework to nonlinear constraints NMF formulations.

Improved HEPA Filter Technology for Flexible and Rigid Containment Barriers

International Nuclear Information System (INIS)

Pinson, Paul Arthur

1998-01-01

Safety and reliability in glovebox operations can be significantly improved and waste packaging efficiencies can be increased by inserting flexible, lightweight, high capacity HEPA filters into the walls of plastic sheet barriers. This HEPA filter/barrier technology can be adapted to a wide variety of applications: disposable waste bags, protective environmental barriers for electronic equipment, single or multiple use glovebag assemblies, flexible glovebox wall elements, and room partitions. These reliable and inexpensive filtered barriers have many uses in fields such as radioactive waste processing, HVAC filter changeout, vapor or grit blasting, asbestos cleanup, pharmaceutical, medical, biological, and electronic equipment containment. The applications can result in significant cost savings, improved operational reliability and safety, and total waste volume reduction. This technology was developed at the Argonne National Laboratory-West (ANL-W) in 1993 and has been used at ANL-W since then at the TRU Waste Characterization Chamber Gloveboxes. Another 1998 AGS Conference paper titled ''TRU Waste Characterization Gloveboxes'', presented by Mr. David Duncan of ANL-W, describes these boxes

DNA sekventering af bakterier i renseanlæg

DEFF Research Database (Denmark)

Albertsen, Mads; Nierychlo, Marta; Nielsen, Per Halkjær

nye muligheder, som vi ikke har turde drømme om indtil nu. Siden 2006 har vi i samarbejde med 54 danske renseanlæg, rådgivere (Krüger, Kemira) og Dansk Spildevandsteknisk Forening indsamlet prøver til MiDAS (Den Mikrobielle Database for Aktivt Slam) for at undersøge mikrobiologien og dens relation til...... drift og design af anlæggene. Vi kan nu f.eks. se hvilke bakteriearter, som findes i de danske anlæg, hvilke der er hyppige, hvilke anlægsparametre der er vigtige for artssammensætningen, og hvor lang tid det tager at få en stabil proces efter ændringer af drift eller procesdesign. Desuden giver de MiDAS...... karakterisering af mikrobiologien bliver brugt til, og hvordan den nye viden, der er indsamlet i MiDAS over de sidste 10 år, begynder at udmønte sig i konkrete værktøjer til trouble-shooting på de enkelte renseanlæg. Disse vil bl.a. omfatte forbedret identifikation og kontrol af visse trådformede bakterier samt...

Users guide for the ANL IBM SPx

Energy Technology Data Exchange (ETDEWEB)

Gropp, W.; Lusk, E.

1994-12-01

This guide presents the features of the IBM SPx installed in the Mathematics and Computer Science Division at Argonne National Laboratory. The guide describes the available hardware and software, access policies, and hints for using the system productively.

Supplemental site inspection for Air Force Plant 59, Johnson City, New York, Volume 1: Investigation report

Energy Technology Data Exchange (ETDEWEB)

Nashold, B.; Rosenblatt, D.; Hau, J. [and others

1995-08-01

This summary describes a Supplemental Site Inspection (SSI) conducted by Argonne National Laboratory (ANL) at Air Force Plant 59 (AFP 59) in Johnson City, New York. All required data pertaining to this project were entered by ANL into the Air Force-wide Installation Restoration Program Information System (IRPIMS) computer format and submitted to an appropriate authority. The work was sponsored by the United States Air Force as part of its Installation Restoration Program (IRP). Previous studies had revealed the presence of contaminants at the site and identified several potential contaminant sources. Argonne`s study was conducted to answer questions raised by earlier investigations.

Safety analysis of IFR fuel processing in the Argonne National Laboratory Fuel Cycle Facility

International Nuclear Information System (INIS)

Charak, I; Pedersen, D.R.; Forrester, R.J.; Phipps, R.D.

1993-01-01

The Integral Fast Reactor (IFR) concept developed by Argonne National Laboratory (ANL) includes on-site processing and recycling of discharged core and blanket fuel materials. The process is being demonstrated in the Fuel Cycle Facility (FCF) at ANL's Idaho site. This paper describes the safety analyses that were performed in support of the FCF program; the resulting safety analysis report was the vehicle used to secure authorization to operate the facility and carry out the program, which is now under way. This work also provided some insights into safety-related issues of a commercial IFR fuel processing facility. These are also discussed

2016 Inspection and Annual Site Status Report for the Site A/Plot M, Illinois, Decommissioned Reactor Site July 2016

Energy Technology Data Exchange (ETDEWEB)

Murl, Jeffrey [USDOE Office of Legacy Management, Washington, DC (United States); Miller, Michele [Navarro Research and Engineering, Oak Ridge, TN (United States)

2016-07-01

The Site A/Plot M, Illinois, Decommissioned Reactor Site was inspected on May 17, 2016. The site, located within Cook County forest preserve that is open to the public, was found to be in good condition with one exception. Erosion on top of the grass-covered mound at Plot M continues to be a concern as presented in previous inspections. Ruts form in the soil on top of Plot M as a result of bike traffic using the open field as a pass thru between established bike trails within the forest preserve. Argonne National Laboratory (ANL) who is contracted directly from U.S. Department of Energy (DOE) has filled in the ruts with top soil and reseeding remains an ongoing process. Reseeded areas from 2015 are progressing nicely. No cause for a follow-up inspection was identified. In 2015, ANL plugged and abandoned 8 of 25 monitoring wells (BH41, BH51, BH52, BH54, DH9, DH10, DH13, and DH17). The 17 groundwater monitoring wells remaining at the site were inspected to confirm that they were locked and in good condition. Preliminary environmental monitoring results for 2015 are provided in a draft report titled Surveillance of Site A and Plot M, Report for 2015, prepared by ANL. The report also contains results of an independent analysis conducted by the Illinois Emergency Management Agency on some of the samples collected by ANL in 2015. The draft report states that the results of the surveillance program continue to indicate that the impact of radioactivity at Site A/Plot M is very low and does not endanger the health of those living in the area or visiting the site. The ANL monitoring report will be made available to the public on the DOE Office of Legacy Management public website when it is issued as final. A new county forest preserve campsite opened in 2015 at Bull Frog Lake, which is east of Plot M. Hiking trails connect Bull Frog Lake with Site A/Plot M. The site might receive more traffic from forest preserve visitors now that this new campsite is opened.

Argonne National Laboratory - West's approach to filter characterization

International Nuclear Information System (INIS)

Miller, T. A.

1999-01-01

Like other DOE facilities, ANL-W uses a variety of nuclear grade, industrial grade, or furnace-type particulate filters to control airborne radioactivity and hazardous contaminants in radiological containment structures or processes. As designed, these filters entrain and ultimately concentrate contaminants in the media. Toxic metal contaminants include cadmium, chromium, lead; and mercury present in sufficient concentrations to exhibit the hazardous waste characteristic of toxicity as defined in 40 CFR 261.24. Radionuclide contaminants deposited in the media may at times accumulate in sufficient quantity to classify the filter as transuranic or remote-handled waste. Upon their removal from the ventilation system, these particulate filters become wastes, which must be characterized to determine their hazardous and radioactive classifications. A well defined filter characterization process is essential for the proper/consistent waste characterization and minimization and for maintaining personnel radiological exposures as-low-as-reasonably-achievable (ALARA) (1,2). ANL-W has developed an approach to filter sampling and characterization to meet these needs. The ANL-W filter sampling and characterization process is designed to ensure representative sampling and/or process knowledge is utilized in characterizing the filters. The data obtained through sampling and/or process knowledge is used to show compliance with the Resource Conservation and Recovery Act (3) and Treatment/Storage/Disposal Facility Waste Acceptance Criteria. The ANL-W filter characterization involves the collection of process information, filter handling and sampling, sample analysis, data management filter characterization, and waste handling. Each element of the process is streamlined to ensure proper characterization while minimizing radiological exposure to maintenance workers, samplers, laboratory personnel, and waste handlers

The status of uranium-silicon alloy fuel development for the RERTR program

International Nuclear Information System (INIS)

Domagala, R.F.; Wiencek, T.C.; Thresh, H.R.; Stahl, D.

1983-01-01

As part of the national Reduced Enrichment Research and Test Reactor (RERTR) Program, Argonne National Laboratory (ANL) is engaged in a fuel-alloy development project. The fuel alloys are dispersed in an aluminum matrix and metallurgically roll-bonded within 6061 Al alloy. To date, 'miniplates' with up to 40 vol. fuel alloy have been successfully fabricated. Thirty-one of these plates have been or are being irradiated in the Oak Ridge Reactor (ORR). Three different fuels have been used in the ANL miniplates: U 3 Si (U + 4 wt.% Si), U 3 Si 2 (U + 7.4 wt.% Si), or ''U 3 SiAl'' (U + 3.5 wt.% Si + 1.5 wt.% Al). All three are candidates for permitting higher fuel loadings and thus lower enrichments of 235 U than would be possible with either UAl x or U 3 O 8 , the current fuels for plate-type elements. The enrichment level employed at ANL is ∼19.8%. Continuing effort involves the production of miniplates with up to ∼60 vol. % fuel, the development of a technology for full-size plate fabrication, and post-irradiation examination of miniplates already removed from the ORR. (author)

Performance comparison of liquid metal and gas cooled ATW system point designs

International Nuclear Information System (INIS)

Yang, W.S.; Taiwo, T.A.; Hill, R.N.; Khalil, H.S.; Wade, D.C.

2001-01-01

As part of the Advanced Accelerator Application (AAA) program in the U.S., preliminary design studies have been performed at Argonne National Laboratory (ANL) and Los Alamos National Laboratory (LANL) to define and compare candidate Accelerator Transmutation of Waste (ATW) systems. The studies at ANL have focused primarily on the transmutation blanket component of the overall system. Lead-bismuth eutectic (LBE), sodium, and gas cooled systems are among the blanket technology options currently under consideration. This paper summarizes the results from neutronics trade studies performed at ANL. Core designs have been developed for LBE and sodium cooled 840 MWt fast spectrum accelerator driven systems employing re-cycle. Additionally, neutronics analyses have been performed for a helium-cooled 600 MWt hybrid thermal and fast spectrum system proposed by General Atomics (GA), which is operated in the critical mode for three cycles and in a subcritical accelerator driven mode for a subsequent single cycle. For these three point designs, isotopic inventories, consumption rates, and annual burnup rates are compared. The mass flows and the ultimate loss of transuranic (TRU) isotopes to the waste stream per unit of heat generated during transmutation are also compared on a consistent basis. (author)

Laboring Until Labor: The Prevalence and Correlates of Antenatal Maternity Leave in the United States.

Science.gov (United States)

Goodman, Julia M

2018-02-01

Introduction Most women in the U.S. are employed during pregnancy and work until the month of childbirth. For many, working throughout pregnancy poses little threat to their health; however, women experiencing difficult pregnancies and/or working in strenuous or inflexible jobs may benefit from taking time from work as they approach childbirth, but almost no empirical evidence examines antenatal leave (ANL). Methods Using a national survey of English-speaking women, this paper offers the first national description of ANL and examines state policy predictors of uptake. Results Thirty-seven percent of employed women worked until the week their baby was due. After controlling for characteristics of women and their jobs, living in a state with any or multiple leave laws increased the probability of ANL by 14 and 23% points, respectively. Women living in states with multiple leave laws stopped work almost 2 weeks earlier than women in states without a policy. Discussion Paid leave policies currently being considered at the federal, state, and local levels should consider the potential impact on antenatal leave, in addition to postnatal leave, and how they influence population health.

Validation and application of a physics database for fast reactor fuel cycle analysis

International Nuclear Information System (INIS)

McKnight, R.D.; Stillman, J.A.; Toppel, B.J.; Khalil, H.S.

1994-01-01

An effort has been made to automate the execution of fast reactor fuel cycle analysis, using EBR-II as a demonstration vehicle, and to validate the analysis results for application to the IFR closed fuel cycle demonstration at EBR-II and its fuel cycle facility. This effort has included: (1) the application of the standard ANL depletion codes to perform core-follow analyses for an extensive series of EBR-II runs, (2) incorporation of the EBR-II data into a physics database, (3) development and verification of software to update, maintain and verify the database files, (4) development and validation of fuel cycle models and methodology, (5) development and verification of software which utilizes this physics database to automate the application of the ANL depletion codes, methods and models to perform the core-follow analysis, and (6) validation studies of the ANL depletion codes and of their application in support of anticipated near-term operations in EBR-II and the Fuel Cycle Facility. Results of the validation tests indicate the physics database and associated analysis codes and procedures are adequate to predict required quantities in support of early phases of FCF operations

A state of the art on metallic fuel technology development

Energy Technology Data Exchange (ETDEWEB)

Hwang, Woan; Kang, Hee Young; Nam, Cheol; Kim, Jong Oh [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1997-12-31

Since worldwide interest turned toward ceramic fuels before the full potential of metallic fuel could be achieved in the late 1960`s, the development of metallic fuels continued throughout the 1970`s at ANL`s experimental breeder reactor II (EBR-II) because EBR-II continued to be fueled with the metallic uranium-fissium alloy, U-5Fs. During this decade the performance limitations of metallic fuel were satisfactorily resolved resolved at EBR-II. The concept of the IFR developed at ANL since 1984. The technical feasibility had been demonstrated and the technology database had been established to support its practicality. One key features of the IFR is that the fuel is metallic, which brings pronounced benefits over oxide in improved inherent safety and lower processing costs. At the outset of the 1980`s, it appeared that metallic fuels are recognized as a professed viable option with regard to safety, integral fuel cycle, waste minimization and deployment economics. This paper reviews the key advances in the last score and summarizes the state-of the art on metallic fuel technology development. (author). 29 refs., 1 tab.

Status of RF superconductivity at Argonne

Energy Technology Data Exchange (ETDEWEB)

Shepard, K.W.

1989-01-01

Development of a superconducting (SC) slow-wave structures began at Argonne National Laboratory (ANL) in 1971, and led to the first SC heavy-ion linac (ATLAS - the Argonne Tandem-Linac Accelerating System), which began regularly scheduled operation in 1978. To date, more than 40,000 hours of bean-on target operating time has been accumulated with ATLAS. The Physics Division at ANL has continued to develop SC RF technology for accelerating heavy-ions, with the result that the SC linac has, up to the present, has been in an almost continuous process of upgrade and expansion. It should be noted that this has been accomplished while at the same time maintaining a vigorous operating schedule in support of the nuclear and atomic physics research programs of the division. In 1987, the Engineering Physics Division at ANL began development of SC RF components for the acceleration of high-brightness proton and deuterium beams. This work has included the evaluation of RF properties of high-{Tc} oxide superconductors, both for the above and for other applications. The two divisions collaborated while they worked on several applications of RF SC, and also worked to develop the technology generally. 11 refs., 6 figs.

Methods and codes for neutronic calculations of the MARIA research reactor

International Nuclear Information System (INIS)

Andrzejewski, K.; Kulikowska, T.; Bretscher, M.M.; Hanan, N.A.; Matos, J.E.

1998-01-01

The core of the MARIA high flux multipurpose research reactor is highly heterogeneous. It consists of beryllium blocks arranged in 6x8 matrix, tubular fuel assemblies, control rods and irradiation channels. The reflector is also heterogeneous and consists of graphite blocks clad with aluminium. Its structure is perturbed by the experimental beam tubes. This paper presents methods and codes used to calculate the MARIA reactor neutronics characteristics and experience gained thus far at IAE and ANL. At ANL the methods of MARIA calculations were developed in connection with RERTR program. At IAE the package of programs was developed to help its operator in optimization of fuel utilization. (author)

Production of MO-99 from LEU targets-base-side processing

International Nuclear Information System (INIS)

Vandegrift, George F.; Koma, Yoshikazu; Cols, Hector; Conner, Cliff; Aase, Scott; Peter, Magdalin; Walker, David; Leonard, Ralph A.; Snelgrove, James L.

2000-01-01

Argonne National Laboratory (ANL) is cooperating with the Argentine Comision Nacional de Energia Atomica (CNEA) to convert their 99 Mo production process, which uses high enriched uranium (HEU), to low-enriched uranium (LEU). Progress discussed in this year's paper includes optimization of (1) the digestion of LEU foil by sodium hydroxide solution and (2) the primary recovery of molybdenum by anion exchange. Also discussed are ANL/CNEA plans for demonstrating the irradiation and digestion of LEU-foil targets and recovering 99 Mo in Argentina later this year. Our results show that, up to this point in our study, conversion of the CNEA process to LEU appears viable. (author)

Forundersøgelser til etablering af biogasanlæg i Bio-Energipark Tønder

DEFF Research Database (Denmark)

Holm-Nielsen, Jens Bo

. De sigter mod at belyse og afklare væsentlige forhold om biogasproduktionsanlægget vedrørende: (1) leverancegrundlag for husdyrgødning, biomasse m.v., (2) anlæggets opbygning og funktion, (3) afsætning af biogas og forarbejdet gødning/biomasse, (4) økonomiske forhold og organisatorisk ramme, (5...... informationssystem har skabt overblik over beliggenhed og størrelse af de potentielle leverandører af gylle til et kommende anlæg, og en række væsentlige forhold omkring transportafstand og alternative placeringsmuligheder er blevet belyst. Gennem interviews og dialog med områdets landmænd er det klarlagt...

Utility industry evaluation of the metal fuel facility and metal fuel performance for liquid metal reactors

International Nuclear Information System (INIS)

Burstein, S.; Gibbons, J.P.; High, M.D.; O'Boyle, D.R.; Pickens, T.A.; Pilmer, D.F.; Tomonto, J.R.; Weinberg, C.J.

1990-02-01

A team of utility industry representatives evaluated the liquid metal reactor metal fuel process and facility conceptual design being developed by Argonne National Laboratory (ANL) under Department of Energy sponsorship. The utility team concluded that a highly competent ANL team was making impressive progress in developing high performance advanced metal fuel and an economic processing and fabrication technology. The utility team concluded that the potential benefits of advanced metal fuel justified the development program, but that, at this early stage, there are considerable uncertainties in predicting the net overall economic benefit of metal fuel. Specific comments and recommendations are provided as a contribution towards enhancing the development program. 6 refs

Review process and quality assurance in the EBR-II probabilistic risk assessment

International Nuclear Information System (INIS)

Roglans, J.; Hill, D.J.; Ragland, W.A.

1992-01-01

A Probabilistic Risk Assessment (PRA) of the Experimental Breeder Reactor II (EBR-II), a Department of Energy (DOE) Category A reactor, has recently been completed at Argonne National Laboratory (ANL). Within the scope of the ANL QA Programs, a QA Plan specifically for the EBR-II PRA was developed. The QA Plan covered all aspects of the PRA development, with emphasis on the procedures for document and software control, and the internal and external review process. The effort spent in the quality assurance tasks for the EBR-II PRA has reciprocated by providing acceptance of the work and confidence in the quality of the results

Safety aspects of the US advanced LMR [liquid metal reactor] design

International Nuclear Information System (INIS)

Pedersen, D.R.; Gyorey, G.L.; Marchaterre, J.F.; Rosen, S.

1989-01-01

The cornerstones of the United States Advanced Liquid Metal Cooled Reactor (ALMR) program sponsored by the Department of Energy are: the plant design program at General Electric based on the PRISM (Power Reactor Innovative Small Module) concept, and the Integral Fast Reactor program (IFR) at Argonne National Laboratory (ANL). The goal of the US program is to produce a standard, commercial ALMR, including the associated fuel cycle. This paper discusses the US regulatory framework for design of an ALMR, safety aspects of the IFR program at ANL, the IFR fuel cycle and actinide recycle, and the ALMR plant design program at GE. 6 refs., 5 figs

Final report for the Light Water Breeder Reactor proof-of-breeding analytical support project

International Nuclear Information System (INIS)

Graczyk, D.G.; Hoh, J.C.; Martino, F.J.; Nelson, R.E.; Osudar, J.; Levitz, N.M.

1987-05-01

The technology of breeding 233 U from 232 Th in a light water reactor is being developed and evaluated by the Westinghouse Bettis Atomic Power Laboratory (BAPL) through operation and examination of the Shippingport Light Water Breeder Reactor (LWBR). Bettis is determining the end-of-life (EOL) inventory of fissile uranium in the LWBR core by nondestructive assay of a statistical sample comprising approximately 500 EOL fuel rods. This determination is being made with an irradiated-fuel assay gauge based on neutron interrogation and detection of delayed neutrons from each rod. The EOL fissile inventory will be compared with the beginning-of-life fissile loading of the LWBR to determine the extent of breeding. In support of the BAPL proof-of-breeding (POB) effort, Argonne National Laboratory (ANL) carried out destructive physical, chemical, and radiometric analyses on 17 EOL LWBR fuel rods that were previously assayed with the nondestructive gauge. The ANL work included measurements on the intact rods; shearing of the rods into pre-designated contiguous segments; separate dissolution of each of the more than 150 segments; and analysis of the dissolver solutions to determine each segment's uranium content, uranium isotopic composition, and loading of selected fission products. This report describes the facilities in which this work was carried out, details operations involved in processing each rod, and presents a comprehensive discussion of uncertainties associated with each result of the ANL measurements. Most operations were carried out remotely in shielded cells. Automated equipment and procedures, controlled by a computer system, provided error-free data acquisition and processing, as well as full replication of operations with each rod. Despite difficulties that arose during processing of a few rod segments, the ANL destructive-assay results satisfied the demanding needs of the parent LWBR-POB program

Final report for the Light Water Breeder Reactor proof-of-breeding analytical support project

Energy Technology Data Exchange (ETDEWEB)

Graczyk, D.G.; Hoh, J.C.; Martino, F.J.; Nelson, R.E.; Osudar, J.; Levitz, N.M.

1987-05-01

The technology of breeding /sup 233/U from /sup 232/Th in a light water reactor is being developed and evaluated by the Westinghouse Bettis Atomic Power Laboratory (BAPL) through operation and examination of the Shippingport Light Water Breeder Reactor (LWBR). Bettis is determining the end-of-life (EOL) inventory of fissile uranium in the LWBR core by nondestructive assay of a statistical sample comprising approximately 500 EOL fuel rods. This determination is being made with an irradiated-fuel assay gauge based on neutron interrogation and detection of delayed neutrons from each rod. The EOL fissile inventory will be compared with the beginning-of-life fissile loading of the LWBR to determine the extent of breeding. In support of the BAPL proof-of-breeding (POB) effort, Argonne National Laboratory (ANL) carried out destructive physical, chemical, and radiometric analyses on 17 EOL LWBR fuel rods that were previously assayed with the nondestructive gauge. The ANL work included measurements on the intact rods; shearing of the rods into pre-designated contiguous segments; separate dissolution of each of the more than 150 segments; and analysis of the dissolver solutions to determine each segment's uranium content, uranium isotopic composition, and loading of selected fission products. This report describes the facilities in which this work was carried out, details operations involved in processing each rod, and presents a comprehensive discussion of uncertainties associated with each result of the ANL measurements. Most operations were carried out remotely in shielded cells. Automated equipment and procedures, controlled by a computer system, provided error-free data acquisition and processing, as well as full replication of operations with each rod. Despite difficulties that arose during processing of a few rod segments, the ANL destructive-assay results satisfied the demanding needs of the parent LWBR-POB program.

Minutes of the 2. Meeting of the WPRS / EGRPANS / Sodium Fast Reactor Task Force (SFR)

International Nuclear Information System (INIS)

Ivanov, Evgeny; Kereszturi, Andras; Pataki, I.; Tota, A.; Vertes, P.; Kim, Taek K.; Taiwo, T.A.; Kugo, Teruhiko; Lee, Yi Kang; Messaoudi, Nadia; Michel-Sendis, Franco; ); Pascal, Vincent; Buiron, Laurent; Varaine, Frederic; Ponomarev, Alexander

2012-01-01

Five organizations (SCK/CEN, KIT, KFKI, CEA, ANL) participated in the Sodium-cooled fast reactor (SFR) Benchmark calculations and all results were collected and compiled by CEA and ANL. The compiled results of the large size cores and medium size cores were presented by V. Pascal (CEA) and T. K. Kim (ANL), respectively. Separately, A. Kereszturi presented his recently updated results. It was observed that there is wide variation in core multiplication factor, kinetics parameters, and reactivity feedback coefficients. In particular, compared to the CEA results, ANL calculated smaller k-eff, Doppler constant, but higher sodium void worth and control rod worth. The core modeling issue (heterogeneous vs. homogeneous) and solution method (diffusion vs. transport) were identified as the potential reasons of these discrepancies, including the minor impacts from the depletion chains and lumped fission product modeling. All participants agreed that additional investigation was needed to identify the reasons of these discrepancies. In addition, V. Pascal presented the informative notes of the reactivity feedback calculations methodology proposed by CEA. This document brings together the 5 presentations (slides) given at this meeting: 1 - SFR Task Force : Core behavior during transient as a function of power size and fuel nature (L. Buiron, V. Pascal, F. Varaine); 2 - Sodium Fast Reactor core Feedback and Transient response (SFRFT) Expert Group: preliminary benchmark results for large cores (L. Buiron, V. Pascal, F. Varaine); 3 - Numerical Benchmark Results for 1000 MWth Sodium-cooled Fast Reactor (T.K. Kim and T.A. Taiwo); 4 - Preliminary results of the WPRS Sodium-Cooled Fast Reactor Benchmark problems (A. Kereszturi, I. Pataki, A. Tota, P. Vertes); 5 - SFR Task Force : proposal for Feedback coefficients estimation methodology (L. Buiron, V.Pascal, F. Varaine)

Refurbishment of an Analytical Laboratory Hot Cell Facility

International Nuclear Information System (INIS)

Rosenberg, K.; Henslee, S.P.; Michelbacher, J.A.; Coleman, R.M.

1997-01-01

An Analytical Laboratory Hot Cell (ALHC) Facility at Argonne National Laboratory-West (ANL-W) was in service for nearly thirty years. In order to comply with DOE regulations governing such facilities and meet ANL-W programmatic requirements, a major refurbishment effort was undertaken. All penetrations within the facility were sealed; the ventilation system was redesigned, upgraded and replaced; the manipulators were replaced; the hot cell windows were removed, refurbished, and reinstalled; all hot cell utilities were replaced; a lead-shielded glovebox housing an Inductively Coupled Plasma - Atomic Emission Spectrometer (ICP-AES) System was interfaced with the hot cells, and a new CO2 fire suppression system and other ALHC support equipment were installed

Argonne National Laboratory patent portfolio

International Nuclear Information System (INIS)

Huguelet, B.C.

1976-01-01

This booklet contains the abstracts of all active U. S. patents on technology items that originated at ANL, the applicability of which is not limited to nuclear reactors. Also listed are the titles of all ANL-originated nuclear-related U. S. patents that are still in force. Selected technology items for which patent applications have been filed and are available for licensing are included in several categories. Categories included in this booklet are as follows: atmospheric and earth sciences; biological and medical sciences; chemistry and chemical engineering; cryogenics and superconductivity; electronics and electrical engineering; energy conversion; measurements and controls; methods and devices; materials and fabrication; physics, accelerators and fusion; and selected nuclear-related technology

Thermal hydraulic considerations in liquid-metal-cooled components of tokamak fusion reactors

International Nuclear Information System (INIS)

Picologlou, B.F.; Reed, C.B.; Hua, T.Q.

1989-01-01

The basic considerations of MHD thermal hydraulics for liquid-metal-cooled blankets and first walls of tokamak fusion reactors are discussed. The liquid-metal MHD program of Argonne National Laboratory (ANL) dedicated to analytical and experimental investigations of reactor relevant MHD flows and development of relevant thermal hydraulic design tools is presented. The status of the experimental program and examples of local velocity measurements are given. An account of the MHD codes developed to date at ANL is also presented as is an example of a 3-D thermal hydraulic analysis carried out with such codes. Finally, near term plans for experimental investigations and code development are outlined. 20 refs., 8 figs., 1 tab

Supplemental site inspection for Air Force Plant 59, Johnson City, New York, Volume 3: Appendices F-Q

Energy Technology Data Exchange (ETDEWEB)

Nashold, B.; Rosenblatt, D.; Hau, J. [and others

1995-08-01

This summary describes a Supplemental Site Inspection (SSI) conducted by Argonne National Laboratory (ANL) at Air Force Plant 59 (AFP 59) in Johnson City, New York. All required data pertaining to this project were entered by ANL into the Air Force-wide Installation Restoration Program Information System (IRPIMS) computer format and submitted to an appropriate authority. The work was sponsored by the United States Air Force as part of its Installation Restoration Program (IRP). Previous studies had revealed the presence of contaminants at the site and identified several potential contaminant sources. Argonne`s study was conducted to answer questions raised by earlier investigations. This volume consists of appendices F-Q, which contain the analytical data from the site characterization.

Pilot-scale equipment development for lithium-based reduction of spent oxide fuel

International Nuclear Information System (INIS)

Herrmann, S. D.

1998-01-01

An integral function of the electrometallurgical conditioning of DOE spent nuclear fuel is the standardization of waste forms. Argonne National Laboratory (ANL) has developed and is presently demonstrating the electrometallurgical conditioning of sodium-bonded metal fuel from Experimental Breeder Reactor II, resulting in uranium, ceramic waste, and metal waste forms. Engineering studies are underway at ANL in support of pilot-scale equipment development, which would precondition irradiated oxide fuel and likewise demonstrate the application of electrometallurgical conditioning to such non-metallic fuels. This paper highlights the integration of proposed spent oxide fuel conditioning with existing electrometallurgical processes. Additionally, technical bases for engineering activities to support a scale up of an oxide reduction process are described

Romerske veje i Syditalien

DEFF Research Database (Denmark)

Bekker-Nielsen, Tønnes

2018-01-01

I andet århundrede e.Kr. lod kejser Trajan en ny, 300 kilometer lang hovedvej anlægge til aflastning af en eksisterende vej gennem Syditalien. Ved at sammenligne de to vejanlæg får man et enestående indblik i den romerske ingeniørkunsts udvikling over en periode på 400 år.......I andet århundrede e.Kr. lod kejser Trajan en ny, 300 kilometer lang hovedvej anlægge til aflastning af en eksisterende vej gennem Syditalien. Ved at sammenligne de to vejanlæg får man et enestående indblik i den romerske ingeniørkunsts udvikling over en periode på 400 år....

Analytical Chemistry Laboratory: Progress report for FY 1988

International Nuclear Information System (INIS)

Green, D.W.; Heinrich, R.R.; Graczyk, D.G.; Lindahl, P.C.; Erickson, M.D.

1988-12-01

The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for fiscal year 1988 (October 1987 through September 1988). The Analytical Chemistry Laboratory is a full-cost recovery service center, with the primary mission of providing a broad range of analytical chemistry support services to the scientific and engineering programs at ANL. In addition, the ACL conducts a research program in analytical chemistry, works on instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL handles a wide range of analytical problems, from routine standard analyses to unique problems that require significant development of methods and techniques

Analytical Chemistry Laboratory progress report for FY 1989

International Nuclear Information System (INIS)

Green, D.W.; Heinrich, R.R.; Graczyk, D.G.; Lindahl, P.C.; Erickson, M.D.

1989-12-01

The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year 1989 (October 1988 through September 1989). The Analytical Chemistry Laboratory is a full-cost-recovery service center, with the primary mission of providing a broad range of analytical chemistry support services to the scientific and engineering programs at ANL. In addition, the ACL conducts a research program in analytical chemistry, works on instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL handles a wide range of analytical problems, from routine standard analyses to unique problems that require significant development of methods and techniques

Analytical Chemistry Laboratory: Progress report for FY 1988

Energy Technology Data Exchange (ETDEWEB)

Green, D.W.; Heinrich, R.R.; Graczyk, D.G.; Lindahl, P.C.; Erickson, M.D.

1988-12-01

The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for fiscal year 1988 (October 1987 through September 1988). The Analytical Chemistry Laboratory is a full-cost recovery service center, with the primary mission of providing a broad range of analytical chemistry support services to the scientific and engineering programs at ANL. In addition, the ACL conducts a research program in analytical chemistry, works on instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL handles a wide range of analytical problems, from routine standard analyses to unique problems that require significant development of methods and techniques.

Status of RF superconductivity at Argonne

International Nuclear Information System (INIS)

Shepard, K.W.

1989-01-01

Development of a superconducting (SC) slow-wave structures began at Argonne National Laboratory (ANL) in 1971, and led to the first SC heavy-ion linac (ATLAS - the Argonne Tandem-Linac Accelerating System), which began regularly scheduled operation in 1978. To date, more than 40,000 hours of bean-on target operating time has been accumulated with ATLAS. The Physics Division at ANL has continued to develop SC RF technology for accelerating heavy-ions, with the result that the SC linac has, up to the present, has been in an almost continuous process of upgrade and expansion. It should be noted that this has been accomplished while at the same time maintaining a vigorous operating schedule in support of the nuclear and atomic physics research programs of the division. In 1987, the Engineering Physics Division at ANL began development of SC RF components for the acceleration of high-brightness proton and deuterium beams. This work has included the evaluation of RF properties of high-T c oxide superconductors, both for the above and for other applications. The two divisions collaborated while they worked on several applications of RF SC, and also worked to develop the technology generally. 11 refs., 6 figs

Environmental Survey preliminary report, Argonne National Laboratory, Argonne, Illinois

International Nuclear Information System (INIS)

1988-11-01

This report presents the preliminary findings of the first phase of the Environmental Survey of the United States Department of Energy's (DOE) Argonne National Laboratory (ANL), conducted June 15 through 26, 1987. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. The team includes outside experts supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with ANL. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at ANL, and interviews with site personnel. The Survey team developed a Sampling and Analysis (S ampersand A) Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The S ampersand A Plan will be executed by the Oak Ridge National Laboratory (ORNL). When completed, the S ampersand A results will be incorporated into the Argonne National Laboratory Environmental Survey findings for inclusion in the Environmental Survey Summary Report. 75 refs., 24 figs., 60 tabs

Applications of synchrotron radiation to Chemical Engineering Science: Workshop report

International Nuclear Information System (INIS)

1991-07-01

This report contains extended abstracts that summarize presentations made at the Workshop on Applications of Synchrotron Radiation to Chemical Engineering Science held at Argonne National Laboratory (ANL), Argonne, IL, on April 22--23, 1991. The talks emphasized the application of techniques involving absorption fluorescence, diffraction, and reflection of synchrotron x-rays, with a focus on problems in applied chemistry and chemical engineering, as well as on the use of x-rays in topographic, tomographic, and lithographic procedures. The attendees at the workshop included experts in the field of synchrotron science, scientists and engineers from ANL, other national laboratories, industry, and universities; and graduate and undergraduate students who were enrolled in ANL educational programs at the time of the workshop. Talks in the Plenary and Overview Session described the status of and special capabilities to be offered by the Advanced Photon Source (APS), as well as strategies and opportunities for utilization of synchrotron radiation to solve science and engineering problems. Invited talks given in subsequent sessions covered the use of intense infrared, ultraviolet, and x-ray photon beams (as provided by synchrotrons) in traditional and nontraditional areas of chemical engineering research related to electrochemical and corrosion science, catalyst development and characterization, lithography and imaging techniques, and microanalysis

Technical evaluation of available state of Nevada survey instruments

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-02-01

Argonne National Laboratory (ANL) is reviewing the survey research studies completed by Mountain West Research (1987-1989) for the state of Nevada`s Nuclear Waste Project Office. In this research, 14 survey instruments were used to seek data on whether perceptions of risk could be associated with the possible siting of a high-level radioactive waste repository in Nevada and could be a dominant source of potential, significant, adverse economic impacts. This report presents results from phase 1 of the review, in which ANL contracted with the National Opinion Research Center (NORC) at the University of Chicago to evaluate the technical merits of the nine survey instruments that ANL had been able to acquire. The scope of NORC`s work was limited to rating the questions and stating their strengths and weaknesses. NORC concluded that the surveys could provide valuable data about risk perceptions and potential behavioral responses. NORC identified a few minor problems with a number of questions and the calculated response rates but claimed these problems would probably not have any major biasing effect. The NORC evaluation would have been more complete if the terms used in the questionnaires had been defined, all survey instruments had been acquired, and all data had been made available to the public.

Technical evaluation of available state of Nevada survey instruments

International Nuclear Information System (INIS)

1993-02-01

Argonne National Laboratory (ANL) is reviewing the survey research studies completed by Mountain West Research (1987-1989) for the state of Nevada's Nuclear Waste Project Office. In this research, 14 survey instruments were used to seek data on whether perceptions of risk could be associated with the possible siting of a high-level radioactive waste repository in Nevada and could be a dominant source of potential, significant, adverse economic impacts. This report presents results from phase 1 of the review, in which ANL contracted with the National Opinion Research Center (NORC) at the University of Chicago to evaluate the technical merits of the nine survey instruments that ANL had been able to acquire. The scope of NORC's work was limited to rating the questions and stating their strengths and weaknesses. NORC concluded that the surveys could provide valuable data about risk perceptions and potential behavioral responses. NORC identified a few minor problems with a number of questions and the calculated response rates but claimed these problems would probably not have any major biasing effect. The NORC evaluation would have been more complete if the terms used in the questionnaires had been defined, all survey instruments had been acquired, and all data had been made available to the public

Environmental Survey preliminary report, Argonne National Laboratory, Argonne, Illinois

Energy Technology Data Exchange (ETDEWEB)

1988-11-01

This report presents the preliminary findings of the first phase of the Environmental Survey of the United States Department of Energy's (DOE) Argonne National Laboratory (ANL), conducted June 15 through 26, 1987. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. The team includes outside experts supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with ANL. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at ANL, and interviews with site personnel. The Survey team developed a Sampling and Analysis (S A) Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The S A Plan will be executed by the Oak Ridge National Laboratory (ORNL). When completed, the S A results will be incorporated into the Argonne National Laboratory Environmental Survey findings for inclusion in the Environmental Survey Summary Report. 75 refs., 24 figs., 60 tabs.

The determination of PCBs in Rocky Flats Type IV waste sludge by gas chromatography/electron capture detection. Part 2

International Nuclear Information System (INIS)

Parish, K.J.; Applegate, D.V.; Postlethwait, P.D.; Boparai, A.S.; Reedy, G.T.

1994-12-01

Before disposal, radioactive sludge (Type IV) from Rocky Flats Plant (RFP) must be evaluated for polychlorinated biphenyl (PCB) content. The Type IV sludge consists of organic solvents, degreasers, cutting oils, and transuranic (TRU) waste mixed with calcium silicate (MicroCel E reg-sign and Oil Dri reg-sign to form a grease or paste-like material. For laboratory testing, a nonradioactive simulated Type 17V RFP sludge was prepared at Argonne National Laboratory-East (ANL-E). This sludge has a composition similar to that expected from field samples. In an earlier effort, a simplified method was developed for extraction, cleanup of extract, and determination of PCBs in samples of simulated sludge spiked with Aroclors 1254 and 1260. The simplified method has now been used to determine the presence and quantities of other Aroclors in the simulated sludge, namely, Aroclors 10 1 6, 1221, 1232, 1242, and 1248. The accuracy and precision of the data for these Aroclors were found to be similar to the data for sludges spiked with Aroclors 1254 and 1260. Since actual sludges may vary in composition, the method was also verified by analyzing another source of Type IV simulated sludge, prepared by Argonne National Laboratory-West (ANL-W)

High-performance batteries for electric-vehicle propulsion and stationary energy storage. Progress report, October 1977--September 1978

Energy Technology Data Exchange (ETDEWEB)

Nelson, P.A.; Barney, D.L.; Steunenberg, R.K.

1978-11-01

The research, development, and management activities of the programs at Argonne National Laboratory (ANL) and at industrial subcontractors' laboratories on high-temperature batteries during the period October 1977--September 1978 are reported. These batteries are being developed for electric-vehicle propulsion and for stationary-energy-storage applications. The present cells, which operate at 400 to 500/sup 0/C, are of a vertically oriented, prismatic design with one or more inner positive electrodes of FeS or FeS/sub 2/, facing electrodes of lithium--aluminum alloy, and molten LiCl--KCl electrolyte. During this fiscal year, cell and battery development work continued at ANL, Eagle--Picher Industries, Inc., the Energy Systems Group of Rockwell International, and Gould Inc. Related work was also in progress at the Carborundum Co., General Motors Research Laboratories, and various other organizations. A major event was the initiation of a subcontract with Eagle--Picher Industries to develop, design, and fabricate a 40-kWh battery (Mark IA) for testing in an electric van. Conceptual design studies on a 100-MWh stationary-energy-storage module were conducted as a joint effort between ANL and Rockwell International. A significant technical advance was the development of multiplate cells, which are capable of higher performance than bicells. 89 figures, 57 tables.

Applications of synchrotron radiation to Chemical Engineering Science: Workshop report

Energy Technology Data Exchange (ETDEWEB)

1991-07-01

This report contains extended abstracts that summarize presentations made at the Workshop on Applications of Synchrotron Radiation to Chemical Engineering Science held at Argonne National Laboratory (ANL), Argonne, IL, on April 22--23, 1991. The talks emphasized the application of techniques involving absorption fluorescence, diffraction, and reflection of synchrotron x-rays, with a focus on problems in applied chemistry and chemical engineering, as well as on the use of x-rays in topographic, tomographic, and lithographic procedures. The attendees at the workshop included experts in the field of synchrotron science, scientists and engineers from ANL, other national laboratories, industry, and universities; and graduate and undergraduate students who were enrolled in ANL educational programs at the time of the workshop. Talks in the Plenary and Overview Session described the status of and special capabilities to be offered by the Advanced Photon Source (APS), as well as strategies and opportunities for utilization of synchrotron radiation to solve science and engineering problems. Invited talks given in subsequent sessions covered the use of intense infrared, ultraviolet, and x-ray photon beams (as provided by synchrotrons) in traditional and nontraditional areas of chemical engineering research related to electrochemical and corrosion science, catalyst development and characterization, lithography and imaging techniques, and microanalysis.

ANL--LASL workshop on advanced neutron detection systems

International Nuclear Information System (INIS)

Kitchens, T.A.

1979-06-01

A two-day workshop on advanced neutron detectors and associated electronics was held in Los Alamos on April 5--6, 1979, as a part of the Argonne National Laboratory--Los Alamos Scientific Laboratory Coordination on neutron scattering instrumentation. This report contains an account of the information presented and conclusions drawn at the workshop

Differences between LASL- and ANL-processed cross sections

International Nuclear Information System (INIS)

Kidman, R.B.; MacFarlane, R.E.; Becker, M.

1978-03-01

As part of the Los Alamos Scientific Laboratory (LASL) cross-section processing development, LASL cross sections and results from MINX/1DX system are compared to the Argonne National Laboratory cross sections and results from the ETOE-2/MC 2 -2 system for a simple reactor problem. Exact perturbation theory is used to establish the eigenvalue effect of every isotope group cross-section difference. Cross sections, cross-section differences, and their eigenvalue effects are clearly and conveniently displayed and compared on a group-by-group basis

ANL pre analysis of the SHEBA/CERES experiments

International Nuclear Information System (INIS)

Palmiotti, G.; Smith, M.; Klann, R.; Fujita, E.; Imel, G.

2000-01-01

The French and British nuclear programs have prepared a series of natural uranium oxide fuel samples spiked with small amounts of the individual fission products which makeup a large fraction of the total neutron absorption by fission products in spent nuclear fuel. Both programs have utilized these samples in experimental reactors and have inferred the worth of the individual fission products. These results have been used to validate the cross sections used in criticality safety calculations. These measurements constitute a major element in support of spent fuel burnup credit in these countries

Superconducting magnet systems for the ANL EPR design

International Nuclear Information System (INIS)

Turner, L.R.; Wang, S.T.; Kim, S.H.; Huang, Y.C.; Smith, R.P.

1978-01-01

The magnet systems for the current Argonne experimental power reactor (EPR) design build on the earlier designs but incorporate a number of improvements. The toroidal field (TF) coil system consists of 16 coils of the constant tension shape, with NbTi, copper, and stainless steel as superconductor, stabilizer, and support material respectively. They are designed for 10 T operation at 3.7 K or 9 T operation at 4.2 K. Two changes from earlier designs permit a saving in material requirements. The coils are wound with the conductor in precompression and the support material in pretension so that when the coils are energized, the stainless steel experiences a stress of 60,000 psi while the copper stress does not exceed 15,000 psi. Both the copper and NbTi are graded, with higher current densities where magnetic and radiation effects are smaller. The ohmic heating (OH) coil system consists of a central solenoid plus ten other coils, all located outside the TF coils for ease of maintenance. The NbTi-copper coils are cryostable and operate at 4.2 K. The solenoid is segmented, with rings of insulation between segments to transfer the centering force from the TF coils to an insulating cylinder inside the OH solenoid. Locating the OH solenoid inside the support cylinder plus raising the central field to 8 T, enables the OH system to develop more volt-seconds than the earlier designs, even though the plasma major radius is smaller. The superconducting equilibrium field coils, also outside the TF coils, provide the field pattern required for a D-shaped plasma

ANL four-meter calorimeter design and operation manual

International Nuclear Information System (INIS)

Perry, R.B.; Lewis, R.N.; Youngdahl, G.A.; Jung, E.A.; Roche, C.T.

1980-02-01

The four-meter fuel rod calorimetric system measures the thermal power produced by radioactive decay of fuel rods containing Pu. The Pu mass is related to the measured power through the weighted average of the product of the isotopic decay energies and the decay constants of the Pu isotopes present. U content has no effect since the thermal power produced by the U nuclides is insignificant when compared to Pu. Radiations from Pu are alpha particles and low-energy photons. This calorimeter will measure samples producing power up to 1.5 watts at a rate of one sample every 120 min. The instrument consists of a data-acquisition module made up of a microprocessor, with an 8K-byte nonvolatile memory, a control cabinet and the calorimeter chamber

ANL small-sample calorimeter system design and operation

International Nuclear Information System (INIS)

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

1978-07-01

The Small-Sample Calorimetric System is a portable instrument designed to measure the thermal power produced by radioactive decay of plutonium-containing fuels. The small-sample calorimeter is capable of measuring samples producing power up to 32 milliwatts at a rate of one sample every 20 min. The instrument is contained in two packages: a data-acquisition module consisting of a microprocessor with an 8K-byte nonvolatile memory, and a measurement module consisting of the calorimeter and a sample preheater. The total weight of the system is 18 kg

Automated reasoning applications to design validation and sneak function analysis

International Nuclear Information System (INIS)

Stratton, R.C.

1984-01-01

Argonne National Laboratory (ANL) is actively involved in the LMFBR Man-Machine Integration (MMI) Safety Program. The objective of this program is to enhance the operational safety and reliability of fast-breeder reactors by optimum integration of men and machines through the application of human factors principles and control engineering to the design, operation, and the control environment. ANL is developing methods to apply automated reasoning and computerization in the validation and sneak function analysis process. This project provides the element definitions and relations necessary for an automated reasoner (AR) to reason about design validation and sneak function analysis. This project also provides a demonstration of this AR application on an Experimental Breeder Reactor-II (EBR-II) system, the Argonne Cooling System

Analytical Chemistry Laboratory progress report for FY 1991

Energy Technology Data Exchange (ETDEWEB)

Green, D.W.; Heinrich, R.R.; Graczyk, D.G.; Lindahl, P.C.; Boparai, A.S.

1991-12-01

The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year 1991 (October 1990 through September 1991). This is the eighth annual report for the ACL. The Analytical Chemistry Laboratory is a full-cost-recovery service center, with the primary mission of providing a broad range of analytical chemistry support services to the scientific and engineering programs at ANL. In addition, the ACL conducts a research program in analytical chemistry, works on instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL handles a wide range of analytical problems, from routine standard analyses to unique problems that require significant development of methods and techniques.

Innovative environmental restoration and waste management technologies at Argonne National Laboratory

International Nuclear Information System (INIS)

Helt, J.E.

1993-01-01

Cleanup of contaminated sites and management of wastes have become major efforts of the US Department of Energy. Argonne National Laboratory (ANL) is developing several new technologies to meet the needs of this national effort. Some of these efforts are being done in collaboration with private sector firms. An overview of the ANL and private sector efforts will be presented. The following four specific technologies will be discussed in detail: (1) a minimum additive waste stabilization (MAWS) system for treating actinide-contaminated soil and groundwater; (2) a magnetic separation system, also for cleanup of actinide-contaminated soil and groundwater; (3) a mobile evaporator/concentrator system for processing aqueous radioactive and mixed waste; and (4) a continuous emission monitor for ensuring that waste incineration meets environmental goals

An in-house alternative to traditional SDI services at Argonne National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Noel, R.E.; Dominiak, R.R.

1997-02-20

Selective Dissemination of Information (SDIs) are based on automated, well-defined programs that regularly produce precise, relevant bibliographic information. Librarians have typically turned to information vendors such as Dialog or STN international to design and implement these searches for their users in business, academia, and the science community. Because Argonne National Laboratory (ANL) purchases the Institute for Scientific Information (ISI) Current Contents tapes (all subject areas excluding Humanities). ANL scientists enjoy the benefit of in-house developments with BASISplus software programming and no longer need to turn to outside companies for reliable SDI service. The database and its customized services are known as ACCESS (Argonne Current Contents Electronic Search Service). Through collaboration with librarians on Boolean logic and selection of terms, users can now design their own personal profiles to comb the new data, thereby avoiding service fees from outside providers. Based on the feedback from scientists, it seems that this new service can help transform the ANL distributed libraries into more efficient central functioning entities that better serve the users. One goal is to eliminate the routing of paper copies of many new journal issues to different library locations for users to browse; instead users may be expected to rely more on electronic dissemination of both table of contents and customized SDIs for new scientific and technical information.

The PAMTRAK system and its operational issues

International Nuclear Information System (INIS)

Dahly, B.; Walters, G.

1995-01-01

A system has been developed by Sandia National Laboratories (SNL) as part of the joint laboratory project with Los Alamos National Laboratory and Argonne National Laboratory-West (ANL-W). The objective is to provide support for Safeguards and Security and Nuclear Materials Control and Accountability within the DOE complex. Since its original design PAMTRAK has been enhanced to include material monitoring, personnel monitoring, and video surveillance. Material monitoring is provided by the WATCH (Wireless Alarm Transmission of Container Handling) subsystem by performing continuous surveillance via constantly monitored Tamper Indicating Devices of all material not directly involved in the fuel manufacturing process. Personnel tracking uses radio frequency and infrared sensors to detect unauthorized access to restricted areas and to enforce constant monitoring of containers or other objects within a ''region of interest'' in a storage vault or other restricted area. Advantages of combining these sensor subsystems include reducing personnel radiation exposure by extending the time between required physical inventory intervals as well as adding robustness to existing security measures. PAMTRAK is being demonstrated as part of the integrated materials monitoring and accounting system in the Fuels and Manufacturing Facility (FMF) located at ANL-W. This paper will describe the technologies employed for installation of the system by SNL, as well as the operational issues involved in using the system at ANL-W

Programming Post-Translational Control over the Metabolic Labeling of Cellular Proteins with a Noncanonical Amino Acid.

Science.gov (United States)

Thomas, Emily E; Pandey, Naresh; Knudsen, Sarah; Ball, Zachary T; Silberg, Jonathan J

2017-08-18

Transcriptional control can be used to program cells to label proteins with noncanonical amino acids by regulating the expression of orthogonal aminoacyl tRNA synthetases (aaRSs). However, we cannot yet program cells to control labeling in response to aaRS and ligand binding. To identify aaRSs whose activities can be regulated by interactions with ligands, we used a combinatorial approach to discover fragmented variants of Escherichia coli methionyl tRNA synthetase (MetRS) that require fusion to associating proteins for maximal activity. We found that these split proteins could be leveraged to create ligand-dependent MetRS using two approaches. When a pair of MetRS fragments was fused to FKBP12 and the FKBP-rapamycin binding domain (FRB) of mTOR and mutations were introduced that direct substrate specificity toward azidonorleucine (Anl), Anl metabolic labeling was significantly enhanced in growth medium containing rapamycin, which stabilizes the FKBP12-FRB complex. In addition, fusion of MetRS fragments to the termini of the ligand-binding domain of the estrogen receptor yielded proteins whose Anl metabolic labeling was significantly enhanced when 4-hydroxytamoxifen (4-HT) was added to the growth medium. These findings suggest that split MetRS can be fused to a range of ligand-binding proteins to create aaRSs whose metabolic labeling activities depend upon post-translational interactions with ligands.

76 FR 336 - Notice of NEPA Public Scoping Meeting Information for the Great Lakes and Mississippi River...

Science.gov (United States)

2011-01-04

... site: Use the Web comment function found at http://www.glmris.anl.gov ; NEPA Scoping Meeting: USACE is... Street, Ypsilanti, MI. 8. Tuesday, February 8, 2011: National Great Rivers Museum (Adjacent to Melvin...

Screening of Gas-Cooled Reactor Thermal-Hydraulic and Safety Analysis Tools and Experimental Database

International Nuclear Information System (INIS)

Lee, Won Jae; Kim, Min Hwan; Lee, Seung Wook

2007-08-01

This report is a final report of I-NERI Project, 'Screening of Gas-cooled Reactor Thermal Hydraulic and Safety Analysis Tools and Experimental Database 'jointly carried out by KAERI, ANL and INL. In this study, we developed the basic technologies required to develop and validate the VHTR TH/safety analysis tools and evaluated the TH/safety database information. The research tasks consist of; 1) code qualification methodology (INL), 2) high-level PIRTs for major nucleus set of events (KAERI, ANL, INL), 3) initial scaling and scoping analysis (ANL, KAERI, INL), 4) filtering of TH/safety tools (KAERI, INL), 5) evaluation of TH/safety database information (KAERI, INL, ANL) and 6) key scoping analysis (KAERI). The code qualification methodology identifies the role of PIRTs in the R and D process and the bottom-up and top-down code validation methods. Since the design of VHTR is still evolving, we generated the high-level PIRTs referencing 600MWth block-type GT-MHR and 400MWth pebble-type PBMR. Nucleus set of events that represents the VHTR safety and operational transients consists of the enveloping scenarios of HPCC (high pressure conduction cooling: loss of primary flow), LPCC/Air-Ingress (low pressure conduction cooling: loss of coolant), LC (load changes: power maneuvering), ATWS (anticipated transients without scram: reactivity insertion), WS (water ingress: water-interfacing system break) and HU (hydrogen-side upset: loss of heat sink). The initial scaling analysis defines dimensionless parameters that need to be reflected in mixed convection modeling and the initial scoping analysis provided the reference system transients used in the PIRTs generation. For the PIRTs phenomena, we evaluated the modeling capability of the candidate TH/safety tools and derived a model improvement need. By surveying and evaluating the TH/safety database information, a tools V and V matrix has been developed. Through the key scoping analysis using available database, the modeling

Screening of Gas-Cooled Reactor Thermal-Hydraulic and Safety Analysis Tools and Experimental Database

Energy Technology Data Exchange (ETDEWEB)

Lee, Won Jae; Kim, Min Hwan; Lee, Seung Wook (and others)

2007-08-15

This report is a final report of I-NERI Project, 'Screening of Gas-cooled Reactor Thermal Hydraulic and Safety Analysis Tools and Experimental Database 'jointly carried out by KAERI, ANL and INL. In this study, we developed the basic technologies required to develop and validate the VHTR TH/safety analysis tools and evaluated the TH/safety database information. The research tasks consist of; 1) code qualification methodology (INL), 2) high-level PIRTs for major nucleus set of events (KAERI, ANL, INL), 3) initial scaling and scoping analysis (ANL, KAERI, INL), 4) filtering of TH/safety tools (KAERI, INL), 5) evaluation of TH/safety database information (KAERI, INL, ANL) and 6) key scoping analysis (KAERI). The code qualification methodology identifies the role of PIRTs in the R and D process and the bottom-up and top-down code validation methods. Since the design of VHTR is still evolving, we generated the high-level PIRTs referencing 600MWth block-type GT-MHR and 400MWth pebble-type PBMR. Nucleus set of events that represents the VHTR safety and operational transients consists of the enveloping scenarios of HPCC (high pressure conduction cooling: loss of primary flow), LPCC/Air-Ingress (low pressure conduction cooling: loss of coolant), LC (load changes: power maneuvering), ATWS (anticipated transients without scram: reactivity insertion), WS (water ingress: water-interfacing system break) and HU (hydrogen-side upset: loss of heat sink). The initial scaling analysis defines dimensionless parameters that need to be reflected in mixed convection modeling and the initial scoping analysis provided the reference system transients used in the PIRTs generation. For the PIRTs phenomena, we evaluated the modeling capability of the candidate TH/safety tools and derived a model improvement need. By surveying and evaluating the TH/safety database information, a tools V and V matrix has been developed. Through the key scoping analysis using available database, the

Finite-element treatment of concrete cracking and thermal structural analysis

International Nuclear Information System (INIS)

Marchertas, A.H.

1981-01-01

The objective of this presentation is to describe the work on analytical modeling of concrete behavior at the Argonne National Laboratory (ANL) stressing in particular the approaches that are found to be most promising

Reducing Mercury Pollution from Artisanal and Small-Scale Gold Mining

Science.gov (United States)

To reduce airborne mercury emissions from these Gold Shops, EPA and the Argonne National Laboratory (ANL) have partnered to design a low cost, easily constructible technology called the Gold Shop Mercury Capture System (MCS).

Beam tests of the 12 MHz RFQ RIB injector for ATLAS

International Nuclear Information System (INIS)

Clifft, B. E.; Kaye, R. A.; Kedzie, M.; Shepard, K. W.

1999-01-01

Beam tests of the ANL 12 MHz Radio-Frequency Quadruple (RFQ), designed for use as the initial element of an injector system for radioactive beams into the existing ATLAS accelerators, are in progress. Recent high-voltage tests of the RFQ without beam achieved the design intervane voltage of 100 kV CW, enabling beam tests with A/q as large as 132 using beams from the ANL Physics Division 4 MV Dynamitron accelerator facility. Although the RFQ was designed for bunched beams, initial tests have been performed with unbunched beams. Experiments with stable, unbunched beams of singly-charged 132 Xe and 84 Kr measured the output beam energy distribution as a function of the RFQ operating voltage. The observed energies are in excellent agreement with numerical beam simulations

Analytical Chemistry Laboratory progress report for FY 1985

Energy Technology Data Exchange (ETDEWEB)

Green, D.W.; Heinrich, R.R.; Jensen, K.J.

1985-12-01

The Analytical Chemistry Laboratory is a full-cost-recovery service center, with the primary mission of providing a broad range of technical support services to the scientific and engineering programs at ANL. In addition, ACL conducts a research program in analytical chemistry, works on instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL handles a wide range of analytical problems, from routine standard analyses to unique problems that require significant development of methods and techniques. The purpose of this report is to summarize the technical and administrative activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year 1985 (October 1984 through September 1985). This is the second annual report for the ACL. 4 figs., 1 tab.

TRUEX process: a new dimension in management of liquid TRU wastes

International Nuclear Information System (INIS)

Schulz, W.W.; Horwitz, E.P.

1986-01-01

The TRUEX process is one of the, if not the, most exciting and potentially useful nuclear separations processes to be developed since the PUREX process was developed and applied in the 1950s. Attesting to its potential widespread use, Rockwell Hanford and ANL investigators, in a joint effort, are developing and testing TRUEX process flow sheets for removal of TRU elements from several Hanford Site wastes including the Plutonium Finishing Plant and complexed concentrate wastes. The TRUEX process also appears to be well suited to removal of plutonium and Am from aqueous chloride wastes generated during plutonium processing operations at the Los Alamos National Lab. (LANL); collaborative efforts between LANL and ANL scientists to develop and demonstrate TRUEX process flow sheets for treatment of LANL site chloride wastes are currently under way

National ignition facility environment, safety, and health management plan

International Nuclear Information System (INIS)

1995-11-01

The ES ampersand H Management Plan describes all of the environmental, safety, and health evaluations and reviews that must be carried out in support of the implementation of the National Ignition Facility (NIF) Project. It describes the policy, organizational responsibilities and interfaces, activities, and ES ampersand H documents that will be prepared by the Laboratory Project Office for the DOE. The only activity not described is the preparation of the NIF Project Specific Assessment (PSA), which is to be incorporated into the Programmatic Environmental Impact Statement for Stockpile Stewardship and Management (PEIS). This PSA is being prepared by Argonne National Laboratory (ANL) with input from the Laboratory participants. As the independent NEPA document preparers ANL is directly contracted by the DOE, and its deliverables and schedule are agreed to separately with DOE/OAK

Analytical Chemistry Laboratory progress report for FY 1985

International Nuclear Information System (INIS)

Green, D.W.; Heinrich, R.R.; Jensen, K.J.

1985-12-01

The Analytical Chemistry Laboratory is a full-cost-recovery service center, with the primary mission of providing a broad range of technical support services to the scientific and engineering programs at ANL. In addition, ACL conducts a research program in analytical chemistry, works on instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL handles a wide range of analytical problems, from routine standard analyses to unique problems that require significant development of methods and techniques. The purpose of this report is to summarize the technical and administrative activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year 1985 (October 1984 through September 1985). This is the second annual report for the ACL. 4 figs., 1 tab

Nanofluid Technology: Current Status and Future Research

Energy Technology Data Exchange (ETDEWEB)

Choi, Stephen U.-S. [Argonne National Lab. (ANL), Argonne, IL (United States). Energy Technology Division

1998-10-20

Downscaling or miniaturization has been a recent major trend in modern science and technology. Engineers now fabricate microscale devices such as microchannel heat exchangers, and micropumps that are the size of dust specks. Further major advances would be obtained if the coolant flowing in the microchannels were to contain nanoscale particles to enhance heat transfer. Nanofluid technology will thus be an emerging and exciting technology of the 21st century. This paper gives a brief history of the Advanced Fluids Program at Argonne National Laboratory (ANL), discusses the concept of nanofluids, and provides an overview of the R&D program at ANL on the production, property characterization, and performance of nanofluids. It also describes examples of potential applications and benefits of nanofluids. Finally, future research on the fundamentals and applications of nanofluids is addressed.

Beam tests of the 12 MHz RFQ RIB injector for ATLAS.

Energy Technology Data Exchange (ETDEWEB)

Clifft, B. E.; Kaye, R. A.; Kedzie, M.; Shepard, K. W.

1999-05-06

Beam tests of the ANL 12 MHz Radio-Frequency Quadruple (RFQ), designed for use as the initial element of an injector system for radioactive beams into the existing ATLAS accelerators, are in progress. Recent high-voltage tests of the RFQ without beam achieved the design intervane voltage of 100 kV CW, enabling beam tests with A/q as large as 132 using beams from the ANL Physics Division 4 MV Dynamitron accelerator facility. Although the RFQ was designed for bunched beams, initial tests have been performed with unbunched beams. Experiments with stable, unbunched beams of singly-charged {sup 132}Xe and {sup 84}Kr measured the output beam energy distribution as a function of the RFQ operating voltage. The observed energies are in excellent agreement with numerical beam simulations.

High Energy Physics Division semiannual report of research activities, January 1, 1990--June 30, 1990

International Nuclear Information System (INIS)

1990-12-01

This report discusses research programs at ANL in High Energy Physics. The major categories of this research are: experimental programs; theoretical program; experimental facilities research; accelerator research and development; and SSC detector research and development

Proceedings of the USNRC/EPRI/ANL heated crevice seminar.

Energy Technology Data Exchange (ETDEWEB)

Park, J. Y.; Fruzzetti, K.; Muscara, J.; Diercks, D. R.; Energy Technology; EPRI; USNRC

2003-08-31

An international Heated Crevice Seminar, sponsored by the Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Argonne National Laboratory, and the Electric Power Research Institute, was held at Argonne National Laboratory on October 7-11, 2002. The objective of the seminar was to provide a working forum for the exchange of information by contributing experts on current issues related to corrosion in heated crevices, particularly as it relates to the integrity of PWR steam generator tubes. Forty-five persons from six countries attended the seminar, including representatives from government agencies, private industry and consultants, government research laboratories, nuclear vendors, and electrical utilities. The seminar opened with keynote talks on secondary-side crevice environments associated with IGA and IGSCC of mill-annealed Alloy 600 steam generator tubes and the submodes of corrosion in heat transfer crevices. This was followed by technical sessions on (1) Corrosion in Crevice Geometries, (2) Experimental Methods, (3) Results from Experimental Studies, and (4) Modeling. The seminar concluded with a panel discussion on the present understanding of corrosive processes in heated crevices and future research needs.

DOE/ANL/HTRI heat exchanger tube vibration data bank

International Nuclear Information System (INIS)

Halle, H.; Chenoweth, J.M.; Wambsganss, M.W.

1980-02-01

Development of a new heat exchanger tube vibration data bank at Argonne National Laboratory is described. Comprehensive case histories on heat exchangers that have experienced tube-vibration problems and units that have been trouble-free are accumulated and this information is rendered available for evaluation, improvement, and development of vibration-prediction methods and design guidelines. Discussions include difficulties in generating a data bank, data form development, and solicitation efforts. Also included are 15 case histories upon which the data bank will be built. As new case histories are received, they will be assembled and published as addenda to this report

Analysis of transient fuel failure mechanisms: selected ANL programs

International Nuclear Information System (INIS)

Deitrich, L.W.

1975-01-01

Analytical programs at Argonne National Laboratory related to fuel pin failure mechanisms in fast-reactor accident transients are described. The studies include transient fuel pin mechanics, mechanics of unclad fuel, and mechanical effects concerning potential fuel failure propagation. (U.S.).

Radiological protection guidelines for the Formerly Utilized Sites Remedial Action Program and remote Surplus Facilities Management Program

International Nuclear Information System (INIS)

Gilbert, T.L.

1985-01-01

The need for a definitive basis for radiological guidelines and criteria for FUSRAP became apparent by 1981 and led ORO to sponsor a joint ANL/BNI/LANL/ORO effort under the chairmanship of Wayne Hansen (LANL) that resulted in a final FUSRAP radiological guidelines document in March 1983. A separate effort to develop guidelines for remedial action criteria for SFMP was in progress at PNL. The need to coordinate both efforts with impending revisions of DOE Radiological Protection Standards and impending new developments in EPA and NRC Radiological Protection Standards led to convening of the first DOE Workshop on Remedial Action Criteria in Gaithersburg, Maryland, in February 1984, followed by a second workshop in June 1984 at ANL. The major decisions were to base the criteria on dosimetry models and basic limits currently recommended by the International Commission on Radiological Protection, to emphasize the development and use of site-specific rather than generic guidelines and criteria for residual radionuclide concentrations in the ground, and to prepare a manual to accompany the guidelines that would present procedures and tables for deriving site-specific soil guidelines and criteria for the remedial action programs. A joint ANL/LANL/ORNL/PNL effort to prepare a definitive set of guidelines and a manual has been initiated. The scope, status, and current plans for this effort, and some of the key issues, are presented. 10 references, 1 table

The Sodium Process Facility at Argonne National Laboratory-West

International Nuclear Information System (INIS)

Michelbacher, J.A.; Henslee, S.P.; McDermott, M.D.; Price, J.R.; Rosenberg, K.E.; Wells, P.B.

1998-01-01

Argonne National Laboratory-West (ANL-W) has approximately 680,000 liters of raw sodium stored in facilities on site. As mandated by the State of Idaho and the US Department of Energy (DOE), this sodium must be transformed into a stable condition for land disposal. To comply with this mandate, ANL-W designed and built the Sodium Process Facility (SPF) for the processing of this sodium into a dry, sodium carbonate powder. The major portion of the sodium stored at ANL-W is radioactively contaminated. The sodium will be processed in three separate and distinct campaigns: the 290,000 liters of Fermi-1 primary sodium, the 50,000 liters of the Experimental Breeder Reactor-II (EBR-II) secondary sodium, and the 330,000 liters of the EBR-II primary sodium. The Fermi-1 and the EBR-II secondary sodium contain only low-level of radiation, while the EBR-II primary sodium has radiation levels up to 0.5 mSv (50 mrem) per hour at 1 meter. The EBR-II primary sodium will be processed last, allowing the operating experience to be gained with the less radioactive sodium prior to reacting the most radioactive sodium. The sodium carbonate will be disposed of in 270 liter barrels, four to a pallet. These barrels are square in cross-section, allowing for maximum utilization of the space on a pallet, minimizing the required landfill space required for disposal

The Sodium Process Facility at Argonne National Laboratory-West

Energy Technology Data Exchange (ETDEWEB)

Michelbacher, J.A.; Henslee, S.P. McDermott, M.D.; Price, J.R.; Rosenberg, K.E.; Wells, P.B.

1998-07-01

Argonne National Laboratory-West (ANL-W) has approximately 680,000 liters of raw sodium stored in facilities on site. As mandated by the State of Idaho and the US Department of Energy (DOE), this sodium must be transformed into a stable condition for land disposal. To comply with this mandate, ANL-W designed and built the Sodium Process Facility (SPF) for the processing of this sodium into a dry, sodium carbonate powder. The major portion of the sodium stored at ANL-W is radioactively contaminated. The sodium will be processed in three separate and distinct campaigns: the 290,000 liters of Fermi-1 primary sodium, the 50,000 liters of the Experimental Breeder Reactor-II (EBR-II) secondary sodium, and the 330,000 liters of the EBR-II primary sodium. The Fermi-1 and the EBR-II secondary sodium contain only low-level of radiation, while the EBR-II primary sodium has radiation levels up to 0.5 mSv (50 mrem) per hour at 1 meter. The EBR-II primary sodium will be processed last, allowing the operating experience to be gained with the less radioactive sodium prior to reacting the most radioactive sodium. The sodium carbonate will be disposed of in 270 liter barrels, four to a pallet. These barrels are square in cross-section, allowing for maximum utilization of the space on a pallet, minimizing the required landfill space required for disposal.

Radiological protection guidelines for the Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program

International Nuclear Information System (INIS)

Gilbert, T.L.

1984-01-01

The need for a definitive basis for radiological guidelines and criteria for FUSRAP became apparent by 1981 and led ORO to sponsor a joint ANL/BNI/LANL/ORO effort under the chairmanship of Wayne Hansen (LANL) that resulted in a final FUSRAP radiological guidelines document in March 1983. A separate effort to develop guidelines for remedial action criteria for SFMP was in progress at PNL. The need to coordinate both efforts with impending revisions of DOE Radiological Protection Standards and impending new developments in EPA and NRC Radiological Protection Standards led to convening of the first DOE Workshop on Remedial Action Criteria in Gaithersburg, Maryland, in February 1984, followed by a second workshop in June 1984 at ANL. The major decisions were to base the criteria on dosimetry models and basic limits currently recommended by the International Commission on Radiological Protection, to emphasize the development and use of site-specific rather than generic guidelines and criteria for residual radionuclide concentrations in the ground, and to prepare a manual to accompany the guidelines that would present procedures and tables for deriving site-specific soil guidelines and criteria for the remedial action programs. A joint ANL/LANL/ORNL/PNL effort to prepare a definitive set of guidelines and a manual has been initiated. The scope, status, and current plans for this effort, and some of the key issues, are presented. 10 references, 1 table

Fusion power plant simulations: a progress report

International Nuclear Information System (INIS)

Cook, J.M.; Pattern, J.S.; Amend, W.E.

1976-01-01

The objective of the fusion systems analysis at ANL is to develop simulations to compare alternative conceptual designs of magnetically confined fusion power plants. The power plant computer simulation progress is described. Some system studies are also discussed

EPICS release 3.11 specific documentation -- EPICS release notes for 3.11

International Nuclear Information System (INIS)

1994-01-01

EPICS release 3.11 is now ready for user testing. A person who wants to set up a simplified application environment to boot an IOC and create databases using R3.11 should follow the directions in Appendix B, page 27, of the EPICS Source/Release Control Manual, Sept. 20, 1993. The R3.11 EPICS path at ANL/APS is /net/phebos/epics/R3.11 so the command to get the new release is /net/phebos/epics/R3.11/Unix/share/bin/getrel /net/phebos/epics/R3.11. An existing R3.8 short form report can be copied to this new directory and used to create a database. ANL/APS is currently testing an Application Developers Source/Release control system. It is not yet ready for general distribution. Attached are the EPICS R3.11 release notes

Calculation of photon dose for Dalat research reactor in case of loss of reactor tank water

International Nuclear Information System (INIS)

Le Vinh Vinh; Huynh Ton Nghiem; Nguyen Kien Cuong

2007-01-01

Photon sources of actinides and fission products were estimated by ORIGEN2 code with the modified cross-section library for Dalat research reactor (DRR) using new cross-section generated by WIMS-ANL code. Photon sources of reactor tank water calculated from the experimental data. MCNP4C2 with available non-analog Monte Carlo model and ANSI/ANL-6.1.1-1977 flux-to-dose factors were used for dose estimation. The agreement between calculation results and those of measurements showed that the methods and models used to get photon sources and dose were acceptable. In case the reactor water totally leaks out from the reactor tank, the calculated dose is very high at the top of reactor tank while still low in control room. In the reactor hall, the operation staffs can access for emergency works but with time limits. (author)

Removal of an acid fume system contaminated with perchlorates located within hot cell

International Nuclear Information System (INIS)

Rosenberg, K.E.; Henslee, S.P.; Vroman, W.R.; Krsul, J.R.; Michelbacher, J.A.; Knighton, G.C.

1992-09-01

An add scrubbing system located within the confines of a highly radioactive hot cell at Argonne National Laboratory-West (ANL-W) was remotely removed. The acid scrubbing system was routinely used for the dissolution of irradiated reactor fuel samples and structural materials. Perchloric acid was one of the acids used in the dissolution process and remained in the system with its inherent risks. Personnel could not enter the hot cell to perform the dismantling of the acid scabbing system due to the high radiation field and the explosion potential associated with the perchlorates. A robot was designed and built at ANL-W and used to dismantle the system without the need for personnel entry into the hot cell. The robot was also used for size reduction of removed components and loading of the removed components into waste containers

User Interface Program for secure electronic tags

International Nuclear Information System (INIS)

Cai, Y.; Koehl, E.R.; Carlson, R.D.; Raptis, A.C.

1995-05-01

This report summarizes and documents the efforts of Argonne National Laboratory (ANL) in developing a secure tag communication user interface program comprising a tag monitor and a communication tool. This program can perform the same functions as the software that was developed at the Lawrence Livermore National Laboratory (LLNL), but it is enhanced with a user-friendly screen. It represents the first step in updating the TRANSCOM Tracking System (TRANSCOM) by incorporating a tag communication screen menu into the main menu of the TRANSCOM user program. A working version of TRANSCOM, enhanced with ANL secure-tag graphics, will strongly support the Department of Energy Warhead Dismantlement/Special Nuclear Materials Control initiatives. It will allow commercial satellite tracking of the movements and operational activities of treaty-limited items and transportation vehicles throughout Europe and the former USSR, as well as the continental US

Analytical Chemistry Laboratory progress report for FY 1984

International Nuclear Information System (INIS)

Green, D.W.; Heinrich, R.R.; Jensen, K.J.; Stetter, J.R.

1985-03-01

Technical and administrative activities of the Analytical Chemistry Laboratory (ACL) are reported for fiscal year 1984. The ACL is a full-cost-recovery service center, with the primary mission of providing a broad range of technical support services to the scientific and engineering programs at ANL. In addition, ACL conducts a research program in analytical chemistry, works on instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL is administratively within the Chemical Technology Division, the principal user, but provides technical support for all of the technical divisions and programs at ANL. The ACL has three technical groups - Chemical Analysis, Instrumental Analysis, and Organic Analysis. Under technical activities 26 projects are briefly described. Under professional activities, a list is presented for publications and reports, oral presentations, awards and meetings attended. 6 figs., 2 tabs

A 1.5 MJ cryostatic stable superconducting ohmic-heating coil

International Nuclear Information System (INIS)

Wang, S.-T.; Kim, S.H.; Praeg, W.F.; Krieger, C.I.

1978-01-01

As early as FY 1975, ANL had recognized the clear advantage of a superconducting ohmic-heating (OH) coil and proposed a five-year pulsed coil and power supply development program to ERDA. With modest funding made available by ERDA in FY 1977 and the use of substantial equipment inventory at ANL, a small but agressive development program was advanced to the construction of a 1.5 MJ model coil. The principle objective in building the 1.5 MJ ac coil is to demonstrate ac cryostability of a large coil with a dB/dt ranging from 2 T/s up to 14 T/s. The results of basic cable development and tests will be described. The design and construction of a prototype 1.5 MJ cryostable pulsed coil and its nonmetallic cryostat will be presented. (author)

MHD and heat transfer benchmark problems for liquid metal flow in rectangular ducts

International Nuclear Information System (INIS)

Sidorenkov, S.I.; Hua, T.Q.; Araseki, H.

1994-01-01

Liquid metal cooling systems of a self-cooled blanket in a tokamak reactor will likely include channels of rectangular cross section where liquid metal is circulated in the presence of strong magnetic fields. MHD pressure drop, velocity distribution and heat transfer characteristics are important issues in the engineering design considerations. Computer codes for the reliable solution of three-dimensional MHD flow problems are needed for fusion relevant conditions. Argonne National Laboratory and The Efremov Institute have jointly defined several benchmark problems for code validation. The problems, described in this paper, are based on two series of rectangular duct experiments conducted at ANL; one of the series is a joint ANL/Efremov experiment. The geometries consist of variation of aspect ratio and wall thickness (thus wall conductance ratio). The transverse magnetic fields are uniform and nonuniform in the axial direction

Pilot-scale equipment development for pyrochemical treatment of spent oxide fuel

International Nuclear Information System (INIS)

Herrmann, S. D.

1999-01-01

Fundamental objectives regarding spent nuclear fuel treatment technologies include, first, the effective distribution of spent fuel constituents among product and stable waste forms and, second, the minimization and standardization of waste form types and volumes. Argonne National Laboratory (ANL) has developed and is presently demonstrating the electrometallurgical treatment of sodium-bonded metal fuel from Experimental Breeder Reactor II, resulting in an uranium product and two stable waste forms, i.e. ceramic and metallic. Engineering efforts are underway at ANL to develop pilot-scale equipment which would precondition irradiated oxide fuel via pyrochemical processing and subsequently allow for electrometallurgical treatment of such non-metallic fuels into standard product and waste forms. This paper highlights the integration of proposed spent oxide fuel treatment with existing electrometallurgical processes. System designs and technical bases for development of pilot-scale oxide reduction equipment are also described

JAERI RERTR program

International Nuclear Information System (INIS)

Sato, M.

1983-01-01

In 1979, Japan Atomic Energy Research Institute (JAERI) has started a five year program for the utilization of reduced enrichment uranium fuel, in place of currently used highly enriched uranium fuel for the JAERI Research and Test Reactors (RERTR), such as the JRR-2 (10 MWt), the JRR-4 35 MWt), the JMTR(50 MWO and the JMTRC (100 Wt, nuclear mockup of the JMTR), for contributing to the reduction of proliferation concerns. In order to assess the feasibility of converting the JAERI reactors to use of fuel with reduced enrichment uranium, ANL and JAERI have embarked on a joint study program since January 1980. This document provides outlines of the JAERI RERTR Program and of the ANL-JAERI Joint Study, and main results of JAERI's Phase A report which was made under the joint study

Elevated radon levels in buildings: an investigation of potential sources in Region V arising from energy-conserving practices

International Nuclear Information System (INIS)

May, H.A.

1979-01-01

Some trends in single dwelling construction, and the resulting possibility of increased radiation exposure from radon progeny to the inhabitants, are identified. The number of such dwellings available and convenient for an ANL study is estimated. Preliminary measurements are reported

Cellular and muscular growth patterns during sipunculan development

DEFF Research Database (Denmark)

Kristof, Alen; Wollesen, Tim; Maiorova, Anastassya S

2011-01-01

Sipuncula is a lophotrochozoan taxon with annelid affinities, albeit lacking segmentation of the adult body. Here, we present data on cell proliferation and myogenesis during development of three sipunculan species, Phascolosoma agassizii, Thysanocardia nigra, and Themiste pyroides. The first anl...

ASTM STANDARD GUIDE FOR EVALUATING DISPOSAL OPTIONS FOR REUSE OF CONCRETE FROM NUCLEAR FACILITY DECOMMISSIONING

International Nuclear Information System (INIS)

Phillips, Ann Marie; Meservey, Richard H.

2003-01-01

Within the nuclear industry, many contaminated facilities that require decommissioning contain huge volumes of concrete. This concrete is generally disposed of as low-level waste at a high cost. Much of the concrete is lightly contaminated and could be reused as roadbed, fill material, or aggregate for new concrete, thus saving millions of dollars. However, because of the possibility of volumetric contamination and the lack of a method to evaluate the risks and costs of reusing concrete, reuse is rarely considered. To address this problem, Argonne National Laboratory-East (ANL-E) and the Idaho National Engineering and Environmental Laboratory teamed to write a ''concrete protocol'' to help evaluate the ramifications of reusing concrete within the U.S. Department of Energy (DOE). This document, titled the Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Site (1) is based on ANL-E's previously developed scrap metal recycle protocols; on the 10-step method outlined in DOE's draft handbook, Controlling Release for Reuse or Recycle of Property Containing Residual Radioactive Material (2); and on DOE Order 4500.5, Radiation Protection of the Public and the Environment (3). The DOE concrete protocol was the basis for the ASTM Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning, which was written to make the information available to a wider audience outside DOE. The resulting ASTM Standard Guide is a more concise version that can be used by the nuclear industry worldwide to evaluate the risks and costs of reusing concrete from nuclear facility decommissioning. The bulk of the ASTM Standard Guide focuses on evaluating the dose and cost for each disposal option. The user calculates these from the detailed formulas and tabulated data provided, then compares the dose and cost for each disposal option to select the best option that meets regulatory requirements. With this information

Irradiation effects on reactor structural materials. Semiannual progress report, March 1975--July 1975

International Nuclear Information System (INIS)

Claudson, T.T.

1975-12-01

Mechanical properties and irradiation effects are reported by Aerojet, ANL, AI, GE, HEDL, NRL, ORNL, PNL, and Univ. of Cincinnati for: Type 304, 304L, and 316 stainless steels; Inconel 718; nickel; Ni alloys; V alloys; Mo; Nb; and Nb--1 Zr

Status of REBUS fuel management software development for RERTR applications

International Nuclear Information System (INIS)

Olson, Arne P.

2000-01-01

The REBUS-5 burnup code has evolved substantially in order to meet the needs of the ANL RERTR Program. This paper presents a summary of the past changes and improvements in the capabilities of this software, and also identifies future plans. (author)

Getting the most D and D ''know how'' before starting to plan your decommissioning project

International Nuclear Information System (INIS)

Boing, L. E.

1999-01-01

Over the last 20 years, the Decommissioning Program of the ANL-East Site has successfully decommissioned numerous facilities including: three research reactors (a 100 MW BWR, a smaller 250 kW biological irradiation reactor and a 10 kW research reactor), a critical assembly, a suite of 61 plutonium gloveboxes in 9 laboratories, a fuels fabrication facility and several non-reactor (waste management and operations) facilities. In addition, extensive decontamination work was performed on 5 hot cells formerly used in a joint ANL/US Navy R and D program. Currently the D and D of the CP-5 research reactor is underway as is planning for several other future D and D projects. The CP-5 facility was also used as a test bed for the evaluation of select evolving D and D technologies to ascertain their value for use in future D and D projects

The procedures used to review safety analysis reports for packagings submitted to the US Department of Energy for certification

International Nuclear Information System (INIS)

Popper, G.F.; Raske, D.T.; Turula, P.

1988-01-01

This paper presents an overview of the procedures used at the Argonne National Laboratory (ANL) to review Safety Analysis Reports for Packagings (SARPs) submitted to the US Department of Energy (DOE) for issuance of a Certificate of Compliance. Prior to certification and shipment of a packaging for the transport of radioactive materials, a SARP must be prepared describing the design, contents, analyses, testing, and safety features of the packaging. The SARP must be reviewed to ensure that the specific packaging meets all DOE orders and federal regulations for safe transport. The ANL SARP review group provides an independent review and evaluation function for the DOE to ensure that the packaging meets all the prescribed requirements. This review involves many disciplines and includes evaluating the general information, drawings, construction details, operating procedures, maintenance and test programs, and the quality assurance plan for compliance with requirements. 14 refs., 6 figs

Experimental investigations of long-term interactions of molten UO2 with MgO and concrete at Argonne National Laboratory

International Nuclear Information System (INIS)

Stein, R.P.; Farhadieh, R.; Pedersen, D.R.; Gunther, W.H.; Purviance, R.T.

1982-01-01

Experimental work at Argonne is being performed to investigate the long-term molten-core-debris retention capability of the ex-vessel cavity following a postulated meltdown accident. The eventual objective of the work is to determine if normal structural material (concrete) or a specifically selected sacrificial material (MgO) located in the ex-vessel cavity region can effectively contain molten core debris. The materials under investigation at ANL are various types of concrete (limestone, basalt and magnetite) and commercially-available MgO brick. Results are presented of the status of real material experimental investigation at ANL into (1) molten UO 2 pool heat transfer, (2) long-term molten UO 2 penetration into concrete and (3) long-term molten UO 2 penetration into refractory substrates. The decay heating in the fuel has been simulated by direct electrical heating permitting the study of the long-term interaction

Experimental investigations of long-term interactions of molten UO2 with MgO and concrete at Argonne National Laboratory

International Nuclear Information System (INIS)

Stein, R.P.; Farhadieh, R.; Pedersen, D.R.; Gunther, W.H.; Purviance, R.T.

1982-01-01

Experimental work at Argonne is being performed to investigate the long-term molten core debris retention capability of the ex-vessel cavity following a postulated meltdown accident. The eventual objective of the work is to determine if normal structural material (concrete) or a specifically selected sacrificial material (MgO) located in the ex-vessel cavity region can effectively contain molten core debris. The materials under investigation at ANL are various types of concrete (limestone, basalt and magnetite) and commercially-available MgO brick. Results are presented of the status of real material experimental investigation at ANL into 1) molten UO 2 pool heat transfer, 2) long-term molten UO 2 penetration into concrete and 3) long-term molten UO 2 penetration into refractory substrates. The decay heating in the fuel has been simulated by direct electrical heating permitting the study of the long-term interaction

Supported Single-Site Ti(IV) on a Metal–Organic Framework for the Hydroboration of Carbonyl Compounds

Energy Technology Data Exchange (ETDEWEB)

Huang, Zhiyuan [College; amp, Molecular Sciences, Institute of Advanced Studies, Wuhan University, Wuhan 430072, PR China; Chemical; amp, Engineering Division, Argonne National Laboratory, Lemont, Illinois 60439, United States; Liu, Dong [College; amp, Molecular Sciences, Institute of Advanced Studies, Wuhan University, Wuhan 430072, PR China; Chemical; amp, Engineering Division, Argonne National Laboratory, Lemont, Illinois 60439, United States; Camacho-Bunquin, Jeffrey [Chemical; amp, Engineering Division, Argonne National Laboratory, Lemont, Illinois 60439, United States; Zhang, Guanghui [Department; Yang, Dali [College; amp, Molecular Sciences, Institute of Advanced Studies, Wuhan University, Wuhan 430072, PR China; Chemical; amp, Engineering Division, Argonne National Laboratory, Lemont, Illinois 60439, United States; López-Encarnación, Juan M. [Chemical; amp, Engineering Division, Argonne National Laboratory, Lemont, Illinois 60439, United States; Department; Xu, Yunjie [Department; Ferrandon, Magali S. [Chemical; amp, Engineering Division, Argonne National Laboratory, Lemont, Illinois 60439, United States; Niklas, Jens [Chemical; amp, Engineering Division, Argonne National Laboratory, Lemont, Illinois 60439, United States; Poluektov, Oleg G. [Chemical; amp, Engineering Division, Argonne National Laboratory, Lemont, Illinois 60439, United States; Jellinek, Julius [Chemical; amp, Engineering Division, Argonne National Laboratory, Lemont, Illinois 60439, United States; Lei, Aiwen [College; amp, Molecular Sciences, Institute of Advanced Studies, Wuhan University, Wuhan 430072, PR China; Chemical; amp, Engineering Division, Argonne National Laboratory, Lemont, Illinois 60439, United States; Bunel, Emilio E. [Chemical; amp, Engineering Division, Argonne National Laboratory, Lemont, Illinois 60439, United States; Delferro, Massimiliano [Chemical; amp, Engineering Division, Argonne National Laboratory, Lemont, Illinois 60439, United States

2017-10-10

ABSTRACT: A stable and structurally well-defined titanium alkoxide catalyst supported on a metal-organic-framework (MOF) of UiO-67 topology (ANL1-Ti(OiPr)2) was synthesized and fully characterized by a variety of analytical and spectroscopic techniques, including BET, TGA, PXRD, XAS, DRIFT, SEM, and DFT computations. The Ti-functionalized MOF was demonstrated active for the catalytic hydroboration of a wide range of aldehydes and ketones with HBpin as the boron source. Compared to traditional homogeneous and supported hydroboration catalysts, ANL1-Ti(OiPr)2 is completely recyclable and reusable, making it a promising hydroboration catalyst alternative for green and sustainable chemical synthesis. DFT calculations suggest that the catalytic hydroboration proceeds via a (1) hydride transfer between the active Ti-hydride species and a carbonyl moiety (rate determining step), and (2) alkoxide transfer (intramolecular σ-bond metathesis) to generate the boronate ester product.

Studies of N ~ 40 Ni isotopes via neutron-knockout (nKO) and deep-inelastic (DI) reactions

Science.gov (United States)

Chiara, C. J.; Recchia, F.; Gade, A.; Janssens, R. V. F.; Walters, W. B.

2013-10-01

V. BADER, T. BAUGHER, D. BAZIN, J.S. BERRYMAN, B.A. BROWN, C. LANGER, N. LARSON, S.N. LIDDICK, E. LUNDERBERG, S. NOJI, C. PROKOP, S.R. STROBERG, S. SUCHYTA, D. WEISSHAAR, S. WILLIAMS, NSCL/MSU, M. ALBERS, M. ALCORTA, P.F. BERTONE, M.P. CARPENTER, J. CHEN, C.R. HOFFMAN, F.G. KONDEV, T. LAURITSEN, A.M. ROGERS, D. SEWERYNIAK, S. ZHU, ANL, C.M. CAMPBELL, LBNL, H.M. DAVID, D.T. DOHERTY, U. of Edinburgh/ANL, A. KORICHI, CSNSM-IN2P3/ANL, C.J. LISTER, U. of Mass.-Lowell, K. WIMMER, Central Mich. U. -- Excited states in 68Ni were populated in 2nKO reactions at NSCL. Prompt γ rays were detected with the GRETINA array located in front of the S800 separator. A hodoscope at the S800 focal plane captured the 68Ni ions, where isomeric decays could be correlated with prompt γ rays. Decay of the first excited state, a 0+ isomer, was observed, confirming that its energy substantially differs from the literature value. Comparing the decay patterns of excited states with shell-model calculations provides insight into their underlying structure. Data from 70Zn + 208Pb DI reactions studied with Gammasphere provide results consistent with the 2nKO. Single-particle strengths are also under investigation in the odd- A Ni isotopes via 1nKO reactions. Supported in part by the DoE (DE-FG02-94ER40834, DE-AC02-06CH11357), NSF (PHY-1102511), and NNSA (DE-NA0000979).

239 240Pu in Lake Michigan: 1971 to 1978

International Nuclear Information System (INIS)

Wahlgren, M.A.; Nelson, D.M.; Orlandini, K.A.; Kucera, E.T.

1978-01-01

The plutonium concentration data presented previously have consisted primarily of results from studies of short-term variations, i.e., the annual plutonium cycle conducted at Lake Michigan station ANL-5, 12 km SW of Grand Haven, Michigan. In this report, mean annual concentrations of total plutonium in unfiltered water from far off-shore (> 30 km) stations for the period 1971 through 1977, and from station ANL-5 (1975 through 1978) are summarized to establish the long-term trend in plutonium concentration in Lake Michigan. The results presented show that the mean annual concentration in the water column is similar at ANL-5 and at offshore stations and has decreased at the rate of only 6% per year during the period 1972 through 1978. The nearly constant concentration indicates that steady-state equilibria exist between plutonium inputs to the lake and the loss of plutonium from the water column. Observations suggest the existence of an active redox cycle for Pu in Lake Michigan. In this cycle, Pu IV atoms in solution are continually taken up by particulate materials but may be oxidized within microzones of the particles such as freshly deposited manganese coatings and also in solution by agents such as dissolved oxygen. In turn, the concentration of Pu VI in solution may be limited by reaction with reducing constituents of the coloidal-sized fraction (or decomposer organisms such as bacteria or fungi, which might have been present after filtration) and with planktonic organisms in the environment to produce Pu IV and thus maintain the cycle

Direct Neuronal Glucose Uptake Is Required for Contextual Fear Acquisition in the Dorsal Hippocampus

Directory of Open Access Journals (Sweden)

Liang Kong

2017-11-01

Full Text Available The metabolism of glucose is a nearly exclusive source of energy for maintaining neuronal survival, synaptic transmission and information processing in the brain. Two glucose metabolism pathways have been reported, direct neuronal glucose uptake and the astrocyte-neuron lactate shuttle (ANLS, which can be involved in these functions simultaneously or separately. Although ANLS in the dorsal hippocampus (DH has been proved to be required for memory consolidation, the specific metabolic pathway involved during memory acquisition remains unclear. The DH and amygdala are two key brain regions for acquisition of contextual fear conditioning (CFC. In 2-NBDG experiments, we observed that 2-NBDG-positive neurons were significantly increased during the acquisition of CFC in the DH. However, in the amygdala and cerebellum, 2-NBDG-positive neurons were not changed during CFC training. Strikingly, microinjection of a glucose transporter (GLUT inhibitor into the DH decreased freezing values during CFC training and 1 h later, while injection of a monocarboxylate transporter (MCT inhibitor into the amygdala also reduced freezing values. Therefore, we demonstrated that direct neuronal glucose uptake was the primary means of energy supply in the DH, while ANLS might supply energy in the amygdala during acquisition. Furthermore, knockdown of GLUT3 by a lentivirus in the DH impaired the acquisition of CFC. Taken together, the results indicated that there were two different glucose metabolism pathways in the DH and amygdala during acquisition of contextual fear memory and that direct neuronal glucose uptake in the DH may be regulated by GLUT3.

Argonne Research Library | Argonne National Laboratory

Science.gov (United States)

Argonne Argonne Research Library The Argonne Research Library supports the scientific and technical research needs of Argonne National Laboratory employees. Our library catalog is available via the Research questions or concerns, please contact us at librarians@anl.gov. Contact the Library Argonne Research Library

Some physics considerations for TEPR designs

International Nuclear Information System (INIS)

Hogan, J.T.; Rome, J.A.; McAlees, D.G.; Attenberger, S.E.

1975-01-01

A simplified version of the Oak Ridge Tokamak Transport Code is used to assess the implications of confinement scaling, impurity trapping of neutral beam particles and plasma currents driven by neutral injection. The ORNL, ANL and GAC experimental power reactor reference designs are considered

Sintering and Particle Dynamics in Supported Metal Catalysts

DEFF Research Database (Denmark)

Hansen, Thomas Willum

2006-01-01

viser en god overensstemmelse med en kinetisk beskrivelse af sintringsraten under industrielle betingelser, så observationerne i elektronmikroskopet må formodes at være repræsentative for sintring i et industrielt anlæg. Resultaterne indikerer yderligere, at keramikkens overfladestruktur har en kraftig...

Report to users of ATLAS

International Nuclear Information System (INIS)

Ahmad, I.; Glagola, B.

1995-05-01

This report contains discussing in the following areas: Status of the Atlas accelerator; highlights of recent research at Atlas; concept for an advanced exotic beam facility based on Atlas; program advisory committee; Atlas executive committee; and Atlas and ANL physics division on the world wide web

On description of Δ(1232) region in the Rein-Sehgal model

International Nuclear Information System (INIS)

Graczyk, Krzysztof M.; Sobczyk, Jan T.

2007-01-01

New vector and axial form factors in the Rein-Sehgal model are proposed. The vector part is constructed after experimental fits of the helicity amplitudes for electroproduction of Δ(1232) resonance. The axial part is calculated after Q 2 distribution of events in the ANL experiment

U.S. Department of Energy awards $200 million for next-generation

Science.gov (United States)

, U.S. Congressman Bill Foster, Cray V.P. Marketing & Development Barry Bolding, and Argonne Science and Energy Lynn Orr, U.S. Congressman Bill Foster, Cray V.P. Marketing & Development Barry details on today's announcement. Please monitor Argonne's social media channels at http://www.anl.gov/news

76 FR 66958 - Notice of Availability of the Supplement to the Draft Programmatic Environmental Impact Statement...

Science.gov (United States)

2011-10-28

... site: Using the online comment form available on the project Web site: http://solareis.anl.gov . This... measures, in its investment and deployment strategies and decision-making process. This guidance, based on... Solar PEIS include the Arizona Game and Fish Department; the California Energy Commission and Public...

Measurements of reactor-relevant electromagnetic effects with the FELIX facility

International Nuclear Information System (INIS)

Turner, L.R.; Hua, T.Q.; Knott, M.J.; Lee, S.Y.; McGhee, D.G.; Wehrle, R.B.

1986-01-01

Recent experiments with the FELIX (Fusion Electromagnetic Induction eXperiment) facility at Argonne National Laboratory (ANL) suggest that the expected electromagnetic forces and torques in a tokamak first wall, blanket, and shield (FWBS) system can be modelled by a single eddy current mode, with a simple characterization

Storlandbrug i Danmark

DEFF Research Database (Denmark)

Rentz-Petersen, Nee

2011-01-01

Med udgangspunkt i storlandbrugets udfordringer med at indpasse deres nye produktionsanlæg i det danske kulturlandskab, introduceres et nyt princip for helhedsplanlægning for nye storlandbrug anlagt på 'bar mark'. Forslaget indeholder produktionsbygning med tilhørende tekniske anlæg, samt 3 bepla...

Den danske regionskonstruktion

DEFF Research Database (Denmark)

Klausen, Kurt Klaudi; Christoffersen, Henrik

Region Midtjylland er i centrum for analysen men den omfatter også regionsdannelsen i almindelighed. Der anlægges i analysen på samme tid et politologisk, organisationsteoretisk og økonomisk resonnement. Regionsdannelsen finder sted på baggrund af de setup Strukturreformen har sat, men udfoldes p...

Separation science and technology. Semiannual progress report, October 1993 - March 1994

International Nuclear Information System (INIS)

Vandegrift, G.F.; Aase, S.B.; Buchholz, B.

1997-12-01

This document reports on the work done by the Separations Science and Technology Programs of the Chemical Technology Division, Argonne National Laboratory (ANL), in the period October 1993-March 1994. This effort is mainly concerned with developing the TRUEX process for removing and concentrating actinides from acidic waste streams contaminated with transuranic (TRU) elements. The objectives of TRUEX processing are to recover valuable TRU elements and to lower disposal costs for the nonTRU waste product of the process. Other projects are underway with the objective of developing (1) evaporation technology for concentrating radioactive waste and product streams such as those generated by the TRUEX process, (2) treatment schemes for liquid wastes stored are being generated at ANL, (3) a process based on sorbing modified TRUEX solvent on magnetic beads to be used for separation of contaminants from radioactive and hazardous waste streams, and (4) a process that uses low-enriched uranium targets for production of 99 Mo for nuclear medicine uses

Fuel relocation mechanism based on microstructures of debris

International Nuclear Information System (INIS)

Strain, R.V.; Neimark, L.A.; Sanecki, J.E.

1988-05-01

Argonne National Laboratory (ANL) has performed a number of examinations to determine the microstructure and micro-chemistry of samples of debris from the TMI-2 reactor. These examinations have been a small part of the overall effort to gain an understanding of the TMI-2 accident. As a result of these overall efforts, a general scenario of the response of the core components has been established. In this paper we will describe the microstructure and micro-chemistry of debris from the lower plenum of the reactor and relate these data to a segment of the general scenario dealing with the relocation of this material. The primary tools used at ANL for the examination of material from the TMI-2 core were optical microscopy, scanning electron microscopy and Energy Dispersive X-Ray Spectroscopy, and Scanning Auger Spectroscopy. In some cases these techniques were augmented by the use of gamma spectroscopy, autoradiography, and X-ray diffraction analysis

Control room habitability survey of licensed commercial nuclear power generating stations

International Nuclear Information System (INIS)

Driscoll, J.W.

1988-10-01

This document presents the results of a survey of control room habitability systems at twelve commercial nuclear generating stations. The survey, conducted by Argonne National Laboratory (ANL), is part of an NRC program initiated in response to concerns and recommendations of the Advisory Committee on Reactor Safeguards (ACRS). The major conclusion of the report is that the numerous types of potentially significant discrepancies found among the surveyed plants may be indicative of similar discrepancies throughout the industry. The report provides plant-specific and generalized findings regarding safety functions with respect to the consistency of the design, construction, operation and testing of control room habitability systems and corresponding Technical Specifications compared with descriptions provided in the license basis documentation including assumptions in the operator toxic gas concentration and radiation dose calculations. Calculations of operator toxic gas concentrations and radiation doses were provided in the license basis documentation and were not performed by the ANL survey team. Recommendation for improvements are provided in the report

Flaw evaluation of thermally aged cast stainless steel in light-water reactor applications

International Nuclear Information System (INIS)

Lee, S.; Kuo, P.T.; Wichman, K.; Chopra, O.

1997-01-01

Cast stainless steel may be used in the fabrication of the primary loop piping, fittings, valve bodies, and pump casings in light-water reactors. However, this material is subject to embrittlement due to thermal aging at the reactor temperature, that is 290 o C (550 o F). The Argonne National Laboratory (ANL) recently completed a research program and the results indicate that the lower-bound fracture toughness of thermally aged cast stainless steel is similar to that of submerged arc welds (SAWs). Thus, the US Nuclear Regulatory Commission (NRC) staff has accepted the use of SAW flaw evaluation procedures in IWB-3640 of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code to evaluate flaws in thermally aged cast stainless steel for a license renewal evaluation. Alternatively, utilities may estimate component-specific fracture toughness of thermally aged cast stainless steel using procedures developed at ANL for a case-by-case flaw evaluation. (Author)

On the use of the autocorrelation and covariance methods for feedforward control of transverse angle and position jitter in linear particle beam accelerators

International Nuclear Information System (INIS)

Barr, D.S.

1994-01-01

It is desired to design a predictive feedforward transverse jitter control system to control both angle and position jitter in pulsed linear accelerators. Such a system will increase the accuracy and bandwidth of correction over that of currently available feedback correction systems. Intrapulse correction is performed. An offline process actually ''learns'' the properties of the jitter, and uses these properties to apply correction to the beam. The correction weights calculated offline are downloaded to a real-time analog correction system between macropulses. Jitter data were taken at the Los Alamos National Laboratory (LANL) Ground Test Accelerator (GTA) telescope experiment at Argonne National Laboratory (ANL). The experiment consisted of the LANL telescope connected to the ANL ZGS proton source and linac. A simulation of the correction system using this data was shown to decrease the average rms jitter by a factor of two over that of a comparable standard feedback correction system. The system also improved the correction bandwidth

Tritium management in fusion reactors

International Nuclear Information System (INIS)

Galloway, T.R.

1978-05-01

This is a review paper covering the key environmental and safety issues and how they have been handled in the various magnetic and inertial confinement concepts and reference designs. The issues treated include: tritium accident analyses, tritium process control, occupational safety, HTO formation rate from the gas-phase, disposal of tritium contaminated wastes, and environmental impact--each covering the Joint European Tokamak (J.E.T. experiment), Tokamak Fusion Test Reactor (TFTR), Russian T-20, The Next Step (TNS) designs by Westinghouse/ORNL and General Atomic/ANL, the ANL and ORNL EPR's, the G.A. Doublet Demonstration Reactor, the Italian Fintor-D and the ORNL Demo Studies. There are also the following full scale plant reference designs: UWMAK-III, LASL's Theta Pinch Reactor Design (RTPR), Mirror Fusion Reactor (MFR), Tandem Mirror Reactor (TMR), and the Mirror Hybrid Reactor (MHR). There are four laser device breakeven experiments, SHIVA-NOVA, LLL reference designs, ORNL Laser Fusion power plant, the German ''Saturn,'' and LLL's Laser Fusion EPR I and II

How we shipped our flip and standard too

International Nuclear Information System (INIS)

Deigl, H.J.; Feltz, D.E.

1984-01-01

This paper highlights the planning and handling activities for the shipment of irradiated TRIGA fuel from Texas A and M University to the Argonne National Lab/West (ANL/West) reactor facility at Idaho Falls, Idaho. Attention is focused on the enormous time spent on the planning and preparations prior to the shipment. The actual handling time at the NSCR for three shipping packages containing a total 51 elements was only 4 days, but, the time spent in planning and preparation exceeded 16 months. The fuel was transferred for shipment without incident - and from a health physics standpoint the exercise went very well. Whole body exposures and hand doses were minimal for such a large undertaking. ANL/West health physicists reported contamination of the lifting devices for the HFIR when they received the cask. These pieces were wipe tested and contamination was found to be less than 200 dpm. If they were contaminated we were extremely fortunate during handling not to contaminate our facility or personnel

Superconducting RF Development at Nuclear Science Centre

CERN Document Server

Roy, Amit

2005-01-01

A Superconducting Linac is being installed as a booster for the 15 UD Pelletron accelerator at Nuclear Science Centre (NSC). The accelerating structure for this linac is a Nb QWR cavity, designed and fabricated as a joint collaboration between NSC and ANL, USA. Initial cavities required for the first linac module were fabricated at ANL. For fabrication of cavities required for future modules a Superconducting Resonator Fabrication Facility has been set up at NSC. Three quarter wave resonator (QWR) cavities have been fabricated using the in-house facility. This facility has been used for repairs on the resonators which sprung leaks. Fabrication of fifteen resonators for the second and third linac modules is under progress. Eight resonators along with a superconducting solenoid has been installed in the first linac cryostat and tested for energy gain with a pulsed beam of 90 MeV Si from the Pelletron. Acceleration of the ions to 96 MeV was measured downstream and beam transmission through the linac was measured...

Artificial intelligence applications to design validation and sneak function analysis

International Nuclear Information System (INIS)

Stratton, R.C.

1985-01-01

An objective of the US space reactor program is to design systems with high reliability and safety of control over long operating lifetimes. Argonne National Laboratory (ANL) is a participant in the National Man-Machine Integration (MMI) program for Liquid Metal Fast Breeder Reactors (LMFBR). A purpose of this program is to promote the development of concepts and technologies that enhance the operational safety and reliability of fast-breeder reactors. Much of the work is directly applicable to the space reactor program. This paper reports on one of the MMI projects being developed by ANL. The project reported pertains to an automated system that demonstrates the use of artificial intelligence (AI) for design validation (DA) and sneak function analysis (SFA). The AI system models the design specification and the physical design of the cooling process assigned to the Argon Cooling System (ACS) at Experimental Breeder Reactor II (EBR-II). The models are developed using heuristic knowledge and natural laws. 13 refs

On the use of the autocorrelation and covariance methods for feedforward control of transverse angle and position jitter in linear particle beam accelerators

International Nuclear Information System (INIS)

Barr, D.S.

1993-01-01

It is desired to design a predictive feedforward transverse jitter control system to control both angle and position jitter in pulsed linear accelerators. Such a system will increase the accuracy and bandwidth of correction over that of currently available feedback correction systems. Intrapulse correction is performed. An offline process actually open-quotes learnsclose quotes the properties of the jitter, and uses these properties to apply correction to the beam. The correction weights calculated offline are downloaded to a real-time analog correction system between macropulses. Jitter data were taken at the Los Alamos National Laboratory (LANL) Ground Test Accelerator (GTA) telescope experiment at Argonne National Laboratory (ANL). The experiment consisted of the LANL telescope connected to the ANL ZGS proton source and linac. A simulation of the correction system using this data was shown to decrease the average rms jitter by a factor of two over that of a comparable standard feedback correction system. The system also improved the correction bandwidth

Vacuum system for the Argonne 6 GeV synchrotron light source

International Nuclear Information System (INIS)

Wehrle, R.; Moenich, J.

1985-01-01

The ANL vacuum system for the 6 GeV light source storage ring features non-evaporable strip getter pumps for uniform pumping around the ring within a gas desorption antechamber, and it also features lumped getter pumping directly under and above crotch radiation absorbers that are positioned after each bending magnet. Based on experiments at ANL in 1980 and by others, the technical and economical advantages have been established for the use of the distributed NeG pumps of non-magnetic strips coated with a non-evaporable Zr Al getter matrix. The NeG strip pump lifetime approaches ten years. The antechamber improves the isolation of the gas desorption process from the main beam chamber and beam. The combination of these vacuum techniques; the NeG strip getter pumps, the gas desorption antechambers, and the lumped ion and lumped getter pumping provide a unique and reliable system for maintaining long beam lifetime

OECD benchmark a of MOX fueled PWR unit cells using SAS2H, triton and mocup

International Nuclear Information System (INIS)

Ganda, F.; Greenspan, A.

2005-01-01

Three code systems are tested by applying them to calculate the OECD PWR MOX unit cell benchmark A. The codes tested are the SAS2H code sequence of the SCALE5 code package using 44 group library, MOCUP (MCNP4C + ORIGEN2), and the new TRITON depletion sequence of SCALE5 using 238 group cross sections generated using CENTRM with continuous energy cross sections. The burnup-dependent k ∞ and actinides concentration calculated by all three code-systems were found to be in good agreement with the OECD benchmark average results. Limited results were calculated also with the WIMS-ANL code package. WIMS-ANL was found to significantly under-predict k ∞ as well as the concentration of Pu 242 , consistently with the predictions of the WIMS-LWR reported by two of the OECD benchmark participants. Additionally, SAS2H is benchmarked against MOCUP for a hydride fuel containing unit cell, giving very satisfactory agreement. (authors)

Treatment of mixed radioactive liquid wastes at Argonne National Laboratory

International Nuclear Information System (INIS)

Vandegrift, G.F.; Chamberlain, D.B.; Conner, C.

1994-01-01

Aqueous mixed waste at Argonne National Laboratory (ANL) is traditionally generated in small volumes with a wide variety of compositions. A cooperative effort at ANL between Waste Management (WM) and the Chemical Technology Division (CMT) was established, to develop, install, and implement a robust treatment operation to handle the majority of such wastes. For this treatment, toxic metals in mixed-waste solutions are precipitated in a semiautomated system using Ca(OH) 2 and, for some metals, Na 2 S additions. This step is followed by filtration to remove the precipitated solids. A filtration skid was built that contains several filter types which can be used, as appropriate, for a variety of suspended solids. When supernatant liquid is separated from the toxic-metal solids by decantation and filtration, it will be a low-level waste (LLW) rather than a mixed waste. After passing a Toxicity Characteristic Leaching Procedure (TCLP) test, the solids may also be treated as LLW

Liquid metal MHD and heat transfer in a tokamak blanket slotted coolant channel

International Nuclear Information System (INIS)

Reed, C.B.; Hua, T.Q.; Black, D.B.; Kirillov, I.R.; Sidorenkov, S.I.; Shapiro, A.M.; Evtushenko, I.A.

1993-01-01

A liquid metal MHD (Magnetohydrodynamic)/heat transfer test was conducted at the ALEX (Argonne Liquid Metal Experiment) facility of ANL (Argonne National Laboratory), jointly between ANL and NIIEFA (Efremov Institute). The test section was a rectangular slotted channel geometry (meaning the channel has a high aspect ratio, in this case 10:1, and the long side is parallel to the applied magnetic field). Isothermal and heat transfer data were collected. A heat flux of ∼9 W/cm 2 was applied to the top horizontal surface (the long side) of the test section. Hartmann Numbers to 1050 (2 Tesla), interaction parameters to 9 x 10 3 , Peclet numbers of 10--200, based on the half-width of the small dimension (7mm), and velocities of 1--75 cm/sec. were achieved. The working fluid was NaK (sodium potassium eutectic). All four interior walls were bare, 300-series stainless steel, conducting walls

Chemical Shuttle Additives in Lithium Ion Batteries

Energy Technology Data Exchange (ETDEWEB)

Patterson, Mary

2013-03-31

The goals of this program were to discover and implement a redox shuttle that is compatible with large format lithium ion cells utilizing LiNi{sub 1/3}Mn{sub 1/3}Co{sub 1/3}O{sub 2} (NMC) cathode material and to understand the mechanism of redox shuttle action. Many redox shuttles, both commercially available and experimental, were tested and much fundamental information regarding the mechanism of redox shuttle action was discovered. In particular, studies surrounding the mechanism of the reduction of the oxidized redox shuttle at the carbon anode surface were particularly revealing. The initial redox shuttle candidate, namely 2-(pentafluorophenyl)-tetrafluoro-1,3,2-benzodioxaborole (BDB) supplied by Argonne National Laboratory (ANL, Lemont, Illinois), did not effectively protect cells containing NMC cathodes from overcharge. The ANL-RS2 redox shuttle molecule, namely 1,4-bis(2-methoxyethoxy)-2,5-di-tert-butyl-benzene, which is a derivative of the commercially successful redox shuttle 2,5-di-tert-butyl-1,4-dimethoxybenzene (DDB, 3M, St. Paul, Minnesota), is an effective redox shuttle for cells employing LiFePO{sub 4} (LFP) cathode material. The main advantage of ANL-RS2 over DDB is its larger solubility in electrolyte; however, ANL-RS2 is not as stable as DDB. This shuttle also may be effectively used to rebalance cells in strings that utilize LFP cathodes. The shuttle is compatible with both LTO and graphite anode materials although the cell with graphite degrades faster than the cell with LTO, possibly because of a reaction with the SEI layer. The degradation products of redox shuttle ANL-RS2 were positively identified. Commercially available redox shuttles Li{sub 2}B{sub 12}F{sub 12} (Air Products, Allentown, Pennsylvania and Showa Denko, Japan) and DDB were evaluated and were found to be stable and effective redox shuttles at low C-rates. The Li{sub 2}B{sub 12}F{sub 12} is suitable for lithium ion cells utilizing a high voltage cathode (potential that is higher

ANL calculational methodologies for determining spent nuclear fuel source term

International Nuclear Information System (INIS)

McKnight, R. D.

2000-01-01

Over the last decade Argonne National Laboratory has developed reactor depletion methods and models to determine radionuclide inventories of irradiated EBR-II fuels. Predicted masses based on these calculational methodologies have been validated using available data from destructive measurements--first from measurements of lead EBR-II experimental test assemblies and later using data obtained from processing irradiated EBR-II fuel assemblies in the Fuel Conditioning Facility. Details of these generic methodologies are described herein. Validation results demonstrate these methods meet the FCF operations and material control and accountancy requirements

Xylanase production by Aspergillus niger ANL 301 using agro - wastes

African Journals Online (AJOL)

If you would like more information about how to print, save, and work with PDFs, Highwire Press provides a helpful Frequently Asked Questions about PDFs. Alternatively, you can download the PDF file directly to your computer, from where it can be opened using a PDF reader. To download the PDF, click the Download link ...

Transverse beam containment in the ANL 4-GeV microtron

International Nuclear Information System (INIS)

Colton, E.

1983-01-01

Optical systems have been designed to contain the electrons during the acceleration from 0.185 to 4.0 GeV. These systems are located in the dispersive straight sections and maintain a matched dispersion-free beam with β* = 15.0 m in the linac centers, and transverse beam waists in the centers of the dispersive straight sections. A thin-lens code has been developed to design the multi-energy system. Three versions of the focussing systems have been evolved: (i) two quadruople triplets for E less than or equal to 1.62 GeV; (ii) a single triplet for 1.655 less than or equal to E 2.215 GeV, and (iii) a pentaquad system for E greater than or equal to 2.250 GeV. For case (i) we step the exit edges for the 60 0 bending magnets so as to simulate a zero degree edge - this reduces vertical defocussing effects to an acceptable value. At the higher energies the exit edge angles are -60 0 . The entrance angles are 15 0 on the linac sides of the dipoles. Energy behavior of the Twiss parameters and quadrupole strengths are presented

Ring magnets for the synchrotron x-ray source at ANL

International Nuclear Information System (INIS)

Praeg, W.F.; Thompson, K.M.; Kim, S.H.

1987-03-01

The designs of the bending, focusing, and correction magnetic for the storage ring are described. The computer-optimized pole-tip contours of the dipole, quadrupole, and sextupole magnets and the construction and assembly techniques keep the field errors within the specified limits. Horizontal and vertical steering corrections are provided by separate magnets in addition to a steering capability included in the sextupole magnets

The USP pelletron-superconducting linac project in conjunction with ANL

International Nuclear Information System (INIS)

Sala, O.; Pessoa, E.F.

1988-12-01

This report is a synopsis of the present day technology involved in the use of superconducting radio frequency resonators as accelerating units for heavy ion beams and the plans for employing this technology in the new extension of the Sao Paulo Pelletron accelerator in a cooperative program with Argonne National Laboratory, USA. (author) [pt

Pulse compression system for the ANL 20 MeV linac

International Nuclear Information System (INIS)

Mavrogenes, G.; Norem, J.; Simpson, J.

1986-01-01

This paper describes the pulse compression system being built on the Argonne 20 MeV electron linac. The system is designed to rotate the bunch from the present measured pulse length of 38 psec FWHM, to pulse lengths of 5 to 6 ps with the large instantaneous currents (1 to 4 kA) possible instantaneous current. This system was necessary to extend the study of reactive fragments of molecules to the time scale of a few picoseconds, in particular to examine the chemistry of electrons and ions before and during relaxation of the surrounding media. These experiments are not sensitive to the beam energy spread, High Energy Physics experiments studying wake fields have also been proposed using the short bunches and the facility was designed so that the wake field experiment could share the beam bunching system. The 20 MeV electron linac uses a double gap, 12th subharmonic prebuncher together with a one wavelength 1.3 Ghz prebuncher to produce a single pulse of 38 ps from one occupied rf bucket. Beam emittances of 15.7 mmmr have been measured for 40 nC of accelerated charge and 8 mmmr at 10 nC. The energy spread of dE/E = 1% (FWHM) has been measured at 40 nC. Thus the accelerated beam has excellent time structure, high current, and good emittance

ANL ITER high-heat-flux blanket-module heat transfer experiments

International Nuclear Information System (INIS)

Kasza, K.E.

1992-02-01

An Argonne National Laboratory facility for conducting tests on multilayered slab models of fusion blanket designs is being developed; some of its features are described. This facility will allow testing under prototypic high heat fluxes, high temperatures, thermal gradients, and variable mechanical loadings in a helium gas environment. Steady and transient heat flux tests are possible. Electrical heating by a two-sided, thin stainless steel (SS) plate electrical resistance heater and SS water-cooled cold panels placed symmetrically on both sides of the heater allow achievement of global one-dimensional heat transfer across blanket specimen layers sandwiched between the hot and cold plates. The heat transfer characteristics at interfaces, as well as macroscale and microscale thermomechanical interactions between layers, can be studied in support of the ITER engineering design effort. The engineering design of the test apparatus has shown that it is important to use multidimensional thermomechanical analysis of sandwich-type composites to adequately analyze heat transfer. This fact will also be true for the engineering design of ITER

Design for ANL 7 GeV storage ring vacuum system

International Nuclear Information System (INIS)

Wehrle, R.B.; Nielsen, R.W.

1988-01-01

The 7-GeV Advanced Photon Source (APS) design includes a storage ring having a 1060-m circumference with the capability of accommodating 34 insertion devices (ID) and their associated photon beam lines. An additional 35 photon lines can be provided from bending magnets. The vacuum system for the storage ring is designed to maintain a beam-on operating pressure of 1n Torr or less to achieve a positron beam lifetime of approximately 20 hours. The vacuum system and it's current developmental status are described

Målrettet uddannelse i anlæggelse af perifer nerveblokade

DEFF Research Database (Denmark)

Lind, Morten Nikolaj; Kristensen, Billy Bjarne

2011-01-01

Peripheral nerve blockade (PNB) is an important part of the anaesthesiologist's armamentarium. It constitutes an alternative to general anaesthesia, thus it is important that all anaesthesiologists have adequate skills in this area. Lack of sufficient experience during training makes many graduat...... uncomfortable about performing PNB. An answer to this problem is to provide adequate education in PNB in the early stage of postgraduate training. This article presents how we, at our institution, have set up a PNB program that provides value....

Otizmle Yaşamı Ne Kadar Anlıyoruz?

OpenAIRE

AKGÜL, Esra Macaroğlu

2013-01-01

The paper includes an introduction to “autism” for those who do not have an adequate information about it or who would like to understand the situation with all details. Parents and schools are the two important agencies that can make life easier for children with autism. Therefore; it is necessary to understand how parents of children with autism think and behave, as well as understanding how teachers and other individuals in schools act towards them. The paper describes autism in the first ...

Comparison of ANL containment codes with SNR-300 simulation experiments

International Nuclear Information System (INIS)

Marchertas, A.H.; Wang, C.Y.; Fistedis, S.H.

1976-01-01

A comparison of REXCO and ICECO code predictions is made with data obtained from experiments of LMFBR excursion models. The comparisons are based on published results of tests conducted for the safety analysis of the SNR-300 fast breeder. The test configurations consist of a centrally located spherical source immersed in a pool of water which is encased in a cylindrical container. The cylinical walls of the container are prestressed by holddown bolts which span the two rigid ends. The space above the surface of the water within the container is occupied by air. Although certain aspects of the tests could not be simulated by the analytical models exactly, the comparison of results shows quite close agreement. The fact that the REXCO and ICECO codes involve different analytical formulations, their own close correspondence of results lends added credence to the value of analytical predictions

Utilizing benchmark data from the ANL-ZPR diagnostic cores program

International Nuclear Information System (INIS)

Schaefer, R. W.; McKnight, R. D.

2000-01-01

The support of the criticality safety community is allowing the production of benchmark descriptions of several assemblies from the ZPR Diagnostic Cores Program. The assemblies have high sensitivities to nuclear data for a few isotopes. This can highlight limitations in nuclear data for selected nuclides or in standard methods used to treat these data. The present work extends the use of the simplified model of the U9 benchmark assembly beyond the validation of k eff . Further simplifications have been made to produce a data testing benchmark in the style of the standard CSEWG benchmark specifications. Calculations for this data testing benchmark are compared to results obtained with more detailed models and methods to determine their biases. These biases or corrections factors can then be applied in the use of the less refined methods and models. Data testing results using Versions IV, V, and VI of the ENDF/B nuclear data are presented for k eff , f 28 /f 25 , c 28 /f 25 , and β eff . These limited results demonstrate the importance of studying other integral parameters in addition to k eff in trying to improve nuclear data and methods and the importance of accounting for methods and/or modeling biases when using data testing results to infer the quality of the nuclear data files

Recent developments in the target facilities at Argonne National Laboratory

International Nuclear Information System (INIS)

Greene, J.P.; Thomas, G.E.

1989-01-01

A description is given of recent developments in the target facility at Argonne National Laboratory (ANL). Highlights include equipment upgrades which enable us to provide enhanced capabilities for support of the Argonne Heavy-Ion ATLAS Accelerator Project. Also, future plans and additional equipment acquisitions will be discussed. (orig.)

FELIX construction status and experimental program

International Nuclear Information System (INIS)

Turner, L.R.; Praeg, W.F.; Knott, M.J.; Lari, R.J.; McGhee, D.G.; Wehrle, R.B.

1983-01-01

FELIX (Fusion Electromagnetic Induction Experiment) is an experimental test facility being constructed at Argonne National Laboratory (ANL) for the study of electromagnetic effects in the first wall/blanket/shield (FWBS) systems of fusion reactors. The facility design, construction status, experimental program, instrumentation, and associated computer-code comparisons are described

Kvalitet i dagtilbud

DEFF Research Database (Denmark)

Christensen, Kira Saabye; Petersen, Mimi; Tireli, Üzeyir

Denne bog er en grundbog til den specialiseringen Dagtilbudspædagogik på den nye pædagoguddannelse. Bogen bidrager til at udvikle den studerendes generelle vidensgrundlag, studieaktivitet og professionalisering. I bogen anlægges et etisk og videnskabeligt perspektiv på dagtilbudspædagogik og pæda...

Kvalitet I dagtilbud

DEFF Research Database (Denmark)

Christensen, Kira Saabye; Petersen, Mimi; Tireli, Üzeyir

Denne bog er en grundbog til den specialiseringen Dagtilbudspædagogik på den nye pædagoguddannelse. Bogen bidrager til at udvikle den studerendes generelle vidensgrundlag, studieaktivitet og professionalisering. I bogen anlægges et etisk og videnskabeligt perspektiv på dagtilbudspædagogik og pæda...

Byens puls rykker indendørs

DEFF Research Database (Denmark)

Dickson, Thomas

2003-01-01

Fusionen mellem GlaxoWellcome og SmithKlineBeecham er beseglet med opførelsen af et nyt hovedkontor lidt uden for London. Anlæggets største attraktion er en 150 meter lang glasoverdækket gade, der rummer en række praktiske og sociale funktioner....

Beitrag zur Kenntnis und Verbreitung von Galathea Australiensis Stimpson, 1858, (Crustacea Decapoda, Anomura, Galatheidae) nebst Beschreibung eines Neotypus

NARCIS (Netherlands)

Lewinsohn, Ch.

1967-01-01

Anlässlich der Vorbereitung einer Publikation über die Anomuren des Roten Meeres, wurde u.a. auch Material der Gattung Galathea dieser Region untersucht. Dabei ergab sich das Problem einer richtigen Bestimmung von Galathea australiensis Stimpson, 1858. Diese Art wurde von Balss (1915: 2-3), an Hand

Somaæstetisk blik på undervisningsiscenesættelser

DEFF Research Database (Denmark)

Justiniano, Birgitte

Afhandlingen er en undersøgelse af skolers organisering og disses betydning for eleveres mulighed for udvikling af færdigheder, der modsvarer samfunds behov og forventninger. Afhandlingen anlægger et somaæstetisk didaktisk blik på undervisningsiscenesættelser, hvor ønsket er at indfange relatione...

78 FR 16483 - Notice of Availability of the Draft Uranium Leasing Program Programmatic Environmental Impact...

Science.gov (United States)

2013-03-15

... Protection Agency (EPA); Colorado Department of Transportation; Colorado Division of Reclamation, Mining, and... via the internet at http://ulpeis.anl.gov/ gov/. DOE will give equal weight to written, email, and... Court, among other things, invalidated the July 2007 PEA and FONSI; stayed the ULP leases; and ordered...

IPNS upgrade: A feasibility study

International Nuclear Information System (INIS)

1995-04-01

Many of Argonne National Laboratory's (ANL's) scientific staff members were very active in R ampersand D work related to accelerator-based spoliation sources in the 1970s and early 1980s. In 1984, the Seitz/Eastman Panel of the National Academy of Sciences reviewed U.S. materials science research facilities. One of the recommendations of this panel was that the United States build a reactor-based steady-state source, the Advanced Neutron Source (ANS), at Oak Ridge National Laboratory. Subsequently, R ampersand D activities related to the design of an accelerator-based source assumed a lower priority. The resumption of pulsed-source studies in this country started simultaneously with design activities in Europe aimed at the European Spallation Source (ESS). The European Community funded a workshop in September 1991 to define the parameters of the ESS. Participants in this workshop included both accelerator builders and neutron source users. A consortium of European countries has proposed to build a 5-MW pulsed source, and a feasibility study is currently under way. Soon after the birth of the ESS, a small group at ANL set about bringing themselves up to date on pulsed-source information since 1984 and studied the feasibility of upgrading ANL's Intense Pulsed Neutron Source (IPNS) to 1 MW by means of a rapidly cycling synchrotron that could be housed, along with its support facilities, in existing buildings. In early 1993, the Kohn panel recommended that (1) design and construction of the ANS should be completed according to the proposed project schedule and (2) development of competitive proposals for cost-effective design and construction of a 1-MW pulsed spallation source should be authorized immediately

Recycle of LWR [Light Water Reactor] actinides to an IFR [Integral Fast Reactor

International Nuclear Information System (INIS)

Pierce, R.D.; Ackerman, J.P.; Johnson, G.K.; Mulcahey, T.P.; Poa, D.S.

1991-01-01

A large quantity of actinide elements is present in irradiated Light Water Reactor (LWR) fuel that is stored throughout the world. Because of the high fission-to-capture ratio for the transuranium (TRU) elements with the high-energy neutrons in the metal-fueled Integral Fast Reactor (IFR), that reactor can consume these elements effectively. The stored fuel represents a valuable resource for an expanding application of fast power reactors. In addition, removal of the TRU elements from the spent LWR fuel has the potential for increasing the capacity of a high-level waste facility by reducing the heat loads and increasing the margin of safety in meeting licensing requirements. Argonne National Laboratory (ANL) is developing a pyrochemical process, which is compatible with the IFR fuel cycle, for the recovery of TRU elements from LWR fuel. The proposed product is a metallic actinide ingot, which can be introduced into the electrorefining step of the IFR process. The major objective of the LWR fuel recovery process is high TRU element recovery, with decontamination a secondary issue, because fission product removal is accomplished in the IFR process. The extensive pyrochemical processing studies of the 1960s and 1970s provide a basis for the design of possible processes. Two processes were selected for laboratory-scale investigation. One is based on the Salt Transport Process studied at ANL for mixed-oxide fast reactor fuel, and the other is based on the blanket processing studies done for ANL's second Experimental Breeder Reactor (EBR-2). This paper discusses the two processes and is a status report on the experimental studies. 5 refs., 2 figs., 2 tabs

Analytical Chemistry Laboratory Progress Report for FY 1994

Energy Technology Data Exchange (ETDEWEB)

Green, D.W.; Boparai, A.S.; Bowers, D.L. [and others

1994-12-01

The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year (FY) 1994 (October 1993 through September 1994). This annual report is the eleventh for the ACL and describes continuing effort on projects, work on new projects, and contributions of the ACL staff to various programs at ANL. The Analytical Chemistry Laboratory is a full-cost-recovery service center, with the primary mission of providing a broad range of analytical chemistry support services to the scientific and engineering programs at ANL. The ACL also has a research program in analytical chemistry, conducts instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL handles a wide range of analytical problems. Some routine or standard analyses are done, but it is common for the Argonne programs to generate unique problems that require significant development of methods and adaption of techniques to obtain useful analytical data. The ACL has four technical groups -- Chemical Analysis, Instrumental Analysis, Organic Analysis, and Environmental Analysis -- which together include about 45 technical staff members. Talents and interests of staff members cross the group lines, as do many projects within the ACL. The Chemical Analysis Group uses wet- chemical and instrumental methods for elemental, compositional, and isotopic determinations in solid, liquid, and gaseous samples and provides specialized analytical services. Major instruments in this group include an ion chromatograph (IC), an inductively coupled plasma/atomic emission spectrometer (ICP/AES), spectrophotometers, mass spectrometers (including gas-analysis and thermal-ionization mass spectrometers), emission spectrographs, autotitrators, sulfur and carbon determinators, and a kinetic phosphorescence uranium analyzer.

Neutron issues in the JANUS mouse program

International Nuclear Information System (INIS)

Carnes, B.A.; Grahn, D.

1990-01-01

Over the last 25 years, the JANUS program in the Biological and Medical Research Division at Argonne National Laboratory (ANL) has compiled a database on the response of both sexes of an F 1 hybrid mouse, the B6CF 1 (C57BL/6 x BALB/c), to external whole- body irradiation by 60 Co γ-rays and fission neutrons. Three basic patterns of exposure for both neutrons and γ-rays have been investigated: single exposures, 24 equal once-weekly exposures, and 60 equal once-weekly exposures. All irradiations were terminated at predetermined total doses, with dose calculated in centigrays at the midline of the mouse. Three endpoints will be discussed in this paper: (1) life shortening, (2) a point estimate for cumulative mortality, and (3) the hazard function. Life shortening is used as an analysis endpoint because it summarizes, in a single index, the integrated effect of all injuries accumulated by an organism. Histopathological analyses of the mice used in the ANL studies have indicated that 85% of the deaths were caused by neoplasms. Connective tissue tumors were the dominant tumor in the B6CF 1 mouse, with tumors of lymphoreticular origin accounting for approximately 80% of this class. The latter two endpoints will therefore be used to describe the life table experience of mice dying from the lymphoreticular class of tumors. Dose-response models will be applied to the three endpoints in order to describe the response function for neutron exposures, evaluate the effect of dose range and pattern of exposure on the response function for neutrons, and provide a set of neutron relative biological effectiveness (RBE) values of the ANL database. 25 refs

Stabilization and disposal of Argonne-West low-level mixed wastes in ceramicrete waste forms

International Nuclear Information System (INIS)

Barber, D. B.; Singh, D.; Strain, R. V.; Tlustochowicz, M.; Wagh, A. S.

1998-01-01

The technology of room-temperature-setting phosphate ceramics or Ceramicretetrademark technology, developed at Argonne National Laboratory (ANL)-East is being used to treat and dispose of low-level mixed wastes through the Department of Energy complex. During the past year, Ceramicretetrademark technology was implemented for field application at ANL-West. Debris wastes were treated and stabilized: (a) Hg-contaminated low-level radioactive crushed light bulbs and (b) low-level radioactive Pb-lined gloves (part of the MWIR number s ign AW-W002 waste stream). In addition to hazardous metals, these wastes are contaminated with low-level fission products. Initially, bench-scale waste forms with simulated and actual waste streams were fabricated by acid-base reactions between mixtures of magnesium oxide powders and an acid phosphate solution, and the wastes. Size reduction of Pb-lined plastic glove waste was accomplished by cryofractionation. The Ceramicretetrademark process produces dense, hard ceramic waste forms. Toxicity Characteristic Leaching Procedure (TCLP) results showed excellent stabilization of both Hg and Pb in the waste forms. The principal advantage of this technology is that immobilization of contaminants is the result of both chemical stabilization and subsequent microencapsulation of the reaction products. Based on bench-scale studies, Ceramicretetrademark technology has been implemented in the fabrication of 5-gal waste forms at ANL-West. Approximately 35 kg of real waste has been treated. The TCLP is being conducted on the samples from the 5-gal waste forms. It is expected that because the waste forms pass the limits set by the EPAs Universal Treatment Standard, they will be sent to a radioactive-waste disposal facility

Use of acceptable knowledge to demonstrate TRAMPAC compliance

International Nuclear Information System (INIS)

Whitworth, Julia; Becker, Blair; Guerin, David; Shokes, Tamara

2004-01-01

Recently, Los Alamos National Laboratory-Carlsbad Operations (LANL-CO) has supported the Central Characterization Project (CCP) managed by the U.S. Department of Energy (DOE) in the shipment of transuranic (TRU) waste from various small-quantity TRU waste generators to hub sites or other DOE sites in TRUPACT-II shipping containers. This support has involved using acceptable knowledge (AK) to demonstrate compliance with various requirements of Revision 19 of the TRUPACT-II Authorized Methods of Payload Compliance (TRAMPAC). LANL-CO has worked to facilitate TRUPACT-II shipments from the University of Missouri Research Reactor (MURR) and Lovelace Respiratory Research Institute (LRRI) to Argonne National Laboratory-East (ANL-E) and Los Alamos National Laboratory (LANL), respectively. The latter two sites have TRU waste certification programs approved to ship waste to the Waste Isolation Pilot Plant (WIPP) for disposal. In each case, AK was used to satisfy the necessary information to ship the waste to other DOE facilities. For the purposes of intersite shipment, AK provided data to WIPP Waste Information System (WWIS) transportation modules to ensure that required information was obtained prior to TRUPACT-II shipments. The WWIS modules were used for the intersite shipments, not to enter certification data into WWIS, but rather to take advantage of a validated system to ensure that the containers to be shipped were compliant with TRAMPAC requirements, particularly in the evaluation of quantitative criteria. LANL-CO also assisted with a TRAMPAC compliance demonstration for homogeneous waste containers shipped in TRUPACT-II containers from ANL-E to Idaho National Engineering and Environmental Laboratory (INEEL) for the purpose of core sampling. The basis for the TRAMPAC compliance determinations was AK regarding radiological composition, chemical composition, TRU waste container packaging, and absence of prohibited items. Also, even in the case where AK is not used to

Methemoglobin Formation and Characterization of Hemoglobin Adducts of Carcinogenic Aromatic Amines and Heterocyclic Aromatic Amines.

Science.gov (United States)

Pathak, Khyatiben V; Chiu, Ting-Lan; Amin, Elizabeth Ambrose; Turesky, Robert J

2016-03-21

Arylamines (AAs) and heterocyclic aromatic amines (HAAs) are structurally related carcinogens formed during the combustion of tobacco or cooking of meat. They undergo cytochrome P450 mediated N-hydroxylation to form metabolites which bind to DNA and lead to mutations. The N-hydroxylated metabolites of many AAs also can undergo a co-oxidation reaction with oxy-hemolgobin (HbO2) to form methemoglobin (met-Hb) and the arylnitroso intermediates, which react with the β-Cys(93) chain of Hb to form Hb-arylsulfinamide adducts. The biochemistry of arylamine metabolism has been exploited to biomonitor certain AAs through their Hb arylsulfinamide adducts in humans. We examined the reactivity of HbO2 with the N-hydroxylated metabolites of 4-aminobiphenyl (ABP, HONH-ABP), aniline (ANL, HONH-ANL), and the HAAs 2-amino-9H-pyrido[2,3-b]indole (AαC, HONH-AαC), 2-amino-1-methyl-6-phenylimidazo[4,5-b]pyridine (PhIP, HONH-PhIP), and 2-amino-3,8-dimethylimidazo[4,5-f]quinoxaline (MeIQx, HONH-MeIQx). HONH-ABP, HO-ANL, and HONH-AαC induced methemoglobinemia and formed Hb sulfinamide adducts. However, HONH-MeIQx and HONH-PhIP did not react with the oxy-heme complex, and met-Hb formation and chemical modification of the β-Cys(93) residue were negligible. Molecular modeling studies showed that the distances between the H-ON-AA or H-ON-HAA substrates and the oxy-heme complex of HbO2 were too far away to induce methemoglobinemia. Different conformational changes in flexible helical and loop regions around the heme pocket induced by the H-ON-AA or H-ON-HAAs may explain the different proclivities of these chemicals to induce methemoglobinemia. Hb-Cys(93β) sulfinamide and sulfonamide adducts of ABP, ANL, and AαC were identified, by Orbitrap MS, following the proteolysis of Hb with trypsin, Glu-C, or Lys-C. Hb sulfinamide and sulfonamide adducts of ABP were identified in the blood of mice exposed to ABP, by Orbitrap MS. This is the first report of the identification of intact Hb

TV-constrained incremental algorithms for low-intensity CT image reconstruction

DEFF Research Database (Denmark)

Rose, Sean D.; Andersen, Martin S.; Sidky, Emil Y.

2015-01-01

constraint can be guided by an image reconstructed by filtered backprojection (FBP). We apply our algorithm to low-dose synchrotron X-ray CT data from the Advanced Photon Source (APS) at Argonne National Labs (ANL) to demonstrate its potential utility. We find that the algorithm provides a means of edge-preserving...

Kombinerede sol/varmepumpeanlæg i praksis

DEFF Research Database (Denmark)

Andersen, Elsa; Furbo, Simon

2010-01-01

I rapporten analyseres målinger fra kombinerede sol/varmepumpeanlæg i praksis. Anlæggene er installeret af Nordic Energy Group og målingerne er ligeledes foretaget af Nordic Energy Group. Analysen viser at energiforbruget og energiprisen kan reduceres betragteligt ved at installere et kombianlæg ...

Perspectives on Social Exclusion and Inclusion in Denmark

DEFF Research Database (Denmark)

Madsen, Aase Mygind

2007-01-01

Artiklen argumenterer for, at det er vigtigt at være bevidst om, hvorvidt man anlægger et stratifikations(kritisk eori)- eller et differentierings(funktionalisme)- perspektiv på forståelser af eksklusion og inklusion - ikke mindst, når man foretager opmåling af antal ekskluderede indenfor forskel...

FELIX construction status and experimental program

International Nuclear Information System (INIS)

Turner, L.R.; Peag, W.F.

1983-01-01

FELIX (Fusion Electromagnetic Induction eXperiment) is an experimental test facility being constructed at Argonne National Laboratory (ANL) for the study of electromagnetic effects in the first wall/blanket/shield (FWBS) systems of fusion reactors. The facility design, construction status, experimental program, instrumentation, and associated computer-code comparisons are described

Argonne Code Center: compilation of program abstracts

Energy Technology Data Exchange (ETDEWEB)

Butler, M.K.; DeBruler, M.; Edwards, H.S.

1976-08-01

This publication is the tenth supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the document are as follows: preface; history and acknowledgements; abstract format; recommended program package contents; program classification guide and thesaurus; and abstract collection. (RWR)

Argonne Code Center: compilation of program abstracts

International Nuclear Information System (INIS)

Butler, M.K.; DeBruler, M.; Edwards, H.S.

1976-08-01

This publication is the tenth supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the document are as follows: preface; history and acknowledgements; abstract format; recommended program package contents; program classification guide and thesaurus; and abstract collection

Design Analysis of a Prepackaged Nuclear Power Plant for an Ice Cap Location

Science.gov (United States)

1959-01-15

to any rod drive component. Alco designed and built for ANL a prototype drive for the ALPR , This t prototype was extensively tested and approved...the Alco built ALPR rod drives now in operation at Arco, Rod position indication is by means of 2 synchros which are gear driven on the rod side

Energiforbruget i 6 bygninger

DEFF Research Database (Denmark)

Johnsen, Kjeld

Rapporten omhandler en forundersøgelse af energiforbrugets fordeling på anlæg og komponenter i 6 bygninger: et omsorgscenter, en kontorbygning, et supermarked og tre skoler. Undersøgelsen er et led i arbejdet på at tilvejebringe et grundlag for energiøkonomisk planlægning af nye bygninger og...

Bioinformatic analysis to discover putative drug targets against ...

African Journals Online (AJOL)

/

2012-01-26

Jan 26, 2012 ... JVIRTUAL GEL. GELBANK was available from the NCBI FTP server. This website incorporates only completed genomes and information pertinent to 2-DE. Link is available at www.gelbank.anl.gov. JVirGel is a software for the simulation and analysis of proteomics data (http://www.jvirgel.de/). The Java TM.

Erhvervslivets spidser

DEFF Research Database (Denmark)

Ellersgaard, Christoph; Grau Larsen, Anton

2018-01-01

Denne artikel anlægger et netværksanalytisk blik på erhvervslivets indflydelse. Ved at se på netværket mellem lederne af de største organisationer inden for de fem sektorer, der dominerer det danske magtnetværk - erhvervsliv, politik, stat, fagbevægelse og videnskab - vises, hvordan erhvervslivet...

Human Health Exposure Assessment for Rocky Mountain Arsenal Study Area Evaluations. Volume 6-B. Western Study Area Exposure Assessment Version 4.1

Science.gov (United States)

1990-09-01

Prpae f9 r FIUR ?--81L C)ora 2Aagv 61iefrPoe n hs lAnl sDtceRocky~ ~ ~ ~~~~~~~~91 O~~iiAsea lau IthnoLbv ndctrLvl Abar~~~ ge14 15~ rigE 0.4n, ar

Emissionsfaktorer og emissionsopgørelse for decentral kraftvarme

DEFF Research Database (Denmark)

Nielsen, M.; Illerup, J. B.

Der er udarbejdet nye emissionsfaktorer for decentrale kraftvarmeværker <25 MWe. Emissionsfaktorerne er baseret på såvel projektmålinger som eksisterende målinger foretaget på danske værker. Følgende anlægstyper er omfattet af udred-ningen: Affaldsbaseret kraftvarme, halm- og træfyrede kraftvarme...

København Befæstning

DEFF Research Database (Denmark)

Clemmesen, Michael Hesselholt

I denne første samlede fremstilling af Københavns Befæstnings militære historie fortælles om Danmarks sikkerhedspolitiske problemer i spillet mellem stormagterne og den rivende militærteknologiske udvikling i årene op til 1. Verdenskrig, om de forsvarspolitiske overvejelser bag anlægget, om den...

Netplanlægning

DEFF Research Database (Denmark)

Hansen, S.

Anvisningen er udarbejdet som grundlag for den byggetekniske undervisning og som støtte for praksis ved planlægning og styring af bygge- og anlægsarbejder. Netplanlægningens teori og den praktiske anvendelse af netplanlægningsmetoden gennemgås. Desuden omtales netplanlægning med edb, og der gives...

Chemical Technology Division Annual Report 2000

International Nuclear Information System (INIS)

Lewis, D.; Gay, E. C.; Miller, J. F.; Einziger, R. E.; Green, D. W.

2001-01-01

The Chemical Technology Division (CMT) is one of eight engineering research divisions within Argonne National Laboratory (ANL), one of the U.S. government's oldest and largest research laboratories. The University of Chicago oversees the laboratory on behalf of the U.S. Department of Energy (DOE). Argonne's mission is to conduct basic scientific research, to operate national scientific facilities, to enhance the nation's energy resources, and to develop better ways to manage environmental problems. Argonne has the further responsibility of strengthening the nation's technology base through developing industrial technology and transferring that technology to industry. The Chemical Technology Division is a diverse early-stage engineering organization, specializing in the treatment of spent nuclear fuel, development of advanced power sources, and management of both high- and low-level nuclear wastes. Although this work is often indistinguishable from basic research, our efforts are directed toward the practical devices and processes that are covered by ANL's mission. Additionally, the Division operates the Analytical Chemistry Laboratory, which provides a broad range of analytical services to ANL and other organizations. The Division is multi-disciplinary. Its people have formal training as ceramists; physicists; material scientists; electrical, mechanical, chemical, and nuclear engineers; and chemists. They have experience working in academia, urban planning, and the petroleum, aluminum, and automotive industries. Their skills include catalysis, ceramics, electrochemistry, metallurgy, nuclear magnetic resonance spectroscopy, and petroleum refining, as well as the development of nuclear waste forms, batteries, and high-temperature superconductors. In this annual report we present an overview of the technical programs together with representative highlights. The report is not intended to be comprehensive or encyclopedic, but to serve as an indication of the condition

Comparison of the FRM-II HEU design with an alternative LEU design. Attachment

International Nuclear Information System (INIS)

Hanan, N.A.; Mo, S.C.; Smith, R.S.; Matos, J.E.

2004-01-01

After presentation of the foregoing paper by Dr. Nelson Hanan of Argonne National Laboratory (ANL) proposing an alternative LEU core with one fuel ring and a power level of 33 MW, a presentation was made by Dr. Klaus Boning of the Technical University of Munich comparing the FRM-II HEU design with an LEU design by Tlm that had two fuel rings and a power level of 40 MW. Dr. Boning raised the following issues concerning the use of LEU fuel in FRM-H reactor designs: (1) qualification of HEU and LEU silicide fuels, (2) gamma heating in the heavy water reflector, (3) the radiological consequences of hypothetical accidents, and (4) cost and schedule. These issues are addressed in this Attachment. In his presentation, Dr. Hanan mentioned that ANL was also investigating other LEU designs. This work led to a second alternative LEU design that has the same neutron flux performance (8 x 10 14 n/cm 2 /s peak neutron flux in the reflector) and the same fuel lifetime (50 full power days) as the HEU design, but uses LEU silicide fuel with a uranium density of only 4.5 g/cm 3 . This design was achieved by using a fuel plate that has a fuel meat thickness of 0.76 mm, a cladding thickness of 0.38 mm, and a water channel gap of 2.2 mm. A comparison is shown of the main characteristics of this second alternative LEU design with those of the FRM-II HEU design. The ANL core again has one fuel ring with the same dimensions. With this LEU design, a two stage process is no longer necessary because LEU silicide fuel with a uranium density of 4.5 g/cm 3 is fully qualified, licensable, and available now for use in a high flux reactor such as the FRM-II

Timeframe Dependent Fragment Ions Observed in In-Source Decay Experiments with β-Casein Using MALDI MS.

Science.gov (United States)

Sekiya, Sadanori; Nagoshi, Keishiro; Iwamoto, Shinichi; Tanaka, Koichi; Takayama, Mitsuo

2015-09-01

The fragment ions observed with time-of-flight (TOF) and quadrupole ion trap (QIT) TOF mass spectrometers (MS) combined with matrix-assisted laser desorption/ionization in-source decay (MALDI-ISD) experiments of phosphorylated analytes β-casein and its model peptide were compared from the standpoint of the residence timeframe of analyte and fragment ions in the MALDI ion source and QIT cell. The QIT-TOF MS gave fragment c-, z'-, z-ANL, y-, and b-ions, and further degraded fragments originating from the loss of neutrals such as H(2)O, NH(3), CH(2)O (from serine), C2H4O (from threonine), and H(3)PO(4), whereas the TOF MS merely showed MALDI source-generated fragment c-, z'-, z-ANL, y-, and w-ions. The fragment ions observed in the QIT-TOF MS could be explained by the injection of the source-generated ions into the QIT cell or a cooperative effect of a little internal energy deposition, a long residence timeframe (140 ms) in the QIT cell, and specific amino acid effects on low-energy CID, whereas the source-generated fragments (c-, z'-, z-ANL, y-, and w-ions) could be a result of prompt radical-initiated fragmentation of hydrogen-abundant radical ions [M + H + H](+) and [M + H - H](-) within the 53 ns timeframe, which corresponds to the delayed extraction time. The further degraded fragment b/y-ions produced in the QIT cell were confirmed by positive- and negative-ion low-energy CID experiments performed on the source-generated ions (c-, z'-, and y-ions). The loss of phosphoric acid (98 u) from analyte and fragment ions can be explained by a slow ergodic fragmentation independent of positive and negative charges.

Timeframe Dependent Fragment Ions Observed in In-Source Decay Experiments with β-Casein Using MALDI MS

Science.gov (United States)

Sekiya, Sadanori; Nagoshi, Keishiro; Iwamoto, Shinichi; Tanaka, Koichi; Takayama, Mitsuo

2015-09-01

The fragment ions observed with time-of-flight (TOF) and quadrupole ion trap (QIT) TOF mass spectrometers (MS) combined with matrix-assisted laser desorption/ionization in-source decay (MALDI-ISD) experiments of phosphorylated analytes β-casein and its model peptide were compared from the standpoint of the residence timeframe of analyte and fragment ions in the MALDI ion source and QIT cell. The QIT-TOF MS gave fragment c-, z'-, z-ANL, y-, and b-ions, and further degraded fragments originating from the loss of neutrals such as H2O, NH3, CH2O (from serine), C2H4O (from threonine), and H3PO4, whereas the TOF MS merely showed MALDI source-generated fragment c-, z'-, z-ANL, y-, and w-ions. The fragment ions observed in the QIT-TOF MS could be explained by the injection of the source-generated ions into the QIT cell or a cooperative effect of a little internal energy deposition, a long residence timeframe (140 ms) in the QIT cell, and specific amino acid effects on low-energy CID, whereas the source-generated fragments (c-, z'-, z-ANL, y-, and w-ions) could be a result of prompt radical-initiated fragmentation of hydrogen-abundant radical ions [M + H + H]+ and [M + H - H]- within the 53 ns timeframe, which corresponds to the delayed extraction time. The further degraded fragment b/y-ions produced in the QIT cell were confirmed by positive- and negative-ion low-energy CID experiments performed on the source-generated ions (c-, z'-, and y-ions). The loss of phosphoric acid (98 u) from analyte and fragment ions can be explained by a slow ergodic fragmentation independent of positive and negative charges.

Results of performance and emission testing when co-firing blends of dRDF/COAL in a 440 MWe cyclone fired combustor

International Nuclear Information System (INIS)

Ohlsson, O.O.

1993-01-01

Argonne National Laboratory (ANL) together with the University of North Texas (UNT) have developed an improved method for converting refuse (residential, commercial and institutional waste) into an environmentally safe and economical fuel. In this method, recyclable metals, glass, and some plastic products are separated from the refuse. The remaining fraction, consisting primarily of cellulosic materials is then combined with a calcium hydroxide binding additive and formed into cylindrical pellets. These pellets are dense and odorless, can be stored for extended periods of time without biological or chemical degradation, and due to their increased bulk density are more durable and can be more easily conveyed, handled, and transported than other types of waste-derived fuel pellets. Laboratory and pilot-scale research studies, followed by full-scale combustion tests undertaken by DOE, ANL and UNT, in June--July of 1987 have indicated that binder-enhanced dRDF pellets can be successfully cofired with high sulfur coal in spreader-stoker combustors. The results of these combustion tests indicated significant reductions of SO 2 , NO x and CO 2 in the flue gases, and the reduction of heavy metals and organics in the ash residue. Dioxins and furans, both in the flue gas and in the ash residues were below detectable levels. Additional commercial-scale combustion tests have recently been conducted by DOE, NREL, ANL and several industrial participants including Otter Tail Power Company, Reuter, Inc., XL Recycling and Marblehead Lime Company, under a collaborative research and development agreement (CRADA). A large 440 MW e cyclone-fired combustor was tested at Big Stone City, South Dakota on October 26--27, 1992. This paper describes the cyclone-fired combustion tests, the flue gas emission and ash samples that were collected, the analyses that were performed on these samples, and the final test results

Alkaline-Side Extraction of Cesium from Savannah River Tank Waste Using a Calixarene-Crown Ether Extractant

Energy Technology Data Exchange (ETDEWEB)

Bonnesen, P.V.; Delmau, L.H.; Haverlock, T.J.; Moyer, B.A.

1998-12-01

Results are presented supporting the viability of the alkaline-side CSEX process as a potential replacement for the In-Tank Precipitation process for removal of cesium from aqueous high-level waste (HLW) at the Savannah River Site (SRS). Under funding from the USDOE Efficient Separations and Crosscutting program, a flowsheet was suggested in early June of 1998, and in the following four months, this flowsheet underwent extensive testing, both in batch tests at ORNL and ANL and in two centrifugal-contactor tests at ANL. To carry out these tests, the initial ESP funding was augmented by direct funds from Westinghouse Savannah River Corporation. The flowsheet employed a solvent containing a calixarene-crown hybrid compound called BoBCalixC6 that was invented at ORNL and can now be obtained commercially for government use from IBC Advanced Technologies. This special extractant is so powerful and selective that it can be used at only 0.01 M, compensating for its expense, but a modifier is required for use in an aliphatic diluent, primarily to increase the cesium distribution ratio D{sub Cs} in extraction. The modifier selected is a relatively economical fluorinated alcohol called Cs3, invented at ORNL and so far available. only from ORNL. For the flowsheet, the modifier is used at 0.2 M in the branched aliphatic kerosene Isopar{reg_sign} L. Testing at ORNL and ANL involved simulants of the SRS HLW. After extraction of the Cs from the waste simulant, the solvent is scrubbed with 0.05 M HNO{sub 3} and stripped with a solution comprised of 0.0005 M HNO{sub 3} and 0.0001 M CsNO{sub 3}. The selection of these conditions is justified in this report, both on the basis of experimental data and underlying theory.

An alternative LEU design for the FRM-II

International Nuclear Information System (INIS)

Hanan, N.A.; Mo, S.C.; Smith, R.S.; Matos, J.E.

1997-02-01

The Alternative LEU Design for the FRM-II proposed by the RERTR Program at Argonne National Laboratory (ANL) has a compact core consisting of a single fuel element that uses LEU silicide fuel with a uranium density of 4.5 g/cm[sup 3] and has a power level of 32 MW. Both the HEU design by the Technical University of Munich (TUM) and the alternative LEU design by ANL have the same fuel lifetime (50 days) and the same neutron flux performance (8 x 10[sup 14] n/cm[sup 2]/s in the reflector). LEU silicide fuel with 4.5 g/cm[sup 3] has been thoroughly tested and is fully-qualified, licensable, and available now for use in a high flux reactor such as the FRM-II. Computer models for the HEU and LEU designs have been exchanged between TUM and ANL and discrepancies have been resolved. The following issues are addressed: qualification of HEU and LEU silicide fuels, stability of the fuel plates, gamma heating in the heavy water reflector, a hypothetical accident involving the configuration of the reflector, a loss of primary coolant flow transient due to an interrupted power supply, the radiological consequences of larger fission product and plutonium inventories in the LEU core, and cost and schedule. Calculations were also done to address the possibility that new high density LEU fuels could be developed that would allow conversion of the TUM HEU design to LEU fuel. Based on the excellent results for the Alternative LEU Design that were obtained in these analyses, the RERTR Program concludes that all of the major technical issues regarding use of LEU fuel instead of HEU fuel in the FRM-II have been successfully resolved and that it is definitely feasible to use LEU fuel in the FRM-II without compromising the safety or performance of the facility

Planning for closure and deactivation of the EBR-II complex

International Nuclear Information System (INIS)

Michelbacher, J.A.; Henslee, S.P.; Poland, H.F.; Wells, P.B.

1997-01-01

In January 1994, DOE terminated the Integral Fast Reactor (IFR) Program. Argonne National Laboratory-West (ANL-W) prepared a detailed plan to put Experimental Breeder Reactor-II (EBR-II) in a safe condition, including removal of irradiated fueled subassemblies from the plant, transfer of subassemblies, and removal and stabilization of primary and secondary sodium liquid heat transfer metal. The goal of deactivation is to stabilize the EBR-II complex until decontamination and decommissioning (D ampersand D) is implemented, thereby minimizing maintenance and surveillance. Deactivation of a sodium cooled reactor presents unique concerns. Residual sodium in the primary and secondary systems must be either reacted or inerted to preclude concerns with explosive sodium-air reactions. Also, residual sodium on components will effectively solder these items in place, making removal unfeasible. Several special cases reside in the primary system, including primary cold traps, a cesium trap, a cover gas condenser, and systems containing sodium-potassium alloy. The sodium or sodium-potassium alloy in these components must be reacted in place or the components removed. The Sodium Components Maintenance Shop at ANL-W provides the capability for washing primary components, removing residual quantities of sodium while providing some decontamination capacity. Considerations need to be given to component removal necessary for providing access to primary tank internals for D ampersand D activities, removal of hazardous materials, and removal of stored energy sources. ANL-W's plan for the deactivation of EBR-II addresses these issues, providing for an industrially and radiologically safe complex, requiring minimal surveillance during the interim period between deactivation and D ampersand D. Throughout the deactivation and closure of the EBR-II complex, federal environmental concerns will be addressed, including obtaining the proper permits for facility condition and waste processing

75 FR 76447 - Notice of Intent to Prepare a Draft Environmental Impact Statement (EIS), Initiate the Public...

Science.gov (United States)

2010-12-08

... on- line registration for those wanting to make an oral comment at a public meeting, as well as the... and Great Lakes basins. These two basins are connected by man-made channels that, in the past...://glmris.anl.gov ; NEPA Scoping Meeting: USACE is hosting scoping meetings and asks those who want to make...

Supervisand og supervisor

DEFF Research Database (Denmark)

Jacobsen, Claus Haugaard

2007-01-01

Kapitlet redegør for aspekter ved det komplekse forhold mellem supervisand og supervisor, og der anlægges en række forskellige perspektiver. Først beskrives forholdet fra supervisandens perspektiv. At indtræde i rollen som supervisand er, foruden at være lærerigt og fagligt udviklende, ofte også ...

Resource recovery from waste incineration residues

DEFF Research Database (Denmark)

Allegrini, Elisa

Affaldsforbrænding er i mange lande en vigtig teknologi til behandling og energiudnyttelse af affald. Udover energi resulterer forbrænding også i produktion af asker. Størstedelen af askerne udgøres af slagge, som efter behandling har gode tekniske egenskaber og kan anvendes til bygge- og anlægsf...

Underwater radiotelemetry system

International Nuclear Information System (INIS)

Prepejchal, W.; Haumann, J.

1975-01-01

A previous report outlined our requirements and design philosophy for a telemetry system which allows the monitoring of fish movements, physiological parameters, and environmental conditions in thermal discharge areas. This report describes the system that was developed at ANL between 1974 and 1975 and which has been used to track salmonid fishes since fall 1975

Mobility chains analysis of technologies for passenger cars and light duty vehicles fueled with biofuels : application of the Greet model to project the role of biomass in America's energy future (RBAEF) project.

Energy Technology Data Exchange (ETDEWEB)

Wu, M.; Wu, Y.; Wang, M; Energy Systems

2008-01-31

The Role of Biomass in America's Energy Future (RBAEF) is a multi-institution, multiple-sponsor research project. The primary focus of the project is to analyze and assess the potential of transportation fuels derived from cellulosic biomass in the years 2015 to 2030. For this project, researchers at Dartmouth College and Princeton University designed and simulated an advanced fermentation process to produce fuel ethanol/protein, a thermochemical process to produce Fischer-Tropsch diesel (FTD) and dimethyl ether (DME), and a combined heat and power plant to co-produce steam and electricity using the ASPEN Plus{trademark} model. With support from the U.S. Department of Energy (DOE), Argonne National Laboratory (ANL) conducted, for the RBAEF project, a mobility chains or well-to-wheels (WTW) analysis using the Greenhouse gases, Regulated Emissions, and Energy use in Transportation (GREET) model developed at ANL. The mobility chains analysis was intended to estimate the energy consumption and emissions associated with the use of different production biofuels in light-duty vehicle technologies.

Solubility investigations in support of ultrasensitive noble gas detector development

International Nuclear Information System (INIS)

Gross, K.C.; Andersen, A.; Russ, W.R.; Stuenkel, D.; Valentine, J.D.

1998-01-01

Argonne National Laboratory (ANL) and the University of Cincinnati (UC) have been developing a new class of ultrasensitive noble gas detectors that are based upon the ANL discovery that corn oil has a high affinity for heavy noble gas absorption at room temperature but releases the noble gases with warming or by other low-energy-input means. Environmental applications for this new class of fluid-based detectors include ultrahigh sensitivity radioxenon detectors for comprehensive test ban treaty surveillance, improved fission gas detectors for enhanced environmental surveillance in the vicinity of US Department of Energy, US Department of Defense, and US Nuclear Regulatory Commission licensed facilities, and improved integrating Rn detectors for earthquake prediction. They present the results of theoretical and experimental investigations into the solubility phenomena of heavy noble gases (Rn, Xe, and Kr) in triglyceride oils. They intend for the findings presented herein to be used to guide future selection, development, and refinement of vegetable and other hydrocarbon oils to bring further enhancements to noble gas detection efficiencies

Evaluating advanced LMR [liquid metal reactor] reactivity feedbacks using SSC

International Nuclear Information System (INIS)

Slovik, G.C.; Van Tuyle, G.J.; Kennett, R.J.; Cheng, H.S.

1988-01-01

Analyses of the PRISM and SAFR Liquid Metal Reactors with SSC are discussed from a safety and licensing perspective. The PRISM and SAFR reactors with metal fuel are designed for inherent shutdown responses to loss-of-flow and loss-of-heat-sink events. The demonstration of this technology was performed by EBR-II during experiments in April 1986 by ANL (Planchon, et al.). Response to postulated TOPs (control rod withdrawal) are made acceptable largely by reducing reactivity swings, and therefore minimizing the size of possible ractivity insertions. Analyses by DOE and the contractors GE, RI, and ANL take credit for several reactivity feedback mechanisms during transient calculations. These feedbacks include Doppler, sodium density, and thermal expansion of the grid plates, the load pads, the fuel (axial) and the control rod which are now factored into the BNL SSC analyses. The bowing feedback mechanism is not presently modeled in the SSC due to its complexity and subsequent large uncertainty. The analysis is conservative by not taking credit for this negative feedback mechanism. Comparisons of BNL predictions with DOE contractors are provided

NDE of stainless steel and on-line leak monitoring of LWRs. Annual report, October 1983-September 1984

International Nuclear Information System (INIS)

Kupperman, D.S.; Claytor, T.N.; Prine, D.W.

1985-04-01

The application of ultrasonic velocity and attenuation measurements to characterize the microstructure of structural materials is discussed. Results of a workshop on NDE of stainless steel pipes with weld overlays are presented. No currently available, single leak-detection method for reactor cooling systems combines optimal leakage detection sensitivity, leak-locating ability, and leakage measurement accuracy. Current practice with regard to leak detection has been reviewed and assessed for 74 operating plants, including both BWRs and PWRs. Seven cracks, including three field-induced IGSCC specimens and two thermal-fatigue cracks, have been installed in the acoustic leak detection (ALD) facility at ANL. Cross-correlation techniques to improve leak location capabilities have been successfully demonstrated on the laboratory pipe run by use of 375-kHz transducers on waveguides and an electronically simulated leak signal. Preliminary leak detection and location tests have also been run at ANL with a breadboard ALD system. In addition to ALD experiments, laboratory tests have been carried out to help assess the effectiveness of moisture-sensitive tape

A state of the art on metallic fuel technology development

International Nuclear Information System (INIS)

Hwang, Woan; Kang, Hee Young; Nam, Cheol; Kim, Jong Oh

1997-01-01

Since worldwide interest turned toward ceramic fuels before the full potential of metallic fuel could be achieved in the late 1960's, the development of metallic fuels continued throughout the 1970's at ANL's experimental breeder reactor II (EBR-II) because EBR-II continued to be fueled with the metallic uranium-fissium alloy, U-5Fs. During this decade the performance limitations of metallic fuel were satisfactorily resolved resolved at EBR-II. The concept of the IFR developed at ANL since 1984. The technical feasibility had been demonstrated and the technology database had been established to support its practicality. One key features of the IFR is that the fuel is metallic, which brings pronounced benefits over oxide in improved inherent safety and lower processing costs. At the outset of the 1980's, it appeared that metallic fuels are recognized as a professed viable option with regard to safety, integral fuel cycle, waste minimization and deployment economics. This paper reviews the key advances in the last score and summarizes the state-of the art on metallic fuel technology development. (author). 29 refs., 1 tab

Use of ENPEP for developing a strategy for the energy and electricity system in Romania

International Nuclear Information System (INIS)

Popovici, D.

1997-01-01

In Romania, the energy and electricity sector needs to be restructured and modernized to meet the requirements of both market economy and environmental protection. For these reasons, Romania has shown some interest in launching ENPEP studies. In the frame of a technical cooperation project between the Romanian Ministry of Industry, the International Atomic Energy Agency (IAEA) and the Argonne National Laboratory (ANL), MAED and ELECTRIC (WASP) models have been used since 1990 to determine optimal expansion plans of the electric power system. After the successful conclusion of the testing of BALANCE and IMPACTS models under Romania's conditions, these models are now being used for planning the development of the energy system. In order to adapt the models to the particular conditions of Romania, an attempt was made, in cooperation with the International Atomic Energy Agency (IAEA) and Argonne National Laboratory (ANL), to find proper solutions to allow the modelling of specific processes and to overcome some restrictions of the models. This paper presents some of these solutions and suggestions for further improvement of the models. (author). 3 figs, 5 tabs

Tokamak power systems studies, FY 1986: A second stability power reactor

International Nuclear Information System (INIS)

Ehst, D.; Baker, C.; Billone, M.

1987-03-01

This report presents the results of the work at Argonne National Laboratory (ANL) during FY-1986 on the Tokamak Power Systems Study (TPSS). The purpose of the TPSS is to explore and develop ideas that would lead to improvements in the tokamak as a power reactor concept. The work at ANL concentrated on plasma engineering, impurity control, and the blanket/first wall/shield system. The work in FY-1986 extended these studies and focused them on a reference design point. The key features of the design point include: second stability regime with higher β and larger aspect ratio, steady-state operation with fast wave current drive, impurity control via a self-pumped slot limiter, a self-cooled liquid lithium, vanadium alloy blanket with simplified poloidal flow, and reduced reactor building volume with vertical lift maintenance. Sufficient work was carried out to report a preliminary cost estimate. In addition, reactor implications of steady-state operation in the first stability regime were also studied. 174 refs., 124 figs., 65 tabs

Use of ENPEP for developing a strategy for the energy and electricity system in Romania

Energy Technology Data Exchange (ETDEWEB)

Popovici, D [Institute of Power Studies and Design, Bucharest (Romania)

1997-09-01

In Romania, the energy and electricity sector needs to be restructured and modernized to meet the requirements of both market economy and environmental protection. For these reasons, Romania has shown some interest in launching ENPEP studies. In the frame of a technical cooperation project between the Romanian Ministry of Industry, the International Atomic Energy Agency (IAEA) and the Argonne National Laboratory (ANL), MAED and ELECTRIC (WASP) models have been used since 1990 to determine optimal expansion plans of the electric power system. After the successful conclusion of the testing of BALANCE and IMPACTS models under Romania`s conditions, these models are now being used for planning the development of the energy system. In order to adapt the models to the particular conditions of Romania, an attempt was made, in cooperation with the International Atomic Energy Agency (IAEA) and Argonne National Laboratory (ANL), to find proper solutions to allow the modelling of specific processes and to overcome some restrictions of the models. This paper presents some of these solutions and suggestions for further improvement of the models. (author). 3 figs, 5 tabs.

Engineering evaluation of a formerly utilized MED/AEC site. Site A and Plot M, Palos Forest Preserve, Palos Park, Illinois

International Nuclear Information System (INIS)

1979-09-01

This engineering evaluation report (EER) addresses one of these MED/AEC sites known as Site A/Plot M, located in Palos Park, Illinois. The EER describes in technical detail a number of options for remedial action that could be taken with respect to the contamination at Site A/Plot M and presents estimates of the costs associated with these options. A companion document, Environmental Analysis Report on a Formerly Utilized MED/AEC Site, Site A and Plot M, Palos Forest Preserve, Palos Park, Illinois (ANL/ES-79), has also been prepared. It describes in detail the existing site environment and evaluates the environmental impacts of the various remedial options discussed in this report. This EER contributes to a better understanding of the mitigation or resolution of environmental problems posed by the subject MED/AEC site and serves as a basis for determining whether or not remedial actions are warranted. The knowledge derived from the evaluation of a number of remedial options should be helpful in the final disposition of other MED/AEC sites located elsewhere

Run-Beyond-Cladding-Breach (RBCB) test results for the Integral Fast Reactor (IFR) metallic fuels program

International Nuclear Information System (INIS)

Batte, G.L.; Hoffman, G.L.

1990-01-01

In 1984 Argonne National Laboratory (ANL) began an aggressive program of research and development based on the concept of a closed system for fast-reactor power generation and on-site fuel reprocessing, exclusively designed around the use of metallic fuel. This is the Integral Fast Reactor (IFR). Although the Experimental Breeder Reactor-II (EBR-II) has used metallic fuel since its creation 25 yeas ago, in 1985 ANL began a study of the characteristics and behavior of an advanced-design metallic fuel based on uranium-zirconium (U-Zr) and uranium-plutonium-zirconium (U-Pu-Zr) alloys. During the past five years several areas were addressed concerning the performance of this fuel system. In all instances of testing the metallic fuel has demonstrated its ability to perform reliably to high burnups under varying design conditions. This paper will present one area of testing which concerns the fuel system's performance under breach conditions. It is the purpose of this paper to document the observed post-breach behavior of this advanced-design metallic fuel. 2 figs., 1 tab

Solubility investigations in support of ultrasensitive noble gas detector development

International Nuclear Information System (INIS)

Gross, K. C.

1998-01-01

Argonne National Laboratory (ANL) and the University of Cincinnati (UC) have been developing a new class of ultrasensitive noble gas detectors that are based upon the ANL discovery that corn oil has a high affinity for heavy noble gas absorption at room temperature, but releases the noble gases with warming or by other low-energy-input means. Environmental applications for this new class of fluid-based detectors include ultrahigh sensitivity radioxenon detectors for Comprehensive Test Ban Treaty Surveillance, improved fission gas detectors for enhanced environmental surveillance in the vicinity of DOE, DOD, and NRC-licensed facilities, and improved integrating Rn detectors for earthquake prediction. The purpose of the present paper is to present the results of theoretical and experimental investigations into the solubility phenomena of heavy noble gases (Rn, Xe, and Kr) in triglyceride oils. It is the authors' intention that the findings presented herein may be used to guide future selection, development, and refinement of vegetable and other hydrocarbon oils to bring further enhancements to noble gas detection efficiencies

Computer software summaries. Numbers 1 through 423

International Nuclear Information System (INIS)

1979-09-01

The National Energy Software Center (NESC) serves as the software exchange and information center for the US Department of Energy and the Nuclear Regulatory Commission. A major activity of the Center is the preparation and publication of two reports issued periodically - the Center's compilation of program abstracts, ANL-7411, and this software summaries report, ANL-8040. The abstracts describe the softward packages available in the software exchange library maintained and distributed by the Center. The summaries describe agency-sponsored software that is at the specification stage, under development, being checked out, in use, or available at agency offices, laboratories, and contractor installations. Summaries describe software that is not included in the NESC library due to its preliminary status or because it is believed to be of limited interest. The purpose of the summaries report is to keep agency and contractor personnel informed as to the existence, status, and availability of computer programs within the agency, and thereby minimize duplication costs and maximize the value of agency software development efforts

Liquid metal reactor deactivation as applied to the experimental breeder reactor - II

International Nuclear Information System (INIS)

Earle, O. K.; Michelbacher, J. A.; Pfannenstiel, D. F.; Wells, P. B.

1999-01-01

The Experimental Breeder Reactor-II (EBR-II) at Argonne National Laboratory-West (ANL-W) was shutdown in September, 1994. This sodium cooled reactor had been in service since 1964, and by the US Department of Energy (DOE) mandate, was to be placed in an industrially and radiologically safe condition for ultimate decommissioning. The deactivation of a liquid metal reactor presents unique concerns. The first major task associated with the project was the removal of all fueled assemblies. In addition, sodium must be drained from systems and processed for ultimate disposal. Residual quantities of sodium remaining in systems must be deactivated or inerted to preclude future hazards associated with pyrophoricity and generation of potentially explosive hydrogen gas. A Sodium Process Facility (SPF) was designed and constructed to react the elemental sodium from the EBR-II primary and secondary systems to sodium hydroxide for disposal. This facility has a design capacity to allow the reaction of the complete inventory of sodium at ANL-W in less than two years. Additional quantities of sodium from the Fermi-1 reactor are also being treated at the SPF

Die Suche nach den Gottesteilchen

CERN Multimedia

2007-01-01

2008 wird der größte jemals gebaute Teilchenbeschleuniger in Betrieb genommen Anlässlich des Mathematik-Jahres 2008 hat der Experimentalphysiker der Universität Hamburg und der designierte Generaldirektor des europäischen Zentrums für Teilchenphysik CERN in Genf, Rolf-Dieter Heuer, die Bedeutung des Dialogs zwischen Naturwissenschaftlern und Philosophen hervorgehoben.

Advantage and Challenges of $Nb_3Sn$ Superconducting Undulators

Energy Technology Data Exchange (ETDEWEB)

Zlobin, A. V. [Fermilab; Barzi, E. [Fermilab; Turrinoni, D. [Fermilab; Ivanyushenkov, Yu. [Argonne; Kesgin, I. [Argonne

2018-04-01

Utilization of Nb3Sn superconducting wires offers the possibility to increase undulators’ nominal operation field and temperature margin, but requires overcoming chal-lenges that are described in this paper. The achievable field levels for a Nb3Sn version of superconducting undulators being developed at APS-ANL and the conductor choice are also presented and discussed.

Intermedialität als Grundsatzdiskussion. Zum Sammelband Sprechen über Bilder. Sprechen in Bildern: Studien zum Wechselverhältnis von Bild und Sprache

Directory of Open Access Journals (Sweden)

Angela Oster

2016-01-01

Full Text Available Der Sammelband Sprechen über Bilder. Sprechen in Bildern bietet mehr als nur einen weiteren Beitrag zur Intermedialität. Er erforscht anlässlich des interartialen Austauschs zwischen Bild unf Text die Modi der Wissenschaft und versucht, diesbezüglich neue Impulse zu geben. Methodisch wird dabei die Rezeptionsästhetik favorisiert.

U.S. Army’s Ground Vehicle Energy Storage R&D Programs & Goals

Science.gov (United States)

2010-11-10

STATEMENT Approved for public release; distribution unlimited 13. SUPPLEMENTARY NOTES Briefing to ARPA-E BEEST Meeting 14. ABSTRACT NA 15...Program Collaboration & DOD Customers DOE Material Developers Battery Developers ANL USABC National Labs Universities Industrial Developers...qualification for military lead acid batteries; 6 water baths, 31 circuits, 1 thermal chamber • Electrochemical Research & Analysis Lab (EARL

Joint Coordinating Committee on environmental restoration and waste management (JCCEM) support, technology transfer, and special projects

International Nuclear Information System (INIS)

Edgar, D.E.

1993-01-01

Argonne National Laboratory (ANL) assisted in identifying and evaluating foreign technologies to meet EM needs; supported the evaluation, removal, and/or revision of barriers to international technology and information transfer/exchange; facilitated the integration and coordination of U.S. government international environmental restoration and waste management activities; and enhanced U.S. industry's competitiveness in the international environmental technology market

Conflicted Worlds of Multilingual Communities in Africa: Literacy Tangled in Words

Science.gov (United States)

Maganda, Dainess

2016-01-01

Drawing from a sociocultural perspective of literacy, with the goal to promote the use of African Native Languages (ANL) in schools, I conducted a Participatory Action Research in one multilingual primary school community in North West Tanzania. For three weeks, 19 teachers, 19 parents and 119 6th grade students collaborated with each other in a…

Syv veje til branding

DEFF Research Database (Denmark)

Hermansen, Judy

2008-01-01

Mange brandingbøger kommer med én bestemt opskrift på, hvad branding er for noget, og hvad det er for nogle strategier, man skal anlægge. Men der ligger altid mange antagelser bag de gode råd, som bare aldrig bliver sagt explicit. Hvilke antagelser bygger relationsteorien fx på? Eller Martin...

RETRAN02/MOD02: an outside perspective

International Nuclear Information System (INIS)

Wei, T.Y.C.

1984-03-01

ANL recently participated in a review of the RETRAN02/MOD02 code to determine the range of accuracy, the reliability and the reproducibility of results obtained with the code for Chapter 15 non-LOCA system transients for both pressurized water reactors (PWRs) and boiling water reactors (BWRs). This paper summarizes the technical aspects of that review

Bogens perspektiv

DEFF Research Database (Denmark)

Uggerhøj, Lars; Nissen, Maria Appel; Pringle, Keith

2007-01-01

en forståelse af, hvordan hjælp bliver mulig. Et vigtigt tema er forestillingen om enpowerment og magt som noget konstruktivt. Forfatterne anlægger dermed en lidt anden, og mere optimistisk, synsvinkel på det sociale arbejdes muligheder, end det ofte har været tilfældet i de senere års toneangivende...

Erkendelsesmæssig differentiering

DEFF Research Database (Denmark)

Zeuner, Lilli

2017-01-01

Kapitlet belyser forskellige sociologiske forståelser af kultur. Det giver en historisk gennemgang og peger bl.a. på, at der kan anlægges to tilgange til at forstå og begribe kultur inden for sociologien. På den ene side er der den tilgang, som ser kulturen som en differentierende faktor, og på d...

Are we ready to test QED in two-electron ions

International Nuclear Information System (INIS)

Ermolaev, A.M.

1981-01-01

The great improvement on the accuracy of the measured transition intervals in two-electron ions achieved recently is discussed with reference to reports of Berry (ANL) and Silver (Oxford) on the precision determination of the 2s 3 S 1 - 2p 3 P/sub J/, J = 0, and 2, intervals in the ions with intermediate Z

ANL-1(A) - Development of nondestructive evaluation methods for structural ceramics

International Nuclear Information System (INIS)

Ellingson, W.A.; Roberts, R.A.; Gopalsami, N.; Dieckman, S.; Hentea, T.; Vaitekunas, J.J.

1989-01-01

This section includes the following papers: Development of Nondestructive Evaluation Methods for Structural Ceramics; Effects of Flaws on the Fracture Behavior of Structural Ceramics; Design, Fabrication, and Interface Characterization of Ceramic Fiber-Ceramic Matrix Composites; Development of Advanced Fiber-Reinforced Ceramics; Modeling of Fibrous Preforms for CVD Infiltration; NDT of Advanced Ceramic Composite Materials; Joining of Silicon Carbide Reinforced Ceramics; Superconducting Film Fabrication Research; Short Fiber Reinforced Structural Ceramics; Structural Reliability and Damage Tolerance of Ceramic Composites for High-Temperature Applications; Fabrication of Ceramic Fiber-Ceramic Matrix Composites by Chemical Vapor Infiltration; Characterization of Fiber-CVD Matrix interfacial Bonds; Microwave Sintering of Superconducting Ceramics; Improved Ceramic Composites Through Controlled Fiber-Matrix Interactions; Evaluation of Candidate Materials for Solid Oxide Fuel Cells; Ceramic Catalyst Materials: Hydrous Metal Oxide Ion-Exchange Supports for Coal Liquefaction; and Investigation of Properties and Performance of Ceramic Composite Components

Komplikationer efter anlæggelse og tilbagelægning af loopileostomi

DEFF Research Database (Denmark)

El-Hussuna, Alaa; Bülow, Steffen; Lauritsen, Morten

2011-01-01

A protective loop ileostomy is used to reduce the incidence and consequences of anastomotic failure following colorectal resection. Closure of a loop ileostomy is associated with low mortality but many studies have demonstrated high morbidity rates. The aim of this review is to examine the existing...

ANL technical support program for DOE Environmental Restoration and Waste Management

International Nuclear Information System (INIS)

Bates, J.K.; Bradley, C.R.; Buck, E.C.; Cunnane, J.C.; Dietz, N.L.; Ebert, W.L.; Emery, J.W.; Feng, X.; Gerding, T.J.; Gong, M.; Hoh, J.C.; Mazer, J.J.; Wronkiewicz, D.J.; Bourcier, W.L.; Morgan, L.E.; Newton, L.; Nielsen, J.K.; Phillips, B.L.; Ewing, R.C.; Wang, L.; Li, H.; Tomozawa, M.

1993-05-01

A program was established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site. This report covers progress in FY 1992 on the following tasks: 1. A compendium of the characteristics of high-level nuclear waste borosilicate glass has been written. 2. A critical review of important parameters that affect the reactivity of glass in an unsaturated environment is being prepared. 3. A series of tests has been started to evaluate the reactivity of fully radioactive glasses in a high-level waste repository environment and compare it to the reactivity of synthetic, nonradioactive glasses of similar composition. 4. The effect of radiation upon the durability of waste glasses at a high glass surface area-to-liquid volume (SA/V) ratio and a high gas-to-liquid volume ratio will be assessed. These tests address both vapor and high SA/V liquid conditions. 5. A series of tests is being performed to compare the extent of reaction of nuclear waste glasses at various SAN ratios. Such differences in the SAN ratio may significantly affect glass durability. 6. A series of natural analogue tests is being analyzed to demonstrate a meaningful relationship between experimental and natural alteration conditions. 7. Analytical electron microscopy (AEM), infrared spectroscopys and nuclear resonant profiling are being used to assess the glass/water reaction pathway by identifying intermediate phases that appear on the reacting glass. Additionally, colloids from the leach solutions are being studied using AEM. 8. A technical review of AEM results is being provided. 9. A study of water diffusion involving nuclear waste glasses is being performed. 10. A mechanistically based model is being developed to predict the performance of glass over repository-relevant time periods

High power testing oa ANL X-band dielectric-loaded accelerating structures

International Nuclear Information System (INIS)

Power, J. G.; Gai, W.; Jing, C.; Konecny, R.; Gold, S. H.; Kinkead, A. K.

2002-01-01

In the second phase of a program to develop a compact accelerator based on a dielectric-loaded accelerating structure, we have conducted high power tests on a traveling-wave and a standing-wave prototype. Indications are that the traveling-wave structure achieved an accelerating gradient of 3-5 MV/m before the input coupling window failed, while the standing wave structure was poorly matched at high power due to contamination of copper residue on its coupling window. To solve both of these problems, a new method for coupling RF into the structures has been developed. The new couplers and the rest of the modular structure are currently under construction and will be tested at the Naval Research Laboratory shortly

Physics Division annual review, 1 April 1975--31 March 1976. [ANL

Energy Technology Data Exchange (ETDEWEB)

Garvey, G. T.

1976-01-01

An overview is given of Physics Division activities in the following areas: the heavy-ion booster; medium-energy physics; heavy-ion physics; low-energy charged-particle physics; accelerator operations; neutron physics; theoretical nuclear physics, and atomic and molecular physics. A bibliography of publications amounts to 27 pages. (RWR)

Evaluation of advanced and current leak detection systems

International Nuclear Information System (INIS)

Kupperman, D.S.

1988-01-01

U.S. Nuclear Regulatory Commission Guide 1.45 recommends the use of at least three different detection methods in reactors to detect leakage. Monitoring of both sump-flow and airborne particulate radioactivity is mandatory. A third method can involve either monitoring of condensate flow rate from air coolers or monitoring of airborne gaseous radioactivity. Although the methods currently used for leak detection reflect the state of the art, other techniques may be developed and used. Since the recommendations of Regulatory Guide 1.45 are not mandatory, Licensee Event Report Compilations have been reviewed to help establish actual capabilities for leak detection. The review of event reports, which had previously covered the period of June 1985 to August 1986 has been extended, and now covers events to June 1987. The total number of significant events is now 83. These reports have provided documented, sometimes detailed, summaries of reactor leaks. They have helped establish the capabilities of existing systems to detect and locate leaks. Differences between PWRs and BWRs with regard to leak detection have now been analyzed. With regard to detection methods, the greatest differences between reactor types are as follows: (a) The sump pump is reported as the detection method more frequently in BWRs than in PWRs (64% vs. 35%). (b) The radiation monitor is reported as the detection method (excluding false alarms) more frequently in PWRs. Current efforts at Argonne National Laboratory (ANL) to evaluate advanced acoustic leak detection methods are directed toward the generation and analysis of acoustic data from large (0.5 to 10 gal/min) leaks and modification of the software of the GARD/ANL advanced acoustic leak detection system. In order to reach the goal of 10 gal/min leaks, the Steam Generator Test Facility at ANL has been modified to carry out the leak testing. Tests were carried out with water at 525 deg. F and 1100 psi leaking through a fatigue crack in a 4-in

Ex-post evaluation by bibliometric method. Institutional comparison among 9 resembled foreign research institutes by using the energy citation database (ECD)

International Nuclear Information System (INIS)

Yanagisawa, Kazuaki

2007-09-01

From a viewpoint of ex-post evaluation, research papers published from nine resembled nuclear research institutes located in Japan, the U.S.A., Germany and France were compared by a bibliometric method. A research database used was the Energy Citation Database (ECD) owned by USDOE. ECD is a database run by USDOE and has a high frequency of research paper acquisition assembled in the U.S. Response speed of ECD on the Website is quick and all logged data can be handled easily. INIS database is run by the International Atomic Energy Agency (IAEA) and contains a lot of nuclear research papers collected from the member countries such as the U.S.A., Japan, Germany and France. INIS underestimates about 20% of the U.S.A. data than that of ECD. I. Institutional Comparison. (1) ECD shows that a total number of research papers published during 25 years (1978-2002) was of the order of the ORNL (34, 149 papers)>SNL>ANL>BNL>Idaho (>Karlsruhe>JAERI>Jeulich>Cadarache). Where, INIS shows it as ORNL>JAERI. (2) ECD can show a long-term data comparison with a time span more than 50 years (1953-2002). Disclosed research papers were of the order of the ORNL (55,857)>ANL (37,129)>SNL (24,628)>BNL (24,829)> Idaho (2,398). There were many records loaded without publication dates-over 50,000. Because of this, any searches which use dates are not finding these documents. Typically, the author found over 5,000 SNL items in the NSA range of records. SNL also kept a lot of defense reports, those are not disclosed yet. One had better know a historical background of each cite as to the case for long-range dates comparison. (3) ECD founds that research papers at a five-year period varied those numbers. At past (10), thus 1988-1922, paper reduction occurred sharply at most US-institutes. This might be attributed to lay-offs, funding shifts or complete elimination of programs, a policy change in reporting requirements for contract reporting deliverables. Definitions of what constituted STI (science

Sloshing analysis of tanks containing multiple fluid layers

International Nuclear Information System (INIS)

Uras, R.A.; Tang, Yu.

1994-01-01

The effect of liquid density changes in high level radioactive liquid waste storage tanks is studied. The density variations with the liquid depth is modeled by layers of piece wise constant densities. A computational formulation based on the finite element method is presented. The computer code FLUSTR-ANL has been modified for the analysis of the sloshing response under seismic excitation

Research, development and demonstration of nickel-zinc batteries for electric vehicle propulsion. Annual report, 1978

Energy Technology Data Exchange (ETDEWEB)

1979-10-01

The work carried out under the Yardney Contract with ANL for R, D and D on nickel zinc batteries over the past year was directed in three major areas: (1) elucidating the failure modes of the nickel-zinc battery system; (2) improving performance of the system; and (3) effecting a cost reduction program. Progress on the three areas is reported. (TFD)

Heavy ion fusion program. Semi-annual progress report, October 1, 1979-March 30, 1980

International Nuclear Information System (INIS)

1980-01-01

HIF activity at ANL during FY 1980 has been primarily concentrated on conceptual design work, and on initial tests of the independently-phased rf acceleration cavities. Calculations for near-term foil-heating experiments were carried out, and a specific cost-effective synchrotron (Beam Development Facility) plan was developed. Program logics were further refined, and some conceptual reactor issues were addressed

UCLA accelerator research ampersand development. Progress report

International Nuclear Information System (INIS)

1997-01-01

This report discusses work on advanced accelerators and beam dynamics at ANL, BNL, SLAC, UCLA and Pulse Sciences Incorporated. Discussed in this report are the following concepts: Wakefield acceleration studies; plasma lens research; high gradient rf cavities and beam dynamics studies at the Brookhaven accelerator test facility; rf pulse compression development; and buncher systems for high gradient accelerator and relativistic klystron applications

Den guddommelige æstetik

DEFF Research Database (Denmark)

Moutamid, Mina El

2007-01-01

I denne artikel anlægges to perspektiver på det æstetiske i et forsøg på at identificere et forhold mellem det æstetiske og det religiøse. Med udgangspunkt i en fænomenologisk karakteristik af den religiøse oplevelse påvises en række lighedspunkter med den æstetiske oplevelse. Desuden defineres d...

Lean praktik

DEFF Research Database (Denmark)

2018-01-01

Værktøjet er en arbejdsmetode for evalueringsprocesser på bygge-, anlægs og renoveringsprojekter i forbindelse med erhvervspraktik. Formålet er en styrkelse af en integreret læringsproces, så håndværkere og ingeniører opnår indsigt i hinandens forudsætninger, bliver bedre til at lytte til hinande...

Atomic spectrum of plutonium

International Nuclear Information System (INIS)

Blaise, J.; Fred, M.; Gutmacher, R.G.

1984-08-01

This report contains plutonium wavelengths, energy level classifications, and other spectroscopic data accumulated over the past twenty years at Laboratoire Aime Cotton (LAC) Argonne National Laboratory (ANL), and Lawrence Livermore National Laboratory (LLNL). The primary purpose was term analysis: deriving the energy levels in terms of quantum numbers and electron configurations, and evaluating the Slater-Condon and other parameters from the levels

Learning by Explaining Examples to Oneself: A Computational Model

Science.gov (United States)

1992-02-01

rules. of which 28 rep~resented common senise phtysirs (e.g.. a taut rope tied to a object pulls onl it ) and 17 represented ()vr-gnerlizt inssuch as...the ,mii~ jduid( ii ot refer to anl examiplle to achieve tilie goal. thliu we cla-si tied lie goalI as beingp resolved bY EIIL( * llliimi v all mlv 1i e

Standard reference and other important nuclear data. Supplement 1 to the report BNL-NCS-51123 (Dec. 1979) = ENDF-300 = IAEA-NDS-15/300 (microfiche)

Energy Technology Data Exchange (ETDEWEB)

Bhat, M R [ed.

1981-03-01

The document contains inserts to be added to the report `Standard Reference and Other Important Nuclear Data` (BNL-NCS-51123, ENDF-300), including the following two articles: Fast Neutron Capture in {sup 238}U and {sup 232}Th by W.P. Poentiz (ANL), and {sup 239}Pu Decay Power Discrepancy by T.R. England and P.G. Young (LANL) Refs, figs

Aluminiumsmelter og vandkraft i det centrale Vestgrønland

DEFF Research Database (Denmark)

Johansen, Poul; Aastrup, Peter; Boertmann, David

. Landskabsoplevelsen, herunder stilheden og uberørtheden, tiltrækker mange turister og bruges til at markedsføre området. Transmissionslinjer og andre anlæg vil påvirke naturoplevelsen på en måde som de fleste vil opfatte som negativ. Nogle lokale turistaktører ser dog muligheder for at tiltrække flere turister i...

Dynamic Stability of Maglev Systems,

Science.gov (United States)

1992-04-01

AD-A259 178 ANL-92/21 Materials and Components Dynamic Stability of Technology Division Materials and Components Maglev Systems Technology Division...of Maglev Systems Y. Cai, S. S. Chen, and T. M. Mulcahy Materials and Components Technology Division D. M. Rote Center for Transportation Research...of Maglev System with L-Shaped Guideway ......................................... 6 3 Stability of M aglev System s

Heavy ion fusion program. Semi-annual progress report, October 1, 1979-March 30, 1980

Energy Technology Data Exchange (ETDEWEB)

1980-01-01

HIF activity at ANL during FY 1980 has been primarily concentrated on conceptual design work, and on initial tests of the independently-phased rf acceleration cavities. Calculations for near-term foil-heating experiments were carried out, and a specific cost-effective synchrotron (Beam Development Facility) plan was developed. Program logics were further refined, and some conceptual reactor issues were addressed.

Energioptimering VAV eller CAV?

DEFF Research Database (Denmark)

Kærn, Martin Ryhl; Barky, Tarek; Andersen, Dan Bomholt

2008-01-01

Når et HVAC-anlæg projekteres, vælges der oftest mellem fortrængnings- og opblandingsventilation. Herefter vælges hvorvidt luftfl owet skal være variabelt eller konstant – det vil sige, om der skal vælges. VAV eller CAV. Dette valg mellem VAV eller CAV bør foretages på baggrund af en vurdering af...

Fulltext PDF

Indian Academy of Sciences (India)

The relativistic wave equation of the electron ranks anlO- ng the highest achievements of 20th century science. Dirac's two papers on the subject published in 1928 are the following:- P.A.M. Dirac, Proc. Roy. Soc. Al17, 610, 1928. P.A.M. Dirac, Proc. Roy. Soc. Al18, 351, 1928. Dirac himself is supposed to have reuw.rked that ...

Development of a hand-portable photoionization time-of-flight mass spectrometer

International Nuclear Information System (INIS)

Dieckman, S.L.; Bostrom, G.A.; Waterfield, L.G.; Jendrzejczyk, J.A.; Raptis, A.C.

1996-01-01

ANL is currently developing a portable chemical sensor system based on laser desorption photoionization time-of-flight mass spectrometry. It will incorporate direct sampling, a cryocooler base sample adsorption and concentration, and direct surface multiphoton ionization. All components will be in a package 9 x 11 x 4 in., weighing 15-18 lbs. A sample spectrum is given for a NaCl sample

Decontamination and decommissioning of the Argonne National Laboratory East Area radioactively contaminated surplus facilities: Final report

International Nuclear Information System (INIS)

Kline, W.H.; Fassnacht, G.F.; Moe, H.J.

1987-07-01

ANL has decontaminated and decommissioned (D and D) seven radiologically contaminated surplus facilities at its Illinois site: a ''Hot'' Machine Shop (Building 17) and support facilities; Fan House No. 1 (Building 37), Fan House No. 2 (Building 38), the Pangborn Dust Collector (Building 41), and the Industrial Waste Treatment Plant (Building 34) for exhaust air from machining of radioactive materials. Also included were a Nuclear Materials Storage Vault (Building 16F) and a Nuclear Research Laboratory (Building 22). The D and D work involved dismantling of all process equipment and associated plumbing, ductwork, drain lines, etc. After radiation surveys, floor and wall coverings, suspended ceilings, room partitions, pipe, conduit and electrical gear were taken down as necessary. In addition, underground sewers were excavated. The grounds around each facility were also thoroughly surveyed. Contaminated materials and soil were packaged and shipped to a low-level waste burial site, while nonactive debris was buried in the ANL landfill. Clean, reusable items were saved, and clean metal scrap was sold for salvage. After the decommissioning work, each building was torn down and the site relandscaped. The project was completed in 1985, ahead of schedule, with substantial savings

Deployment of phytoremediation at the 317/319 area at Argonne National Laboratory - East

International Nuclear Information System (INIS)

Negri, M. C.; Hinchman, R. R.; Quinn, J.; Wozniak, J.

2000-01-01

The 317 and 319 Areas are located on the extreme southern end of the ANL-E site, immediately adjacent to the DuPage County Waterfall Glen Forest Preserve. The 317 Area is an active hazardous and radioactive waste processing and storage area. In the late 1950s, liquid waste was placed in the unit known as the French Drain. Since that time, this waste has migrated into underlying soil and groundwater. The principal environmental concern in the 317 Area is the presence of several VOCs in the soil and groundwater and low levels of tritium in the groundwater beneath and down gradient of the site. The 319 Area Landfill and French Drain are located immediately adjacent to the 317 Area. The principal environmental concern in the 319 Area is the presence of radioactive materials in the waste mound, in the leachate in the mound, and in the shallow groundwater immediately down gradient of the landfill. Several interim actions have already been implemented in this area, to reduce the VOC and tritium releases from these areas, as the result of the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) conducted from December 1994 through September 1996

Evaluation of Li3N accumulation in a fused LiCl/Li salt matrix

International Nuclear Information System (INIS)

Eberle, C. S.

1998-01-01

Pyrochemical conditioning of spent nuclear fuel for the purpose of final disposal is currently being demonstrated at Argonne National Laboratory (ANL), and ongoing research in this area includes the demonstration of this process on spent oxide fuel. In conjunction with this research a pilot scale of the preprocessing stage is being designed by ANL-W to demonstrate the in situ hot cell capability of the chemical reduction stage. An impurity evaluation was completed for a Li/LiCl salt matrix in the presence of spent LWR uranium oxide fuel. A simple analysis was performed in which the sources of impurities in the salt matrix were only from the cell atmosphere. Only reactions with the lithium were considered. The levels of impurities were shown to be highly sensitive system conditions. A predominance diagram for the Li-O-N system was constructed for the device, and the general oxidation, nitridation and combined reactions were calculated as a function of oxygen and nitrogen partial pressure. These calculations and hotcell atmosphere data were used to determine the total number and type of impurities expected in the salt matrix and the mass rate for the device was determined

Evaluations of 1990 PRISM design revisions

International Nuclear Information System (INIS)

Van Tuyle, G.J.; Slovik, G.C.; Chan, B.C.; Aronson, A.L.; Kennett, R.J.

1992-03-01

Analyses of the 1990 version of the PRISM Advanced Liquid Metal Reactor (ALMR) design are presented and discussed. Most of the calculations were performed using BNL computer codes, particularly SSC and MINET. In many cases, independent BNL calculations were compared against analyses presented by General Electric when they submitted the PRISM design revisions for evaluation by the Nuclear Regulatory Commission (NRC). The current PRISM design utilizes the metallic fuel developed by Argonne National Laboratory (ANL) which facilitates the passive/''inherent'' shutdown mechanism that acts to shut down reactor power production whenever the system overheats. There are a few vulnerabilities in the passive shutdown, with the most worrisome being the positive feedback from sodium density decreases or sodium voiding. Various postulated unscrammed events were examined by GE and/or BNL, and much of the analysis discussed in this report is focused on this category of events. For the most part, the BNL evaluations confirm the information submitted by General Electric. The principal areas of concern are related to the performance of the ternary metal fuel, and may be resolved as ANL continues with its fuel development and testing program

A preliminary assessment of sup(239,240)Pu concentrations in a stream near Argonne National Laboratory

International Nuclear Information System (INIS)

Singh, H.; Marshall, J.S.

1977-01-01

The plutonium levels in Sawmill Creek, a stream which flows through the site of the Argonne National Laboratory have been determined and are compared here with the environmental levels reported in related studies. The major source of artificial radioactivity in the creek is Argonne's nuclear facilities which produce low-level wastes following clean-up and dilution in the ANL sewage plant. Samples were collected within 1 mile upstream and 1 mile downstream of ANL's waste discharge into the creek. Samples consisted of filtered water, filterable solids, whole water, Cladophora sp., sunfish (gill and G.I. tracts), isopods, and sediments. Results showed that: (1) The filterable solids from the effluent water contained 99% of 239 Pu in contrast to 37% from the upstream water sample. (2) The downstream 239 Pu levels in the whole water of Sawmill Creek were much higher than those reported in related studies. (3) 239 Pu appears to be scavenged primarily by Cladophora sp. in the downstream water of the creek. (4) Fish G.I. tract and its content contained seven times more 239 Pu activity than fish gills. (U.K.)

Analytical and experimental investigations of magnetohydrodynamic flows near the entrance to a strong magnetic field

International Nuclear Information System (INIS)

Picologlou, B.F.; Reed, C.B.; Dauzvardis, P.V.; Walker, J.S.

1986-01-01

A program of analytical and experimental investigations in MHD flows has been established at Argonne National Lab. (ANL) within the framework of the Blanket Technology Program. An experimental facility for such investigations has been built and is being operated at ANL. The investigations carried out on the Argonne Liquid-Metal engineering EXperiment (ALEX) are complemented by analysis carried out at the Univ. of Illinois. The first phase of the experimental program is devoted to investigations of well-defined cases for which analytical solutions exist. Such testing will allow validation and increased confidence in the theory. Because analytical solutions exist for only a few cases, which do not cover the entire range of anticipated flow behavior, confining testing to these cases will not be an adequate validation of the theory. For this reason, this phase involves testing and a companion analytical effort aimed toward obtaining solutions for a broad range of cases, which, although simple in geometry, are believed to encompass the range of flow phenomena relevant to fusion. This parallel approach is necessary so that analysis will guide and help plan the experiments, whereas the experimental results will provide information needed to validate and/or refine the analysis

Radiation blistering of Nb implanted sequentially with helium ions of different energies (3-500 keV)

International Nuclear Information System (INIS)

Guseva, M.I.; Gusev, V.; Krasulin, U.L.; Martinenko, U.V.; Das, S.K.; Kaminsky, M.S.

1976-01-01

Cold rolled, polycrystalline niobium samples were irradiated at room temperature with 4 He + ions sequentially at 14 different energies over an energy range from 3 keV--500 keV in steps of 50 keV. The dose for each energy was chosen to give an approximately uniform concentration of helium between the implant depths corresponding to 3 keV and 500 keV. In one set of experiments the irradiations were started at the Kurchatov Institute with 3 keV 4 He + ions and extended up to 80 keV in several steps. Subsequently, the same target area was irradiated with 4 He + ions at Argonne National Laboratory (ANL) starting at 100 keV and increased to 500 keV in steps of 50 keV. Another set of irradiations were started at ANL with 500 keV 4 He + ions and continued with decreasing ion energies to 100 keV. Subsequently, the same area was irradiated at the Kurchatov Institute starting at 80 keV and continued with decreasing ion energies to 3 keV. Both sets of irradiations were completed for two different total doses, 0.5 C cm -2 and 1.0 C cm -2

An improved out-cell to in-cell rapid transfer system at the HFEF-south

International Nuclear Information System (INIS)

Bacca, J.P.; Sherman, E.K.

1990-01-01

The Argonne National Laboratory (ANL) Hot Fuel Examination Facility-South (HFEF-S), located at the ANL-West site of the Idaho National Engineering Laboratory, is currently undergoing extensive refurbishment and modifications in preparation for its use, beginning in 1991, in demonstrating remote recycling of fast reactor, metal-alloy fuel as part of the US Department of Energy liquid-metal reactor, Integral Fast Reactor (IFR) program. Included in these improvements to HFEF-S is a new, small-item, rapid transfer system (RTS). When installed, this system will enable the rapid transfer of small items from the hot-cell exterior into the argon cell (argon-gas atmosphere) of the facility without necessitating the use of time-consuming and laborious procedures. The new RTS will also provide another important function associated with HFEF-S hot-cell operation in the IFR Fuel Recycle Program; namely, the rapid insertion of clean, radioactive contamination-measuring smear paper specimens into the hot cells for area surveys, and the expedited removal of these contaminated (including alpha as well as beta/gamma contamination) smears from the argon cell for transfer to an adjacent health physics field laboratory in the facility for nuclear contamination/radiation counting

Large-scale Intelligent Transporation Systems simulation

Energy Technology Data Exchange (ETDEWEB)

Ewing, T.; Canfield, T.; Hannebutte, U.; Levine, D.; Tentner, A.

1995-06-01

A prototype computer system has been developed which defines a high-level architecture for a large-scale, comprehensive, scalable simulation of an Intelligent Transportation System (ITS) capable of running on massively parallel computers and distributed (networked) computer systems. The prototype includes the modelling of instrumented ``smart`` vehicles with in-vehicle navigation units capable of optimal route planning and Traffic Management Centers (TMC). The TMC has probe vehicle tracking capabilities (display position and attributes of instrumented vehicles), and can provide 2-way interaction with traffic to provide advisories and link times. Both the in-vehicle navigation module and the TMC feature detailed graphical user interfaces to support human-factors studies. The prototype has been developed on a distributed system of networked UNIX computers but is designed to run on ANL`s IBM SP-X parallel computer system for large scale problems. A novel feature of our design is that vehicles will be represented by autonomus computer processes, each with a behavior model which performs independent route selection and reacts to external traffic events much like real vehicles. With this approach, one will be able to take advantage of emerging massively parallel processor (MPP) systems.

Establishment of the international collaboration and licensing preparation planning for the specific design of a prototype SFR

International Nuclear Information System (INIS)

Kim, Y. G.; Joo, H. K.; Cho, C. H.; Yoo, J. W.; Lee, D. U.; Ahn, K. S.; Hwang, Y. S.

2013-05-01

The conceptual design of prototype of Gen IV SFR (PGSFR) will be early determined through the review of the international experts. After this, the technology demonstration plan and validation of fuel design will be determined in more detail. The project will be accomplished efficiently by introducing the proven technology already validated from the international collaboration. The conceptual design and its requirements of PGSFR will be reviewed by ANL, who has a lot of design experiences in the metal fueled SFR development. The collaboration with ANL has been done through Work For Others (WFO) contract, and the MOU was signed between SFRA and Terra Power(USA), and SFRA and IGCAR. The licensing issues raised during PFBR and FBTR licensing in India will be discussed and reflected into the PGSFR design by inviting the high level expert from India, for example Dr. Chetal in IGCAR. The specific design, technology validation plan and fuel development plan will be established in more detail through the annual International Technical Review Meeting (ITRM) and experimental facilities available from the international institute and companies, which will be the basis for shortening the project period and to reduce the development cost

Characterization of Wild-type and Temperature Sensitive Mutants of HSV-1 DNA Polymerase

Science.gov (United States)

1988-08-15

serum; PEI, polyethyleneimine; DEAE, diethylaminomethyl; DEAE-T~M, DEAE-Trisacryl-M chromatography resin; HAP, Hydroxyapatite PC...is currently much interest in assigjing enzymatic activities to the five unidenti- fied gene products, anl ir purifying these products to determine...mM potassium phosphate. The final purification step i n this scheme was a hydroxyapatite column from which the HSV DNA poly- merase was eluted with

Electron-cloud measurements and simulations for the APS

International Nuclear Information System (INIS)

Furman, M.A.; Pivi, M.; Harkay, K.C.; Rosenberg, R.A.

2001-01-01

We compare experimental results with simulations of the electron cloud effect induced by a positron beam at the APS synchrotron light source at ANL, where the electron cloud effect has been observed and measured with dedicated probes. We find good agreement between simulations and measurements for reasonable values of certain secondary electron yield (SEY) parameters, most of which were extracted from recent bench measurements at SLAC

Radioverdener

DEFF Research Database (Denmark)

for The Beatles. I denne indføring i Danmarks radiohistorie anlægger bogens forskere ikke kun et tilbageskuende blik. De udfolder også radioens rolle på det 21. århundredes digitale scene: Takket være podcasts og web-radio har vi ikke blot fået nye lyttervaner, vi har også fået adgang til mange af fortidens...

Precision tomographic analysis of reactor fuels

Energy Technology Data Exchange (ETDEWEB)

Lee, Yong Deok; Lee, Chang Hee; Kim, Jong Soo; Jeong, Jwong Hwan; Nam, Ki Yong

2001-03-01

For the tomographical assay, search of current status, analysis of neutron beam characteristics, MCNP code simulation, sim-fuel fabrication, neutron experiment for sim-fuel, multiaxes operation system design were done. In sensitivity simulation, the reconstruction results showed the good agreement. Also, the scoping test at ANL was very helpful for actual assay. Therefore, the results are applied for HANARO tomographical system setup and consecutive next research.

Precision tomographic analysis of reactor fuels

International Nuclear Information System (INIS)

Lee, Yong Deok; Lee, Chang Hee; Kim, Jong Soo; Jeong, Jwong Hwan; Nam, Ki Yong

2001-03-01

For the tomographical assay, search of current status, analysis of neutron beam characteristics, MCNP code simulation, sim-fuel fabrication, neutron experiment for sim-fuel, multiaxes operation system design were done. In sensitivity simulation, the reconstruction results showed the good agreement. Also, the scoping test at ANL was very helpful for actual assay. Therefore, the results are applied for HANARO tomographical system setup and consecutive next research

Computational model for superconducting toroidal-field magnets for a tokamak reactor

International Nuclear Information System (INIS)

Turner, L.R.; Abdou, M.A.

1978-01-01

A computational model for predicting the performance characteristics and cost of superconducting toroidal-field (TF) magnets in tokamak reactors is presented. The model can be used to compare the technical and economic merits of different approaches to the design of TF magnets for a reactor system. The model has been integrated into the ANL Systems Analysis Program. Samples of results obtainable with the model are presented

Studies of neutron irradiation effects at IPNS-REF

International Nuclear Information System (INIS)

Kirk, M.A.

1983-09-01

Neutron irradiation effects studies at the Radiation Effects Facility (REF) at the Intense Pulsed Neutron Source (IPNS) located at Argonne National Laboratory (ANL) are reviewed. A brief history of the development of this user facility is followed by an overview of the scientific program. Experiments unique to a spallation neutron source are covered in more detail. Future direction of research at this facility is suggested

Final Report: Experimental Investigation of Nonlinear Plasma Wake-Fields

International Nuclear Information System (INIS)

Rosenzweig, J.

1997-01-01

We discuss the exploration of the newly proposed blowout regime of the plasma wakefield accelerator and advanced photoinjector technology for linear collider applications. The plasma wakefield experiment at ANL produced several ground-breaking results in the physics of the blowout regime. The photoinjector R and D effort produced breakthroughs in theoretical, computational, and experimental methods in high brightness beam physics. Results have been published

YALINA Booster subcritical assembly modeling and analyses

International Nuclear Information System (INIS)

Talamo, A.; Gohar, Y.; Aliberti, G.; Cao, Y.; Zhong, Z.; Kiyavitskaya, H.; Bournos, V.; Fokov, Y.; Routkovskaya, C.; Sadovich, S.

2010-01-01

Full text: Accurate simulation models of the YALINA Booster assembly of the Joint Institute for Power and Nuclear Research (JIPNR)-Sosny, Belarus have been developed by Argonne National Laboratory (ANL) of the USA. YALINA-Booster has coupled zones operating with fast and thermal neutron spectra, which requires a special attention in the modelling process. Three different uranium enrichments of 90%, 36% or 21% were used in the fast zone and 10% uranium enrichment was used in the thermal zone. Two of the most advanced Monte Carlo computer programs have been utilized for the ANL analyses: MCNP of the Los Alamos National Laboratory and MONK of the British Nuclear Fuel Limited and SERCO Assurance. The developed geometrical models for both computer programs modelled all the details of the YALINA Booster facility as described in the technical specifications defined in the International Atomic Energy Agency (IAEA) report without any geometrical approximation or material homogenization. Materials impurities and the measured material densities have been used in the models. The obtained results for the neutron multiplication factors calculated in criticality mode (keff) and in source mode (ksrc) with an external neutron source from the two Monte Carlo programs are very similar. Different external neutron sources have been investigated including californium, deuterium-deuterium (D-D), and deuterium-tritium (D-T) neutron sources. The spatial neutron flux profiles and the neutron spectra in the experimental channels were calculated. In addition, the kinetic parameters were defined including the effective delayed neutron fraction, the prompt neutron lifetime, and the neutron generation time. A new calculation methodology has been developed at ANL to simulate the pulsed neutron source experiments. In this methodology, the MCNP code is used to simulate the detector response from a single pulse of the external neutron source and a C code is used to superimpose the pulse until the

Project Management Plan for the Idaho National Engineering Laboratory Waste Isolation Pilot Plant Experimental Test Program

International Nuclear Information System (INIS)

Connolly, M.J.; Sayer, D.L.

1993-11-01

EG ampersand G Idaho, Inc. and Argonne National Laboratory-West (ANL-W) are participating in the Idaho National Engineering Laboratory's (INEL's) Waste Isolation Pilot Plant (WIPP) Experimental Test Program (WETP). The purpose of the INEL WET is to provide chemical, physical, and radiochemical data on transuranic (TRU) waste to be stored at WIPP. The waste characterization data collected will be used to support the WIPP Performance Assessment (PA), development of the disposal No-Migration Variance Petition (NMVP), and to support the WIPP disposal decision. The PA is an analysis required by the Code of Federal Regulations (CFR), Title 40, Part 191 (40 CFR 191), which identifies the processes and events that may affect the disposal system (WIPP) and examines the effects of those processes and events on the performance of WIPP. A NMVP is required for the WIPP by 40 CFR 268 in order to dispose of land disposal restriction (LDR) mixed TRU waste in WIPP. It is anticipated that the detailed Resource Conservation and Recovery Act (RCRA) waste characterization data of all INEL retrievably-stored TRU waste to be stored in WIPP will be required for the NMVP. Waste characterization requirements for PA and RCRA may not necessarily be identical. Waste characterization requirements for the PA will be defined by Sandia National Laboratories. The requirements for RCRA are defined in 40 CFR 268, WIPP RCRA Part B Application Waste Analysis Plan (WAP), and WIPP Waste Characterization Program Plan (WWCP). This Project Management Plan (PMP) addresses only the characterization of the contact handled (CH) TRU waste at the INEL. This document will address all work in which EG ampersand G Idaho is responsible concerning the INEL WETP. Even though EG ampersand G Idaho has no responsibility for the work that ANL-W is performing, EG ampersand G Idaho will keep a current status and provide a project coordination effort with ANL-W to ensure that the INEL, as a whole, is effectively and

'Experience with decommissioning of research and test reactors at Argonne National Laboratory'

International Nuclear Information System (INIS)

Bhattacharyya, S.K.; Yule, T.J.; Fellhauer, C.R.; Boing, L.E.

2002-01-01

A large number of research reactors around the world have reached the end of their useful operational life. Many of these are kept in a controlled storage mode awaiting decontamination and decommissioning (D and D). At Argonne National Laboratory located near Chicago in the United States of America, significant experience has been gained in the D and D of research and test reactors. These experiences span the entire range of activities in D and D - from planning and characterization of the facilities to the eventual disposition of all waste. A multifaceted D nd D program has been in progress at the Argonne National Laboratory - East site for nearly a decade. The program consists of three elements: - D and D of nuclear facilities on the site that have reached the end of their useful life; - Development and demonstrations of technologies that help in safe and cost effective D and D; - Presentation of training courses in D and D practices. Nuclear reactor facilities have been constructed and operated at the ANL-E site since the earliest days of nuclear power. As a result, a number of these early reactors reached end-of-life long before reactors on other sites and were ready for D and D earlier. They presented an excellent set of test beds on which D and D practices and technologies could be demonstrated in environments that were similar to commercial reactors, but considerably less hazardous. As shown, four reactor facilities, plutonium contaminated glove boxes and hot cells, a cyclotron facility and assorted other nuclear related facilities have been decommissioned in this program. The overall cost of the program has been modest relative to the cost of comparable projects undertaken both in the U.S. and abroad. The safety record throughout the program was excellent. Complementing the actual operations, a set of D and D technologies are being developed. These include robotic methods of tool handling and operation, chemical and laser decontamination techniques, sensors

ANL/Star project: a new architecture for large scale theoretical physics computations

International Nuclear Information System (INIS)

Rushton, A.M.

1985-01-01

The project reported consists of two phases, each of which has goals of substantial physics content on its own. In Phase 1, we have selected Star Technologies' ST-100 as the array processor for the prototype coupled system and have installed one on a Vax 11/750 host. Our goals with this system are to institute a substantial program in computational physics at Argonne based on the power provided by this system and thereby to gain experience with both the hardware and software architecture of the ST-100. In Phase II, we propose to build a prototype consisting of two coupled array processors with shared memory to prove that this design can achieve high speed and efficiency in a readily extensible and cost-effective manner. This will implement all of the hardware and software modifications necessary to extend this design to as many as 64 (or more) nodes. In our design, we seek to minimize the changes made in the standard system hardware and software; this drastically reduces the effort required by our group to implement such a design and enables us to more readily incorporate the companies' upgrades to the array processor. It should be emphasized that our design is intended as a special purpose system for theoretical calculations; however it can be efficiently applied to a surprisingly broad class of problems. I shall discuss first the architecture of the ST-100 and then the physics program being currently implemented on a single system. Finally the proposed design of the coupled system is presented

Introduction statement at the panel discussion [contributed by James L. Snelgrove, ANL

International Nuclear Information System (INIS)

Snelgrove, James L.

1993-01-01

I just wanted to say a few words about the fuel demonstration part of the RERTR program, especially about our near-term activities. In the near-term we are considering three types of demonstrations. One of those is the irradiation of individual fuel elements in the ORR. These elements are to be essentially identical to the current ORR elements except that the enrichment will be 45% and the uranium density in the fuel meat will be somewhere in the neighborhood of 42 wt %. The exact loading hasn't been determined at this time, and preliminary work is underway to determine this. I think that I should point out that we really feel that the licensing basis is already available for what we are calling near-term fuel. That basis exists because of the extensive data obtained in the development of fuel for the ATR and for the HFIR. Those two reactors plus a few others are already making use of fuels loaded to this density at, of course, 93% enrichment. We don't see any real need from a metallurgical point of view to go through the complete demonstrations again. What we are doing though is loading this fuel with an enrichment and density which will be applicable in many cases in the near term, as it was mentioned yesterday, putting it in the ORR, burning it up, and doing a reasonable amount of post-irradiation examination. This data, we think, will be useful in licensing. Dr. Kanda mentioned in a comment earlier today that through the joint study with our program the Japanese are wanting to gain certain information from these experiments. We think that the experiments can satisfy those requirements. We would also be very interested to hear from any of the rest of you, the users, those of you who have to be concerned about gaining these licensing approvals, what sorts of information might really be needed here for any near-term work. We're planning to irradiate at least some elements to the order of, I would say, 90% burnup. Now, as it turns out in these elements at this enrichment and density, 90% burnup doesn't even surpass the burnup levels that have already been demonstrated as acceptable in the 93%-enriched fuels, and, therefore, one doesn't expect to find any swelling problems or any metallurgical-type problems at all. We will go through certain postirradiation examinations, however, but unless we see the need from some of the early parts of the examinations, we don't plan extensive metallurgical examinations. For these experiments, we would encourage participation by any fuel vendor who is interested in providing a few elements. We are not talking about many, maybe the order of two or three per vendor, which could be used in this program and would then, at least, provide a look to the rest of the world at elements made by particular vendors to particular enrichments and irradiated to good burnups. The other parts of our program in the near-term have to do with whole core demonstrations, and the one that is really planned at this time is the Ford Nuclear Reactor at the University of Michigan. The primary purpose of this demonstration is to have a core in which we can investigate the physics and safety characteristics of 20%-enriched fuel and compare them with those of the 93%-enriched cores. We will also use the data for verification of our analytical methods, so that when these methods are applied in evaluating the potential of other reactors for use of reduced-enrichment fuel, one will have increased confidence in the methods. I point out, of course, that there have been other reactors run with 20%-enriched fuel. However, that fuel was used quite awhile ago, and it's difficult today to obtain the sort of data in which we are really interested. The measurements in the FNR are planned to look at detailed flux distributions in the core and reflectors and at the ends of beam ports. It is also planned to measure the typical sorts of reactor characteristics which are always necessary to show that you're meeting your technical specifications and safety requirements.. The Ford Nuclear Reactor is an NRC licensed facility, and, as such, the University of Michigan will have to obtain licensing approval from NRC. We're hoping for the full cooperation of NRC, and we've been basically told that that will be forthcoming. We certainly don't anticipate that there are any new safety issues involved. We say te basis is there, and it's up to us, in cooperation with the University of Michigan, to demonstrate to the NRC that this is true. Out of this work will then come some documents that will be very useful as reference documents for any further near-term conversions using this type of fuel. I conclude my remarks here, and I will be happy to answer any questions

ANL stochastic-cooling experiments using the FNAL 200-MeV cooling ring

International Nuclear Information System (INIS)

Hogrefe, R.L.; Kellogg, K.D.; Konecny, R.S.; Kramer, S.L.; Simpson, J.D.; Suddeth, D.E.; Hardek, T.W.

1981-01-01

Studies of stochastic momentum cooling are being conducted on the FNAL 200-MeV Storage Ring. The specific goal of the activity is to establish confidence in the theory and simulation methods used to describe the cooling process, and to develop techniques and devices suitable for use in the antiproton-accumulation scheme now planned for construction at FNAL. A summary of the activity, including hardware design, results of experiments, comparison with theory, and implications for the antiproton accumulator are presented

ANL/Star project: a new architecture for large scale theoretical physics computations

Energy Technology Data Exchange (ETDEWEB)

Rushton, A.M.

1985-01-01

The project reported consists of two phases, each of which has goals of substantial physics content on its own. In Phase 1, we have selected Star Technologies' ST-100 as the array processor for the prototype coupled system and have installed one on a Vax 11/750 host. Our goals with this system are to institute a substantial program in computational physics at Argonne based on the power provided by this system and thereby to gain experience with both the hardware and software architecture of the ST-100. In Phase II, we propose to build a prototype consisting of two coupled array processors with shared memory to prove that this design can achieve high speed and efficiency in a readily extensible and cost-effective manner. This will implement all of the hardware and software modifications necessary to extend this design to as many as 64 (or more) nodes. In our design, we seek to minimize the changes made in the standard system hardware and software; this drastically reduces the effort required by our group to implement such a design and enables us to more readily incorporate the companies' upgrades to the array processor. It should be emphasized that our design is intended as a special purpose system for theoretical calculations; however it can be efficiently applied to a surprisingly broad class of problems. I shall discuss first the architecture of the ST-100 and then the physics program being currently implemented on a single system. Finally the proposed design of the coupled system is presented.

A fifth harmonic rf bunch monitor for the ANL-APS electron linac

International Nuclear Information System (INIS)

Nassiri, A.; Grelick, A.

1993-01-01

The function of a fifth harmonic (14.28 GHz) bunch monitor is to provide a signal which is proportional to the electron beam bunch size. The monitoring of the rf power signal at 14.28 GHz enables the operator to optimize the rf bunching of the beam at the end of the first accelerating section where the full bunching has been formed and remains mainly constant in size throughout the rest of the electron linac. A modified version of the SLAC original bunch monitor has been fabricated and its rf properties measured. This paper describes the design and the initial measurement results

A fifth harmonic RF bunch monitor for the ANL-APS electron linac

International Nuclear Information System (INIS)

Nassiri, A.; Grelick, A.

1993-01-01

The function of a fifth harmonic (14.28 GHz) bunch monitor is to provide a signal which is proportional to the electron beam bunch size. The monitoring of the rf power signal at 14.28 GHz enables the operator to optimize the rf bunching of the beam at the end of the first accelerating section where the full bunching has been formed and remains mainly constant in size throughout the rest of the electron linac. A modified version of the SLAC original bunch monitor has been fabricated and its rf properties measured. This paper describes the design and the initial measurements results

Reducing The Nuclear Danger

Science.gov (United States)

1995-10-01

off convention • Eliminate the civil use of HEU (includes RERTR ) • Reduce stockpiles of civil HEU and plutonium • Promote alternatives to the...these countries. ANL supports the Department’s Reduced Enrichment for Research and Test Reactor ( RERTR ) Program by providing the technical means to...scientists and engineers at 60 institutes in Russia, Ukraine, Kazakhstan and Belarus. The United States and Russia have agreed to pursue a joint RERTR

Low Rate Transmission of Video Signals Using Adaptive Delta Modulation.

Science.gov (United States)

1983-08-15

903-80-C-0476 / . PERFORMING ORGANIZATION NAME AND ADDRESS 10. PROGRAM ELEMENT. PROJECT, TASK AREA & WORK UNIT NUMBERS Research Foundation of CUNY on...transmitted phase, for the demodulation of the signal. AM is presently being used to transmit multilevel * symbols by vestigial or single sideband...34: Vestigial Sideband -- Duobinary 3600 4-Phase + AM 4800" 4-Phase + AM * Vestigial Sideband 8-PSK 7200 Phase and Amplitude Modulation 9600 Phase anl

Escape and transmission probabilities in cylindrical geometry

International Nuclear Information System (INIS)

Bjerke, M.A.

1980-01-01

An improved technique for the generation of escape and transmission probabilities in cylindrical geometry was applied to the existing resonance cross section processing code ROLAIDS. The algorithm of Hwang and Toppel, [ANL-FRA-TM-118] (with modifications) was employed. The probabilities generated were found to be as accurate as those given by the method previously applied in ROLAIDS, while requiring much less computer core storage and CPU time

Report to users of ATLAS, January 1998

International Nuclear Information System (INIS)

Ahmad, I.; Hofman, D.

1998-01-01

This report is aimed at informing users about the operating schedule, user policies, and recent changes in research capabilities. It covers the following subjects: (1) status of the Argonne Tandem-Linac Accelerator System (ATLAS) accelerator; (2) the move of Gammasphere from LBNL to ANL; (3) commissioning of the CPT mass spectrometer at ATLAS; (4) highlights of recent research at ATLAS; (5) Program Advisory Committee; and (6) ATLAS User Group Executive Committee

Formerly utilized MED/AEC sites remedial action program: radiological survey of the Museum of Science and Industry, 57th Street and Lake Shore Drive, Chicago, Illinois. Final report

International Nuclear Information System (INIS)

1979-02-01

From August 15, 1946 until July 15, 1953, ANL occupied part of the Museum of Science and Industry in Chicago; some handling of radioactive materials took place. In a radiation survey taken of the areas in 1977, instrument and smear surveys were made, and air and soil samples were counted. Results indicate there is no identifiable residual radioactivity remaining from MED/AEC operations during the period 1946 through 1953

Aerodynamics of Supersonic Lifting Bodies

Science.gov (United States)

1981-02-01

Correction Velocity Ratio, y = 1.4 .. ......... . . . . 38 9 Perturbation Pressure Coefficient on the Body Surface .... 41 10 Pressure Coefficient on...Secant Method and Exper.1ent ... ....... 119 40 Geometrica . :onfinmration anl 7ro)r;1Tnate Systens ....... 125 41 1pheri. •a. 1-rinites...due to pitching p contribution due to plunging 8 shock wave w wedge z contribution due to pitching about Ln 0 free stream Superscripts (c) correction

China - Nicht alles Gold, was glänzt!

OpenAIRE

Kolle, Christian

2008-01-01

Anlässlich der XXIX. olympischen Sommerspiele in Peking beschäftigt sich die August-Ausgabe der Recherche Spezial mit den zahlreichen sozialwissenschaftlichen Aspekten und Facetten, die der bevölkerungsreichste Staat der Erde zu bieten hat. Der rasante Aufstieg zur Wirtschaftsmacht innerhalb von nur drei Jahrzehnten hat dem chinesischen Staat zwar internationale Anerkennung gepaart mit ängstlicher Ehrfurcht beschert, ist aber gleichzeitig auch Ursprung einer Reihe von sozialen Problemen i...

Macrodistribution of 226Ra in the human skeleton as determined in vitro by gamma-ray spectrometry

International Nuclear Information System (INIS)

Essling, M.A.; Huff, D.R.

1976-01-01

A large number of γ-ray measurements of 226 Ra in human bone has been made both at MIT and CHR-ANL. These data are analyzed for correlations of the specific activity ratio of a bone group with other parameters, an interlaboratory comparison of the measurements, and an estimate of the errors expected when a whole-body content is calculated from the 226 Ra determination on a partial skeleton

Boes Skov 1 Udgravningsberetning

DEFF Research Database (Denmark)

Løvschal, Mette; Søndergaard, Louise; Vinter, Michael

2018-01-01

. Aktivitetsområdet rummer flere keramikrige gruber, ildsteder samt en kogestensgrube. På baggrund af keramikken kan oldtidsagrene og grubekomplekset dateres til omtrent den samme periode: yngre bronzealder-førromersk jernalder med en koncentration i førromersk jernalder periode 1. Aktivitetsområdet er tegnet i 1......:10 til 1:50, oversigtskortene er 1:75 til 1:250 og enkelte øvrige anlæg er tegnet i 1:20....

Vorhersagbarkeit einer koronaren Herzkrankheit im Rahmen einer arbeitsmedizinischen Vorsorgeuntersuchung

OpenAIRE

Berghoff, Bent Elger

2004-01-01

Angesichts der hohen Prävalenz der koronaren Herzkrankheit in der Bundesrepublik Deutschland sollte deren frühe Erkennung wesentlicher Bestandteil einer arbeitsmedizinischen Vorsorgeuntersuchung sein. Dies sollte nicht nur zum Schutz des betroffenen Arbeitnehmers geschehen, sondern auch zum Schutz Dritter, die als Folge einer unerwarteten Manifestation gefährdet werden könnten. Mehrere Gesetze und Verordnungen schreiben daher verschiedene Anlässe vor, die eine spezielle arbeitsmedizinisch...

Crevice Corrosion Behavior of 45 Molybdenum-Containing Stainless Steels in Seawater.

Science.gov (United States)

1981-12-01

Armco, Avesta Jernverks, Cabot, Carpenter Technology, Crucible, Eastern, Firth-Brown, Huntington, Jessup, Langley Alloys, and Uddeholm. 16...Department of Energy, Report ANL/OTEC-BCM-022. 7. Wallen, B., and M. Liljas, " Avesta 254 SMO - A New, High Molybdenum Stainless Steel," presented at NKM8...1977).; 11. Wallen, B., " Avesta 254 SMO - A Stainless Steel for Seawater Service," presented at the Advanced Stainless Steels for Turbine Condensors

Absence of large M1 excitations in 208Pb below 8.4 MeV

International Nuclear Information System (INIS)

Holt, R.J.; Jackson, H.E.; Laszewski, R.M.; Specht, J.R.

1979-01-01

A very high-resolution measurement of the 208 Pb(γ-n 0 ) 207 Pb reaction was performed by use of the unique picopulse and the newly-installed neutron flight paths at the ANL electron linac facility. The 7.99-MeV resonance (E/sub n/ = 610 keV) exhibited a level-level interference pattern with the 7.98-MeV, E1 resonance in 208 Pb. 1 figure

Response to ‘comment on recent modeling studies of astrocyte–neuron metabolic interactions': much ado about nothing

OpenAIRE

Mangia, Silvia; DiNuzzo, Mauro; Giove, Federico; Carruthers, Anthony; Simpson, Ian A; Vannucci, Susan J

2011-01-01

For many years, a tenet of cerebral metabolism held that glucose was the obligate energy substrate of the mammalian brain and that neuronal oxidative metabolism represented the majority of this glucose utilization. In 1994, Pellerin and Magistretti formulated the astrocyte–neuron lactate shuttle (ANLS) hypothesis, in which astrocytes, not neurons, metabolized glucose, with subsequent transport of the glycolytically derived lactate to fuel the energy needs of the neuron during neurotransmissio...