Los Alamos National Laboratory Yucca Mountain Site Characterization Project 1994 quality program status report

Energy Technology Data Exchange (ETDEWEB)

Bolivar, S.L.

1996-03-01

This status report is for calendar year 1994. It summarizes the annual activities and accomplishments of the Los Alamos National Laboratory Yucca Mountain Site Characterization Project (YMP or Project) quality assurance program. By identifying the accomplishments of the quality program, a baseline is established that will assist in decision making, improve administrative controls and predictability, and allow us to annually identify adverse trends and to evaluate improvements. This is the fourth annual status report.

Los Alamos National Laboratory Yucca Mountain Site Characterization Project 1993 Quality Program status report

International Nuclear Information System (INIS)

Boliver, S.L.

1995-05-01

This status report is for calendar year 1993. It summarizes the annual activities and accomplishments of the Los Alamos National Laboratory (Los Alamos) Yucca Mountain Site Characterization Project (YMP or Project) quality assurance program. By identifying the accomplishments of the quality program, we establish a baseline that will assist in decision making, improve administrative controls and predictability, and allow us to annually identify long term trends and to evaluate improvements. This is the third annual status report (Bolivar, 1992; Bolivar, 1994). This report is divided into two primary sections: Program Activities and Trend Analysis. Under Program Activities, programmatic issues occurring in 1993 are discussed. The goals for 1993 are also listed, followed by a discussion of their status. Lastly, goals for 1994 are identified. The Trend Analysis section is a summary of 1993 quarterly trend reports and provides a good overview of the quality assurance issues of the Los Alamos YMP

Los Alamos National Laboratory Yucca Mountain Site Characterization Project 1993 Quality Program status report

Energy Technology Data Exchange (ETDEWEB)

Bolivar, S.L.

1995-05-01

This status report is for calendar year 1993. It summarizes the annual activities and accomplishments of the Los Alamos National Laboratory (Los Alamos) Yucca Mountain Site Characterization Project (YMP or Project) quality assurance program. By identifying the accomplishments of the quality program, we establish a baseline that will assist in decision making, improve administrative controls and predictability, and allow us to annually identify long term trends and to evaluate improvements. This is the third annual status report (Bolivar, 1992; Bolivar, 1994). This report is divided into two primary sections: Program Activities and Trend Analysis. Under Program Activities, programmatic issues occurring in 1993 are discussed. The goals for 1993 are also listed, followed by a discussion of their status. Lastly, goals for 1994 are identified. The Trend Analysis section is a summary of 1993 quarterly trend reports and provides a good overview of the quality assurance issues of the Los Alamos YMP.

Software quality assurance on the Yucca Mountain Site Characterization Project

International Nuclear Information System (INIS)

Matras, J.R.

1993-01-01

The Yucca Mountain Site Characterization Project (YMP) has been involved over the years in the continuing struggle with establishing acceptable Software Quality Assurance (SQA) requirements for the development, modification, and acquisition of computer programs used to support the Mined Geologic Disposal System. These computer programs will be used to produce or manipulate data used directly in site characterization, design, analysis, performance assessment, and operation of repository structures, systems, and components. Scientists and engineers working on the project have claimed that the SQA requirements adopted by the project are too restrictive to allow them to perform their work. This paper will identify the source of the original SQA requirements adopted by the project. It will delineate the approach used by the project to identify concerns voiced by project engineers and scientists regarding the original SQA requirements. It will conclude with a discussion of methods used to address these problems in the rewrite of the original SQA requirements

Ympärileikatun naisen raskausajan ja synnytyksen hoito : hoidon ja seksuaaliohjauksen kulmakivet terveydenhuollon ammattihenkilöille

OpenAIRE

Ryhänen, Marjo; Savinainen, Oona; Suokas, Saana

2016-01-01

Naisten ympärileikkaus eli sukupuolielinten silpominen tarkoittaa kaikkia niitä toimenpiteitä, joissa ulkoiset synnytyselimet poistetaan joko osittain tai kokonaan muun kuin lääketieteellisen syyn takia. Syy naisten ympärileikkaukseen ei tule uskonnosta vaan täysin perinteistä, joiden mukaan nainen ei olisi säädyllinen ilman ympärileikkausta. Tämän hetkinen tilasto osoittaa noin 130 miljoonan tytön tai naisen olevan ympärileikattu. Naisten ympärileikkaus aiheuttaa lukuisia terveyshaittoja nai...

Ympäristövastuu Pohjois-Savon Osuuspankissa

OpenAIRE

Karjalainen, Toni

2012-01-01

Opinnäytetyön tarkoituksena oli tarkastella ekologisesta näkökulmasta kuinka ympäristövastuu toteutuu Pohjois-Savon Osuuspankissa. Tarkastelun kohteena oli tutkia, mitä ympäristövastuun eteen on jo tehty ja millaisia toimia on mahdollista vielä tehdä. Tutkimuksen kohteena oli myös selvittää mitä arvoa Green Office – ohjelmasta on ja miten sen käyttöönotto toteutuu. Tutkimus toteutettiin kahdessa osassa. Ensin lähettiin sähköpostilla strukturoitu kysely neljälle henkilölle, joista jokaisel...

ISO 14001 -standardin mukaisen ympäristöjärjestelmän luominen : case: Plastep Oy

OpenAIRE

Harju, Siiri

2016-01-01

Opinnäytetyön tavoitteena oli luoda kattavan ympäristökartoituksen sisältävä ISO 14001 -standardin mukainen ympäristöjärjestelmä Plastep Oy:lle. Lisäksi tarkoituksena oli suunnitella yrityksen ympäristönsuojelun tilaa mahdollisimman luotettavasti kuvaava ympäristömittari sekä tarkastella muovin ruiskuvaluyritykseen kohdistuvia tulevaisuuden näkymiä ympäristönsuojelun näkökulmasta. Opinnäytetyössä esitellään ISO 14001 -ympäristöjärjestelmä sekä kyseisen standardin sisältä...

Yucca Mountain Site Characterization Project Waste Package Plan

International Nuclear Information System (INIS)

Harrison-Giesler, D.J.; Jardine, L.J.

1991-02-01

The goal of the US Department of Energy's (DOE) Yucca Mountain Site Characterization Project (YMP) waste package program is to develop, confirm the effectiveness of, and document a design for a waste package and associated engineered barrier system (EBS) for spent nuclear fuel and solidified high-level nuclear waste (HLW) that meets the applicable regulatory requirements for a geologic repository. The Waste Package Plan describes the waste package program and establishes the technical approach against which overall progress can be measured. It provides guidance for execution and describes the essential elements of the program, including the objectives, technical plan, and management approach. The plan covers the time period up to the submission of a repository license application to the US Nuclear Regulatory Commission (NRC). 1 fig

Ympäristömyötäinen tekstiilituotemallisto lapsille

OpenAIRE

Jääskeläinen, Heidi

2009-01-01

Opinnäytetyön tavoitteena oli tarkastella tekstiilien ympäristömyötäistä suunnittelua ja luoda sen mukainen uniikki tekstiilituotemallisto lapsille. Tuotteet suunniteltiin opintojen päätyttyä aloitettavan yritystoiminnan alkumallistoksi. Opinnäytetyön teoriaosuus jakautuu kolmeen osaan: ympäristömyötäiseen suunnitteluun, tuotesuunnitteluun ja tuotannonsuunnitteluun. Kutakin teoriaosuutta käsitellään opinnäytetyön suunnitteluprojektin näkökulmasta. Opinnäytetyön yhteydessä toteutettiin päi...

GENISES: A GIS Database for the Yucca Mountain Site Characterization Project

International Nuclear Information System (INIS)

Beckett, J.

1991-01-01

This paper provides a general description of the Geographic Nodal Information Study and Evaluation System (GENISES) database design. The GENISES database is the Geographic Information System (GIS) component of the Yucca Mountain Site Characterization Project Technical Database (TDB). The GENISES database has been developed and is maintained by EG ampersand G Energy Measurements, Inc., Las Vegas, NV (EG ampersand G/EM). As part of the Yucca Mountain Project (YMP) Site Characterization Technical Data Management System, GENISES provides a repository for geographically oriented technical data. The primary objective of the GENISES database is to support the Yucca Mountain Site Characterization Project with an effective tool for describing, analyzing, and archiving geo-referenced data. The database design provides the maximum efficiency in input/output, data analysis, data management and information display. This paper provides the systematic approach or plan for the GENISES database design and operation. The paper also discusses the techniques used for data normalization or the decomposition of complex data structures as they apply to GIS database. ARC/INFO and INGRES files are linked or joined by establishing ''relate'' fields through the common attribute names. Thus, through these keys, ARC can allow access to normalized INGRES files greatly reducing redundancy and the size of the database

Data Qualification Report For: Thermodynamic Data File, DATA0.YMP.R0 For Geochemical Code, EQ3/6?

International Nuclear Information System (INIS)

P.L. Cloke

2000-09-01

The objective of this work is to evaluate the adequacy of chemical thermodynamic data provided by Lawrence Livermore National Laboratory (LLNL) as DataO.ymp.ROA in response to an input request submitted under AP-3.14Q. This request specified that chemical thermodynamic data available in the file, Data0.com.R2, be updated, improved, and augmented for use in geochemical modeling used in Process Model Reports (PMRs) for Engineered Barrier Systems, Waste Form, Waste Package, Unsaturated Zone, and Near Field Environment, as well as for Performance Assessment. The data are qualified in the temperature range 0 to 100 C. Several Data Tracking Numbers (DTNs) associated with Analysis/Model Reports (AMR) addressing various aspects of the post-closure chemical behavior of the waste package and the Engineered Barrier System that rely on EQ316 outputs to which these data are used as input, are Principal Factor affecting. This qualification activity was accomplished in accordance with the AP-SIII.2Q using the Technical Assessment method. A development plan, TDP-EBS-MD-000044, was prepared in accordance with AP-2.13Q and approved by the Responsible Manager. In addition, a Process Control Evaluation was performed in accordance with AP-SV.1Q. The qualification method, selected in accordance with AP-SIII.2Q, was Technical Assessment. The rationale for this approach is that the data in File Data0.com.R2 are considered Handbook data and therefore do not themselves require qualification. Only changes to Data0.com.R2 required qualification. A new file has been produced which contains the database Data0.ymp.R0, which is recommended for qualification as a result of this action. Data0.ymp.R0 will supersede Data0.com.R2 for all Yucca Mountain Project (YMP) activities

Multitasking domain decomposition fast Poisson solvers on the Cray Y-MP

Science.gov (United States)

Chan, Tony F.; Fatoohi, Rod A.

1990-01-01

The results of multitasking implementation of a domain decomposition fast Poisson solver on eight processors of the Cray Y-MP are presented. The object of this research is to study the performance of domain decomposition methods on a Cray supercomputer and to analyze the performance of different multitasking techniques using highly parallel algorithms. Two implementations of multitasking are considered: macrotasking (parallelism at the subroutine level) and microtasking (parallelism at the do-loop level). A conventional FFT-based fast Poisson solver is also multitasked. The results of different implementations are compared and analyzed. A speedup of over 7.4 on the Cray Y-MP running in a dedicated environment is achieved for all cases.

Cost estimate of high-level radioactive waste containers for the Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

Russell, E.W.; Clarke, W. [Lawrence Livermore National Lab., CA (United States); Domian, H.A. [Babcock and Wilcox Co., Lynchburg, VA (United States); Madson, A.A. [Kaiser Engineers California Corp., Oakland, CA (United States)

1991-08-01

This report summarizes the bottoms-up cost estimates for fabrication of high-level radioactive waste disposal containers based on the Site Characterization Plan Conceptual Design (SCP-CD). These estimates were acquired by Babcock and Wilcox (B&S) under sub-contract to Lawrence Livermore National Laboratory (LLNL) for the Yucca Mountain Site Characterization Project (YMP). The estimates were obtained for two leading container candidate materials (Alloy 825 and CDA 715), and from other three vendors who were selected from a list of twenty solicited. Three types of container designs were analyzed that represent containers for spent fuel, and for vitrified high-level waste (HLW). The container internal structures were assumed to be AISI-304 stainless steel in all cases, with an annual production rate of 750 containers. Subjective techniques were used for estimating QA/QC costs based on vendor experience and the specifications derived for the LLNL-YMP Quality Assurance program. In addition, an independent QA/QC analysis is reported which was prepared by Kasier Engineering. Based on the cost estimates developed, LLNL recommends that values of $825K and $62K be used for the 1991 TSLCC for the spent fuel and HLW containers, respectively. These numbers represent the most conservative among the three vendors, and are for the high-nickel anstenitic steel (Alloy 825). 6 refs., 7 figs.

Cost estimate of high-level radioactive waste containers for the Yucca Mountain Site Characterization Project

International Nuclear Information System (INIS)

Russell, E.W.; Clarke, W.; Domian, H.A.; Madson, A.A.

1991-08-01

This report summarizes the bottoms-up cost estimates for fabrication of high-level radioactive waste disposal containers based on the Site Characterization Plan Conceptual Design (SCP-CD). These estimates were acquired by Babcock and Wilcox (B ampersand S) under sub-contract to Lawrence Livermore National Laboratory (LLNL) for the Yucca Mountain Site Characterization Project (YMP). The estimates were obtained for two leading container candidate materials (Alloy 825 and CDA 715), and from other three vendors who were selected from a list of twenty solicited. Three types of container designs were analyzed that represent containers for spent fuel, and for vitrified high-level waste (HLW). The container internal structures were assumed to be AISI-304 stainless steel in all cases, with an annual production rate of 750 containers. Subjective techniques were used for estimating QA/QC costs based on vendor experience and the specifications derived for the LLNL-YMP Quality Assurance program. In addition, an independent QA/QC analysis is reported which was prepared by Kasier Engineering. Based on the cost estimates developed, LLNL recommends that values of $825K and $62K be used for the 1991 TSLCC for the spent fuel and HLW containers, respectively. These numbers represent the most conservative among the three vendors, and are for the high-nickel anstenitic steel (Alloy 825). 6 refs., 7 figs

Data Qualification Report For: Thermodynamic Data File, DATA0.YMP.R0 For Geochemical Code, EQ3/6 

Energy Technology Data Exchange (ETDEWEB)

P.L. Cloke

2001-10-16

The objective of this work is to evaluate the adequacy of chemical thermodynamic data provided by Lawrence Livermore National Laboratory (LLNL) as DataO.ymp.ROA in response to an input request submitted under AP-3.14Q. This request specified that chemical thermodynamic data available in the file, Data0.com.R2, be updated, improved, and augmented for use in geochemical modeling used in Process Model Reports (PMRs) for Engineered Barrier Systems, Waste Form, Waste Package, Unsaturated Zone, and Near Field Environment, as well as for Performance Assessment. The data are qualified in the temperature range 0 to 100 C. Several Data Tracking Numbers (DTNs) associated with Analysis/Model Reports (AMR) addressing various aspects of the post-closure chemical behavior of the waste package and the Engineered Barrier System that rely on EQ316 outputs to which these data are used as input, are Principal Factor affecting. This qualification activity was accomplished in accordance with the AP-SIII.2Q using the Technical Assessment method. A development plan, TDP-EBS-MD-000044, was prepared in accordance with AP-2.13Q and approved by the Responsible Manager. In addition, a Process Control Evaluation was performed in accordance with AP-SV.1Q. The qualification method, selected in accordance with AP-SIII.2Q, was Technical Assessment. The rationale for this approach is that the data in File Data0.com.R2 are considered Handbook data and therefore do not themselves require qualification. Only changes to Data0.com.R2 required qualification. A new file has been produced which contains the database Data0.ymp.R0, which is recommended for qualification as a result of this action. Data0.ymp.R0 will supersede Data0.com.R2 for all Yucca Mountain Project (YMP) activities.

Työympäristön vaikutus toimistotyöntekijän tuottavuuteen

OpenAIRE

Bågman, Tomas

2012-01-01

Opinnäytetyössä tutkittiin fyysisten ympäristötekijöiden vaikutuksia toimistotyötä tekevän työntekijän tuottavuuteen ja suunniteltiin Pikval Oy:n suunnitteluosastolle uusi layout. Työntekijän tuottavuuteen vaikuttavia asioita ympäristön suhteen ovat rakennus, sisäilmasto, akustiset olot, valaistus ja niiden alaosiot. Melu ja keskeytykset osoittautuivat olevan merkittäviä tuottavuuteen vaikuttavia tekijöitä joihin tulisi kiinnittää huomiota toimiston layoutia suunnitellessa. Avoin ...

Yucca Mountain Site Characterization Project exploratory studies facilities construction status

International Nuclear Information System (INIS)

Allan, J.N.; Leonard, T.M.

1993-01-01

This paper discusses the progress to date on the construction planning and development of the Yucca Mountain Site Characterization Project (YMP) Exploratory Studies Facilities (ESF). The purpose of the ESF is to determine early site suitability and to characterize the subsurface of the Yucca Mountain site to assess its suitability for a potential high level nuclear waste repository. The present ESF configuration concept is for two main ramps to be excavated by tunnel boring machines (TBM) from the surface to the Topopah Spring Member of the Paintbrush Tuff Formation. From the main ramps, slightly above Topopah Spring level, supplemental ramps will be penetrated to the Calico Hills formation below the potential repository. There will be exploratory development drifts driven on both levels with the Main Test Area being located on the Topopah Spring level, which is the level of the proposed repository. The Calico Hills formation lies below the Topopah Spring member and is expected to provide the main geo-hydrologic barrier between the potential repository and the underlying saturated zones in the Crater Flat Tuff

Puupilkkeiden ympärivuotisen valmistuksen kannattavuus : Case Yritys X

OpenAIRE

Haaranen, Niina

2013-01-01

Opinnäytetyössä selvitettiin yritykselle taloudellisesti kannattavin toimintavaihtoehto, jotta yrityksessä voidaan luopua metsäkoneurakoinnista ja keskittyä puupilkkeiden valmistukseen ja myyntiin ympärivuotisesti. Työssä tavoiteltiin luotettavaa ja toteuttamiskelpoista ratkaisua päätöksentekotilanteeseen. Yrityksen eri toimintavaihtoehtoja lähestyttiin ensiksi perehtymällä kannattavuuslaskennan teoriaan: investointi- ja kustannuslaskentaan sekä hinnoitteluun ja katetuottolaskentaan. Tämä...

Technical data base quarterly report, April--June 1992; Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-09-01

The acquisition and development of technical data are activities that provide the information base from which the Yucca mountain Site will be characterized and may P-ventually be licensed as a high-level waste repository. The Project Technical Data Base (TDB) is the repository for the regional and site-specific technical data required in intermediate and license application analyses and models. The TDB Quarterly Report provides the mechanism for identifying technical data currently available from the Project TDB. Due to the variety of scientific information generated by YMP activities, the Project TDB consists of three components, each designed to store specific types of data. The Site and Engineering Properties Data Base (SEPDB) maintains technical data best stored in a tabular format. The Geographic Nodal Information Study and Evaluation System (GENISES), which is the Geographic Information System (GIS) component of the Project TDB, maintains spatial or map-like data. The Geologic and Engineering Materials Bibliography of Chemical Species (GEMBOCHS) data base maintains thermodynamic/geochemical data needed to support geochemical reaction models involving the waste package and repository geochemical environment. Each of these data bases are addressed independently within the TDB Quarterly Report.

Project control - the next generation

International Nuclear Information System (INIS)

Iorii, V.F.; McKinnon, B.L.

1993-01-01

The Yucca Mountain Site Characterization Project (YMP) is the U.S. Department of Energy's (DOE) second largest Major System Acquisition Project. We have developed an integrated planning and control system (called PACS) that we believe represents the 'Next Generation' in project control. PACS integrates technical scope, cost, and schedule information for over 50 participating organizations and produces performances measurement reports for science and engineering managers at all levels. Our 'Next Generation' project control too, PACS, has been found to be in compliance with the new DOE Project Control System Guidelines. Additionally, the nuclear utility oversight group of the Edison Electric Institute has suggested PACS be used as a model for other civilian radioactive waste management projects. A 'Next Generation' project control tool will be necessary to do science in the 21st century

Perfluorattujen alkyyliaineiden (PFAS) aiheuttamat ympäristöriskit Suomessa

OpenAIRE

Korkki, Kati

2006-01-01

Perfluoratut alkyyliaineet (PFAS) ovat laaja ryhmä kemikaaleja, joita on käytetty 1950-luvulta saakka teollisuudessa ja kuluttajatuotteissa. 1990-luvun lopulla tuli ilmi, että osa PFAS-aineista on levinnyt ympäristöön ja eliöihin maailmanlaajuisesti. Eniten esillä ollut PFAS-aine, PFOS eli perfluoro-oktaanisulfonaatti, on pysyvä, biokertyvä ja toksinen. Myös pitkäketjuiset perfluorokarboksyylihapot, kuten PFOA eli perfluoro-oktaanihappo, ovat pysyviä ja biokertyviä. Tutkielman tavoitteena oli...

Determination of Importance Evaluation for the ESF Enhanced Characterization of the Repository Block Cross Drift

International Nuclear Information System (INIS)

S. Goodin

2002-01-01

The objective of this DIE is to determine whether the ECRB-Cross-Drift-related activities, as identified in Section 6.0, could potentially impact (1) Yucca Mountain Site Characterization Project (YMP) testing or (2) the waste isolation capabilities of a potential repository at the Yucca Mountain site. Any controls necessary to limit such potential impacts are also identified herein

Mechanical and bulk properties of intact rock collected in the laboratory in support of the Yucca Mountain Site Characterization Project

International Nuclear Information System (INIS)

Price, R.H.; Martin, R.J. III; Boyd, P.J.; Boinott, G.N.

1994-01-01

A comprehensive laboratory investigation is determining the mechanical properties of tuffs for the Yucca Mountain Site Characterization Project (YMP). Most recently, experiments have been performed on tuff samples from a series of drill holes along the planned alignment of the Exploratory Study Facilities (ESF) north ramp. Unconfined compression and indirect tension experiments were performed and the results are being analyzed with the help of bulk property information. The results on samples from eight of the drill holes are presented. In general, the properties vary widely, but are highly dependent on the sample porosity. The developed relationships between mechanical properties and porosity are powerful tools in the effort to model the rock mass response of Yucca Mountain to the emplacement of the potential high-level radioactive waste repository

Ympäristöystävällisyys puhdistusaineiden hankinnassa : vuoropuhelun kautta vertailuperusteet määrittelyyn

OpenAIRE

Merta, Anne

2013-01-01

Tämän opinnäytetyön tavoitteena on selvittää miten julkisen sektorin pesu- ja puhdistusaineiden hankinnoissa voisi lisätä ympäristöystävällisyyttä. Tutkimuksessa pyritään selvittämään miten pesu- ja puhdistusaineita markkinoivien yritysten mielestä ympäristönäkökohtia koskevaa vuoropuhelua käydään julkisen sektorin hankintayksiköiden kanssa, mitä se sisältää, mitä hyötyä vuoropuhelun käymisestä on, ja miten sitä yrityksien mielestä voisi kehittää. Lisäksi tutkimuksessa halutaan selvittää, mit...

Alternative strategies: A means for saving money and time on the Yucca Mountain Project

International Nuclear Information System (INIS)

Wilder, D.G.

1993-01-01

The United States Department of Energy (DOE) is undertaking studies to determine the suitability of Yucca Mountain (YM) as a potential site for disposal of high level nuclear waste. Yucca Mountain is located in an arid environment. Many processes that could contribute to mobilization of radionuclides are either absent or minimized in a dry site. Therefore, Yucca Mountain should have the potential of being a veryfavorable site for disposal of waste. The determination of suitability has no precedence, and the characterization of an and site is complex, requiring intensive studies to determine suitability. The studies undertaken by the Yucca Mountain Site Characterization Project (YMP) are very costly. By a process called performance allocation, the YMP determined strategies to satisfy regulations or meet performance while minimizing costs and schedules. Those involved recognized that allocations should be reviewed as additional information became available. The allocation has not been reviewed nor revised since the initial allocation in the Site Characterization Plan (SCP). The purpose of this paper is to outline alternative allocations that the author feels should be considered based on the additional information that is available at this time

Recent developments in the integrated approach toward characterization of radionuclide transport, Yucca Mountain, Nevada

International Nuclear Information System (INIS)

Simmons, A.M.; Canepa, J.A.

1992-01-01

The radionuclide migration program for the Yucca Mountain Site Characterization Project (YMP) includes studies of radionuclide solubility, sorption, diffusion, and transport. The study plans incorporate all possible parameters of investigation; decision-making strategies for prioritizing the parameters and evaluating their significance were developed in conjunction with the study plans. After definition of explicit research goals for each study, YMP evaluated the applicability of existing data and formulated experimental approaches for obtaining additional data. This resulted in development of individual testing strategies that were integrated into an overall strategy for the radionuclide migration program designed to provide input to credible performance assessments. The strategies allow for decision points at various steps of data collection and testing. They provide a streamlined process toward a defensible level of understanding of chemical retardation and transport processes that will be used to predict the mountain's ability to isolate waste. (author)

Tunneling progress on the Yucca Mountain Project

International Nuclear Information System (INIS)

Hansmire, W.H.; Munzer, R.J.

1996-01-01

The current status of tunneling progress on the Yucca Mountain Project (YMP) is presented in this paper. The Exploratory Studies Facility (ESF), a key part of the YMP, has been long in development and construction is ongoing. This is a progress report on the tunneling aspects of the ESF as of January 1, 1996. For purposes of discussion in this summary, the tunneling has progressed in four general phases. The paper describes: tunneling in jointed rock under low stress; tunneling through the Bow Ridge Fault and soft rock; tunneling through the Imbricate Fault Zone; and Tunneling into the candidate repository formation

Logiikkaohjelmien kirjaston luominen STEP 7 -ympäristöön

OpenAIRE

Perälä, Toni

2013-01-01

Tämän opinnäytetyön toimeksiantajana toimi PLC-Automation Oy. Työn tavoitteena oli luoda yrityksen yhteiseen käyttöön logiikkaohjelmien kirjasto STEP 7 -ympäristöön. Työhön kuului myös käyttöohjeiden kirjoittaminen kerätyille ohjelmille. Päämääränä oli luoda yrityksen käyttöön mahdollisimman kattava logiikkaohjelmien kirjasto. Kirjaston materiaali kerättiin yrityksessä STEP 7:n parissa työskenteleviltä työntekijöiltä sekä itsenäisesti yrityksen projekteista. Kirjaston sisältö rakennettiin yr...

Characterization of surface processes on mineral surfaces in aqueous solutions. Annual report for fiscal year 1993

International Nuclear Information System (INIS)

Leckie, J.O.

1993-11-01

Performance assessments by Los Alamos National Laboratory for the DOE's Yucca Mountain Site Characterization Project (YMP) are being done investigating the environmental risk related to long-term disposal of hazardous wastes resulting from the use of radioactive materials that must subsequently be isolated from the environment. The YMP site, located in southwestern Nevada, is intended for the storage of high-level wastes generated by nuclear energy-related activities, including spent fuel and waste from reprocessed fuel rods. The work covered by this contract is necessary for producing a defensible model and dataset, and may be critical for evaluation of repository compliance. This work, performed by the Environmental Engineering and Science research group at Stanford University, will quantify the adsorption of uranyl on various minerals. The project's principle objective is to provide sorption coefficients for uranyl and other ions of interest to predict radionuclide movements form the repository to accessible environments. This adsorption data is essential for the unambiguous interpretation of field experiments and observations. In this report, details of the activity and progress made with respect to the study of uranyl adsorption on mineral surfaces is presented and discussed

Digitaalisen markkinoinnin keinoja internetin vuorovaikutteisessa ympäristössä : markkinointiresurssien suuntaaminen internetissä

OpenAIRE

Ellonen, Niko

2013-01-01

Tämä opinnäytetyö keskittyy digitaaliseen markkinointiin ja markkinointiresurssien suuntaamiseen internetin vuorovaikutteisessa ympäristössä. Markkinointi on myynnin kasvua tukeva toiminto, jonka tavoitteena on luoda ja tuottaa asiakkaille arvoa ja hallita asiakassuhteita tavoilla, jotka hyödyttävät yritystä ja sen sidosryhmiä. Digitaalinen markkinointi on digitaalisessa muodossa tai mediassa tehtyä markkinointia. Tutkimuksen alussa käsitellään ensin yleisesti markkinoinnin määritelmää ...

Site characterization progress report, Yucca Mountain, Nevada. Number 19, April 1, 1998 - September 30, 1998

International Nuclear Information System (INIS)

1999-06-01

The nineteenth semiannual report of the Yucca Mountain Site Characterization Project (YMP) summarizes activities during the period from April 1, 1998, through September 30, 1998. Project activities are aimed at evaluating Yucca Mountain as a potential location for permanent geologic disposal of nuclear materials, as directed by the Nuclear Waste Policy Act of 1982, as amended (NWPA). The progress report documents activities this period that contribute to completing the Project's near-term programmatic and statutory objectives. These objectives include completing the Viability Assessment, the Environmental Impact Statement (EIS), a possible US Department of Energy (DOE) Secretarial Site Recommendation to the President, and, if the site is suitable, submittal of a license application to the US Nuclear Regulatory Commission (NRC). Project work this period continued to be concentrated in three integrated activities: site characterization, engineering design and construction, and performance assessment. Accomplishments this period and their relation to near-term objectives are briefly summarized

Design considerations for the Yucca Mountain project exploratory shaft facility

International Nuclear Information System (INIS)

Bullock, R.L. Sr.

1990-01-01

This paper reports on the regulatory/requirements challenges of this project which exist because this is the first facility of its kind to ever be planned, characterized, designed, and built under the purview of a U.S. Nuclear Regulatory Agency. The regulations and requirements that flow down to the Architect/Engineer (A/E) for development of the Exploratory Shaft Facility (ESF) design are voluminous and unique to this project. The subsurface design and construction of the ESF underground facility may eventually become a part of the future repository facility and, if so, will require licensing by the Nuclear Regulatory Commission (NRC). The Fenix and Scisson of Nevada-Yucca Mountain Project (FSN-YMP) group believes that all of the UMP design and construction related activities, with good design/construct control, can be performed to meet all engineering requirements, while following a strict quality assurance program that will also meet regulatory requirements

Pala-animaatiohahmojen animointi 2D- ja 3D-ympäristössä

OpenAIRE

Koivisto, Ida

2011-01-01

Opinnäytetyö käsittelee hahmoanimointia digitaalisessa pala-animaatiossa. Työssä keskitytään pääasiassa vertailemaan keskenään kahta hyvin erityyppistä ohjelmaa hahmoanimaattorin työskentely-ympäristöinä. Ohjelmat, joita opinnäytetyössä on käytetty animoimiseen, ovat 3D-ohjelma Cinema 4D sekä 2D-2.5D -ohjelma After Effects. Opinnäytetyö on kirjoitettu hahmoanimaattorin näkökulmasta perustuen käytännön animointityöskentelyyn lasten animaatiosarjassa Ella & Aleksi. Työn tekijä on toiminut p...

Characterizing harmful advanced glycation end-products (AGEs) and ribosylated aggregates of yellow mustard seed phytocystatin: Effects of different monosaccharides

Science.gov (United States)

Ahmed, Azaj; Shamsi, Anas; Bano, Bilqees

2017-01-01

Advanced glycation end products (AGEs) are at the core of variety of diseases ranging from diabetes to renal failure and hence gaining wide consideration. This study was aimed at characterizing the AGEs of phytocystatin isolated from mustard seeds (YMP) when incubated with different monosaccharides (glucose, ribose and mannose) using fluorescence, ultraviolet, circular dichroism (CD) spectroscopy and microscopy. Ribose was found to be the most potent glycating agent as evident by AGEs specific fluorescence and absorbance. YMP exists as a molten globule like structure on day 24 as depicted by high ANS fluorescence and altered intrinsic fluorescence. Glycated YMP as AGEs and ribose induced aggregates were observed at day 28 and 32 respectively. In our study we have also examined the anti-aggregative potential of polyphenol, resveratrol. Our results suggested the anti-aggregative behavior of resveratrol as it prevented the in vitro aggregation of YMP, although further studies are required to decode the mechanism by which resveratrol prevents the aggregation.

Los Alamos National Laboratory Yucca Mountain Site Characterization Project 1992 quality program status report

International Nuclear Information System (INIS)

Bolivar, S.L.; Burningham, A.; Chavez, P.

1994-03-01

This status report summarizes the activities and accomplishments of the Los Alamos Yucca Mountain Site Characterization Project's quality assurance program for calendar year 1992. The report includes major sections on Program Activities and Trend Analysis. Program Activities are discussed periodically at quality meetings. The most significant issue addressed in 1992 has been the timely revision of quality administrative procedures. The procedure revision process was streamlined from 55 steps to 7. The number of forms in procedures was reduced by 38%, and the text reduced by 29%. This allowed revision in 1992 of almost half of all implementing procedures. The time necessary to complete the revision process (for a procedure) was reduced from 11 months to 3 months. Other accomplishments include the relaxation of unnecessarily strict training requirements, requiring quality assurance reviews only from affected organizations, and in general simplifying work processes. All members of the YMP received training to the new Orientation class Eleven other training classed were held. Investigators submitted 971 records to the Project and only 37 were rejected. The software program has 115 programs approved for quality-affecting work. The Project Office conducted 3 audits and 1 survey of Los Alamos activities. We conducted 14 audits and 4 surveys. Eight corrective action reports were closed, leaving only one open. Internally, 22 deficiencies were recognized. This is a decrease from 65 in 1991. Since each deficiency requires about 2 man weeks to resolve, the savings are significant. Problems with writing acceptable deficiency reports have essentially disappeared. Trend reports for 1992 were examined and are summarized herein. Three adverse trends have been closed; one remaining adverse trend will be closed when the affected procedures are revised. The number of deficiencies issued to Los Alamos compared to other participants is minimal

Science education beyond the classroom

International Nuclear Information System (INIS)

Harle, E.J.; Van Natta, D.; Powell, M.L.

1993-01-01

The Yucca Mountain Site Characterization Project (YMP) sponsors a variety of classroom-oriented projects and activities for teachers who request them. Also available, though, are extra-curricular programs. One notably successful program is a workshop designed to award girl and boy scouts with geology and atomic energy merit badges. There was a tremendous response to this workshop--it attracted 450 requests within the first week of its announcement. Since October 1991, the YMP has sponsored five such girl scout workshops and four boy scout workshops, attended by a total of 400 scouts. These workshops demonstrate that highly technical subjects can be taught simply through hands-on activities. The idea behind them is not to teach scouts what to think but, rather, how to think. For adults meanwhile, the YMP offers a monthly lecture series, with each lecture averaging 45 minutes in length with 35 people in attendance. These lectures center on such subjects as volcanoes, earthquakes and hydrology. They are usually delivered by YMP technical staff members, who have learned that complex technical issues are best addressed in a small-group format

Advertising public outreach--going where the people are

International Nuclear Information System (INIS)

Bradford, D.; Burns, D.

1994-01-01

In a continuing effort to invite new and larger segments of the public to participate in Yucca Mountain Site Characterization Project (YMP) Public Outreach Programs, examination of methods to enhance existing Public Outreach advertising programs began in 1993. Apart from the desire to promote greater public awareness and participation of the YMP, the Project itself is receiving less coverage of its scientific aspects in the local media. Since the public is already comfortable receiving messages in these media, this becomes an additional reason to explore and study advertising as a platform for invitations to the public

Science and students: Yucca Mountain project's education outreach program

International Nuclear Information System (INIS)

Gil, A.V.; Larkin, E.L.; Reilly, B.; Austin, P.

1992-01-01

The U.S. Department of Energy (DOE) is very concerned about the lack of understanding of basic science. Increasingly, critical decisions regarding the use of energy, technology, and the environment are being made. A well-educated and science-literate public is vital to the success of these decisions. Science education and school instruction are integral parts of the DOE's public outreach program on the Yucca Mountain Site Characterization Project (YMP). Project staff and scientists speak to elementary, junior high, high school, and university students, accepting all speaking invitations. The objectives of this outreach program include the following: (1) educating Nevada students about the concept of a high-level nuclear waste repository; (2) increasing awareness of energy and environmental issues; (3) helping students understand basic concepts of earth science and geology in relation to siting a potential repository; and (4) giving students information about careers in science and engineering

Multi-CPU plasma fluid turbulence calculations on a CRAY Y-MP C90

International Nuclear Information System (INIS)

Lynch, V.E.; Carreras, B.A.; Leboeuf, J.N.; Curtis, B.C.; Troutman, R.L.

1993-01-01

Significant improvements in real-time efficiency have been obtained for plasma fluid turbulence calculations by microtasking the nonlinear fluid code KITE in which they are implemented on the CRAY Y-MP C90 at the National Energy Research Supercomputer Center (NERSC). The number of processors accessed concurrently scales linearly with problem size. Close to six concurrent processors have so far been obtained with a three-dimensional nonlinear production calculation at the currently allowed memory size of 80 Mword. With a calculation size corresponding to the maximum allowed memory of 200 Mword in the next system configuration, we expect to be able to access close to nine processors of the C90 concurrently with a commensurate improvement in real-time efficiency. These improvements in performance are comparable to those expected from a massively parallel implementation of the same calculations on the Intel Paragon

Multi-CPU plasma fluid turbulence calculations on a CRAY Y-MP C90

International Nuclear Information System (INIS)

Lynch, V.E.; Carreras, B.A.; Leboeuf, J.N.; Curtis, B.C.; Troutman, R.L.

1993-01-01

Significant improvements in real-time efficiency have been obtained for plasma fluid turbulence calculations by microtasking the nonlinear fluid code KITE in which they are implemented on the CRAY Y-MP C90 at the National Energy Research Supercomputer Center (NERSC). The number of processors accessed concurrently scales linearly with problem size. Close to six concurrent processors have so far been obtained with a three-dimensional nonlinear production calculation at the currently allowed memory size of 80 Mword. With a calculation size corresponding to the maximum allowed memory of 200 Mword in the next system configuration, they expect to be able to access close to ten processors of the C90 concurrently with a commensurate improvement in real-time efficiency. These improvements in performance are comparable to those expected from a massively parallel implementation of the same calculations on the Intel Paragon

Safety Basis Report

International Nuclear Information System (INIS)

R.J. Garrett

2002-01-01

As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities

Safety Basis Report

Energy Technology Data Exchange (ETDEWEB)

R.J. Garrett

2002-01-14

As part of the internal Integrated Safety Management Assessment verification process, it was determined that there was a lack of documentation that summarizes the safety basis of the current Yucca Mountain Project (YMP) site characterization activities. It was noted that a safety basis would make it possible to establish a technically justifiable graded approach to the implementation of the requirements identified in the Standards/Requirements Identification Document. The Standards/Requirements Identification Documents commit a facility to compliance with specific requirements and, together with the hazard baseline documentation, provide a technical basis for ensuring that the public and workers are protected. This Safety Basis Report has been developed to establish and document the safety basis of the current site characterization activities, establish and document the hazard baseline, and provide the technical basis for identifying structures, systems, and components (SSCs) that perform functions necessary to protect the public, the worker, and the environment from hazards unique to the YMP site characterization activities. This technical basis for identifying SSCs serves as a grading process for the implementation of programs such as Conduct of Operations (DOE Order 5480.19) and the Suspect/Counterfeit Items Program. In addition, this report provides a consolidated summary of the hazards analyses processes developed to support the design, construction, and operation of the YMP site characterization facilities and, therefore, provides a tool for evaluating the safety impacts of changes to the design and operation of the YMP site characterization activities.

Comparison of CFD Natural Convection and Conduction-only Models for Heat Transfer in the Yucca Mountain Project Drifts

International Nuclear Information System (INIS)

Hadgu, T.; Webb, S.; Itamura, M.

2004-01-01

Yucca Mountain, Nevada has been designated as the nation's high-level radioactive waste repository and the U.S. Department of Energy has been approved to apply to the U.S. Nuclear Regulatory Commission for a license to construct a repository. Heat transfer in the Yucca Mountain Project (YMP) drift enclosures is an important aspect of repository waste emplacement. Canisters containing radioactive waste are to be emplaced in tunnels drilled 500 m below the ground surface. After repository closure, decaying heat is transferred from waste packages to the host rock by a combination of thermal radiation, natural convection and conduction heat transfer mechanism?. Current YMP mountain-scale and drift-scale numerical models often use a simplified porous medium code to model fluid and heat flow in the drift openings. To account for natural convection heat transfer, the thermal conductivity of the air was increased in the porous medium model. The equivalent thermal conductivity, defined as the ratio of total heat flow to conductive heat flow, used in the porous media models was based on horizontal concentric cylinders. Such modeling does not effectively capture turbulent natural convection in the open spaces as discussed by Webb et al. (2003) yet the approach is still widely used on the YMP project. In order to mechanistically model natural convection conditions in YMP drifts, the computational fluid dynamics (CFD) code FLUENT (Fluent, Incorporated, 2001) has been used to model natural convection heat transfer in the YMP emplacement drifts. A two-dimensional (2D) model representative of YMP geometry (e.g., includes waste package, drip shield, invert and drift wall) has been developed and numerical simulations made (Francis et al., 2003). Using CFD simulation results for both natural convection and conduction-only heat transfer in a single phase, single component fluid, equivalent thermal conductivities have been calculated for different Rayleigh numbers. Correlation

Saturated Zone Flow and Transport Expert Elicitation Project

Energy Technology Data Exchange (ETDEWEB)

Coppersmith, Kevin J.; Perman, Roseanne C.

1998-01-01

This report presents results of the Saturated Zone Flow and Transport Expert Elicitation (SZEE) project for Yucca Mountain, Nevada. This project was sponsored by the US Department of Energy (DOE) and managed by Geomatrix Consultants, Inc. (Geomatrix), for TRW Environmental Safety Systems, Inc. The DOE's Yucca Mountain Site Characterization Project (referred to as the YMP) is intended to evaluate the suitability of the site for construction of a mined geologic repository for the permanent disposal of spent nuclear fuel and high-level radioactive waste. The SZEE project is one of several that involve the elicitation of experts to characterize the knowledge and uncertainties regarding key inputs to the Yucca Mountain Total System Performance Assessment (TSPA). The objective of the current project was to characterize the uncertainties associated with certain key issues related to the saturated zone system in the Yucca Mountain area and downgradient region. An understanding of saturated zone processes is critical to evaluating the performance of the potential high-level nuclear waste repository at Yucca Mountain. A major goal of the project was to capture the uncertainties involved in assessing the saturated flow processes, including uncertainty in both the models used to represent the physical processes controlling saturated zone flow and transport, and the parameter values used in the models. So that the analysis included a wide range of perspectives, multiple individual judgments were elicited from members of an expert panel. The panel members, who were experts from within and outside the Yucca Mountain project, represented a range of experience and expertise. A deliberate process was followed in facilitating interactions among the experts, in training them to express their uncertainties, and in eliciting their interpretations. The resulting assessments and probability distributions, therefore, provide a reasonable aggregate representation of the knowledge and

Can we talk? Communications management for the Waste Isolation Pilot Plant, a complex nuclear waste management project

International Nuclear Information System (INIS)

Goldstein, S.A.; Pullen, G.M.; Brewer, D.R.

1995-01-01

Sandia Nuclear Waste Management Program is pursuing for DOE an option for permanently disposing radioactive waste in deep geologic repositories. Included in the Program are the Waste Isolation Pilot Plant (WIPP) Project for US defense program mixed waste the Yucca Mountain Project (YMP) for spent power reactor fuel and vitrified high-level waste, projects for other waste types, and development efforts in environmental decision support technologies. WIPP and YMP are in the public arena, of a controversial nature, and provide significant management challenges. Both projects have large project teams, multiple organization participants, large budgets, long durations, are very complex, have a high degree of programmatic risk, and operate in an extremely regulated environment requiring legal defensibility. For environmental projects like these to succeed, SNL's Program is utilizing nearly all areas in PMI's Project Management Body of Knowledge (PMBOK) to manage along multiple project dimensions such as the physical sciences (e.g., geophysics and geochemistry; performance assessment; decision analysis) management sciences (controlling the triple constraint of performance, cost and schedule), and social sciences (belief systems; public participation; institutional politics). This discussion focuses primarily on communication challenges active on WIPP. How is the WIPP team meeting the challenges of managing communications?'' and ''How are you approaching similar challenges?'' will be questions for a dialog with the audience

Prediction of Pseudo relative velocity response spectra at Yucca Mountain for underground nuclear explosions conducted in the Pahute Mesa testing area at the Nevada testing site; Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

Phillips, J.S.

1991-12-01

The Yucca Mountain Site Characterization Project (YMP), managed by the Office of Geologic Disposal of the Office of Civilian Radioactive Waste Management of the US Department of Energy, is examining the feasibility of siting a repository for commercial, high-level nuclear wastes at Yucca Mountain on and adjacent to the Nevada Test Site (NTS). This work, intended to extend our understanding of the ground motion at Yucca Mountain resulting from testing of nuclear weapons on the NTS, was funded by the Yucca Mountain project and the Military Applications Weapons Test Program. This report summarizes one aspect of the weapons test seismic investigations conducted in FY88. Pseudo relative velocity response spectra (PSRV) have been calculated for a large body of surface ground motions generated by underground nuclear explosions. These spectra have been analyzed and fit using multiple linear regression techniques to develop a credible prediction technique for surface PSRVs. In addition, a technique for estimating downhole PSRVs at specific stations is included. A data summary, data analysis, prediction development, prediction evaluation, software summary and FORTRAN listing of the prediction technique are included in this report.

Läsnätyö ja joustavat työaikamuodot -hanke Uudenmaan elinkeino-, liikenne- ja ympäristökeskuksessa

OpenAIRE

Karsila, Petteri

2014-01-01

Opinnäytetyö tarkastelee toimeksiantajayrityksen Uudenmaan elinkeino-, liikenne ja ympäristökeskuksen läsnätyö ja joustavat työaikamuodot -kokeiluhanketta. Toimeksiantajayrityksen tehtävänä on edistää alueellista kehittämistä hoitamalla valtionhallinnon toimeenpano- ja kehittämistehtäviä toimialueellaan. Tavoitteena oli selvittää läsnätyön ja mobiiliteknologian hyvät ja huonot puolet kohdeorganisaatiossa sekä arvioida, miten muuttaa kohdeorganisaation työn tekemisen tapoja, työkulttuuria...

Office 365 -teeman asentaminen ja käyttöönotto Office 365 -ympäristössä

OpenAIRE

Jokinen, Juho

2015-01-01

Tämän opinnäytetyön tarkoituksena oli asentaa Office 365 -teema asiakkaan julkiseen verkkosivustoon ja tutustua sen hallintaan ja käyttöön. Opinnäytetyön tavoitteena oli saada asiakkaalle toimiva ja helppokäyttöinen käyttöliittymä. Microsoft julkaisi nykyisen Office 365 for Business-palvelun vuonna 2013. Microsoft Office 365 on pilvipohjainen käyttöliittymä. Asennus tehdään asiakkaan tyhjään Office 365 -ympäristöön. Asennuksen vaiheet kuvaillaan tarkasti ja teeman eri elementtejä tutkitaan...

Can we talk? Communications management for the Waste Isolation Pilot Plant, a complex nuclear waste management project

Energy Technology Data Exchange (ETDEWEB)

Goldstein, S.A.; Pullen, G.M.; Brewer, D.R.

1995-07-01

Sandia Nuclear Waste Management Program is pursuing for DOE an option for permanently disposing radioactive waste in deep geologic repositories. Included in the Program are the Waste Isolation Pilot Plant (WIPP) Project for US defense program mixed waste the Yucca Mountain Project (YMP) for spent power reactor fuel and vitrified high-level waste, projects for other waste types, and development efforts in environmental decision support technologies. WIPP and YMP are in the public arena, of a controversial nature, and provide significant management challenges. Both projects have large project teams, multiple organization participants, large budgets, long durations, are very complex, have a high degree of programmatic risk, and operate in an extremely regulated environment requiring legal defensibility. For environmental projects like these to succeed, SNL`s Program is utilizing nearly all areas in PMI`s Project Management Body of Knowledge (PMBOK) to manage along multiple project dimensions such as the physical sciences (e.g., geophysics and geochemistry; performance assessment; decision analysis) management sciences (controlling the triple constraint of performance, cost and schedule), and social sciences (belief systems; public participation; institutional politics). This discussion focuses primarily on communication challenges active on WIPP. How is the WIPP team meeting the challenges of managing communications?`` and ``How are you approaching similar challenges?`` will be questions for a dialog with the audience.

Technology information transfer in public outreach - a new approach

International Nuclear Information System (INIS)

Peck, J.H.; Wadkins, M.L.

1994-01-01

The timely and accurate dissemination to the public of information derived from the site characterization activities on the Yucca Mountain Site Characterization Project (YMP) has sometimes been difficult to achieve. The YMP has many participants who are involved in the gathering and analysis of scientific and engineering data for site characterization. The diversity of the scientific disciplines involved, the uncentralized location of the participant organizations, the difficulty of being able to ask the right questions of the right people, and the translation of technical jargon into understandable terms are but a few of the challenges. The public outreach program of the YMP has done an excellent job of compiling and distributing information over the past few years, but, with the diversity and expansion of field activities in the last two years, the job has become more formidable. A new approach to help resolve this obstacle was instituted in April of 1993, and has been successful in achieving a much more timely and user-friendly discussion of technical information for the public. What is the new approach? The assignment of a technical expert to the public outreach staff whose job is to know what is going on, who is doing what, and what the results are. Based on that knowledge, factual summaries can be generated rapidly and presented to the public in the context of the overall project goals and in a form suitable for a wide range of audiences

Growing interest, growing programs, growing pains: Successfully customizing public outreach

International Nuclear Information System (INIS)

Wadkins, M.; Hill, C.; Hirsch, T.

1994-01-01

Since the mid-1980's, the Institutional and External Affairs staff of the Yucca Mountain Site Characterization Project (YMP) has developed, coordinated, and maintained various public outreach programs to carry out the YMP's open door policy of keeping local communities informed. However, public involvement first requires public knowledge and, therefore, various information programs have been established over the past few years. First came the speakers bureau program, then the exhibits and science centers; and then came the tours and school district educational programs. All these programs were geared toward teaching the mainstream general public about the YMP and issues related to things nuclear. Today, the YMP outreach programs are established and known and the demand from the public has seen a shift. Over 150 top scientists and staff from around the country who have come to work at the YMP have joined the outreach participant pool to speak to the public not only about Yucca Mountain, but about their areas of expertise as well. For this reason, the public has realized a great opportunity for a general science and engineering education resource -- the YMP staff themselves. In a panel discussion, open-quotes Trust and credibility: The central issueclose quotes, proceedings of the National Conference on Risk Communication, it was shown that university professors and science teachers were among the most trusted individuals in terms of public perception and that government staff and contractors the least trusted. However, when you utilize the core educated knowledge of a YMP scientist in order to teach general science and math, you have, to some extent, placed that individual in an educational role and thus increased trust. The YMP scientists enjoy talking about their general science knowledge and we have found that the public likes to hear about it too

Study on quality assurance for high-level radioactive waste disposal project (2). Quality assurance system for the site characterization phase in the Yucca Mountain Project

International Nuclear Information System (INIS)

Takada, Susumu

2006-01-01

The objective of this report is to assist related organizations in the development of quality assurance systems for a high-level radioactive waste disposal system. This report presents detail information with which related organizations can begin the development of quality assurance systems at an initial phase of repository development for a high-level radioactive waste disposal program, including data qualification, model validation, systems and facilities for quality assurance (e.g., technical data management system, sample management facility, etc.), and QA program applicability (items and activities). These descriptions are based on information in QA program for the Yucca Mountain Project (YMP), such as the U.S. Department of Energy (DOE) Quality Assurance Requirements and Description (QARD), DOE/RW-0333P, quality implementing procedures, and reports implemented by the procedures. Additionally, this report includes some brief recommendations for developing of quality assurance systems, such as establishment of quality assurance requirements, measures for establishment of QA system. (author)

Tank waste remediation system characterization project quality policies. Revision 1

International Nuclear Information System (INIS)

Trimble, D.J.

1995-01-01

These Quality Policies (QPs) describe the Quality Management System of the Tank Waste Characterization Project (hereafter referred to as the Characterization Project), Tank Waste Remediation System (TWRS), Westinghouse Hanford Company (WHC). The Quality Policies and quality requirements described herein are binding on all Characterization Project organizations. To achieve quality, the Characterization Project management team shall implement this Characterization Project Quality Management System

The status of Yucca Mountain site characterization activities

International Nuclear Information System (INIS)

Gertz, Carl P.; Larkin, Erin L.; Hamner, Melissa

1992-01-01

The U.S. Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is continuing its studies to determine if Yucca Mountain, Nevada, can safely isolate high-level nuclear waste for the next ten thousand years. As mandated by Congress in 1987, DOE is studying the rocks, the climate, and the water table at Yucca Mountain to ensure that the site is suitable before building a repository adopt 305 meters below the surface. Yucca Mountain, located 160.9 kilometers northwest of Las Vegas, lies on the western edge of the Nevada Test Site. Nevada and DOE have been in litigation over environmental permits needed to conduct studies, but recent court decisions have allowed limited new work to begin. This paper will examine progress made on the Yucca Mountain Site Characterization Project (YMP) during 1991 and continuing into 1992, discuss the complex legal issues and describe new site drilling work. Design work on the underground exploratory studies facility (ESF) will also be discussed. (author)

Formation, characterization, and stability of plutonium (IV) colloid

International Nuclear Information System (INIS)

Hobart, D.E.; Morris, D.E.; Palmer, P.D.; Newton, T.W.

1989-01-01

Plutonium is expected to be a major component of the waste element package in any high-level nuclear waste repository. Plutonium(IV) is known to form colloids under chemical conditions similar to those found in typical groundwaters. In the event of a breach of a repository, these colloids represent a source of radionuclide transport to the far-field environment, in parallel with the transport of dissolved waste element species. In addition, the colloids may decompose or disaggregate into soluble ionic species. Thus, colloids represent an additional term in determining waste element solubility limits. A thorough characterization of the physical and chemical properties of these colloids under relevant conditions is essential to assess the concentration limits and transport mechanisms for the waste elements at the proposed Yucca Mountain Repository site. This report is concerned primarily with recent results obtained by the Yucca Mountain Project (YMP) Solubility Determination Task pertaining to the characterization of the structural and chemical properties of Pu(IV) colloid. Important results will be presented which provides further evidence that colloidal plutonium(IV) is structurally similar to plutonium dioxide and that colloidal plutonium(IV) is electrochemically reactive. 13 refs., 7 figs

Hallittu vapaus luovassa ympäristössä. Oppilaiden käyttäytyminen ja käyttäytymisen hallinta draamatunneilla

OpenAIRE

Anttila, Rosa

2015-01-01

Tavoitteet. Tutkimuksen tavoitteena on tarkastella oppilaiden käyttäytymistä ja käyttäytymisen hallintaa draamatunneilla. Draamakasvatus pohjautuu oppilaslähtöisyyteen ja kokemuksellisuuteen, mikä nähdään erityisenä haasteena käyttäytymisen hallinnalle sekä suurena riskinä häiriökäyttäytymisen syntymiselle. Toisaalta draamakasvatuksessa opitaan yhdessä uutta luoden ja erilaisia ratkaisuja tuottaen, mikä ei ole mahdollista liian kontrolloidussa ympäristössä. Tutkimuksen tarkoituksena on myös s...

Site characterization activities at Stripa and other Swedish projects

International Nuclear Information System (INIS)

Ahlstroehm, P.E.

1991-01-01

The Swedish research programme concerning spent nuclear fuel disposal aims for submitting a siting license application around the year 2000. An important step towards that goal will be the detailed characterization of at least two potential sites in late 1990s. In preparation for such characterization several research projects are conducted. One is the international Stripa Project that includes a site characterization and validation project for a small size granite rock body. The Stripa work also includes further development of instrumentation and measurement techniques. Another project is the Finnsjoen Fracture Zone Project, which is characterizing a subhorizontal zone at depths from 100 to 350 meters. The third project is the new Swedish Hard Rock Laboratory planned at the site of the Oskarshamn nuclear power plant. The preinvestigations and construction of this laboratory include major efforts in development, application and validation of site characterization methodology. (author) 6 figs., 9 refs

Survey of degradation modes of four nickel-chromium-molybdenum alloys

International Nuclear Information System (INIS)

Gdowski, G.E.

1991-03-01

This report examines the degradation modes of four Ni-Cr-Mo alloys under conditions relevant to the Yucca Mountain Site Characterization Project (YMP). The materials considered are Alloys C-276, C-4, C-22, and 625 because they have desirable characteristics for the conceptual design (CD) of the high-level radioactive-waste containers presented in the YMP Site Characterization Plan (SCP). The types of degradation covered in this report are general corrosion; localized corrosion, including pitting and crevice corrosion; stress corrosion cracking in chloride environments; hydrogen embrittlement (HE); and undesirable phase transformations due to a lack of phase stability. Topics not specifically addressed are welding concerns and microbiological corrosion. The four Ni-Cr-Mo alloys have excellent corrosion resistance in chloride environments such as seawater as well as in more aggressive environments. They have significantly better corrosion resistance than the six materials considered for the CD waste container in the YMP SCP. (Those six materials are Types 304L and 3161L stainless steels, Alloy 825, unalloyed copper, Cu(70)-Ni(30), and 7% aluminum bronze.) In seawater, the Ni-Cr-Mo alloys have negligible general corrosion rates and show little evidence of localized corrosion. The four base materials of these alloys are expected to have nearly indistinguishable corrosion resistance in the YMP environments. The strength requirements of the SCP-CD waste container are met by these materials in the annealed condition; in this condition, they are highly resistant to HE. Historically, HE has been noted when these materials have been strengthened (cold-worked) and used in sour gas (H 2 S and CO 2 ) well service -- conditions that are not expected for the YMP. Metallurgical phase stability may be a concern under conditions favoring (1) the formation of intermetallics and carbides, and (2) microstructural ordering

Determination of Importance Evaluation for the ESF Enhanced Charcterization of the Repository Block Cross Drift

Energy Technology Data Exchange (ETDEWEB)

S. Goodin

2002-01-09

The objective of this DIE is to determine whether the ECRB-Cross-Drift-related activities, as identified in Section 6.0, could potentially impact (1) Yucca Mountain Site Characterization Project (YMP) testing or (2) the waste isolation capabilities of a potential repository at the Yucca Mountain site. Any controls necessary to limit such potential impacts are also identified herein.

Application of quality assurance controls to TBM tunneling on the Yucca Mountain Project

International Nuclear Information System (INIS)

Christensen, J.D.

1996-01-01

As part of the Yucca Mountain Project (YMP), a 7.62-meter diameter tunnel is being constructed using a Tunnel Boring Machine (TBM). This tunnel, which may form a portion of a permanent high-level nuclear waste repository, is being constructed under the auspices of a nuclear quality assurance (QA) program. The YMP nuclear QA program applies to items and activities determined to be important to radiological safety, waste isolation, and potential interactions with the environment. The items and activities determined to be important have been assigned a quality assurance classification. This paper focuses on the items (rockbolts, steel sets, and shotcrete) and quality affecting activities involved in providing ground support and excavating the tunnel. Typical activities that have been assigned QA classifications include TBM maintenance, control of water used in the tunnel during construction, and control of diesel emissions in the tunnel. The paper concludes that the key to the successful implementation of nuclear QA requirements for tunneling at Yucca Mountain was the assignment of personnel with the appropriate mix of tunneling and nuclear experience

Area 5 Site characterization project report, FY 1994

International Nuclear Information System (INIS)

Albright, W.; Tyler, S.; Chapman, J.; Miller, M.; Estrella, R.

1994-09-01

The Area 5 Site Characterization Project is designed to determine the suitability of the Radioactive Waste Management Site (RWMS) for disposal of low-level waste (LLW), mixed waste (MW) and transuranic waste (TRU). The Desert Research institute (DRI) has conducted this study for the Area 5 Site Characterization Project for the US Department of Energy, Nevada Operations Office (DOE/NV), Waste Management Division (WMD). The purpose of DRI's Area 5 Site Characterization Project is to characterize important properties of the upper vadose zone which influence infiltration and redistribution of water and transport of solutes as well as to characterize the water quality and hydrologic conditions of the uppermost aquifer. This report describes methods and presents a summary of all data and results from laboratory physical and chemical testing from borehole samples through September 1994. DRI laboratories performed soil water content, soil water potential, soil bulk density, and soil water extract isotope analyses

Yucca Mountain Site characterization project bibliography, January--June 1991

International Nuclear Information System (INIS)

1992-06-01

Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy's Science and Technology Database from January 1, 1990, through December 31, 1991

Letter of Intent for River Protection Project (RPP) Characterization Program: Process Engineering and Hanford Analytical Services and Characterization Project Operations and Quality Assurance

International Nuclear Information System (INIS)

ADAMS, M.R.

2000-01-01

The Characterization Project level of success achieved by the River Protection Project (RPP) is determined by the effectiveness of several organizations across RPP working together. The requirements, expectations, interrelationships, and performance criteria for each of these organizations were examined in order to understand the performances necessary to achieve characterization objectives. This Letter of Intent documents the results of the above examination. It formalizes the details of interfaces, working agreements, and requirements for obtaining and transferring tank waste samples from the Tank Farm System (RPP Process Engineering, Characterization Project Operations, and RPP Quality Assurance) to the characterization laboratory complex (222-S Laboratory, Waste Sampling and Characterization Facility, and the Hanford Analytical Service Program) and for the laboratory complex analysis and reporting of analytical results

FY94 CAG trip reports, CAG memos and other products: Volume 2. Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-15

The Yucca Mountain Site Characterization Project (YMP) of the US DOE is tasked with designing, constructing, and operating an Exploratory Studies Facility (ESF) at Yucca Mountain, Nevada. The purpose of the YMP is to provide detailed characterization of the Yucca Mountain site for the potential mined geologic repository for permanent disposal of high-level radioactive waste. Detailed characterization of properties of the site are to be conducted through a wide variety of short-term and long-term in-situ tests. Testing methods require the installation of a large number of test instruments and sensors with a variety of functions. These instruments produce analog and digital data that must be collected, processed, stored, and evaluated in an attempt to predict performance of the repository. The Integrated Data and Control System (IDCS) is envisioned as a distributed data acquisition that electronically acquires and stores data from these test instruments. IDCS designers are responsible for designing and overseeing the procurement of the system, IDCS Operation and Maintenance operates and maintains the installed system, and the IDCS Data Manager is responsible for distribution of IDCS data to participants. This report is a compilation of trip reports, interoffice memos, and other memos relevant to Computer Applications Group, Inc., work on this project.

FY94 CAG trip reports, CAG memos and other products: Volume 2. Final report

International Nuclear Information System (INIS)

1994-01-01

The Yucca Mountain Site Characterization Project (YMP) of the US DOE is tasked with designing, constructing, and operating an Exploratory Studies Facility (ESF) at Yucca Mountain, Nevada. The purpose of the YMP is to provide detailed characterization of the Yucca Mountain site for the potential mined geologic repository for permanent disposal of high-level radioactive waste. Detailed characterization of properties of the site are to be conducted through a wide variety of short-term and long-term in-situ tests. Testing methods require the installation of a large number of test instruments and sensors with a variety of functions. These instruments produce analog and digital data that must be collected, processed, stored, and evaluated in an attempt to predict performance of the repository. The Integrated Data and Control System (IDCS) is envisioned as a distributed data acquisition that electronically acquires and stores data from these test instruments. IDCS designers are responsible for designing and overseeing the procurement of the system, IDCS Operation and Maintenance operates and maintains the installed system, and the IDCS Data Manager is responsible for distribution of IDCS data to participants. This report is a compilation of trip reports, interoffice memos, and other memos relevant to Computer Applications Group, Inc., work on this project

Fabrication and closure development of nuclear waste containers for storage at the Yucca Mountain, Nevada repository

International Nuclear Information System (INIS)

Russell, E.W.; Nelson, T.A.; Domian, H.A.; LaCount, D.F.; Robitz, E.S.; Stein, K.O.

1989-04-01

US Congress and the President have determined that the Yucca Mountain site in Nevada is to be characterized to determine its suitability for construction of the first US high-level nuclear waste repository. Work in connection with this site is carried out within the Yucca Mountain Project (YMP). Lawrence Livermore National Laboratory (LLNL) has the responsibility for designing, developing, and projecting the performance of the waste package for the permanent storage of high-level nuclear waste. Babcock ampersand Wilcox (B ampersand W) is involved with the YMP as a subcontractor to LLNL. B ampersand W's role is to recommend and demonstrate a method for fabricating the metallic waste container and a method for performing the final closure of the container after it has been filled with waste. Various fabrication and closure methods are under consideration for the production of containers. This paper presents progress to date in identifying and evaluating the candidate manufacturing processes. 2 refs., 1 fig., 7 tabs

Fabrication and closure development of corrosion resistant containers for Nevada's Yucca Mountain high-level nuclear waste repository

International Nuclear Information System (INIS)

Russell, E.W.; Nelson, T.A.; Domian, H.A.; LaCount, D.F.; Robitz, E.S.; Stein, K.O.

1989-11-01

US Congress and the President have determined that the Yucca Mountain site in Nevada is to be characterized to determine its suitability for construction of the first US high-level nuclear waste repository. Work in connection with this site is carried out within the Yucca Mountain Project (YMP). Lawrence Livermore National Laboratory (LLNL) has the responsibility for designing, developing, and projecting the performance of the waste package for the permanent storage of high-level nuclear waste. Babcock ampersand Wilcox (B ampersand W) is involved with the YMP as a subcontractor to LLNL. B ampersand W's role is to recommend and demonstrate a method for fabricating the metallic waste container and a method for performing the final closure of the container after it has been filled with waste. Various fabrication and closure methods are under consideration for the production of containers. This paper presents progress to date in identifying and evaluating the candidate manufacturing processes. 2 refs., 2 figs., 4 tabs

Gypsy Field project in reservoir characterization

Energy Technology Data Exchange (ETDEWEB)

Castagna, John P.; Jr., O' Meara, Daniel J.

2000-01-12

The overall objective of this project was to use extensive Gypsy Field Laboratory and data as a focus for developing and testing reservoir characterization methods that are targeted at improved recovery of conventional oil. This report describes progress since project report DOE/BC/14970-7 and covers the period June 1997-September 1998 and represents one year of funding originally allocated for the year 1996. During the course of the work previously performed, high resolution geophysical and outcrop data revealed the importance of fractures at the Gypsy site. In addition, personnel changes and alternative funding (OCAST and oil company support of various kinds) allowed the authors to leverage DOE contributions and focus more on geophysical characterization.

Tank Waste Remediation System Characterization Project Programmatic Risk Management Plan

International Nuclear Information System (INIS)

Baide, D.G.; Webster, T.L.

1995-12-01

The TWRS Characterization Project has developed a process and plan in order to identify, manage and control the risks associated with tank waste characterization activities. The result of implementing this process is a defined list of programmatic risks (i.e. a risk management list) that are used by the Project as management tool. This concept of risk management process is a commonly used systems engineering approach which is being applied to all TWRS program and project elements. The Characterization Project risk management plan and list are subset of the overall TWRS risk management plan and list

Yucca Mountain Site characterization project bibliography, January--June 1991

International Nuclear Information System (INIS)

Lorenz, J.J.; Stephan, P.M.

1991-09-01

Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy's Energy Science and Technology Database from January 1991 through June 1991. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers, and articles are included in the sponsoring organization's list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it

Yucca Mountain Site Characterization Project bibliography, January--June 1992

International Nuclear Information System (INIS)

1992-01-01

Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy's Energy Science and Technology Database from January 1, 1993, through June 30, 1993. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers, and articles are included in the sponsoring organization's list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it

Yucca Mountain Site Characterization Project Bibliography, July--December 1990

International Nuclear Information System (INIS)

1991-05-01

Following a reorganization of the Office of Civilian Radioactive Waste Management, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountains Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy's Energy Science and Technology Database from July 1990 through December 1990. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers and articles are included in the sponsoring organizations list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it

Yucca Mountain Site characterization project bibliography, January--June 1992

International Nuclear Information System (INIS)

1992-09-01

Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy's Energy Science and Technology Database from January 1, 1992, through June 30, 1992. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor resorts, papers, and articles are included in the sponsoring organization's list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it

Spent nuclear fuels project characterization data quality objectives strategy

International Nuclear Information System (INIS)

Lawrence, L.A.; Thornton, T.A.; Redus, K.S.

1994-12-01

A strategy is presented for implementation of the Data Quality Objectives (DQO) process to the Spent Nuclear Fuels Project (SNFP) characterization activities. Westinghouse Hanford Company (WHC) and the Pacific Northwest Laboratory (PNL) are teaming in the characterization of the SNF on the Hanford Site and are committed to the DQO process outlined in this strategy. The SNFP characterization activities will collect and evaluate the required data to support project initiatives and decisions related to interim safe storage and the path forward for disposal. The DQO process is the basis for the activity specific SNF characterization requirements, termed the SNF Characterization DQO for that specific activity, which will be issued by the WHC or PNL organization responsible for the specific activity. The Characterization Plan prepared by PNL defines safety, remediation, and disposal issues. The ongoing Defense Nuclear Facility Safety Board (DNFSB) requirement and plans and the fuel storage and disposition options studies provide the need and direction for the activity specific DQO process. The hierarchy of characterization and DQO related documentation requirements is presented in this strategy. The management of the DQO process and the means of documenting the DQO process are described as well as the tailoring of the DQO process to the specific need of the SNFP characterization activities. This strategy will assure stakeholder and project management that the proper data was collected and evaluated to support programmatic decisions

Data Qualification Report: Precipitation and Surface Geology Data for Use on the Yucca Mountain Project

International Nuclear Information System (INIS)

C. Wilson

2000-01-01

The unqualified data addressed in this qualification report have been cited in an Analysis Model Report (AMR) to support the Site Recommendation in determining the suitability of Yucca Mountain as a repository for high-level radioactive waste. The unqualified data include precipitation volumes and surface geology maps The precipitation data consist of daily precipitation volumes measured at Yucca Mountain. The surface geology data include identification of the types and surface expressions of geologic units and associated structural features such as faults. These data were directly used in AMR U0010, Simulation of Net Infiltration for Modern and Potential Future Climates, ANL-NBS-HS-000032 (Hevesi et al. 2000), to estimate net infiltration into Yucca Mountain. This report evaluates the unqualified data within the context of supporting studies of this type for the Yucca Mountain Site Characterization Project (YMP). The purpose of this report is to identify data that can be cited as qualified for use in technical products to support the YMP Site Recommendation and that may also be used to support the License Application. The qualified data may either be retained in the original Data Tracking Number (DTN) or placed in new DTNs generated as a result of the evaluation. The appropriateness and limitations (if any) of the data with respect to intended use are addressed in this report. In accordance with Attachment 1 of procedure AP-3.15Q, Rev. 02, Managing Technical Product Inputs, it has been determined that the unqualified precipitation and surface geology data are not used in the direct calculation of Principal Factors for postclosure safety or disruptive events. References to tables, figures, and sections from Hevesi et al. (2000) are based on Rev. 00 of that document

Design basis event consequence analyses for the Yucca Mountain project

International Nuclear Information System (INIS)

Orvis, D.D.; Haas, M.N.; Martin, J.H.

1997-01-01

Design basis event (DBE) definition and analysis is an ongoing and integrated activity among the design and analysis groups of the Yucca Mountain Project (YMP). DBE's are those that potentially lead to breach of the waste package and waste form (e.g., spent fuel rods) with consequent release of radionuclides to the environment. A Preliminary Hazards Analysis (PHA) provided a systematic screening of external and internal events that were candidate DBE's that will be subjected to analyses for radiological consequences. As preparation, pilot consequence analyses for the repository subsurface and surface facilities have been performed to define the methodology, data requirements, and applicable regulatory limits

TBM tunneling on the Yucca Mountain Project: Proceedings

International Nuclear Information System (INIS)

Williamson, G.E.; Gowring, I.M.

1995-01-01

The US Department of Energy's (DOE) Yucca Mountain Project (YMP) is a scientific endeavor to determine the suitability of Yucca Mountain for the first long term, high level nuclear waste repository in the United States. Status of this long-term project form the construction perspective is described. A key element is construction of the Exploratory Studies Facility (ESF), which is being excavated with a 7. 6 m(25 ft) diameter tunnel boring machine (TBM). Development of the ESF may include the excavation of over 15 km (9.3 mi) of tunnel varying in size from 3 to 7.6 m(10 to 25 ft). Prior to construction, extensive constructibility reviews were an interactive part of the final design. Intent was to establish a constructible design that met the long-term stability requirements for radiological safety of a future repository while maintaining flexibility for the scientific investigations and acceptable tunneling productivity

TBM tunneling on the Yucca Mountain Project

International Nuclear Information System (INIS)

Morris, J.P.; Hansmire, W.H.

1995-01-01

The US Department of Energy's (DOE) Yucca Mountain Project (YMP) is a scientific endeavor to determine the suitability of Yucca Mountain for the first long-term, high-level nuclear waste repository in the United States. The current status of this long-term project from the construction perspective is described. A key element is construction of the Exploratory Studies Facility (ESF) Tunnel, which is being excavated with a 7.6 m (25 ft) diameter tunnel boring machine (TBM). Development of the ESF may include the excavation of over 15 km (9.3 mi) of tunnel varying in size from 3.0 to 7.6 m (10 to 25 ft). Prior to construction, extensive constructability reviews were an interactive part of the final design. The intent was to establish a constructable design that met the long-term stability requirements for radiological safety of a future repository, while maintaining flexibility for the scientific investigations and acceptable tunneling productivity

Yucca Mountain Feature, Event, and Process (FEP) Analysis

International Nuclear Information System (INIS)

Freeze, G.

2005-01-01

A Total System Performance Assessment (TSPA) model was developed for the U.S. Department of Energy (DOE) Yucca Mountain Project (YMP) to help demonstrate compliance with applicable postclosure regulatory standards and support the License Application (LA). Two important precursors to the development of the TSPA model were (1) the identification and screening of features, events, and processes (FEPs) that might affect the Yucca Mountain disposal system (i.e., FEP analysis), and (2) the formation of scenarios from screened in (included) FEPs to be evaluated in the TSPA model (i.e., scenario development). YMP FEP analysis and scenario development followed a five-step process: (1) Identify a comprehensive list of FEPs potentially relevant to the long-term performance of the disposal system. (2) Screen the FEPs using specified criteria to identify those FEPs that should be included in the TSPA analysis and those that can be excluded from the analysis. (3) Form scenarios from the screened in (included) FEPs. (4) Screen the scenarios using the same criteria applied to the FEPs to identify any scenarios that can be excluded from the TSPA, as appropriate. (5) Specify the implementation of the scenarios in the computational modeling for the TSPA, and document the treatment of included FEPs. This paper describes the FEP analysis approach (Steps 1 and 2) for YMP, with a brief discussion of scenario formation (Step 3). Details of YMP scenario development (Steps 3 and 4) and TSPA modeling (Step 5) are beyond scope of this paper. The identification and screening of the YMP FEPs was an iterative process based on site-specific information, design, and regulations. The process was iterative in the sense that there were multiple evaluation and feedback steps (e.g., separate preliminary, interim, and final analyses). The initial YMP FEP list was compiled from an existing international list of FEPs from other radioactive waste disposal programs and was augmented by YMP site- and design

Report of the Peer Review Panel on the early site suitability evaluation of the Potential Repository Site at Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-01-01

The US Department of Energy (DOE) Yucca mountain Site Characterization Project Office (YMPO) assigned Science Applications International Corporation (SAIC), the Technical and Management Support Services (T&MSS) contractor to the YmPo, the task of conducting an Early Site Suitability Evaluation (ESSE) of the Yucca mountain site as a potential site for a high-level radioactive waste repository. First, the assignment called for the development of a method to evaluate a single site against the DOE General Guidelines for Recommendation of Sites for Nuclear Waste Repositories, 10 CFR Part 960. Then, using this method, an evaluation team, the ESSE Core Team, of senior YMP scientists, engineers, and technical experts, evaluated new information obtained about the site since publication of the final Environmental Assessment (DOE, 1986) to determine if new suitability/unsuitability findings could be recommended. Finally, the Core Team identified further information and analyses needed to make final determinations for each of the guidelines. As part of the task, an independent peer review of the ESSE report has been conducted. Expertise was solicited that covered the entire spectrum of siting guidelines in 10 CFR Part 960 in order to provide a complete, in-depth critical review of the data evaluated and cited in the ESSE report, the methods used to evaluate the data, and the conclusions and recommendations offered by the report. Fourteen nationally recognized technical experts (Table 2) served on the Peer Review Panel. The comments from the Panel and the responses prepared by the ESSE Core Team, documented on formal Comment Response Forms, constitute the body of this document.

Site environmental report for calendar year 1996: Yucca Mountain site, Nye County, Nevada

International Nuclear Information System (INIS)

1997-11-01

The environmental program established by the Yucca Mountain Site Characterization Office (YMSCO) has been designed and implemented to protect, maintain, and restore environmental quality, minimize potential threats to the environment and the public, and comply with environmental policies and US Department of Energy (DOE) Orders. In accordance with DOE Order 5400.1, General Environmental Protection Program (DOE, 1990a), to be superseded by DOE Order 231.1 (under review), the status of the Yucca Mountain Site Characterization Project (YMP) environmental program has been summarized in this annual Site Environmental Report (SER) to characterize performance, document compliance with environmental requirements, and highlight significant programs and efforts during calendar year 1996

Repository-relevant testing applied to the Yucca Mountain Project

International Nuclear Information System (INIS)

Bates, J.K.; Gerding, T.J.; Veleckis, E.

1989-04-01

A repository environment poses a challenge to developing a testing program because of the diverse nature of conditions that may exist at a given time during the life of the repository. A starting point is to identify whether any potential waste-water contact modes are particularly deleterious to the waste form performance, and whether any interactions between materials present in the waste package environment need to be accounted for during modeling the waste form reaction. The Unsaturated Test method in one approach that has been developed by the Yucca Mountain Project (YMP) to investigate the above issues, and a description of results that have been obtained during the testing of glass and unirradiated UO 2 are the subject of this report. 10 refs., 7 figs., 4 tabs

Aerosol characterization during project POLINAT

Energy Technology Data Exchange (ETDEWEB)

Hagen, D.E.; Hopkins, A.R.; Paladino, J.D.; Whitefield, P.D. [Missouri Univ., Rolla, MO (United States). Cloud and Aerosol Sciences Lab.; Lilenfeld, H.V. [McDonnell Douglas Aerospace-East, St. Louis, MO (United States)

1997-12-31

The objectives of the aerosol/particulate characterization measurements of project POLINAT (POLlution from aircraft emissions In the North ATlantic flight corridor) are: to search for aerosol/particulate signatures of air traffic emissions in the region of the North Atlantic Flight Corridor; to search for the aerosol/particulate component of large scale enhancement (`corridor effects`) of air traffic related species in the North Atlantic region; to determine the effective emission indices for the aerosol/particulate component of engine exhaust in both the near and far field of aircraft exhaust plumes; to measure the dispersion and transformation of the aerosol/particulate component of aircraft emissions as a function of ambient condition; to characterize background levels of aerosol/particulate concentrations in the North Atlantic Region; and to determine effective emission indices for engine exhaust particulates for regimes beyond the jet phase of plume expansion. (author) 10 refs.

Aerosol characterization during project POLINAT

Energy Technology Data Exchange (ETDEWEB)

Hagen, D E; Hopkins, A R; Paladino, J D; Whitefield, P D [Missouri Univ., Rolla, MO (United States). Cloud and Aerosol Sciences Lab.; Lilenfeld, H V [McDonnell Douglas Aerospace-East, St. Louis, MO (United States)

1998-12-31

The objectives of the aerosol/particulate characterization measurements of project POLINAT (POLlution from aircraft emissions In the North ATlantic flight corridor) are: to search for aerosol/particulate signatures of air traffic emissions in the region of the North Atlantic Flight Corridor; to search for the aerosol/particulate component of large scale enhancement (`corridor effects`) of air traffic related species in the North Atlantic region; to determine the effective emission indices for the aerosol/particulate component of engine exhaust in both the near and far field of aircraft exhaust plumes; to measure the dispersion and transformation of the aerosol/particulate component of aircraft emissions as a function of ambient condition; to characterize background levels of aerosol/particulate concentrations in the North Atlantic Region; and to determine effective emission indices for engine exhaust particulates for regimes beyond the jet phase of plume expansion. (author) 10 refs.

Yucca Mountain Site Characterization Project bibliography, 1992--1994. Supplement 4

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-06-01

Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy`s Energy Science and Technology Database from January 1, 1992, through December 31, 1993. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers, and articles are included in the sponsoring organization`s list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it. Earlier information on this project can be found in the first bibliography DOE/TIC-3406, which covers 1977--1985, and its three supplements DOE/OSTI-3406(Suppl.1), DOE/OSTI-3406(Suppl.2), and DOE/OSTI-3406(Suppl.3), which cover information obtained during 1986--1987, 1988--1989, and 1990--1991, respectively. All entries in the bibliographies are searchable online on the NNW database file. This file can be accessed through the Integrated Technical Information System (ITIS) of the US Department of Energy (DOE).

Yucca Mountain Site Characterization Project bibliography, 1992--1993. Supplement 4

International Nuclear Information System (INIS)

1992-06-01

Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy's Energy Science and Technology Database from January 1, 1992, through December 31, 1993. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers, and articles are included in the sponsoring organization's list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it. Earlier information on this project can be found in the first bibliography DOE/TIC-3406, which covers 1977--1985, and its three supplements DOE/OSTI-3406(Suppl.1), DOE/OSTI-3406(Suppl.2), and DOE/OSTI-3406(Suppl.3), which cover information obtained during 1986--1987, 1988--1989, and 1990--1991, respectively. All entries in the bibliographies are searchable online on the NNW database file. This file can be accessed through the Integrated Technical Information System (ITIS) of the US Department of Energy (DOE)

Interface management for the Mined Geologic Disposal System

International Nuclear Information System (INIS)

Ashlock, K.J.

1998-03-01

The purpose of this paper is to present the interface management process that is to be used for Mined Geologic Disposal System (MGDS) development. As part of the systems engineering and integration performed on the Yucca Mountain Project (YMP), interface management is critical in the development of the potential MGDS. The application of interface management on the YMP directly addresses integration between physical elements of the MGDS and the organizations responsible for their development

Gypsy Field Project in Reservoir Characterization

International Nuclear Information System (INIS)

John P. Castagna; William J. Lamb; Carlos Moreno; Roger Young; Lynn Soreghan

2006-01-01

The objective of the Gypsy Project was to properly calculate seismic attributes and integrate these into a reservoir characterization project. Significant progress was made on the project in four areas. (1) Attenuation: In order for seismic inversion for rock properties or calculation of seismic attributes used to estimate rock properties to be performed validly, it is necessary to deal with seismic data that has had true amplitude and frequency content restored to account for earth filtering effects that are generally not included in seismic reservoir characterization methodologies. This requires the accurate measurement of seismic attenuation, something that is rarely achieved in practice. It is hoped that such measurements may also provide additional independent seismic attributes for use in reservoir characterization studies. In 2000, we were concerned with the ground truthing of attenuation measurements in the vicinity of wells. Our approach to the problem is one of extracting as time varying wavelet and relating temporal variations in the wavelet to an attenuation model of the earth. This method has the advantage of correcting for temporal variations in the reflectivity spectrum of the earth which confound the spectral ratio methodology which is the most commonly applied means of measuring attenuation from surface seismic data. Part I of the report describes our efforts in seismic attenuation as applied to the Gypsy data. (2) Optimal Attributes: A bewildering array of seismic attributes is available to the reservoir geoscientist to try to establish correlations to rock properties. Ultimately, the use of such a large number of degrees of freedom in the search for correlations with limited well control leads to common misapplication of statistically insignificant results which yields invalid predictions. Cross-validation against unused wells can be used to recognize such problems, but does not offer a solution to the question of which attributes should be used

Degradation mode survey candidate titanium-base alloys for Yucca Mountain project waste package materials. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Gdowski, G.E.

1997-12-01

The Yucca Mountain Site Characterization Project (YMP) is evaluating materials from which to fabricate high-level nuclear waste containers (hereafter called waste packages) for the potential repository at Yucca Mountain, Nevada. Because of their very good corrosion resistance in aqueous environments titanium alloys are considered for container materials. Consideration of titanium alloys is understandable since about one-third (in 1978) of all titanium produced is used in applications where corrosion resistance is of primary importance. Consequently, there is a considerable amount of data which demonstrates that titanium alloys, in general, but particularly the commercial purity and dilute {alpha} grades, are highly corrosion resistant. This report will discuss the corrosion characteristics of Ti Gr 2, 7, 12, and 16. The more highly alloyed titanium alloys which were developed by adding a small Pd content to higher strength Ti alloys in order to give them better corrosion resistance will not be considered in this report. These alloys are all two phase ({alpha} and {beta}) alloys. The palladium addition while making these alloys more corrosion resistant does not give them the corrosion resistance of the single phase {alpha} and near-{alpha} (Ti Gr 12) alloys.

Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan

International Nuclear Information System (INIS)

GREAGER, T.M.

2000-01-01

The Quality Assurance Project Plan (QAPjP) has been prepared for waste characterization activities to be conducted by the Transuranic (TRU) Project at the Hanford Site to meet requirements set forth in the Waste Isolation Pilot Plan (WIPP) Hazardous Waste Facility Permit, 4890139088-TSDF, Attachment B, including Attachments B1 through B6 (WAP) (DOE, 1999a). The QAPjP describes the waste characterization requirements and includes test methods, details of planned waste sampling and analysis, and a description of the waste characterization and verification process. In addition, the QAPjP includes a description of the quality assurance/quality control (QA/QC) requirements for the waste characterization program. Before TRU waste is shipped to the WIPP site by the TRU Project, all applicable requirements of the QAPjP shall be implemented. Additional requirements necessary for transportation to waste disposal at WIPP can be found in the ''Quality Assurance Program Document'' (DOE 1999b) and HNF-2600, ''Hanford Site Transuranic Waste Certification Plan.'' TRU mixed waste contains both TRU radioactive and hazardous components, as defined in the WLPP-WAP. The waste is designated and separately packaged as either contact-handled (CH) or remote-handled (RH), based on the radiological dose rate at the surface of the waste container. RH TRU wastes are not currently shipped to the WIPP facility

Final Hanford Site Transuranic (TRU) Waste Characterization Qualit Assurance Project Plan

International Nuclear Information System (INIS)

GREAGER, T.M.

1999-01-01

The Transuranic Waste Characterization Quality Assurance Program Plan required each U.S. Department of Energy (DOE) site that characterizes transuranic waste to be sent the Waste Isolation Pilot Plan that addresses applicable requirements specified in the quality assurance project plan (QAPP)

Interface management for the Yucca Mountain Project

International Nuclear Information System (INIS)

1988-12-01

The subject of this report is selection of that portion of physical and informational interfaces that need to be controlled on the Yucca Mountain Project (YMP). Physical interfaces are interactions between physical elements of the mined geologic disposal system; for example, the repository shafts will interface with the shafts in the Exploratory Shaft Facility (ESF), because the ESF shafts will eventually be absorbed into the repository as additional repository shafts. Informational interfaces are interactions involving an exchange of information between organizations working on the mined geologic disposal system; for example, the in situ testing contractor will interact with the site performance assessment contractor and will supply information regarding host rock behavior. This report describes the physical system interfaces that can be identified from analysis of a physical system structure. A discussion of informational interfaces can be found elsewhere. 30 refs., 8 figs., 3 tabs

Waste Tank Vapor Characterization Project: Annual status report for FY 1995

International Nuclear Information System (INIS)

Ligotke, M.W.; Fruchter, J.S.; Huckaby, J.L.; Birn, M.B.; McVeety, B.D.; Evans, J.C. Jr.; Pool, K.H.; Silvers, K.L.; Goheen, S.C.

1995-11-01

This report compiles information collected during the Fiscal Year 1995 pertaining to the waste tank vapor characterization project. Information covers the following topics: project management; organic sampling and analysis; inorganic sampling and analysis; waste tank vapor data reports; and the waste tanks vapor database

Quality assurance program plan for SNF characterization support project

International Nuclear Information System (INIS)

Tanke, J.M.

1997-01-01

This Quality Assurance Program Plan (QAPP) provides information on how the Quality Assurance Program is implemented for the Spent Nuclear Fuel Characterization Support Project. This QAPP has been developed specifically for the Spent Nuclear Fuel Characterization Support Project, per Letter of Instruction (LOI) from Duke Engineering and Services Company, letter No. DESH-9655870, dated Nov. 22, 1996. It applies to those items and tasks which affect the completion of activities identified in the work breakdown structure of the Project Management Plan (PMP) and LOI. These activities include installation of sectioning equipment and furnace, surface and subsurface examinations, sectioning for metallography, and element drying and conditioning testing, as well as project related operations within the 327 facility as it relates to the specific activities of this project. General facility activities are covered in other appropriate QA-PPS. In addition, this QAPP supports the related quality assurance activities addressed in CM-2-14, Hazardous Material Packaging and Shipping,1261 and HSRCM-1, Hanford Site Radiological Control Manual. The 327 Building is currently transitioning from being a Pacific Northwest National Laboratory (PNNL) managed facility to a Babcock and Wilcox Hanford Company (BVMC) managed facility. During this transition process existing procedures and documents will be utilized until replaced by BVMC procedures and documents. These documents conform to the requirements found in PNL-MA-70, Quality Assurance Manual and PNL-MA-8 1, Hazardous Materials Shipping Manual. The Quality Assurance Program Index (QAPI) contained in Table 1 provides a matrix which shows how project activities relate to IO CFR 830.120 and 5700.6C criteria. Quality Assurance program requirements will be addressed separate from the requirements specified in this document. Other Hanford Site organizations/companies may be utilized in support of this project and the subject organizations are

TWRS privatization support project waste characterization database development

International Nuclear Information System (INIS)

1995-11-01

Pacific Northwest National Laboratory requested support from ICF Kaiser Hanford Company in assembling radionuclide and chemical analyte sample data and inventory estimates for fourteen Hanford underground storage tanks: 241-AN-102, -104, -105, -106, and -107, 241-AP-102, -104, and -105, 241-AW-101, -103, and -105, 241 AZ-101 and -102; and 241-C-109. Sample data were assembled for sixteen radionuclides and thirty-five chemical analytes. The characterization data were provided to Pacific Northwest National Laboratory in support of the Tank Waste Remediation Services Privatization Support Project. The purpose of this report is to present the results and document the methodology used in preparing the waste characterization information data set to support the Tank Waste Remediation Services Privatization Support Project. This report describes the methodology used in assembling the waste characterization information and how that information was validated by a panel of independent technical reviewers. Also, contained in this report are the various data sets created: the master data set, a subset, and an unreviewed data set. The master data set contains waste composition information for Tanks 241-AN-102 and -107, 241-AP-102 and -105, 241-AW-101; and 241-AZ-101 and -102. The subset contains only the validated analytical sample data from the master data set. The unreviewed data set contains all collected but unreviewed sample data for Tanks 241-AN-104, -105, and -106; 241-AP-104; 241-AW-103 and-105; and 241-C-109. The methodology used to review the waste characterization information was found to be an accurate, useful way to separate the invalid or questionable data from the more reliable data. In the future, this methodology should be considered when validating waste characterization information

Preliminary drift design analyses for nuclear waste repository in tuff

International Nuclear Information System (INIS)

Hardy, M.P.; Brechtel, C.E.; Goodrich, R.R.; Bauer, S.J.

1990-01-01

The Yucca Mountain Project (YMP) is examining the feasibility of siting a repository for high-level nuclear waste at Yucca Mountain, on and adjacent to the Nevada Test Site (NTS). The proposed repository will be excavated in the Topopah Spring Member, which is a moderately fractured, unsaturated, welded tuff. Excavation stability will be required during construction, waste emplacement, retrieval (if required), and closure to ensure worker safety. The subsurface excavations will be subject to stress changes resulting from thermal expansion of the rock mass and seismic events associated with regional tectonic activity and underground nuclear explosions (UNEs). Analyses of drift stability are required to assess the acceptable waste emplacement density, to design the drift shapes and ground support systems, and to establish schedules and cost of construction. This paper outlines the proposed methodology to assess drift stability and then focuses on an example of its application to the YMP repository drifts based on preliminary site data. Because site characterization activities have not begun, the database currently lacks the extensive site-specific field and laboratory data needed to form conclusions as to the final ground support requirements. This drift design methodology will be applied and refined as more site-specific data are generated and as analytical techniques and methodologies are verified during the site characterization process

Tank waste remediation system characterization project quality policies

International Nuclear Information System (INIS)

Board, D.C.

1997-01-01

This quality plan describes the system used by Characterization Project management to achieve quality. This plan is comprised of eleven quality policies which, when taken together, form a management system deployed to achieve quality. This quality management system is based on the customer's quality requirements known as the 'RULE', 10 CFR 830.120, Quality Assurance

REPOSITORY RADIATION SHIELDING DESIGN GUIDE

International Nuclear Information System (INIS)

M. Haas; E.M. Fortsch

1997-01-01

The scope of this document includes radiation safety considerations used in the design of facilities for the Yucca Mountain Site Characterization Project (YMP). The purpose of the Repository Radiation Shielding Design Guide is to document the approach used in the radiological design of the Mined Geologic Disposal System (MGDS) surface and subsurface facilities for the protection of workers, the public, and the environment. This document is intended to ensure that a common methodology is used by all groups that may be involved with Radiological Design. This document will also assist in ensuring the long term survivability of the information basis used for radiological safety design and will assist in satisfying the documentation requirements of the licensing body, the Nuclear Regulatory Commission (NRC). This design guide provides referenceable information that is current and maintained under the YMP Quality Assurance (QA) Program. Furthermore, this approach is consistent with maintaining continuity in spite of a changing design environment. This approach also serves to ensure common inter-disciplinary interpretation and application of data

REPOSITORY RADIATION SHIELDING DESIGN GUIDE

Energy Technology Data Exchange (ETDEWEB)

M. Haas; E.M. Fortsch

1997-09-12

The scope of this document includes radiation safety considerations used in the design of facilities for the Yucca Mountain Site Characterization Project (YMP). The purpose of the Repository Radiation Shielding Design Guide is to document the approach used in the radiological design of the Mined Geologic Disposal System (MGDS) surface and subsurface facilities for the protection of workers, the public, and the environment. This document is intended to ensure that a common methodology is used by all groups that may be involved with Radiological Design. This document will also assist in ensuring the long term survivability of the information basis used for radiological safety design and will assist in satisfying the documentation requirements of the licensing body, the Nuclear Regulatory Commission (NRC). This design guide provides referenceable information that is current and maintained under the YMP Quality Assurance (QA) Program. Furthermore, this approach is consistent with maintaining continuity in spite of a changing design environment. This approach also serves to ensure common inter-disciplinary interpretation and application of data.

Using an engaging approach to products to help create long-term credibility

International Nuclear Information System (INIS)

McNeill, G.; Larkin, E.

1993-01-01

A long-term, thorough and engaging public information products plan is essential for supporting interaction between Nevadans and the scientists and staff of the US DOE Yucca Mountain Site Characterization Project (YMP). As members of the Institutional and External Affairs office on the YMP in Nevada, our focus is to create successful products for a Nevada audience, in accordance with DOE regulations. Our product plan is broad, but has the same theoretical foundation whether we are developing a new fact sheet of working with a scientist to help him or her communicate effectively. Our goals are to: Create products that help build long-term credibility; communicate honestly about risk; engage the public in meaningful, effective ways; be receptive to hearing Nevadans' concerns and questions; respond in ways that indicate that the public has been heard and respected; and to keep away from the open-quotes usclose quotes versus open-quotes themclose quotes orientation, distinguishing our communication approach from others. Explanations of our rationale, products plan, and goals and techniques for achieving them are stated, and related problems are described

Management and research of desert tortoises for the Yucca Mountain Project

International Nuclear Information System (INIS)

Rautenstrauch, K.R.; Cox, M.K.; Doerr, T.B.; Green, R.A.; Mueller, J.M.; O'Farrell, T.P.; Rakestraw, D.L.

1991-01-01

A program has been developed for the Yucca Mountain Project (YMP) to manage and study the desert tortoise (Gopherus agassizi), a threatened species that occurs at low densities at Yucca Mountain. The goals of this program are to better understand the biology and status of the desert tortoise population at Yucca Mountain, assess impacts on tortoises of site characterization (SC) activities, and minimize those impacts. The first steps we took to develop this program were to compile the available information on tortoise biology at Yucca Mountain, ascertain what information was lacking, and identify the potential impacts on tortoises of SC. We then developed a technical design for identifying and mitigating direct and cumulative impacts and providing information on tortoise biology. Interrelated studies were developed to achieve these objectives. The primary sampling unit for the impact monitoring studies is radiomarked tortoises. Three populations of tortoises will be sampled: individuals isolated from disturbances (control), individuals near major SC activities (direct effects treatment and worst-case cumulative effects treatment), and individuals from throughout Yucca Mountain (cumulative effects treatment). Impacts will be studied by measuring and comparing survival, reproduction, movements, habitat use, health, and diet of these tortoises. A habitat quality model also will be developed and the efficacy of mitigation techniques, such as relocating tortoises, will be evaluated. 29 refs

Microstructural Analyses of Topopah Spring Tuff from the Large Block Test at Fran Ridge, Nevada

International Nuclear Information System (INIS)

Roberts, J.J.

2000-01-01

Microstructural information (e.g., porosity, pore size distribution, and surface area) of porous media is critical to understanding water transport mechanisms and physical properties and their bearing on geophysical measurements. We report microstructural data obtained by mercury injection porosimetry (MIP) on 33 samples of densely welded Topopah Spring tuff from Fran Ridge, Yucca Mountain, Nevada Test Site (NTS), Nevada. The characterization of these samples is also important for the interpretation and analysis of the Large Block Test (LBT) performed in support of the Yucca Mountain Project (YMP). This report includes previously published data on samples from the same location (Roberts and Lin, 1996). We also present information from the Yucca Mountain Site Characterization Project/Lawrence Livermore National Laboratory (YMSCP/LLNL) Large Block Test Engineering Plan (Wilder, 1995) to allow correlation of our data directly to various planes within the Large Block

TWRS privatization support project waste characterization database development. Volume 1

International Nuclear Information System (INIS)

Brevick, C.H.

1995-11-01

Pacific Northwest National Laboratory requested support from ICF Kaiser Hanford Company in assembling radionuclide and chemical analyte sample data and inventory estimates for fourteen Hanford under-ground storage tanks: 241-AN-102, -104, -105, -106, and -107, 241-AP-102, -104, and -105; 241-AW-101, -103, and -105, 241-AZ-101 and-102; and 241-C-109. Sample data were assembled for sixteen radio nuclides and thirty five chemical analytes. The characterization data were provided to Pacific Northwest National Laboratory in support of the Tank Waste Remediation Services Privatization Support Project. The purpose of this report is to present the results and document the methodology used in preparing the waste characterization information data set to support the Tank Waste Remediation Services Privatization Support Project. This report describes the methodology used in assembling the waste characterization information and how that information was validated by a panel of independent technical reviewers. Also, contained in this report are the various data sets created., the master data set, a subset, and an unreviewed data set

Yucca Mountain Site Characterization Project Bibliography, July--December 1994: An update

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-03-01

Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Charactrization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy`s Science and Technology Database from July 1, 1994 through December 31, 1994. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers, and articles are included in the sponsoring organization`s list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it.

Yucca Mountain Site Characterization Project Bibliography, July, December 194: An update

International Nuclear Information System (INIS)

1995-03-01

Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Charactrization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy's Science and Technology Database from July 1, 1994 through December 31, 1994. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers, and articles are included in the sponsoring organization's list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it

SMART 3D SUBSURFACE CONTAMINANT CHARACTERIZATION AT THE BGRR DEC OMMISSIONING PROJECT

International Nuclear Information System (INIS)

HEISER, J.; KALB, P.; SULLIVAN, T.; MILIAN, L.

2002-01-01

The Brookhaven Graphite Research Reactor is currently on an accelerated decommissioning schedule with a completion date projected for 2005. The accelerated schedule combines characterization with removal actions for the various systems and structures. A major project issue involves characterization of the soils beneath contaminated Below Grade Ducts (BGD), the main air ducts connecting the exhaust plenums with the Fan House. The air plenums experienced water intrusion during BGRR operations and after shutdown. The water intrusions were attributed to rainwater leaks into degraded parts of the system, and to internal cooling water system leaks. If the characterization could provide enough information to show that soil contamination surrounding the BGD is either below cleanup guidelines or is very localized and can be ''surgically removed'' at a reasonable cost, the ducts may be decontaminated and left in place. This will provide significant savings compared to breaking up the 170-ft. long concrete duct, shipping the projected 9,000 m 3 of waste off-site and disposing of it in an approved site

Yucca Mountain Site Characterization Project bibliography, July--December 1992: An update, Supplement 3, Addendum 2

International Nuclear Information System (INIS)

1993-04-01

Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy's Energy Science and Technology Database from July 1, 1992, through December 31, 1992. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers, and articles are included in the sponsoring organization's list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it

Yucca Mountain Site Characterization Project bibliography, January--June 1995. Supplement 4, Add.3: An update

Energy Technology Data Exchange (ETDEWEB)

Stephan, P.M. [ed.

1996-01-01

Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy`s Energy Science and Technology Database from January 1, 1995, through June 30, 1995. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers, and articles are included in the sponsoring organization`s list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it.

Yucca Mountain Site Characterization Project Bibliography, January--June 1993. An update: Supplement 4, Addendum 1

Energy Technology Data Exchange (ETDEWEB)

Stephan, P.M. [ed.

1995-01-01

Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy`s Energy Science and Technology Database from January 1, 1994 through June 30, 1994. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers,and articles are included in the sponsoring organization`s list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it.

Yucca Mountain Site Characterization Project Bibliography, January--June 1993. An update: Supplement 4, Addendum 1

International Nuclear Information System (INIS)

Stephan, P.M.

1995-01-01

Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy's Energy Science and Technology Database from January 1, 1994 through June 30, 1994. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers,and articles are included in the sponsoring organization's list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it

Yucca Mountain Site Characterization Project bibliography, January--June 1995. Supplement 4, Add.3: An update

International Nuclear Information System (INIS)

Stephan, P.M.

1996-01-01

Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy's Energy Science and Technology Database from January 1, 1995, through June 30, 1995. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers, and articles are included in the sponsoring organization's list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it

A formal communication process: Pathway to improved policy making

International Nuclear Information System (INIS)

Benson, A.; Robison, A.C.; Seidler, P.E.

1993-01-01

This paper will examine the efforts made and the steps taken by the US DOE's Office of Civilian Radioactive Waste Management (DOE/OCRWM) to establish and keep open lines of communication with officials in Nye County, Nevada, the location of Yucca Mountain, the site of a proposed high-level nuclear waste repository. These efforts include creating policies and procedures for conducting oversight of the Yucca Mountain Site Characterization Project (YMP), as well as developing programs for engaging in technical studies, requests for impact assistance and financial assistance, and ensuring there's a continuous flow of information to the residents of Nevada

Technology projects for characterization--monitoring of volatile organic compounds (VOCs)

Energy Technology Data Exchange (ETDEWEB)

Junk, G.A.; Haas, W.J. Jr.

1992-07-01

One hundred thirty technology project titles related to the characterization of volatile organic compounds (VOCs) at an arid site are listed alphabetically by first contact person in a master compilation that includes phone numbers, addresses, keywords, and short descriptions. Separate tables are presented for 62 field-demonstrated, 36 laboratory-demonstrated, and 35 developing technology projects. The technology projects in each of these three categories are also prioritized in separate summary tables. Additional tables are presented for a number of other categorizations of the technology projects: In Situ; Fiberoptic; Mass Spectrometer; Optical Spectroscopy; Raman or SERS; Ion Mobility or Acoustic; Associated; and Commercial. Four lists of contact person names are provided so details concerning the projects that deal with sampling, and VOCs in gases, waters, and soils (sediments) can be obtained. Finally, seven wide-ranging conclusions based on observations and experiences during this work are presented.

Technology projects for characterization--monitoring of volatile organic compounds (VOCs)

International Nuclear Information System (INIS)

Junk, G.A.; Haas, W.J. Jr.

1992-07-01

One hundred thirty technology project titles related to the characterization of volatile organic compounds (VOCs) at an arid site are listed alphabetically by first contact person in a master compilation that includes phone numbers, addresses, keywords, and short descriptions. Separate tables are presented for 62 field-demonstrated, 36 laboratory-demonstrated, and 35 developing technology projects. The technology projects in each of these three categories are also prioritized in separate summary tables. Additional tables are presented for a number of other categorizations of the technology projects: In Situ; Fiberoptic; Mass Spectrometer; Optical Spectroscopy; Raman or SERS; Ion Mobility or Acoustic; Associated; and Commercial. Four lists of contact person names are provided so details concerning the projects that deal with sampling, and VOCs in gases, waters, and soils (sediments) can be obtained. Finally, seven wide-ranging conclusions based on observations and experiences during this work are presented

Large Area Projection Microstereolithography: Characterization and Optimization of 3D Printing Parameters

Energy Technology Data Exchange (ETDEWEB)

Ng, Melissa R. [Ohlone College, Fremont, CA (United States); Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Moran, Bryan [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bekker, Logan [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dudukovic, Nikola [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2016-08-12

Large Area Projection Microstereolithography (LAPμSL) is a new technology that allows the additive manufacture of parts that have feature sizes spanning from centimeters to tens of microns. Knowing the accuracy of builds from a system like this is a crucial step in development. This project explored the capabilities of the second and newest LAPμSL system that was built by comparing the features of actual builds to the desired structures. The system was then characterized in order to achieve the best results. The photo polymeric resins that were used were Autodesk PR48 and HDDA. Build parameters for Autodesk PR48 were found that allowed the prints to progress while using the full capacity of the system to print quality parts in a relatively short amount of time. One of the larger prints in particular had a print time that was nearly eighteen times faster than it would have been had printed in the first LAPμSL system. The characterization of HDDA resin helped the understanding that the flux of the light projected into the resin also affected the quality of the builds, rather than just the dose of light given. Future work for this project includes exploring the use of other resins in the LAPμSL systems, exploring the use of Raman Spectroscopy to analyze builds, and completing the characterization of the LAPμSL system.

Study of ultrasonic characterization and propagation in austenitic welds: The MOSAICS project

Energy Technology Data Exchange (ETDEWEB)

Chassignole, Bertrand, E-mail: bertrand.chassignole@edf.fr [EDF R and D, MMC department, Les Renardières, 77818 Moret sur Loing (France); Recolin, Patrick, E-mail: patrick.recolin@dcnsgroup.com [DCNS CESMAN, 44620 La montagne (France); Leymarie, Nicolas, E-mail: nicolas.leymarie@cea.fr [CEA LIST, 91191 Gif-sur-Yvette (France); Gueudré, Cécile, E-mail: cecile.gueudre@univ-amu.fr [LMA, Aix Marseille Université, CNRS, UPR 7051, F-13402 Marseille Cedex 20 (France); Guy, Philippe, E-mail: philippe.guy@insa-lyon.fr [INSA Lyon, LVA laboratory, 69621 Villeurbanne (France); Elbaz, Deborah, E-mail: deborah.elbaz@extende.com [Extende, 91400 Orsay (France)

2015-03-31

Regulatory requirements enforce a volumetric inspection of welded components of nuclear equipments. However, the multi-pass austenitic welds are characterized by anisotropic and heterogeneous structures which lead to numerous disturbances of the ultrasonic beam. The MOSAICS project supported by the ANR (French National Research Agency) aims at matching various approaches to improve the prediction of the ultrasonic testing in those welds. The first stage consists in characterizing the weld structure (determination of the columnar grain orientation and measurements of elastic constants and attenuation coefficients). The techniques of characterization provide input data for the modeling codes developed in another task of the project. For example, a 3D version of the finite elements code ATHENA is developed by EDF R and D to take into account anisotropic texture in any direction. Semi-analytical models included in CIVA software are also improved to better predict the ultrasonic propagation in highly anisotropic and heterogeneous structures. The last stage deals with modeling codes validation based on experimental inspections on representative mock-ups containing calibrated defects. The objective of this paper is to give an overview of the MOSAICS project and to present specific results illustrating the various tasks.

Uranium soils integrated demonstration: Soil characterization project report

International Nuclear Information System (INIS)

Cunnane, J.C.; Gill, V.R.; Lee, S.Y.; Morris, D.E.; Nickelson, M.D.; Perry, D.L.; Tidwell, V.C.

1993-08-01

An Integrated Demonstration Program, hosted by the Fernald Environmental Management Project (FEMP), has been established for investigating technologies applicable to the characterization and remediation of soils contaminated with uranium. Critical to the design of relevant treatment technologies is detailed information on the chemical and physical characteristics of the uranium waste-form. To address this need a soil sampling and characterization program was initiated which makes use of a variety of standard analytical techniques coupled with state-of-the-art microscopy and spectroscopy techniques. Sample representativeness is evaluated through the development of conceptual models in an effort to identify and understand those geochemical processes governing the behavior of uranium in FEMP soils. Many of the initial results have significant implications for the design of soil treatment technologies for application at the FEMP

Uranium soils integrated demonstration: Soil characterization project report

Energy Technology Data Exchange (ETDEWEB)

Cunnane, J.C. [Argonne National Lab., IL (United States); Gill, V.R. [Fernald Environmental Restoration Management Corp., Cincinnati, OH (United States); Lee, S.Y. [Oak Ridge National Lab., TN (United States); Morris, D.E. [Los Alamos National Lab., NM (United States); Nickelson, M.D. [HAZWRAP, Oak Ridge, TN (United States); Perry, D.L. [Lawrence Berkeley Lab., CA (United States); Tidwell, V.C. [Sandia National Labs., Albuquerque, NM (United States)

1993-08-01

An Integrated Demonstration Program, hosted by the Fernald Environmental Management Project (FEMP), has been established for investigating technologies applicable to the characterization and remediation of soils contaminated with uranium. Critical to the design of relevant treatment technologies is detailed information on the chemical and physical characteristics of the uranium waste-form. To address this need a soil sampling and characterization program was initiated which makes use of a variety of standard analytical techniques coupled with state-of-the-art microscopy and spectroscopy techniques. Sample representativeness is evaluated through the development of conceptual models in an effort to identify and understand those geochemical processes governing the behavior of uranium in FEMP soils. Many of the initial results have significant implications for the design of soil treatment technologies for application at the FEMP.

Global Threat Reduction Initiative Fuel Thermo-Physical Characterization Project: Sample Management Plan

Energy Technology Data Exchange (ETDEWEB)

Casella, Amanda J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Pereira, Mario M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Steen, Franciska H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2013-01-01

This sample management plan provides guidelines for sectioning, preparation, acceptance criteria, analytical path, and end-of-life disposal for the fuel element segments utilized in the Global Threat Reduction Initiative (GTRI), Fuel Thermo-Physical Characterization Project. The Fuel Thermo-Physical Characterization Project is tasked with analysis of irradiated Low Enriched Uranium (LEU) Molybdenum (U-Mo) fuel element samples to support the GTRI conversion program. Sample analysis may include optical microscopy (OM), scanning electron microscopy (SEM) fuel-surface interface analysis, gas pycnometry (density) measurements, laser flash analysis (LFA), differential scanning calorimetry (DSC), thermogravimetry and differential thermal analysis with mass spectroscopy (TG /DTA-MS), Inductively Coupled Plasma Spectrophotometry (ICP), alpha spectroscopy, and Thermal Ionization Mass Spectroscopy (TIMS). The project will utilize existing Radiochemical Processing Laboratory (RPL) operating, technical, and administrative procedures for sample receipt, processing, and analyses. Test instructions (TIs), which are documents used to provide specific details regarding the implementation of an existing RPL approved technical or operational procedure, will also be used to communicate to staff project specific parameters requested by the Principal Investigator (PI). TIs will be developed, reviewed, and issued in accordance with the latest revision of the RPL-PLN-700, RPL Operations Plan. Additionally, the PI must approve all project test instructions and red-line changes to test instructions.

Management system information of characterization of the dismantling project of Jose Cabrera

International Nuclear Information System (INIS)

Gimeno Blesa, M. E.; Martin Palomo, N.; Gomez Rodriguez, C. A.

2011-01-01

In the proposed dismantling and decommissioning of the Jose Cabrera NPP is designed and implemented a database of physical and radiological inventory, which provides a powerful tool to optimize the storage, monitoring and control of the characterization data. The database is a useful and reliable management system characterization information that facilitates access and information processing, and ensures their integrity and traceability along of the dismantling project.

Yucca Mountain Biological Resources Monitoring Program. Progress report, October 1992--December 1993

International Nuclear Information System (INIS)

1994-05-01

The US Department of Energy (DOE) is required by the Nuclear Waste Policy Act of (as amended in 1987) to study and characterize the suitability of Yucca Mountain as a potential geologic repository for high-level nuclear waste. During site characterization, the DOE will conduct a variety of geotechnical, geochemical, geological, and hydrological studies to determine the suitability of Yucca Mountain as a potential repository. To ensure that site characterization activities do not adversely affect the environment at Yucca Mountain, a program has been implemented to monitor and mitigate potential impacts and ensure activities comply with applicable environmental regulations. This report describes the activities and accomplishments of EG ampersand G Energy Measurements, Inc. (EG ampersand G/EM) from October 1992 through December 1993 for six program areas within the Terrestrial Ecosystem component of the environmental program for the Yucca Mountain Site Characterization Project (YMP): Site Characterization Effects, Desert Tortoises (Gopherus agassizii), Habitat Reclamation, Monitoring and Mitigation, Radiological Monitoring, and Biological Support

Yucca Mountain Biological Resources Monitoring Program. Progress report, January 1994--December 1994

International Nuclear Information System (INIS)

1995-07-01

The US Department of Energy (DOE) is required by the Nuclear Waste Policy Act of 1982 (as amended in 1987) to study and characterize the suitability of Yucca Mountain as a potential geological repository for high-level nuclear waste. During site characterization, the DOE will conduct a variety of geotechnical, geochemical, geological, and hydrological studies to determine the suitability of Yucca Mountain as a potential repository. To ensure that site characterization activities do not adversely affect the environment at Yucca Mountain, a program has been implemented to monitor and mitigate potential impacts and ensure activities comply with applicable environmental regulations. This report describes the activities and accomplishments of EG and G Energy Measurements, Inc. (EG and G/EM) from January 1994 through December 1994 for six program areas within the Terrestrial Ecosystem component of the environmental program for the Yucca Mountain Site Characterization Project (YMP): Site Characterization Effects, Desert Tortoises (Gopherus agassizii), Habitat Reclamation, Monitoring and Mitigation, Radiological Monitoring, and Biological Support

TWRS phase 1 infrastructure project (W-519) characterization

International Nuclear Information System (INIS)

Mitchell, C.J.

1998-01-01

In order to treat the mixed radioactive and hazardous waste stored in 177 underground tanks, the Tank Waste Remediation System (TWRS) program is developing a 'demonstration' site for treatment and immobilization of these wastes by a private contractor. Project W-519 is providing the infrastructure support to this site by developing the designs and emplacing required pipelines, roads, electrical, etc. In support of the TWRS Phase 1 Infrastructure Project (W-519) Characterization, Numatec Hanford Corporation (NHC) contracted with Waste Management Federal Services, Inc., Northwest Operations (WMNW) to investigate a number of locations in and just outside the 200 East Area eastern fenceline boundary. These areas consisted of known or suspected waste lines or waste sites that could potentially impact the construction and emplacement of the proposed facility improvements, including waterlines and roads. These sites were all located subsurface and sugaring would be required to obtain sample material from the desired depth. The soils would then be sampled and submitted to the laboratory for analysis of radioactivity

Draft site characterization analysis of the site characterization report for the Basalt Waste Isolation Project, Hanford, Washington Site. Main report and Appendices A through D

International Nuclear Information System (INIS)

1983-03-01

On November 12, 1982, the US Department of Energy submitted to the US Nuclear Regulatory Commission the Site Characterization Report for the Basalt Waste Isolation Project (DOE/RL 82-3). The Basalt Waste Isolation Project is located on DOE's Hanford Reservation in the State of Washington. NUREG-0960 contains the detailed analysis, by the NRC staff, of the site characterization report. Supporting technical material is contained in Appendices A through W

Transdermal delivery of flurbiprofen from surfactant-based vesicles: particle characterization and the effect of water on in vitro transport.

Science.gov (United States)

Uchino, Tomonobu; Matsumoto, Yuiko; Murata, Akiko; Oka, Toshihiko; Miyazaki, Yasunori; Kagawa, Yoshiyuki

2014-04-10

Flurbiprofen loaded rigid and elastic vesicles comprising the bilayer-forming surfactant sucrose-ester laurate were prepared by the film rehydration and extrusion method. The charge-inducing agent sodium dodecyl sulfate, and the micelle-forming surfactants, sorbitan monolaurate, polyethylene glycol monolaurate, and polysorbate 20, were used to enhance elasticity. Vesicle formulations were evaluated for size, zeta potential, (1)H and (19)F nuclear magnetic resonance (NMR) spectra, and in vitro skin permeation across Yucatan micropig (YMP) skin. Vesicle formulations were stable for 2 weeks and their mean sizes were 95-135 nm. NMR spectroscopy showed that flurbiprofen molecular mobility was restricted by interaction with vesicle components because of entrapment in vesicle bilayers. Moreover, sorbitan monolaurate-containing vesicles strongly retained flurbiprofen molecules. After non-occlusive application to YMP skin, flurbiprofen transport from all vesicle formulations was superior to that of flurbiprofen alone and remarkably decreased after water vaporization. Polarization microscopy and small-angle X-ray diffraction analysis showed that the vesicle formulation was transferred to liquid crystalline state. Suppression of vesicle transition to the liquid crystalline state was observed with applications of both large quantities and diluted samples. The presence of water in the formulations was associated with maintenance of the vesicle structure and greater flurbiprofen transport across YMP skin. Copyright © 2014 Elsevier B.V. All rights reserved.

Visualization and characterization of users in a citizen science project

Science.gov (United States)

Morais, Alessandra M. M.; Raddick, Jordan; Coelho dos Santos, Rafael D.

2013-05-01

Recent technological advances allowed the creation and use of internet-based systems where many users can collaborate gathering and sharing information for specific or general purposes: social networks, e-commerce review systems, collaborative knowledge systems, etc. Since most of the data collected in these systems is user-generated, understanding of the motivations and general behavior of users is a very important issue. Of particular interest are citizen science projects, where users without scientific training are asked for collaboration labeling and classifying information (either automatically by giving away idle computer time or manually by actually seeing data and providing information about it). Understanding behavior of users of those types of data collection systems may help increase the involvement of the users, categorize users accordingly to different parameters, facilitate their collaboration with the systems, design better user interfaces, and allow better planning and deployment of similar projects and systems. Behavior of those users could be estimated through analysis of their collaboration track: registers of which user did what and when can be easily and unobtrusively collected in several different ways, the simplest being a log of activities. In this paper we present some results on the visualization and characterization of almost 150.000 users with more than 80.000.000 collaborations with a citizen science project - Galaxy Zoo I, which asked users to classify galaxies' images. Basic visualization techniques are not applicable due to the number of users, so techniques to characterize users' behavior based on feature extraction and clustering are used.

Site characterization quality assurance for the California LLRW Disposal Site Project

International Nuclear Information System (INIS)

Hanrahan, T.P.; Ench, J.E.; Serlin, C.L.; Bennett, C.B.

1988-01-01

In December of 1985 US Ecology was chosen as the license designee for the State of California's low-level radioactive waste disposal facility. In early 1987, three candidate sites were selected for characterization studies in preparation for identifying the preferred site. The geotechnical characterization activities along with studies of the ecological and archaeological attributes, as well as assessments of the socio-economic impacts and cultural resources all provide input towards selection of the proposed site. These technical studies in conjunction with comments from local citizen committees and other interested parties are used as a basis for determining the proposed site for which full site characterization as required by California licensing requirements are undertaken. The purpose of this paper is to present an overview of the program for Quality Assurance and Quality Control for the site characterization activities on the California LLRW Disposal Site Project. The focus is on three major perspectives: The composite QA Program and two of the primary characterization activities, the geotechnical and the meteorological investigations

NEOShield-2 Project: Final Results on Compositional Characterization of small NEOs

Science.gov (United States)

Barucci, Maria Antonieta; Perna, Davide; Fornasier, Sonia; Doressoundiram, Alain; Lantz, Cateline; Popescu, Marcel; Merlin, Frederic; Fulchignoni, Marcello

2017-10-01

NEOShield-2 project was selected in the framework of the European Commission H2020 program in answer to the call for “Access technologies and characterisation for Near Earth Objects (NEOs)”. NEOShield-2 project (2015-2017) is a follow-up of the first NEOShield (2012-2015) and includes 11 European Institutions and Industries. The main objectives of NEOShield-2 project are: i) technological development on techniques and instruments needed for GNC for possible asteroid missions and ii) characterization of NEOs of small sizes.Our team at LESIA is the leader of the entire observational program which involved complementary techniques to provide physical and compositional characterization of NEOs. Priority has been given to potential space-mission targets, optimized for mitigation or exploration missions. In this framework an agreement with the European Southern Observatory was signed to obtain Guaranteed Time Observations at the 3.6-meter NTT with an allocation of 30 nights to characterize by spectroscopy the composition of the smaller asteroids. The objects with an absolute magnitude larger than 20 were selected, with a priority for the very small newly discovered objects.We obtained more than 170 new spectra of NEOs. The observations were performed with EFOSC2 instrument. We covered the wavelength interval 0.4-0.92 microns, with a resolution of R=~200. The observed asteroids include 29 asteroids with diameters smaller than 100 meters and 71 with diameters between 100 and 300 m.The taxonomic type has been assigned for 137 individual objects. Our results on NEO mineralogical compositions provide a body of reference data directly applicable to the design and development of mitigation-relevant space missions. Within our survey, we found eight D-types with ΔV funding by European Commission Horizon 2020 program (contract No. PROTEC-2-2014-640351).

Testing the spatial neutrality of the REMI net migration equation

International Nuclear Information System (INIS)

Barr, C.F.; Perrigo, T.A.; Daneshvary, N.; Rickman, D.S.

1994-01-01

The U.S. Department of Energy (DOE), Yucca Mountain Site Characterization Project Office (YMPO) is conducting socioeconomic studies in the State of Nevada in accordance with the Nuclear Waste Policy Act of 1982, as amended. The main purpose of the socioeconomic program is to avoid or minimize adverse socioeconomic impacts of the Yucca Mountain Site Characterization Project (YMP) on local communities, counties, and the state of Nevada. This objective is being met by collecting data that can be used by the DOE and affected units of local government to monitor economic and demographic variables and forecast changes that may occur as a direct result of the YMP. One of the tools being used to develop population and employment forecasts in Clark, Lincoln, and Nye counties in Nevada is Regional Economic Modeling Inc.'s (REMI) Economic-Demographic Forecasting and Simulation (EDFS) model. The REMI model is widely used in applied economics for: forecasting and planning; economic development; transportation; energy and natural resources; taxation, budget, and welfare; United States policies; and environmental policies. This model was chosen by the DOE because it is a dynamic econometric model based on accepted economic theory and principles, and because of its favorable rating compared to other available models. The dynamic nature of the model offers improvements in forecasting capabilities over input-output models. Because the DOE is making extensive use of the REMI model, it is necessary to evaluate the model's forecasting performance. This study is an empirical test of the restrictions in the REMI model's net migration equation. The REMI model pools the data across regions to estimate net migration into each region. For this study we will examine Clark County net migration. We hypothesize that due to the differences among regions (such as distance, and geographic and cultural features specific to each region), pooling the data across regions may not be appropriate

Engineered materials characterization report for the Yucca Mountain Site Characterization Project. Volume 3: Corrosion and data modeling

International Nuclear Information System (INIS)

Van Konynenburg, R.A.; McCright, R.D.; Roy, A.K.; Jones, D.A.

1995-08-01

This three-volume report serves several purposes. The first volume provides an introduction to the engineered materials effort for the Yucca Mountain Site Characterization Project. It defines terms and outlines the history of selection and characterization of these materials. A summary of the recent engineered barrier materials characterization workshop is presented, and the current candidate materials are listed. The second volume tabulates design data for engineered materials, and the third volume is devoted to corrosion data, radiation effects on corrosion, and corrosion modeling. The second and third volumes are intended to be evolving documents, to which new data will be added as they become available from additional studies. The initial version of Volume 3 is devoted to information currently available for environments most similar to those expected in the potential Yucca Mountain repository. This is volume three

Characterizing symmetries in a projected entangled pair state

Energy Technology Data Exchange (ETDEWEB)

Perez-Garcia, D; Gonzalez-Guillen, C E [Departamento Analisis Matematico and IMI, Universidad Complutense de Madrid, 28040 Madrid (Spain); Sanz, M; Cirac, J I [Max-Planck-Institut fuer Quantenoptik, Hans-Kopfermann-Str. 1, 85748 Garching (Germany); Wolf, M M [Niels Bohr Institute, Blegdamsvej 17, 2100 Copenhagen (Denmark)], E-mail: dperez@mat.ucm.es

2010-02-15

We show that two different tensors defining the same translational invariant injective projected entangled pair state (PEPS) in a square lattice must be the same up to a trivial gauge freedom. This allows us to characterize the existence of any local or spatial symmetry in the state. As an application of these results we prove that a SU(2) invariant PEPS with half-integer spin cannot be injective, which can be seen as a Lieb-Shultz-Mattis theorem in this context. We also give the natural generalization for U(1) symmetry in the spirit of Oshikawa-Yamanaka-Affleck, and show that a PEPS with Wilson loops cannot be injective.

Conceptual, experimental and computational approaches to support performance assessment of hydrology and chemical transport at Yucca Mountain; Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

Narasimhan, T.N.; Wang, J.S.Y. [Lawrence Berkeley Lab., CA (United States)

1992-07-01

The authors of this report have been participating in the Sandia National Laboratory`s hydrologic performance assessment of the Yucca Mountain, Nevada, since 1983. The scope of this work is restricted to the unsaturated zone at Yucca Mountain and to technical questions about hydrology and chemical transport. The issues defined here are not to be confused with the elaborate hierarchy of issues that forms the framework of the US Department of Energy plans for characterizing the site (DOE, 1989). The overall task of hydrologic performance assessment involves issues related to hydrology, geochemistry, and energy transport in a highly heterogeneous natural geologic system which will be perturbed in a major way by the disposal activity. Therefore, a rational evaluation of the performance assessment issues must be based on an integrated appreciation of the aforesaid interacting processes. Accordingly, a hierarchical approach is taken in this report, proceeding from the statement of the broad features of the site that make it the site for intensive studies and the rationale for disposal strategy, through the statement of the fundamental questions that need to be answered, to the identification of the issues that need resolution. Having identified the questions and issues, the report then outlines the tasks to be undertaken to resolve the issues. The report consists essentially of two parts. The first part deals with the definition of issues summarized above. The second part summarizes the findings of the authors between 1983 and 1989 under the activities of the former Nevada Nuclear Waste Storage Investigations (NNWSI) and the current YMP.

Characterization of the Process Mechanical Cell at the West Valley Demonstration Project

International Nuclear Information System (INIS)

Drake, John; Schneider, Ken; Choroser, Jeff; Hughes, Karl

2003-01-01

The West Valley Demonstration Project has initiated decontamination and dismantlement (D and D) of the most highly radioactive and contaminated cells in a former spent nuclear fuel reprocessing plant. The goals of the D and D project are to remove loose debris in the cells and estimate the residual radioactivity level of legacy plant equipment. To support accomplishment of these goals, a unique characterization approach was developed to gather the information to meet anticipated Waste Isolation Pilot Plant (WIPP) acceptance criteria for remote-handled transuranic waste, and to facilitate segregation and packaging operations. Implementation of the characterization approach included the development and use of innovative, remote technology for measuring gamma radiation within the hot cell. The technology was used to identify and quantify radiation from individual debris items in radiation fields up to 2,000 R/hr (20 sieverts/hr). Sampling and analysis of the debris were also performed via remote handling means. Significant challenges associated with characterizing the highly radioactive and highly contaminated hot cells were encountered. The innovative solutions for meeting these challenges are applicable throughout the Department of Energy Complex and help support the goal of targeting D and D efforts toward reducing risks to public health and the environment

Laser Shot Peening Final Report CRADA No. TC-02059-03

Energy Technology Data Exchange (ETDEWEB)

Stuart, B. C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hackel, L. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2017-09-27

This was a collaborative effort between The Regents of the University of California, Lawrence Livermore National Laboratory (LLNL) and Metal Improvement Company, Inc. (MIC), to further develop the laser shot peening technology. This project had an emphasis on laser development and government and military applications including DOE’s natural gas and oil technology program (NGOTP), Yucca Mountain Project (YMP), F-22 Fighter, etc.

Fundamental remote sensing science research program. Part 1: Scene radiation and atmospheric effects characterization project

Science.gov (United States)

Murphy, R. E.; Deering, D. W.

1984-01-01

Brief articles summarizing the status of research in the scene radiation and atmospheric effect characterization (SRAEC) project are presented. Research conducted within the SRAEC program is focused on the development of empirical characterizations and mathematical process models which relate the electromagnetic energy reflected or emitted from a scene to the biophysical parameters of interest.

Preparation for YMP backfill activities

International Nuclear Information System (INIS)

Conca, J.

1998-01-01

Yucca Mountain activities for FY 1999 are anticipated to require specific information on the chemical and physical properties of the candidate getter materials and other backfill components necessary for defensible modeling of the source term, and possible controlling of the source term. There should be three tasks to this activity: at the end of this report is a draft test plan reflecting the present funding anticipated, the other tasks may be added as funding becomes available. (Task 1) The immobilization capacity of the getter materials for specific radionuclides. This task will primarily include column sorption tests of getter materials with solutions spiked with radionuclides. The getter materials will include Apatite II, MgO (with NaPO 4 plus Ba,SrCO 3 and soluble sulfate, with and without Apatite II), Gibbsite/Boehmite, and Hematite. Radionuclides will include Pu, U, Np, Am, Ra, Tc, and Th. Experiments will be performed under various anticipated repository conditions and with anticipated solution compositions. Occasional batch tests will be used to obtain specific K d s and other thermodynamic data. Solid and liquid analyses will be needed for characterization of the effluent concentrations from the columns to assess performance and for use in geochemical modeling. (Task 2) Intrinsic stability of the getter materials under repository conditions. The use of any candidate getter material will depend upon its anticipated lifetime in the backfill environment. Literature search for any existing data will be performed and augmented by solubility experiments on the getter materials. This is especially important for the reactive materials such as MgO and the soluble sulfates and phosphates that may be a limited lifetime in the backfill. It is also necessary to decide how much getter material to emplace. (Task 3) Diffusion of radionuclides across a Richards Barrier. The Richards Barrier, if emplaced, will act as a hydraulic diversion barrier for the diversion of

K basin sandfilter backwash line characterization project, analytical results for campaign 15

International Nuclear Information System (INIS)

Steen, F.H.

1999-01-01

Sample 183KWBMF was taken from the K West Sandfilter Backwash Pit on August 28, 1998 and received by 222-S Laboratory on August 28, 1998. Analyses were performed in accordance with ''Letter of Instruction for K Basins Sandfilter Backwash Line Samples'' (LOI) in support of the K Basin Sandfilter Backwash Line Characterization Project

Sample performance assessment of a high-level radioactive waste repository: sensitivity analysis

International Nuclear Information System (INIS)

Tkaczyk, A.

2001-01-01

The Yucca Mountain Project (YMP) is the USA's first attempt at long-term storage of High-Level Radioactive Waste (HLW). In theory, the reasoning for such a repository seems sound. In practice, there are many scenarios and cases to be considered while putting such a project into effect. Since a goal of YMP is to minimize dangers associated with long-term storage of HLW, it is important to estimate the dose rate to which current and future generations will be subjected. The lifetime of the repository is simulated to indicate the radiation dose rate to the maximally exposed individual; it is assumed that if the maximally exposed individual would not be harmed by the annual dose, the remaining population will be at even smaller risk. The determination of what levels of exposure can be deemed harmless is a concern, and the results from the simulations as compared against various regulations are discussed. (author)

Sample performance assessment of a high-level radioactive waste repository: sensitivity analysis

Energy Technology Data Exchange (ETDEWEB)

Tkaczyk, A. [Iowa State Univ. of Science and Technology, Ames, IA (United States). Dept. of Mechanical Engineering

2001-07-01

The Yucca Mountain Project (YMP) is the USA's first attempt at long-term storage of High-Level Radioactive Waste (HLW). In theory, the reasoning for such a repository seems sound. In practice, there are many scenarios and cases to be considered while putting such a project into effect. Since a goal of YMP is to minimize dangers associated with long-term storage of HLW, it is important to estimate the dose rate to which current and future generations will be subjected. The lifetime of the repository is simulated to indicate the radiation dose rate to the maximally exposed individual; it is assumed that if the maximally exposed individual would not be harmed by the annual dose, the remaining population will be at even smaller risk. The determination of what levels of exposure can be deemed harmless is a concern, and the results from the simulations as compared against various regulations are discussed. (author)

Waste package/engineered barrier system design concepts for the direct disposal of spent fuel in the potential United States' repository at Yucca Mountain, Nevada

International Nuclear Information System (INIS)

Stahl, D.; Harrison, D.J.

1993-01-01

The goal of the US Department of Energy's (DOE) Yucca Mountain Site Characterization Project (YMP) waste package development program is to design a waste package and associated engineered barrier system (EBS) that meets the applicable regulatory requirements for safe disposal of spent nuclear fuel and solidified high-level waste (HLW) in a geologic repository. Attainment of this goal relies on a multi-barrier approach, the unsaturated nature of the Yucca Mountain site, consideration of technical alternatives, and sufficient resolution of technical and regulatory uncertainties. To accomplish this, an iterative system engineering approach will be used. The NWPA of 1982 limits the content of the first US repository to 70,000 metric tons of heavy metal (MTHM). The DOE Mission Plan describes the implementation of the provisions of the NWPA for the waste management system. The Draft 1988 approach will involve selecting candidate designs, evaluating them against performance requirements, and then selecting one or two preferred designs for further detailed evaluation and final design. The reference design of the waste package described in the YMP Site Characterization Plan is a thin-walled, vertical borehole-emplaced waste package with an air gap between the package and the rock wall. The reference design appeared to meet the design requirement. However, the degree of uncertainty was large. This uncertainty led to considering several more-robust design concepts during the Advanced Conceptual Design phase of the program that include small, drift-emplaced packages and higher capacity, drift-emplaced packages, both partially and totally self-shielded. Metallic as well as ceramic materials are being considered

Project plan for the Background Soil Characterization Project on the Oak Ridge Reservation, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1992-08-01

The Background Soil characterization Project (BSCP) will provide background concentration levels of selected metals, organic compounds, and radionuclides in soils from uncontaminated on-site areas at the Oak Ridge Reservation (ORR), and off-site in the western part of Roane County and the eastern part of Anderson County. The BSCP will establish a database, recommend how to use the data for contaminated site assessment, and provide estimates of the potential human health and environmental risks associated with the background level concentrations of potentially hazardous constituents

Project plan for the Background Soil Characterization Project on the Oak Ridge Reservation, Oak Ridge, Tennessee

Energy Technology Data Exchange (ETDEWEB)

1992-08-01

The Background Soil characterization Project (BSCP) will provide background concentration levels of selected metals, organic compounds, and radionuclides in soils from uncontaminated on-site areas at the Oak Ridge Reservation (ORR), and off-site in the western part of Roane County and the eastern part of Anderson County. The BSCP will establish a database, recommend how to use the data for contaminated site assessment, and provide estimates of the potential human health and environmental risks associated with the background level concentrations of potentially hazardous constituents.

K Basin sandfilter backwash line characterization project, analytical results for Campaign 20

International Nuclear Information System (INIS)

STEEN, F.H.

1999-01-01

Sample 112KWBMF was taken from the K West Sandfilter Backwash Pit on June 1 , 1999, and received by 222-S Laboratory on June 2,1999. Analyses were performed on sample 112KWBMF in accordance with Letter of Instruction for K Basins Sandfilter Backwash Line Samples (LOI) in support of the K Basin Sandfilter Backwash Line Characterization Project

Hydrologic site characterization - the UMTRA project approach

International Nuclear Information System (INIS)

Binkman, J.E.; Hoopes, J.R.

1985-01-01

The United States Environmental Protection Agency (EPA) Standards (40 CFR 192) require site characterization of the hydrogeologic regime at and around each Uranium Mill Tailings Remedial Action (UMTRA) Project site. Also, ''judgements on the possible need for remedial or protective actions for groundwater aquifers should be guided by relevant considerations described in EPA's hazardous waste management system (47 CFR 32274).'' To address those two sets of rules and regulations, a generic approach is being developed. Fourteen primary issues were determined. These issues can be grouped into those that can be determined by documentation of available information and present conditions, those that require extensive field investigations and those that require some form of predictive modeling. To address the various issues requires an integrated effort of hydrogeologists, environmental engineers or scientists and health physicists. In this paper, the approach to the resolution of these fourteen issues is described briefly

Technical data management at the Yucca Mountain Site Characterization Project

International Nuclear Information System (INIS)

Statler, J.; Newbury, C.M.; Heitland, G.W.

1992-01-01

The Department of Energy/Office of Civilian Radioactive waste Management (DOE/OCRWM) is responsible for the characterization of Yucca Mountain, Nevada, to determine its potential as a site of a high-level radioactive waste repository. The characterization of Yucca Mountain encompasses many diverse investigations, both onsite and in laboratories across the country. Investigations are being conducted of the geology, hydrology, mineralogy, paleoclimate, geotechnical properties, and archeology of the area, to name a few. Effective program management requires that data from site investigations be processed, interpreted and disseminated in a timely manner to support model development and validation, repository design, and performance assessment. The Program must also meet regulatory requirements for making the technical data accessible to a variety of external users throughout the life of the Project. Finally, the DOE/OCRWM must make available the data or its description and access location available for use in support of the license application and supporting documentation. To accomplish these objectives, scientific and engineering data, generated by site characterization activities, and technical data, generated by environmental and socioeconomic impact assessment activities, must be systematically identified, cataloged, stored and disseminated in a controlled manner

DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

Energy Technology Data Exchange (ETDEWEB)

T. A. Lee

2005-09-15

The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

International Nuclear Information System (INIS)

Lee, T.A.

2005-01-01

The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

The Rocky Flats Environmental Technology Site beryllium characterization project

International Nuclear Information System (INIS)

Morrell, D.M.; Miller, J.R.; Allen, D.F.

1999-01-01

A site beryllium characterization project was completed at the Rocky Flats Environmental Technology Site (RFETS) in 1997. Information from historical reviews, previous sampling surveys, and a new sampling survey were used to establish a more comprehensive understanding of the locations and levels of beryllium contamination in 35 buildings. A feature of the sampling strategy was to test if process knowledge was a good predictor of where beryllium contamination could be found. Results revealed that this technique was effective at identifying where surface contamination levels might exceed the RFETS smear control level but that it was not effective in identifying where low concentrations of beryllium might be found

K25/K27 Characterization for Demonstrating Criticality Incredibility K-25 / K-27 D and D Project

International Nuclear Information System (INIS)

Haghighi, Mahmoud H.; Howe, Kathleen E.; Chandler, John R.

2008-01-01

The K-25 and K-27 Buildings are currently undergoing decontamination and decommissioning (D and D) as part of a non-time critical removal action. When the enrichment process was shut-down, the process gas equipment and piping was purged to remove UF 6 , but the process gas system was not generally chemically treated to remove solid holdup. Generally, chemical treatment was completed it was not very effective in removing the larger deposits. Because of this, uranium deposits continue to reside throughout the process gas system. There is the potential for unreacted UF 6 to be present, as well. A key part of this project is to locate the remaining significant uranium deposits and manage them appropriately. Since some process gas components in the K-25 and K-27 Buildings contain enriched uranium holdup, it is important to ensure nuclear criticality safety during demolition or subsequent loading and transport of waste. Therefore, a major task in preparation for demolition is to demonstrate that 'criticality is incredible (CI)' in each building area. The U.S. Department of Energy (DOE) and Bechtel Jacobs Company LLC (BJC) are in agreement that proper and thorough characterization of fissile holdup material in the K-25 and K-27 process gas components is a key element in achieving and demonstrating that criticality is incredible, as well as in management of demolition wastes and collection of holdup material. While the classic project scheduling wisdom may indicate that performing all of the data quality objectives (DQO) and planning before the field work starts, the size of the K-25 / K-27 D and D Project combined with the evolving decommissioning plans and re-plans have indicated that a fresh look at what further characterization data are needed to meet the current project requirements. Performing a DQO in the middle of the project allowed a much greater degree of accuracy of the real project data needs than was possible even 22 months ago. The outcome of the DQO work

Characterization of radon penetration of different structural domains of concrete. Final project report

International Nuclear Information System (INIS)

Nielson, K.K.; Rogers, V.C.

1996-05-01

This report documents the research activities by Rogers and Associates Engineering Corporation on grant DE-FG03-93ER61600 during the funded project period from August 1993 to April 1996. The objective of this research was to characterize the mechanisms and rates of radon gas penetration of the different structural domains of the concrete components of residential floor slabs, walls, and associated joints and penetrations. The research was also to characterize the physical properties of the concretes in these domains to relate their radon resistance to their physical properties. These objectives support the broader goal of characterizing which, if any, concrete domains and associated properties constitute robust barriers to radon and which permit radon entry, either inherently or in ways that could be remediated or avoided

Application of QA grading to Yucca Mountain Site Characterization Project items and activities

International Nuclear Information System (INIS)

Murthy, R.B.; Smith, S.C.

1991-01-01

Grading is the act of selecting the quality assurance (QA) measures necessary to develop and maintain confidence in the quality of an item or activity. The list of QA measures from which this selection is made are the 20 criteria of the Yucca Mountain Site Characterization Project Quality Assurance Requirements Document

Earthquakes and nuclear waste: A lesson in media relations

International Nuclear Information System (INIS)

Patrick, S.M.

1993-01-01

The Little Skull Mountain earthquake on June 29, 1992 marked the beginning of a challenging period for the US DOE's Yucca Mountain Site Characterization Project's (YMP's) Public Affairs department. We needed to relay complicated and difficult to understand scientific principals in an easily understandable fashion to local and national media who were hungry for detailed information. Volumes of quickly accumulating data was swiftly sorted, interpreted, and placed in context with other data in order to be properly presented. The main difficulty in this situation was attempting to assure that the information presented led to an intellectual and not emotional analysis of the earthquake. This paper will discuss some of the processes undertaken to meet both the needs of local media as well as our own needs

Site environmental report for calendar year 1997, Yucca Mountain Site, Nye County, Nevada

International Nuclear Information System (INIS)

1998-10-01

This document is the seventh annual Site Environmental Report (SER) submitted by the Yucca Mountain Site Characterization Office (YMSCO) to describe the environmental program implemented by the US Department of Energy (DOE) at Yucca Mountain. As prescribed by the Nuclear Waste Policy Act (NWPA, 1982), this program ensures that site characterization activities are conducted in a manner that minimizes any significant adverse impacts to the environment and complies with all applicable laws and regulations. The most recent guidelines for the preparation of the SER place major emphasis on liquid and gaseous emissions of radionuclides, pollutants or hazardous substances; human exposure to radionuclides; and trends observed by comparing data collected over a period of years. To date, the YMP has not been the source of any radioactive emissions or been responsible for any human exposure to radionuclides. Minuscule amounts of radioactivity detected at the site are derived from natural sources or from dust previously contaminated by nuclear tests conducted in the past at the NTS. Because data for only a few years exist for the site, identification of long-term trends is not yet possible. Despite the lack of the aforementioned categories of information requested for the SER, the YMP has collected considerable material relevant to this report. An extensive environmental monitoring and mitigation program is currently in place and is described herein. Also, as requested by the SER guidelines, an account of YMP compliance with appropriate environmental legislation is provided

Yucca Mountain Project far-field sorption studies and data needs

International Nuclear Information System (INIS)

Meijer, A.

1990-09-01

Batch sorption experiments in which radionuclides dissolved in groundwaters from Yucca Mountain were sorbed onto samples of crushed tuff have resulted in a substantial database of sorption coefficients for radionuclides of interest to the repository program. Although this database has been useful in preliminary evaluations of Yucca Mountain as a potential site for a nuclear waste repository, the database has limitations that must be addressed before it can be used for performance assessment calculations in support of a license application for a waste repository. The purpose of this paper is to: review the applicability of simple (constant) sorption coefficients in transport calculations; review and evaluate alternative methods for the derivation of sorption coefficients; summarize and evaluate the present YMP sorption database to identify areas of data sufficiency and significant data gaps; summarize our current understanding of pertinent sorption mechanisms and associated kinetic parameters; evaluate the significance to the YMP of potential problems in the experimental determination and field application of sorption coefficients as enumerated by the NRC (Nuclear Regulatory Commission, 1987) in its technical position paper on sorption; formulate and evaluate strategies for the resolution of NRC concerns regarding experimental problems; and formulate a position on the sorption coefficient database and the level of understanding of sorption mechanisms likely to be required in the licensing application. 75 refs., 1 fig., 2 tabs

CACAO: A project for a laboratory for the production and characterization of thin radioactive layers

Energy Technology Data Exchange (ETDEWEB)

Bacri, C.O., E-mail: bacri@ipno.in2p3.f [Institut de Physique Nucleaire d' Orsay, 91406 Orsay Cedex, CNRS (UMR8608-IN2P3), Universite Paris-Sud (Paris XI) (France); Petitbon, V.; Pierre, S. [Institut de Physique Nucleaire d' Orsay, 91406 Orsay Cedex, CNRS (UMR8608-IN2P3), Universite Paris-Sud (Paris XI) (France)

2010-02-11

CACAO, Chimie des Actinides et Cibles radioActives a Orsay (actinide chemistry and radioactive targets at Orsay), is a project under construction that consists of the installation of a hot laboratory dedicated to the production and characterization of thin radioactive layers. The project aims to be a joint CNRS-CEA national laboratory to overcome difficulties related mainly to safety issues and to the lack of knowledge and potential manpower. The first goal is to fulfill, at least, the needs of the whole French community, and to be able to coordinate the different activities related to radioactive targets. For this purpose, itis important to be complementary to already existing international installations. Inside this framework, it will of course be possible to produce and/or characterize targets for other users.

CACAO: A project for a laboratory for the production and characterization of thin radioactive layers

Science.gov (United States)

Bacri, C. O.; Petitbon, V.; Pierre, S.; Cacao Group

2010-02-01

CACAO, Chimie des Actinides et Cibles radioActives à Orsay (actinide chemistry and radioactive targets at Orsay), is a project under construction that consists of the installation of a hot laboratory dedicated to the production and characterization of thin radioactive layers. The project aims to be a joint CNRS-CEA national laboratory to overcome difficulties related mainly to safety issues and to the lack of knowledge and potential manpower. The first goal is to fulfill, at least, the needs of the whole French community, and to be able to coordinate the different activities related to radioactive targets. For this purpose, itis important to be complementary to already existing international installations. Inside this framework, it will of course be possible to produce and/or characterize targets for other users.

CACAO: A project for a laboratory for the production and characterization of thin radioactive layers

International Nuclear Information System (INIS)

Bacri, C.O.; Petitbon, V.; Pierre, S.

2010-01-01

CACAO, Chimie des Actinides et Cibles radioActives a Orsay (actinide chemistry and radioactive targets at Orsay), is a project under construction that consists of the installation of a hot laboratory dedicated to the production and characterization of thin radioactive layers. The project aims to be a joint CNRS-CEA national laboratory to overcome difficulties related mainly to safety issues and to the lack of knowledge and potential manpower. The first goal is to fulfill, at least, the needs of the whole French community, and to be able to coordinate the different activities related to radioactive targets. For this purpose, itis important to be complementary to already existing international installations. Inside this framework, it will of course be possible to produce and/or characterize targets for other users.

A dynamical characterization of the uncertainty in projections of regional precipitation change in the semi-arid tropics

Science.gov (United States)

Giannini, A.

2016-12-01

The uncertainty in CMIP multi-model ensembles of regional precipitation change in tropical regions is well known: taken at face value, models do not agree on the direction of precipitation change. Consequently, in adaptation discourse, either projections are discounted, e.g., by giving more relevance to temperature projections, or outcomes are grossly misrepresented, e.g., in extrapolating recent drought into the long-term future. That this is an unsatisfactory state of affairs, given the dominant role of precipitation in shaping climate-sensitive human endeavors in the tropics, is an understatement.Here I will provide a dynamical characterization of the uncertainty in regional precipitation projections that exploits the CMIP multi-model ensembles. This characterization is based on decomposing the moisture budget and relating its terms to the influence of the oceans, specifically to the roles of moisture supply and stabilization of the vertical profile. I will discuss some preliminary findings highlighting the relevance of lessons learned from seasonal-to-interannual prediction. One such lesson is to go beyond the projection taken at face value, and understand physical processes, specifically, the role of the oceans, in order to be able to make qualitative arguments, in addition to quantitative predictions. One other lesson is to abandon the search for the "best model" and exploit the multi-model ensemble to characterize "emergent constraints".

Implementation of Agile project management in spent nuclear fuel characterization process

International Nuclear Information System (INIS)

Vinas Pena, P.

2015-01-01

Full text of publication follows. Spent nuclear fuel characterization (SNFC) is a complex process that covers different areas of analysis and whose final goal is to provide an accurate description of spent nuclear fuel (SNF) status for its future classification for storage and transport. The need to reduce the SNFC processing time maintaining the quality of the product has motivated ENUSA to research and implement Agile project management and human performance techniques. The Agile management techniques are focused in accommodate changes or new requirements in the project during the elaboration process without suffering delays or lose of quality. For its SNF projects ENUSA uses 2 complementary techniques: SCRUM and Kanban. SCRUM methodology is based on divide the process into activities blocks. Each block is a finished part of the final product which allows periodical deliveries of the product and the easy introduction of changes if they are necessary. The characterization process is formed by blocks of activities based on different analysis for every fuel assembly as the existence of leaking rods; the analysis of the structural integrity considering the existence of missing rods, broken or missing grids or grid straps or grid springs...; the corrosion phenomenon on the rod that could affect its integrity during the storage and transport; the burnup of the fuel assembly; the analysis of the rod internal pressure and its effect on rod failure mechanism as creep or on the material embrittlement due to the radial hydride precipitation; the compatibility with the container to avoid operational problems during cask loading and unloading, and any new input based on the regulatory evolution and the industry state of the art. The different analysis can be developed at the same time as they are independent. Kanban methodology consists in a visual representation of the evolution of the process. In a chart, the different activities needed to perform any of the analysis

Second Generation Waste Package Design Study

International Nuclear Information System (INIS)

Armijo, J.S.; Misra, M.; Kar, Piyush

2007-01-01

The following describes the objectives of Project Activity 023 ''Second Generation Waste Package Design Study'' under DOE Cooperative Agreement DE-FC28-04RW12232. The objectives of this activity are: to review the current YMP baseline environment and establish corrosion test environments representative of the range of dry to intermittently wet conditions expected in the drifts as a function of time; to demonstrate the oxidation and corrosion resistance of A588 weathering steel and reference Alloy 22 samples in the representative dry to intermittently dry conditions; and to evaluate backfill and design features to improve the thermal performance analyses of the proposed second-generation waste packages using existing models developed at the University of Nevada, Reno(UNR). The work plan for this project activity consists of three major tasks: Task 1. Definition of expected worst-case environments (humidity, liquid composition and temperature) at waste package outer surfaces as a function of time, and comparison with environments defined in the YMP baseline; Task 2. Oxidation and corrosion tests of proposed second-generation outer container material; and Task 3. Second Generation waste package thermal analyses. Full funding was not provided for this project activity

K Basin Sandfilter Backwash Line Characterization Project and Analytical Results for Campaign 24

International Nuclear Information System (INIS)

STEEN, F.H.

1999-01-01

Sample 203KWBMF was taken from the K West Sandfilter Backwash Pit on November 4, 1999 and received by 2224 Laboratory on November 4, 1999. Analyses were performed on sample 203KWBMF in accordance with ''Letter of Instruction for K Basins sandfilter Backwash Line Samples'' (LOI) in support of the K Basin Sandfilter Backwash Line Characterization Project

Interface management for the Mined Geologic Disposal System

International Nuclear Information System (INIS)

Ashlock, K.J.; Sellers, M.D.

1998-01-01

The Management and Operations (M and O) contractor for the Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) program exists to support DOE in the successful development and operation of an integrated system to manage the nation's spent nuclear fuel and high-level wastes. As part of the system engineering and integration performed on the Yucca Mountain Project (YMP), interface management is critical in the development of the Mined Geologic Disposal System (MGDS). The application of interface management on the YMP directly addresses integration between physical elements of the MGDS and the organizations responsible for their development. An initiative to utilize interface management and the interface control document development process for organizational interfaces is also being pursued to help ensure consistent use of information by multiple organizations

The MEarth Project: Finding the Best Targets for Atmospheric Characterization with JWST

Science.gov (United States)

Berta-Thompson, Z.

2014-04-01

If we want to directly observe the radius, orbit, mass, and atmosphere of a small, cool, habitable exoplanet, our best opportunity is to find such a planet transiting a small, cool, nearby M dwarf star. The MEarth Project is an ongoing all-sky survey for Earth-like planets transiting the closest, smallest M dwarfs in the Galaxy. MEarth aims to find good targets for atmospheric characterization with JWST and the next generation of enormous ground-based telescopes. This poster provides a status update on the MEarth Project, including the progress we've made over the past five years with 8 telescopes in the Northern hemisphere and promising early results from our new installation of 8 more telescopes in the Southern hemisphere.

Final report on the Background Soil Characterization Project at the Oak Ridge Reservation, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Watkins, D.R.; Ammons, J.T.; Branson, J.L.

1993-10-01

This report presents, evaluates, and documents data and results obtained in the Background Soil Characterization Project (BSCP). It is intended to be a stand-alone document for application and use in structuring and conducting remedial investigation and remedial action projects in the Environmental Restoration (ER) Program. The objectives of the BSCP consist of the following: determine background concentrations of organics, metals, and radionuclides in natural soils that are key to environmental restoration projects; provide remediation projects with 100% validated data on background concentrations, which are technically and legally defensible; and quantify baseline risks from background constituents for comparison of risks associated with contaminated sites

Final report on the Background Soil Characterization Project at the Oak Ridge Reservation, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1993-10-01

The Background Soil Characterization Project (BSCP) will provide background concentration levels of selected metals organic compounds, and radionuclides in soils from uncontaminated on-site areas at the Oak Ridge Reservation (ORR), and off-site in the western part of Roane County and the eastern part of Anderson County. The BSCP will establish a database, recommend how to use the data for contaminated site assessment, and provide estimates of the potential human health and environmental risks associated with the background level concentrations of potentially hazardous constituents. This volume contains the data from the Background Soil Characterization Project. When available, the following validation qualifiers are used in the appendixes. When validation qualifiers are not available, the corresponding contract laboratory data qualifiers appearing on the next page are used

Characterization of materials for a reactive transport model validation experiment: Interim report on the caisson experiment. Yucca Mountain Site Characterization Project

International Nuclear Information System (INIS)

Siegel, M.D.; Cheng, W.C.; Ward, D.B.; Bryan, C.R.

1995-08-01

Models used in performance assessment and site characterization activities related to nuclear waste disposal rely on simplified representations of solute/rock interactions, hydrologic flow field and the material properties of the rock layers surrounding the repository. A crucial element in the design of these models is the validity of these simplifying assumptions. An intermediate-scale experiment is being carried out at the Experimental Engineered Test Facility at Los Alamos Laboratory by the Los Alamos and Sandia National Laboratories to develop a strategy to validate key geochemical and hydrological assumptions in performance assessment models used by the Yucca Mountain Site Characterization Project

Characterization of materials for a reactive transport model validation experiment: Interim report on the caisson experiment. Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

Siegel, M.D.; Cheng, W.C. [Sandia National Labs., Albuquerque, NM (United States); Ward, D.B.; Bryan, C.R. [Univ. of New Mexico, Albuquerque, NM (United States). Dept. of Earth and Planetary Sciences

1995-08-01

Models used in performance assessment and site characterization activities related to nuclear waste disposal rely on simplified representations of solute/rock interactions, hydrologic flow field and the material properties of the rock layers surrounding the repository. A crucial element in the design of these models is the validity of these simplifying assumptions. An intermediate-scale experiment is being carried out at the Experimental Engineered Test Facility at Los Alamos Laboratory by the Los Alamos and Sandia National Laboratories to develop a strategy to validate key geochemical and hydrological assumptions in performance assessment models used by the Yucca Mountain Site Characterization Project.

Environmental Restoration Program pollution prevention checklist guide for the facility characterization project phase

International Nuclear Information System (INIS)

1993-09-01

A facility characterization (FC) is conducted to determine the nature and extent contamination at a potential hazardous facility waste site. The information gathered during an FC includes (1) data on the volume and chemical nature of the waste, (2) information on the extent of contamination and the migration potential of the contaminants, (3) preliminary information on evaluation of alternative concepts that can or cannot be considered, and (4)supportive technical and cost data. For the purposes of identification, the following operational phases will be used for definition for this phase of the decommissioning and decontamination process (1) facility characterization before clean up, (2) characterization during clean up, (3) characterization of waste materials, and (4) site characterization after clean up. A key consideration in this process is the prevention of any waste to be generated from these characterization activities. The purpose of this checklist guide is to assist users with incorporating pollution prevention/waste minimization (PP/WM) in all FC phase projects of the Environmental Restoration (ER) Program. This guide will help users document PP/WM activities for technology transfer and reporting requirements. Automated computer screens will be created from the checklist data to assist users with implementing and evaluating waste reduction

Vadose zone characterization project at the Hanford Tank Farms: BY Tank Farm report

International Nuclear Information System (INIS)

Kos, S.E.

1997-02-01

The US Department of Energy Grand Junction Office (GJO) was tasked by the DOE Richland Operations Office (DOE-RL) to perform a baseline characterization of the contamination distributed in the vadoze zone sediment beneath and around the single-shell tanks (SSTs) at the Hanford Site. The intent of this characterization is to determine the nature and extent of the contamination, to identify contamination sources, and to develop a baseline of the contamination distribution that will permit future data comparisons. This characterization work also allows an initial assessment of the impacts of the vadose zone contamination as required by the Resource Conservation and Recovery Act (RCRA). This characterization project involves acquiring information about the vadose zone contamination with borehole geophysical logging methods and documenting that information in a series of reports. Data from boreholes surrounding each tank are compiled into individual Tank Summary Data Reports. The data from each tank farm are then compiled and summarized in a Tank Farm Report. This document is the Tank Farm Report for the BY Tank Farm

Vadose zone characterization project at the Hanford Tank Farms: BY Tank Farm report

Energy Technology Data Exchange (ETDEWEB)

Kos, S.E.

1997-02-01

The US Department of Energy Grand Junction Office (GJO) was tasked by the DOE Richland Operations Office (DOE-RL) to perform a baseline characterization of the contamination distributed in the vadoze zone sediment beneath and around the single-shell tanks (SSTs) at the Hanford Site. The intent of this characterization is to determine the nature and extent of the contamination, to identify contamination sources, and to develop a baseline of the contamination distribution that will permit future data comparisons. This characterization work also allows an initial assessment of the impacts of the vadose zone contamination as required by the Resource Conservation and Recovery Act (RCRA). This characterization project involves acquiring information about the vadose zone contamination with borehole geophysical logging methods and documenting that information in a series of reports. Data from boreholes surrounding each tank are compiled into individual Tank Summary Data Reports. The data from each tank farm are then compiled and summarized in a Tank Farm Report. This document is the Tank Farm Report for the BY Tank Farm.

Characterization of spinal afferent neurons projecting to different chambers of the rat heart.

Science.gov (United States)

Guić, Maja Marinović; Kosta, Vana; Aljinović, Jure; Sapunar, Damir; Grković, Ivica

2010-01-29

The pattern of distribution of spinal afferent neurons (among dorsal root ganglia-DRGs) that project to anatomically and functionally different chambers of the rat heart, as well as their morphological and neurochemical characteristics were investigated. Retrograde tracing using a patch loaded with Fast blue (FB) was applied to all four chambers of the rat heart and labeled cardiac spinal afferents were characterized by using three neurochemical markers. The majority of cardiac projecting neurons were found from T1 to T4 DRGs, whereas the peak was at T2 DRG. There was no difference in the total number of FB-labeled neurons located in ipsilateral and contralateral DRGs regardless of the chambers marked with the patch. However, significantly more FB-labeled neurons projected to the ventricles compared to the atria (859 vs. 715). The proportion of isolectin B(4) binding in FB-labeled neurons was equal among all neurons projecting to different heart chambers (2.4%). Neurofilament 200 positivity was found in greater proportions in DRG neurons projecting to the left side of the heart, whereas calretinin-immunoreactivity was mostly represented in neurons projecting to the left atrium. Spinal afferent neurons projecting to different chambers of the rat heart exhibit a variety of neurochemical phenotypes depending on binding capacity for isolectin B(4) and immunoreactivity for neurofilament 200 and calretinin, and thus represent important baseline data for future studies. (c) 2009 Elsevier Ireland Ltd. All rights reserved.

Final predictions of ambient conditions along the east-west cross drift using the 3-D UZ site-scale model. Level 4 milestone SP33ABM4

International Nuclear Information System (INIS)

Ritcey, A.C.; Sonnenthal, E.L.; Wu, Y.S.; Haukwa, C.; Bodvarsson, G.S.

1998-01-01

In 1998, the Yucca Mountain Site Characterization Project (YMP) is expected to continue construction of an East-West Cross Drift. The 5-meter diameter drift will extend from the North Ramp of the Exploratory Studies Facility (ESF), near Station 19+92, southwest through the repository block, and over to and through the Solitario Canyon Fault. This drift is part of a program designed to enhance characterization of Yucca Mountain and to complement existing surface-based and ESF testing studies. The objective of this milestone is to use the three-dimensional (3-D) unsaturated zone (UZ) site-scale model to predict ambient conditions along the East-West Cross Drift. These predictions provide scientists and engineers with a priori information that can support design and construction of the East-West Cross Drift and associated testing program. The predictions also provide, when compared with data collected after drift construction, an opportunity to test and verify the calibration of the 3-D UZ site-scale model

Standard characterization of phosphate rock samples from the FAO/IAEA phosphate project

International Nuclear Information System (INIS)

Binh, Truong; Zapata, F.

2002-01-01

Phosphate rocks (PR) are phosphate-bearing minerals that vary widely in their inherent characteristics and consequently their agronomic potential. In the framework of a FAO/IAEA networked research project, the evaluation of the agronomic effectiveness of natural and modified PR products under a variety of soil climate and crop management conditions was carried out. The characterization of phosphate rocks is the first and essential step in evaluating their suitability for direct application. If several PR sources are utilized, standardized methods should be used for comparison purposes to determine their agronomic potential. This paper describes the standard characterization of phosphate rock products utilized in the project, in particular the mineralogical and crystallographic analyses, physical analyses, chemical composition and solubility in conventional reagents. A total of 28 phosphate rock samples from 15 countries were collected and analyzed in specialized laboratories. The data on mineralogy, chemical composition and solubility in conventional reagents are closely interrelated. An arbitrary classification of the reactivity of the PR samples was made based on the solubility indices in conventional reagents. On another hand, the results of the crystallographic parameters, calculated indices of absolute solubility, specific surface and porosity reflect the variability of the physical state and the sample pre-conditioning treatment of the analyzed products. A proper characterization of phosphate rock samples should provide the maximum of basic information that can be obtained in a cost-effective manner in normal chemical laboratories. Based on the results of this characterization, the following determinations are recommended: a description of the sample, major elemental (total P, Ca, Mg) composition, solubility in conventional reagents (neutral ammonium citrate, citric and formic acid) and particle size analysis. The classification of PR samples for direct

Poika on suruissansa (2/4 F)

OpenAIRE

2011-01-01

Laulun sanat: Poika on suruissansa, kun on jäänyt kullastansa; kiertää piirin ympäri ja ottaa uuden taas, kiertää piirin ympäri ja ottaa uuden taas! Hih-hei, ja pili-pam-pam-pam, pili-pam-pam-pam, pili-pam-pam-pam! Hih-hei, ja pili-pam-pam-pam! Kiertää piirin ympäri ja

Control of tracers, fluids, and materials for the Yucca Mountain Site Characterization Project

International Nuclear Information System (INIS)

Kalia, H.N.

1993-01-01

This paper describes use and control of tracers, fluids, and materials (TFM) at the Yucca Mountain Site Characterization Project, Management of TFM is necessary to ensure that site characterization activity does not introduce TFM that may have impact on Yucca Mountain's ability to isolate high-level radioactive waste from the accessible environment. All participants must identify TFM used for testing and construction and have the TFM evaluated to ascertain any impact on waste isolation capabilities of the site or on adjacent tests. Two data bases are created to track TFM: a working data base managed by Los Alamos National Lab. and a permanent data base managed by EG ampersand G, which will contain information on actual TFM used

A characterization of linearly repetitive cut and project sets

Science.gov (United States)

Haynes, Alan; Koivusalo, Henna; Walton, James

2018-02-01

For the development of a mathematical theory which can be used to rigorously investigate physical properties of quasicrystals, it is necessary to understand regularity of patterns in special classes of aperiodic point sets in Euclidean space. In one dimension, prototypical mathematical models for quasicrystals are provided by Sturmian sequences and by point sets generated by substitution rules. Regularity properties of such sets are well understood, thanks mostly to well known results by Morse and Hedlund, and physicists have used this understanding to study one dimensional random Schrödinger operators and lattice gas models. A key fact which plays an important role in these problems is the existence of a subadditive ergodic theorem, which is guaranteed when the corresponding point set is linearly repetitive. In this paper we extend the one-dimensional model to cut and project sets, which generalize Sturmian sequences in higher dimensions, and which are frequently used in mathematical and physical literature as models for higher dimensional quasicrystals. By using a combination of algebraic, geometric, and dynamical techniques, together with input from higher dimensional Diophantine approximation, we give a complete characterization of all linearly repetitive cut and project sets with cubical windows. We also prove that these are precisely the collection of such sets which satisfy subadditive ergodic theorems. The results are explicit enough to allow us to apply them to known classical models, and to construct linearly repetitive cut and project sets in all pairs of dimensions and codimensions in which they exist. Research supported by EPSRC grants EP/L001462, EP/J00149X, EP/M023540. HK also gratefully acknowledges the support of the Osk. Huttunen foundation.

Monitored Geologic Repository Project Description Document

International Nuclear Information System (INIS)

Curry, P. M.

2001-01-01

The primary objective of the Monitored Geologic Repository Project Description Document (PDD) is to allocate the functions, requirements, and assumptions to the systems at Level 5 of the Civilian Radioactive Waste Management System (CRWMS) architecture identified in Section 4. It provides traceability of the requirements to those contained in Section 3 of the ''Monitored Geologic Repository Requirements Document'' (MGR RD) (YMP 2000a) and other higher-level requirements documents. In addition, the PDD allocates design related assumptions to work products of non-design organizations. The document provides Monitored Geologic Repository (MGR) technical requirements in support of design and performance assessment in preparing for the Site Recommendation (SR) and License Application (LA) milestones. The technical requirements documented in the PDD are to be captured in the System Description Documents (SDDs) which address each of the systems at Level 5 of the CRWMS architecture. The design engineers obtain the technical requirements from the SDDs and by reference from the SDDs to the PDD. The design organizations and other organizations will obtain design related assumptions directly from the PDD. These organizations may establish additional assumptions for their individual activities, but such assumptions are not to conflict with the assumptions in the PDD. The PDD will serve as the primary link between the technical requirements captured in the SDDs and the design requirements captured in US Department of Energy (DOE) documents. The approved PDD is placed under Level 3 baseline control by the CRWMS Management and Operating Contractor (M and O) and the following portions of the PDD constitute the Technical Design Baseline for the MGR: the design characteristics listed in Table 1-1, the MGR Architecture (Section 4.1), the Technical Requirements (Section 5), and the Controlled Project Assumptions (Section 6)

Direct/Delayed Response Project: Soil-characterization comparison

International Nuclear Information System (INIS)

Fenstermaker, L.K.; Byers, G.E.; Starks, T.H.; Miah, M.J.; Palmer, C.J.

1992-01-01

A large amount of soil characterization data has been collected as a component of the Direct/Delayed Response Project (DDRP) in the acid rain Aquatic Effects Research Program. An interlaboratory comparison study was undertaken to identify the comparability of the data to that obtained from representative soil characterization laboratories. Participating laboratories were selected at random from four regions of the U.S. and two regions of Canada. Two original DDRP contract laboratories also participated. Duplicate samples of six soil audit materials and two liquid soil extracts were sent to each of the laboratories in two separate batches. Laboratories used their own protocols to perform the analyses requested except for the contract laboratories which followed the DDRP protocol. Liquid audits were used in an effort to identify if interlaboratory differences were due to extraction procedures or chemical measurements. A component of the variability in the results was attributed to differences in the methods used such as soil/solution ratios, extractants or extraction procedures. The largest number of different methods used was for the measurement of cation exchange capacity. The results between the DDRP soil survey data and the study's results were compared using Youden-pair plots. In addition, standard statistical tests were performed. Overall, the DDRP data were comparable to the data from the study. However, out of the total 141 comparisons involving results from six or more laboratories, the results from the two contract laboratories did not meet the comparison criteria in 19 cases. Since there was never a case in which both contract laboratories failed, it would appear that the 19 cases which were not comparable were due to random analytical errors, incorrectly reported results, or misapplication of DDRP protocol

Exploratory Shaft Seismic Design Basis Working Group report

International Nuclear Information System (INIS)

Subramanian, C.V.; King, J.L.; Perkins, D.M.; Mudd, R.W.; Richardson, A.M.; Calovini, J.C.; Van Eeckhout, E.; Emerson, D.O.

1990-08-01

This report was prepared for the Yucca Mountain Project (YMP), which is managed by the US Department of Energy. The participants in the YMP are investigating the suitability of a site at Yucca Mountain, Nevada, for construction of a repository for high-level radioactive waste. An exploratory shaft facility (ESF) will be constructed to permit site characterization. The major components of the ESF are two shafts that will be used to provide access to the underground test areas for men, utilities, and ventilation. If a repository is constructed at the site, the exploratory shafts will be converted for use as intake ventilation shafts. In the context of both underground nuclear explosions (conducted at the nearby Nevada Test Site) and earthquakes, the report contains discussions of faulting potential at the site, control motions at depth, material properties of the different rock layers relevant to seismic design, the strain tensor for each of the waveforms along the shaft liners, and the method for combining the different strain components along the shaft liners. The report also describes analytic methods, assumptions used to ensure conservatism, and uncertainties in the data. The analyses show that none of the shafts' structures, systems, or components are important to public radiological safety; therefore, the shafts need only be designed to ensure worker safety, and the report recommends seismic design parameters appropriate for this purpose. 31 refs., 5 figs., 6 tabs

Purification and Characterization of Taq Polymerase: A 9-Week Biochemistry Laboratory Project for Undergraduate Students

Science.gov (United States)

Bellin, Robert M.; Bruno, Mary K.; Farrow, Melissa A.

2010-01-01

We have developed a 9-week undergraduate laboratory series focused on the purification and characterization of "Thermus aquaticus" DNA polymerase (Taq). Our aim was to provide undergraduate biochemistry students with a full-semester continuing project simulating a research-like experience, while having each week's procedure focus on a single…

Summary of field operations Technical Area I well PGS-1. Site-Wide Hydrogeologic Characterization Project

International Nuclear Information System (INIS)

Fritts, J.E.; McCord, J.P.

1995-02-01

The Environmental Restoration (ER) Project at Sandia National Laboratories, New Mexico is managing the project to assess and, when necessary, to remediate sites contaminated by the lab operations. Within the ER project, the site-wide hydrogeologic characterization task is responsible for the area-wide hydrogeologic investigation. The purpose of this task is to reduce the uncertainty about the rate and direction of groundwater flow beneath the area and across its boundaries. This specific report deals with the installation of PGS-1 monitoring well which provides information on the lithology and hydrology of the aquifer in the northern area of the Kirtland Air Force Base. The report provides information on the well design; surface geology; stratigraphy; structure; drilling, completion, and development techniques; and borehole geophysics information

Evaluation of low-level radioactive waste characterization and classification programs of the West Valley Demonstration Project

International Nuclear Information System (INIS)

Taie, K.R.

1994-01-01

The West Valley Demonstration Project (WVDP) is preparing to upgrade their low-level radioactive waste (LLW) characterization and classification program. This thesis describes a survey study of three other DOE sites conducted in support of this effort. The LLW characterization/classification programs of Oak Ridge National Laboratory, Savannah River Site, and Idaho National Engineering Laboratory were critically evaluated. The evaluation was accomplished through tours of each site facility and personnel interviews. Comparative evaluation of the individual characterization/classification programs suggests the WVDP should purchase a real-time radiography unit and a passive/active neutron detection system, make additional mechanical modifications to the segmented gamma spectroscopy assay system, provide a separate building to house characterization equipment and perform assays away from waste storage, develop and document a new LLW characterization/classification methodology, and make use of the supercompactor owned by WVDP

Central and Eastern United States (CEUS) Seismic Source Characterization (SSC) for Nuclear Facilities Project

Energy Technology Data Exchange (ETDEWEB)

Kevin J. Coppersmith; Lawrence A. Salomone; Chris W. Fuller; Laura L. Glaser; Kathryn L. Hanson; Ross D. Hartleb; William R. Lettis; Scott C. Lindvall; Stephen M. McDuffie; Robin K. McGuire; Gerry L. Stirewalt; Gabriel R. Toro; Robert R. Youngs; David L. Slayter; Serkan B. Bozkurt; Randolph J. Cumbest; Valentina Montaldo Falero; Roseanne C. Perman' Allison M. Shumway; Frank H. Syms; Martitia (Tish) P. Tuttle

2012-01-31

This report describes a new seismic source characterization (SSC) model for the Central and Eastern United States (CEUS). It will replace the Seismic Hazard Methodology for the Central and Eastern United States, EPRI Report NP-4726 (July 1986) and the Seismic Hazard Characterization of 69 Nuclear Plant Sites East of the Rocky Mountains, Lawrence Livermore National Laboratory Model, (Bernreuter et al., 1989). The objective of the CEUS SSC Project is to develop a new seismic source model for the CEUS using a Senior Seismic Hazard Analysis Committee (SSHAC) Level 3 assessment process. The goal of the SSHAC process is to represent the center, body, and range of technically defensible interpretations of the available data, models, and methods. Input to a probabilistic seismic hazard analysis (PSHA) consists of both seismic source characterization and ground motion characterization. These two components are used to calculate probabilistic hazard results (or seismic hazard curves) at a particular site. This report provides a new seismic source model. Results and Findings The product of this report is a regional CEUS SSC model. This model includes consideration of an updated database, full assessment and incorporation of uncertainties, and the range of diverse technical interpretations from the larger technical community. The SSC model will be widely applicable to the entire CEUS, so this project uses a ground motion model that includes generic variations to allow for a range of representative site conditions (deep soil, shallow soil, hard rock). Hazard and sensitivity calculations were conducted at seven test sites representative of different CEUS hazard environments. Challenges and Objectives The regional CEUS SSC model will be of value to readers who are involved in PSHA work, and who wish to use an updated SSC model. This model is based on a comprehensive and traceable process, in accordance with SSHAC guidelines in NUREG/CR-6372, Recommendations for Probabilistic

Characterize Human Forward Contamination Project

Science.gov (United States)

Rucker, Michelle

2015-01-01

Let's face it: wherever we go, we will inevitably carry along the little critters that live in and on us. Conventional wisdom has long held that it's unlikely those critters could survive the space environment, but in 2007 microscopic animals called Tardigrades survived exposure to space and in 2008 Cyanobacteria lived for 548 days outside the International Space Station (ISS). But what about the organisms we might reasonably expect a crewed spacecraft to leak or vent? Do we even know what they are? How long might our tiny hitch-hikers survive in close proximity to a warm spacecraft that periodically leaks/vents water or oxygen-and how might they mutate with long-duration exposure? Unlike the Mars rovers that we cleaned once and sent on their way, crew members will provide a constantly regenerating contaminant source. Are we prepared to certify that we can meet forward contamination protocols as we search for life at new destinations? This project has four technical objectives: 1. TEST: Develop a test plan to leverage existing equipment (i.e. ISS) to characterize the kinds of organisms we can reasonably expect pressurized, crewed volumes to vent or leak overboard; as part of testing, we'll need to develop an Extravehicular Activity (EVA)-compatible tool that can withstand the pressure and temperature extremes of space, as well as collect, separate, and store multiple samples; 2. ANALYSIS: Develop an analysis plan to study those organisms in relevant destination environments, including spacecraft-induced conditions; 3. MODEL: Develop a modeling plan to model organism transport mechanisms in relevant destination environments; 4. SHARE: Develop a plan to disseminate findings and integrate recommendations into exploration requirements & ops. In short, we propose a system engineering approach to roadmap the necessary experiments, analysis, and modeling up front--rather than try to knit together disparate chunks of data into a sensible conclusion after the fact.

Response to state comments on the revised draft northeastern regional characterization reports for the Crystalline Repository Project

International Nuclear Information System (INIS)

1985-08-01

The purpose of this document is to respond to the comments received from the States of the Northeastern Region on the revised draft Northeastern Regional Characterization Reports (RCRs). The responses in this document indicate the manner in which the suggestions or comments received have been considered in modifying the revised draft Northeastern RCRs. Both general comments related to the overall Crystalline Repository Project (CRP) and comments on specific sections of the RCRs are addressed. This document responds to Northeastern State comments on both the revised draft Northeastern Regional Geologic Characterization Report (RGCR) and the revised draft Northeastern Regional Environmental Characterization Report (RECR)

Response to state comments on the revised draft Southeastern Regional Characterization Reports for the Crystalline Repository Project

International Nuclear Information System (INIS)

1985-08-01

The purpose of this document is to respond to the comments received from the states of the Southeastern Region on the revised draft Southeastern Regional Characterization Reports (RCRs). The responses in this document indicate the manner in which the suggestions or comments received have been considered in modifying the revised draft Southeastern RCRs. Both general comments related to the overall Crystalline Repository Project (CRP) and comments on specific sections of the RCRs are addressed. This document responds to Southeastern State comments on both the revised draft Southeastern Regional Geologic Characterization Report (RGCR) and the revised draft Southeastern Regional Environmental Characterization Report (RECR)

Total-system performance assessment for Yucca Mountain - SNL second iteration (TSPA-1993); Volume 1

Energy Technology Data Exchange (ETDEWEB)

Wilson, M.L.; Gauthier, J.H.; Barnard, R.W.; Barr, G.E.; Dockery, H.A.; Dunn, E.; Eaton, R.R.; Guerin, D.C.; Lu, N.; Martinez, M.J. [and others

1994-04-01

Sandia National Laboratories has completed the second iteration of the periodic total-system performance assessments (TSPA-93) for the Yucca Mountain Site Characterization Project (YMP). These analyses estimate the future behavior of a potential repository for high-level nuclear waste at the Yucca Mountain, Nevada, site under consideration by the Department of Energy. TSPA-93 builds upon previous efforts by emphasizing YMP concerns relating to site characterization, design, and regulatory compliance. Scenarios describing expected conditions (aqueous and gaseous transport of contaminants) and low-probability events (human-intrusion drilling and volcanic intrusion) are modeled. The hydrologic processes modeled include estimates of the perturbations to ambient conditions caused by heating of the repository resulting from radioactive decay of the waste. Hydrologic parameters and parameter probability distributions have been derived from available site data. Possible future climate changes are modeled by considering two separate groundwater infiltration conditions: {open_quotes}wet{close_quotes} with a mean flux of 10 mm/yr, and {open_quotes}dry{close_quotes} with a mean flux of 0.5 mm/yr. Two alternative waste-package designs and two alternative repository areal thermal power densities are investigated. One waste package is a thin-wall container emplaced in a vertical borehole, and the second is a container designed with corrosion-resistant and corrosion-allowance walls emplaced horizontally in the drift. Thermal power loadings of 57 kW/acre (the loading specified in the original repository conceptual design) and 114 kW/acre (a loading chosen to investigate effects of a {open_quotes}hot repository{close_quotes}) are considered. TSPA-93 incorporates significant new detailed process modeling, including two- and three-dimensional modeling of thermal effects, groundwater flow in the saturated-zone aquifers, and gas flow in the unsaturated zone.

Total-system performance assessment for Yucca Mountain - SNL second iteration (TSPA-1993); Volume 2

Energy Technology Data Exchange (ETDEWEB)

Wilson, M.L.; Barnard, R.W.; Barr, G.E.; Dockery, H.A.; Dunn, E.; Eaton, R.R.; Martinez, M.J. [Sandia National Labs., Albuquerque, NM (United States); Gauthier, J.H.; Guerin, D.C.; Lu, N. [and others

1994-04-01

Sandia National Laboratories has completed the second iteration of the periodic total-system performance assessments (TSPA-93) for the Yucca Mountain Site Characterization Project (YMP). These analyses estimate the future behavior of a potential repository for high-level nuclear waste at the Yucca Mountain, Nevada, site under consideration by the Department of Energy. TSPA-93 builds upon previous efforts by emphasizing YMP concerns relating to site characterization, design, and regulatory compliance. Scenarios describing expected conditions (aqueous and gaseous transport of contaminants) and low-probability events (human-intrusion drilling and volcanic intrusion) are modeled. The hydrologic processes modeled include estimates of the perturbations to ambient conditions caused by heating of the repository resulting from radioactive decay of the waste. Hydrologic parameters and parameter probability distributions have been derived from available site data. Possible future climate changes are modeled by considering two separate groundwater infiltration conditions: {open_quotes}wet{close_quotes} with a mean flux of 10 mm/yr, and {open_quotes}dry{close_quotes} with a mean flux of 0.5 mm/yr. Two alternative waste-package designs and two alternative repository areal thermal power densities are investigated. One waste package is a thin-wall container emplaced in a vertical borehole, and the second is a container designed with corrosion-resistant and corrosion-allowance walls emplaced horizontally in the drift. Thermal power loadings of 57 kW/acre (the loading specified in the original repository conceptual design) and 114 kW/acre (a loading chosen to investigate effects of a {open_quotes}hot repository{close_quotes}) are considered. TSPA-93 incorporates significant new detailed process modeling, including two- and three-dimensional modeling of thermal effects, groundwater flow in the saturated-zone aquifers, and gas flow in the unsaturated zone.

Total-system performance assessment for Yucca Mountain - SNL second iteration (TSPA-1993)

International Nuclear Information System (INIS)

Wilson, M.L.; Gauthier, J.H.; Barnard, R.W.; Barr, G.E.; Dockery, H.A.; Dunn, E.; Eaton, R.R.; Guerin, D.C.; Lu, N.; Martinez, M.J.

1994-04-01

Sandia National Laboratories has completed the second iteration of the periodic total-system performance assessments (TSPA-93) for the Yucca Mountain Site Characterization Project (YMP). These analyses estimate the future behavior of a potential repository for high-level nuclear waste at the Yucca Mountain, Nevada, site under consideration by the Department of Energy. TSPA-93 builds upon previous efforts by emphasizing YMP concerns relating to site characterization, design, and regulatory compliance. Scenarios describing expected conditions (aqueous and gaseous transport of contaminants) and low-probability events (human-intrusion drilling and volcanic intrusion) are modeled. The hydrologic processes modeled include estimates of the perturbations to ambient conditions caused by heating of the repository resulting from radioactive decay of the waste. Hydrologic parameters and parameter probability distributions have been derived from available site data. Possible future climate changes are modeled by considering two separate groundwater infiltration conditions: open-quotes wetclose quotes with a mean flux of 10 mm/yr, and open-quotes dryclose quotes with a mean flux of 0.5 mm/yr. Two alternative waste-package designs and two alternative repository areal thermal power densities are investigated. One waste package is a thin-wall container emplaced in a vertical borehole, and the second is a container designed with corrosion-resistant and corrosion-allowance walls emplaced horizontally in the drift. Thermal power loadings of 57 kW/acre (the loading specified in the original repository conceptual design) and 114 kW/acre (a loading chosen to investigate effects of a open-quotes hot repositoryclose quotes) are considered. TSPA-93 incorporates significant new detailed process modeling, including two- and three-dimensional modeling of thermal effects, groundwater flow in the saturated-zone aquifers, and gas flow in the unsaturated zone

Fabrication, characterization and testing of silicon photomultipliers for the Muon Portal Project

International Nuclear Information System (INIS)

La Rocca, P.; Billotta, S.; Blancato, A.A.; Bonanno, D.; Bonanno, G.; Fallica, G.; Garozzo, S.; Lo Presti, D.; Marano, D.; Pugliatti, C.; Riggi, F.; Romeo, G.; Santagati, G.; Valvo, G.

2015-01-01

The Muon Portal is a recently started Project aiming at the construction of a large area tracking detector that exploits the muon tomography technique to inspect the contents of traveling cargo containers. The detection planes will be made of plastic scintillator strips with embedded wavelength-shifting fibres. Special designed silicon photomultipliers will read the scintillation light transported by the fibres along the strips and a dedicated electronics will combine signals from different strips to reduce the overall number of channels, without loss of information. Different silicon photomultiplier prototypes, both with the p-on-n and n-on-p technologies, have been produced by STMicroelectronics during the last years. In this paper we present the main characteristics of the silicon photomultipliers designed for the Muon Portal Project and describe the setup and the procedure implemented for the characterization of these devices, giving some statistical results obtained from the test of a first batch of silicon photomultipliers

Fabrication, characterization and testing of silicon photomultipliers for the Muon Portal Project

Energy Technology Data Exchange (ETDEWEB)

La Rocca, P., E-mail: paola.larocca@ct.infn.it [Dipartimento di Fisica e Astronomia - Catania (Italy); INFN - Sezione di Catania (Italy); Billotta, S. [INAF - Osservatorio Astrofisico di Catania (Italy); Blancato, A.A.; Bonanno, D. [Dipartimento di Fisica e Astronomia - Catania (Italy); Bonanno, G. [INAF - Osservatorio Astrofisico di Catania (Italy); Fallica, G. [STMicroelectronics - Catania (Italy); Garozzo, S. [INAF - Osservatorio Astrofisico di Catania (Italy); Lo Presti, D. [Dipartimento di Fisica e Astronomia - Catania (Italy); INFN - Sezione di Catania (Italy); Marano, D. [INAF - Osservatorio Astrofisico di Catania (Italy); Pugliatti, C.; Riggi, F. [Dipartimento di Fisica e Astronomia - Catania (Italy); INFN - Sezione di Catania (Italy); Romeo, G. [INAF - Osservatorio Astrofisico di Catania (Italy); Santagati, G. [Dipartimento di Fisica e Astronomia - Catania (Italy); INFN - Sezione di Catania (Italy); Valvo, G. [STMicroelectronics - Catania (Italy)

2015-07-01

The Muon Portal is a recently started Project aiming at the construction of a large area tracking detector that exploits the muon tomography technique to inspect the contents of traveling cargo containers. The detection planes will be made of plastic scintillator strips with embedded wavelength-shifting fibres. Special designed silicon photomultipliers will read the scintillation light transported by the fibres along the strips and a dedicated electronics will combine signals from different strips to reduce the overall number of channels, without loss of information. Different silicon photomultiplier prototypes, both with the p-on-n and n-on-p technologies, have been produced by STMicroelectronics during the last years. In this paper we present the main characteristics of the silicon photomultipliers designed for the Muon Portal Project and describe the setup and the procedure implemented for the characterization of these devices, giving some statistical results obtained from the test of a first batch of silicon photomultipliers.

Yucca Mountain Climate Technical Support Representative

International Nuclear Information System (INIS)

Sharpe, Saxon E

2007-01-01

The primary objective of Project Activity ORD-FY04-012, 'Yucca Mountain Climate Technical Support Representative', was to provide the Office of Civilian Radioactive Waste Management (OCRWM) with expertise on past, present, and future climate scenarios and to support the technical elements of the Yucca Mountain Project (YMP) climate program. The Climate Technical Support Representative was to explain, defend, and interpret the YMP climate program to the various audiences during Site Recommendation and License Application. This technical support representative was to support DOE management in the preparation and review of documents, and to participate in comment response for the Final Environmental Impact Statement, the Site Recommendation Hearings, the NRC Sufficiency Comments, and other forums as designated by DOE management. Because the activity was terminated 12 months early and experience a 27% reduction in budget, it was not possible to complete all components of the tasks as originally envisioned. Activities not completed include the qualification of climate datasets and the production of a qualified technical report. The following final report is an unqualified summary of the activities that were completed given the reduced time and funding

Nevada Test Site Perspective on Characterization and Loading of Legacy Transuranic Drums Utilizing the Central Characterization Project

International Nuclear Information System (INIS)

R.G. Lahoud; J. F. Norton; I. L. Siddoway; L. W. Griswold

2006-01-01

The Nevada Test Site (NTS) has successfully completed a multi-year effort to characterize and ship 1860 legacy transuranic (TRU) waste drums for disposal at the Waste Isolation Pilot Plant (WIPP), a permanent TRU disposal site. This has been a cooperative effort among the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), the U.S. Department of Energy, Carlsbad Field Office (DOE/CBFO), the NTS Management and Operations (M and O) contractor Bechtel Nevada (BN), and various contractors under the Central Characterization Project (CCP) umbrella. The success is due primarily to the diligence, perseverance, and hard work of each of the contractors, the DOE/CBFO, and NNSA/NSO, along with the support of the U.S. Department of Energy, Headquarters (DOE/HQ). This paper presents, from an NTS perspective, the challenges and successes of utilizing the CCP for obtaining a certified characterization program, sharing responsibilities for characterization, data validation, and loading of TRU waste with BN to achieve disposal at WIPP from a Small Quantity Site (SQS) such as the NTS. The challenges in this effort arose from two general sources. First, the arrangement of DOE/CBFO contractors under the CCP performing work and certifying waste at the NTS within a Hazard Category 2 (HazCat 2) non-reactor nuclear facility operated by BN, presented difficult challenges. The nuclear safety authorization basis, safety liability and responsibility, conduct of operations, allocation and scheduling of resources, and other issues were particularly demanding. The program-level and field coordination needed for the closely interrelated characterization tasks was extensive and required considerable effort by all parties. The second source of challenge was the legacy waste itself. None of the waste was generated at the NTS. The waste was generated at Lawrence Livermore National Laboratory (LLNL), Lawrence Berkeley Laboratory (LBL), Lynchburg, Rocky

Waste package materials selection process

International Nuclear Information System (INIS)

Roy, A.K.; Fish, R.L.; McCright, R.D.

1994-01-01

The office of Civilian Radioactive Waste Management (OCRWM) of the United States Department of Energy (USDOE) is evaluating a site at Yucca Mountain in Southern Nevada to determine its suitability as a mined geologic disposal system (MGDS) for the disposal of high-level nuclear waste (HLW). The B ampersand W Fuel Company (BWFC), as a part of the Management and Operating (M ampersand O) team in support of the Yucca Mountain Site Characterization Project (YMP), is responsible for designing and developing the waste package for this potential repository. As part of this effort, Lawrence Livermore National Laboratory (LLNL) is responsible for testing materials and developing models for the materials to be used in the waste package. This paper is aimed at presenting the selection process for materials needed in fabricating the different components of the waste package

PROCESS FOR LICENSE APPLICATION DEVELOPMENT FOR THE GEOLOGIC REPOSITORY

International Nuclear Information System (INIS)

DOUGLAS M. FRANKS AND NORMAN C. HENDERSON

1997-01-01

The Department of Energy (DOE), specifically the Office of Civilian Radioactive Waste Management (OCRWM) has been charged by the U.S. Congress, through the Nuclear Waste Policy Act (NWPA), with the responsibility for obtaining a license to develop a geologic repository. The NRC is the licensing authority for geologic disposal, and its regulations pertinent to construction authorization and license application are specified in 10 CFR Part 60, Disposal of High-Level Radioactive Wastes in Geologic Repositories, (section)60.21ff and (section)60.31ff. This paper discusses the process the Yucca Mountain Site Site Characterization Project (YMP) will use to identify and apply regulatory and industry guidance to development of the license application (LA) for a geologic repository at Yucca Mountain, Nevada. This guidance will be implemented by the ''Technical Guidance Document for Preparation of the License Application'' (TGD), currently in development

Calibrated Properties Model

International Nuclear Information System (INIS)

Ahlers, C.; Liu, H.

2000-01-01

The purpose of this Analysis/Model Report (AMR) is to document the Calibrated Properties Model that provides calibrated parameter sets for unsaturated zone (UZ) flow and transport process models for the Yucca Mountain Site Characterization Project (YMP). This work was performed in accordance with the ''AMR Development Plan for U0035 Calibrated Properties Model REV00. These calibrated property sets include matrix and fracture parameters for the UZ Flow and Transport Model (UZ Model), drift seepage models, drift-scale and mountain-scale coupled-processes models, and Total System Performance Assessment (TSPA) models as well as Performance Assessment (PA) and other participating national laboratories and government agencies. These process models provide the necessary framework to test conceptual hypotheses of flow and transport at different scales and predict flow and transport behavior under a variety of climatic and thermal-loading conditions

Process for license application development for the geologic repository

International Nuclear Information System (INIS)

Franks, D.M.; Henderson, N.C.

1998-01-01

The Department of Energy (DOE), specifically the Office of Civilian Radioactive Waste Management (OCRWM) has been charged by the US Congress, through the Nuclear Waste Policy Act (NWPA), with the responsibility for obtaining a license to develop a geologic repository. The NRC is the licensing authority for geologic disposal, and its regulations pertinent to construction authorization and license application are specified in 10 CFR Part 60, Disposal of High-Level Radioactive Wastes in Geologic Repositories, section 60.21ff and section 60.31ff. This paper discusses the process the Yucca Mountain Site Characterization Project (YMP) will use to identify and apply regulatory and industry guidance to development of the license application (LA) for a geologic repository at Yucca Mountain, Nevada. This guidance will be implemented by the Technical Guidance Document for Preparation of the License Application (TGD), currently in development

Preliminary site characterization radiological monitoring plan for the Nevada Nuclear Waste Storage Investigations Project, Yucca Mountain Site

International Nuclear Information System (INIS)

1987-03-01

The activities described in this plan occur in the early phases of site characterization. This document presents the Preliminary Site Characterization Radiological Monitoring Plan (PSCRMP) for collecting and evaluating data in support of the NNWSI Project. The PSCRMP defines and identifies control procedures for the monitoring activities. The PSCRMP activity will utilize integrating radon monitoring devices, a continuous radon monitor, and a particulate air sampler. These instruments will be used to establish the baseline radioactivity and/or radioactivity released due to early site characterization activities. The sections that follow provide a general project description, the specifics of the monitoring program, and the practices that will be employed to ensure the validity of the collected data by integrating quality assurance into all activities. Section 2 of this document describes the regulatory base of this document. Section 3 describes the site characterization activities which may lead to release of radioactivity. Section 4 provides a description of the potential sources of radioactivity that site characterization could generate. Section 5 summarizes the sampling and monitoring methodology, which will be used to monitor the potential sources of radioactivity. The network of sampling and monitoring equipment is described in Section 6, and Section 7 summarizes the systems operation activities. The data reporting activities are described in Section 8. Finally, a description of the Quality Assurance (QA) and Quality Control (QC) activities is provided in Section 9. Appendix A contains a summary of the procedures to be used in this program, and Appendix B contains technical specification on equipment and services. 20 refs., 11 figs., 2 tabs

Thermal Testing Measurements Report

Energy Technology Data Exchange (ETDEWEB)

R. Wagner

2002-09-26

The purpose of the Thermal Testing Measurements Report (Scientific Analysis Report) is to document, in one report, the comprehensive set of measurements taken within the Yucca Mountain Project Thermal Testing Program since its inception in 1996. Currently, the testing performed and measurements collected are either scattered in many level 3 and level 4 milestone reports or, in the case of the ongoing Drift Scale Test, mostly documented in eight informal progress reports. Documentation in existing reports is uneven in level of detail and quality. Furthermore, while all the data collected within the Yucca Mountain Site Characterization Project (YMP) Thermal Testing Program have been submitted periodically to the Technical Data Management System (TDMS), the data structure--several incremental submittals, and documentation formats--are such that the data are often not user-friendly except to those who acquired and processed the data. The documentation in this report is intended to make data collected within the YMP Thermal Testing Program readily usable to end users, such as those representing the Performance Assessment Project, Repository Design Project, and Engineered Systems Sub-Project. Since either detailed level 3 and level 4 reports exist or the measurements are straightforward, only brief discussions are provided for each data set. These brief discussions for different data sets are intended to impart a clear sense of applicability of data, so that they will be used properly within the context of measurement uncertainty. This approach also keeps this report to a manageable size, an important consideration because the report encompasses nearly all measurements for three long-term thermal tests. As appropriate, thermal testing data currently residing in the TDMS have been reorganized and reformatted from cumbersome, user-unfriendly Input-Data Tracking Numbers (DTNs) into a new set of Output-DTNs. These Output-DTNs provide a readily usable data structure

Characterizing uncertain sea-level rise projections to support investment decisions.

Science.gov (United States)

Sriver, Ryan L; Lempert, Robert J; Wikman-Svahn, Per; Keller, Klaus

2018-01-01

Many institutions worldwide are considering how to include uncertainty about future changes in sea-levels and storm surges into their investment decisions regarding large capital infrastructures. Here we examine how to characterize deeply uncertain climate change projections to support such decisions using Robust Decision Making analysis. We address questions regarding how to confront the potential for future changes in low probability but large impact flooding events due to changes in sea-levels and storm surges. Such extreme events can affect investments in infrastructure but have proved difficult to consider in such decisions because of the deep uncertainty surrounding them. This study utilizes Robust Decision Making methods to address two questions applied to investment decisions at the Port of Los Angeles: (1) Under what future conditions would a Port of Los Angeles decision to harden its facilities against extreme flood scenarios at the next upgrade pass a cost-benefit test, and (2) Do sea-level rise projections and other information suggest such conditions are sufficiently likely to justify such an investment? We also compare and contrast the Robust Decision Making methods with a full probabilistic analysis. These two analysis frameworks result in similar investment recommendations for different idealized future sea-level projections, but provide different information to decision makers and envision different types of engagement with stakeholders. In particular, the full probabilistic analysis begins by aggregating the best scientific information into a single set of joint probability distributions, while the Robust Decision Making analysis identifies scenarios where a decision to invest in near-term response to extreme sea-level rise passes a cost-benefit test, and then assembles scientific information of differing levels of confidence to help decision makers judge whether or not these scenarios are sufficiently likely to justify making such investments

Preliminary selection criteria for the Yucca Mountain Project waste package container material

International Nuclear Information System (INIS)

Halsey, W.G.

1991-01-01

The Department of Energy's Yucca Mountain Project (YMP) is evaluating a site at Yucca Mountain in Nevada for construction of a geologic repository for the storage of high-level nuclear waste. Lawrence Livermore National Laboratory's (LLNL) Nuclear Waste Management Project (NWMP) has the responsibility for design, testing, and performance analysis of the waste packages. The design is performed in an iterative manner in three sequential phases (conceptual design, advanced conceptual design, and license application design). An important input to the start of the advanced conceptual design is the selection of the material for the waste containers. The container material is referred to as the 'metal barrier' portion of the waste package, and is the responsibility of the Metal Barrier Selection and Testing task at LLNL. The selection will consist of several steps. First, preliminary, material-independent selection criteria will be established based on the performance goals for the container. Second, a variety of engineering materials will be evaluated against these criteria in a screening process to identify candidate materials. Third, information will be obtained on the performance of the candidate materials, and final selection criteria and quantitative weighting factors will be established based on the waste package design requirements. Finally, the candidate materials will be ranked against these criteria to determine whether they meet the mandated performance requirements, and to provide a comparative score to choose the material for advanced conceptual design activities. This document sets forth the preliminary container material selection criteria to be used in screening candidate materials. 5 refs

Fluid characterization for miscible EOR projects and CO2 sequestration

DEFF Research Database (Denmark)

Jessen, Kristian; Stenby, Erling Halfdan

2007-01-01

Accurate performance prediction of miscible enhanced-oil-recovery (EOR) projects or CO, sequestration in depleted oil and gas reservoirs relies in part on the ability of an equation-of-state (EOS) model to adequately represent the properties of a wide range of mixtures of the resident fluid...... in the data reduction and demonstrate that for some gas/oil systems, swelling tests do not contribute to a more accurate prediction of multicontact miscibility. Finally, we report on the impact that use of EOS models based on different characterization procedures can have on recovery predictions from dynamic...... and the injected fluid(s). The mixtures that form when gas displaces oil in a porous medium will, in many cases, differ significantly from compositions created in swelling tests and other standard pressure/volume/temperature (PVT) experiments. Multicontact experiments (e.g., slimtube displacements) are often used...

Response to state comments on the draft regional characterization reports for the Crystalline Repository Project

International Nuclear Information System (INIS)

1984-11-01

In May, 1983, the US Department of Energy (DOE) Crystalline Repository Project Office (CPO) issued six draft Regional Characterization Reports (RCRs) for review and comment to the 17 Crystalline States comprising the Northeastern, Southeastern, and North Central crystalline regions. Comment letters were received from 13 of the 17 states. The more than 2000 comments generally focused on the quality and content of the characterization reports and on their intended use in region-to-area screening. These comments were paraphrased and grouped into 23 subjects within the following four topical areas: (1) General and Programmatic; (2) Geologic; (3) Environmental and Socioeconomic; and (4) Editorial. This document provides responses to the comments submitted by the states

Probabilistic comparison of alternative characterization technologies at the Fernald Uranium-in-Soils Integrated Demonstration Project

International Nuclear Information System (INIS)

Rautman, C.A.; McGraw, M.A.; Istok, J.D.; Sigda, J.M.; Kaplan, P.G.

1993-01-01

The performance of four alternative characterization technologies proposed for use in characterization of surficial uranium contamination in soil at the Incinerator and Drum Baling Areas at the Fernald Environmental Management Project in southwestern Ohio has been evaluated using a probabilistic, risk-based decision-analysis methodology. The basis of comparison is to minimize a computed total cost for environmental cleanup. This total-cost-based approach provides a framework for evaluating the trade-offs among remedial investigation, the remedial design, and the risk of regulatory penalties. The approach explicitly recognizes the value of information provided by remedial investigation; additional measurements are only valuable to the extent that the information they provide reduces total cost

Update to Assessment of Direct Disposal in Unsaturated Tuff of Spent Nuclear Fuel and High-Level Waste Owned by U.S. Department of Energy

Energy Technology Data Exchange (ETDEWEB)

P. D. Wheatley (INEEL POC); R. P. Rechard (SNL)

1998-09-01

The overall purpose of this study is to provide information and guidance to the Office of Environmental Management of the U.S. Department of Energy (DOE) about the level of characterization necessary to dispose of DOE-owned spent nuclear fuel (SNF). The disposal option modeled was codisposal of DOE SNF with defense high-level waste (DHLW). A specific goal was to demonstrate the influence of DOE SNF, expected to be minor, in a predominately commercial repository using modeling conditions similar to those currently assumed by the Yucca Mountain Project (YMP). A performance assessment (PA) was chosen as the method of analysis. The performance metric for this analysis (referred to as the 1997 PA) was dose to an individual; the time period of interest was 100,000 yr. Results indicated that cumulative releases of 99Tc and 237Np (primary contributors to human dose) from commercial SNF exceed those of DOE SNF both on a per MTHM and per package basis. Thus, if commercial SNF can meet regulatory performance criteria for dose to an individual, then the DOE SNF can also meet the criteria. This result is due in large part to lower burnup of the DOE SNF (less time for irradiation) and to the DOE SNF's small percentage of the total activity (1.5%) and mass (3.8%) of waste in the potential repository. Consistent with the analyses performed for the YMP, the 1997 PA assumed all cladding as failed, which also contributed to the relatively poor performance of commercial SNF compared to DOE SNF.

Update to Assessment of Direct Disposal in Unsaturated Tuff of Spent Nuclear Fuel and High-Level Waste Owned by U.S. Department of Energy

International Nuclear Information System (INIS)

Wheatley, P.D.; Rechard, R.P.

1998-01-01

The overall purpose of this study is to provide information and guidance to the Office of Environmental Management of the U.S. Department of Energy (DOE) about the level of characterization necessary to dispose of DOE-owned spent nuclear fuel (SNF). The disposal option modeled was codisposal of DOE SNF with defense high-level waste (DHLW). A specific goal was to demonstrate the influence of DOE SNF, expected to be minor, in a predominately commercial repository using modeling conditions similar to those currently assumed by the Yucca Mountain Project (YMP). A performance assessment (PA) was chosen as the method of analysis. The performance metric for this analysis (referred to as the 1997 PA) was dose to an individual; the time period of interest was 100,000 yr. Results indicated that cumulative releases of 99Tc and 237Np (primary contributors to human dose) from commercial SNF exceed those of DOE SNF both on a per MTHM and per package basis. Thus, if commercial SNF can meet regulatory performance criteria for dose to an individual, then the DOE SNF can also meet the criteria. This result is due in large part to lower burnup of the DOE SNF (less time for irradiation) and to the DOE SNF's small percentage of the total activity (1.5%) and mass (3.8%) of waste in the potential repository. Consistent with the analyses performed for the YMP, the 1997 PA assumed all cladding as failed, which also contributed to the relatively poor performance of commercial SNF compared to DOE SNF

Rastaan tarina -lyhytanimaation suunnittelu ja toteutus

OpenAIRE

Kurtti, Sofi

2014-01-01

Opinnäytetyössä perehdytään tarinankerrontaan ja sen historiaan. Työssä tarkastellaan erityisesti, millaisia tarinankerrontatapoja peleissä on, koska niissä tarinankerronnan käyttö on nykyaikana lisääntynyt paljon. Kerrontatapoja ovat esimerkiksi välianimaatiot ja ympäristöstä havaittava kerronta. Ympäristöpohjaiseen kerrontaan kuuluvat esimerkiksi rikkoutuneet rakennukset, muiden kuviteltujen hahmojen jättämät vihjeet tai huomion kiinnittäminen valaistuksen avulla. Ympäristön havainnoinn...

Life cycle methods for environmental assessment of nanotechnology

OpenAIRE

Kekäläinen, Janne

2012-01-01

Tämä tutkielma on kirjallisuuskatsaus, joka antaa yleissilmäyksen erilaisiin elinkaarimetodeihin, joilla voidaan arvioida nanoteknologiaa sisältävien tuotteiden ympäristövaikutuksia. Työssä selvitetään elinkaariajattelun tärkeys ja kuvataan erilaisia ympäristöarviointimenetelmiä. Tässä tutkielmassa tarkastellut menetelmät ovat elinkaariarvionti (LCA), hiilijalanjälki, vesijalanjälki, ekologinen jalanjälki ja ekologinen selkäreppu (MIPS). Työ käsittelee nanoteknologiaan liittyviä ympäristöasio...

Test and characterization of multigap resistive plate chambers for the EEE project

CERN Document Server

Bossini, E

2016-01-01

The Extreme Energy Events project is based on the deployment of cosmic-ray telescopes in Italian high schools with the active contribution of students and teachers. Each telescope is made by three Multigap Resistive Plate Chambers readout by strips. With around 50 telescopes already built and others under construction, specific systems to test and characterize the chambers are needed. In this article I will present a flexible and software-configurable solution to perform chamber efficiency studies with a set of scintillators and hardware to automatically scan detector strips to identify electrical issues. Both systems can provide accurate information but at the same time they can be easily operated by students.

Characterizing changes in the excitability of corticospinal projections to proximal muscles of the upper limb.

Science.gov (United States)

Carson, Richard G; Nelson, Barry D; Buick, Alison R; Carroll, Timothy J; Kennedy, Niamh C; Cann, Rachel Mac

2013-09-01

There has been an explosion of interest in methods of exogenous brain stimulation that induce changes in the excitability of human cerebral cortex. The expectation is that these methods may promote recovery of function following brain injury. To assess their effects on motor output, it is typical to assess the state of corticospinal projections from primary motor cortex to muscles of the hand, via electromyographic responses to transcranial magnetic stimulation. If a range of stimulation intensities is employed, the recruitment curves (RCs) obtained can, at least for intrinsic hand muscles, be fitted by a sigmoid function. To establish whether sigmoid fits provide a reliable basis upon which to characterize the input-output properties of the corticospinal pathway for muscles proximal to the hand, and to assess as an alternative the area under the (recruitment) curve (AURC). A comparison of the reliability of these measures, using RCs obtained for muscles that are frequently the targets of rehabilitation. The AURC is an extremely reliable measure of the state of corticospinal projections to hand and forearm muscles, which has both face and concurrent validity. Construct validity is demonstrated by detection of widely distributed (across muscles) changes in corticospinal excitability induced by paired associative stimulation (PAS). The parameters derived from sigmoid fits are unlikely to provide an adequate means to assess the effectiveness of therapeutic regimes. The AURC can be employed to characterize corticospinal projections to a range of muscles, and gauge the efficacy of longitudinal interventions in clinical rehabilitation. Copyright © 2013 Elsevier Inc. All rights reserved.

RELIABILITY AND ACCURACY ASSESSMENT OF INVASIVE AND NON- INVASIVE SEISMIC METHODS FOR SITE CHARACTERIZATION: FEEDBACK FROM THE INTERPACIFIC PROJECT

OpenAIRE

Garofalo , F.; Foti , S.; Hollender , F.; Bard , P.-Y.; Cornou , C.; Cox , B.R.; Dechamp , A.; Ohrnberger , M.; Sicilia , D.; Vergniault , C.

2017-01-01

International audience; The InterPacific project (Intercomparison of methods for site parameter and velocity profile characterization) aims to assess the reliability of seismic site characterization methods (borehole and surface wave methods) used for estimating shear wave velocity (VS) profiles and other related parameters (e.g., VS30). Three sites, representative of different geological conditions relevant for the evaluation of seismic site response effects, have been selected: (1) a hard r...

Validation procedures used in the Background Soil Characterization Project on the Oak Ridge Reservation, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1993-12-01

The purpose of this report is (1) to document the data validation process developed for the Background Soil Characterization Project (BSCP); (2) to offer members of other project teams and potential data users the benefit of the experience gained in the BSCP in the area of developing project-specific data validation criteria and procedures based on best available guidance and technical information; and (3) to provide input and guidance to the efforts under way within Martin Marietta Energy Systems, Inc., to develop standard operating procedures to streamline and optimize the analytical laboratory data validation process for general use by making it more technically rigorous, consistent, and cost effective. Lessons learned from the BSCP are also provided to meet this end (Sect. 1.3)

Characterization of the central neural projections to brown, white, and beige adipose tissue.

Science.gov (United States)

Wiedmann, Nicole M; Stefanidis, Aneta; Oldfield, Brian J

2017-11-01

The functional recruitment of classic brown adipose tissue (BAT) and inducible brown-like or beige fat is, to a large extent, dependent on intact sympathetic neural input. Whereas the central neural circuits directed specifically to BAT or white adipose tissue (WAT) are well established, there is only a developing insight into the nature of neural inputs common to both fat types. Moreover, there is no clear view of the specific central and peripheral innervation of the browned component of WAT: beige fat. The objective of the present study is to examine the neural input to both BAT and WAT in the same animal and, by exposing different cohorts of rats to either thermoneutral or cold conditions, define changes in central neural organization that will ensure that beige fat is appropriately recruited and modulated after browning of inguinal WAT (iWAT). At thermoneutrality, injection of the neurotropic (pseudorabies) viruses into BAT and WAT demonstrates that there are dedicated axonal projections, as well as collateral axonal branches of command neurons projecting to both types of fat. After cold exposure, central neural circuits directed to iWAT showed evidence of reorganization with a greater representation of command neurons projecting to both brown and beiged WAT in hypothalamic (paraventricular nucleus and lateral hypothalamus) and brainstem (raphe pallidus and locus coeruleus) sites. This shift was driven by a greater number of supraspinal neurons projecting to iWAT under cold conditions. These data provide evidence for a reorganization of the nervous system at the level of neural connectivity following browning of WAT.-Wiedmann, N. M., Stefanidis, A., Oldfield, B. J. Characterization of the central neural projections to brown, white, and beige adipose tissue. © FASEB.

Response to state comments on the revised draft North Central Regional characterization reports for the Crystalline Repository Project

International Nuclear Information System (INIS)

1985-08-01

The purpose of this document is to respond to the comments received from the states of the North Central Region on the revised draft North Central Regional Characterization Reports (RCRs). The responses in this document indicate the manner in which the suggestions or comments received have been considered in modifying the revised draft North Central RCRs. Both general comments related to the overall Crystalline Repository Project (CRP) and comments on specific sections of the RCRs are addressed. This document responds to North Central State comments on both the revised draft North Central Regional Geologic Characterization Report (RGCR) and the revised draft North Central Regional Environmental Characterization Report (RECR)

Engineered materials characterization report for the Yucca Mountain Site Characterization Project. Volume 1, Introduction, history, and current candidates

International Nuclear Information System (INIS)

Van Konynenburg, R.A.; McCright, R.D.; Roy, A.K.; Jones, D.A.

1995-08-01

The purpose of the Yucca Mountain Site Characterization Project is to evaluate Yucca Mountain for its suitability as a potential site for the nation's first high-level nuclear waste repository. As part of this effort, Lawrence Livermore National Laboratory (LLNL) has been occupied for a number of years with developing and evaluating the performance of waste packages for the potential repository. In recent years this work has been carried out under the guidance of and in collaboration with the Management and Operating contractor for the Civilian Radioactive Waste Management System, TRW Environmental Safety Systems, Inc., which in turn reports to the Office of Civilian Radioactive Waste Management of the US Department of Energy. This report summarizes the history of the selection and characterization of materials to be used in the engineered barrier system for the potential repository at Yucca Mountain, describes the current candidate materials, presents a compilation of their properties, and summarizes available corrosion data and modeling. The term ''engineered materials'' is intended to distinguish those materials that are used as part of the engineered barrier system from the natural, geologic materials of the site

Single Shell Tank Waste Characterization Project for Tank B-110, Core 9 - data package and PNL validation summary report

International Nuclear Information System (INIS)

Pool, K.N.; Jones, T.E.; McKinley, S.G.; Tingey, J.M.; Longaker, T.M.; Gibson, J.A.

1990-01-01

This Data Package contains results obtained by Pacific Northwest Laboratory (PNL) staff in the characterization and analyses of Core 9 segments taken from the Single-Shell Tank (SST) 110B. The characterization and analysis of Core 9 segments are outlined in the Waste Characterization Plan for Hanford Site Single-Shell Tanks and in the Pacific Northwest Laboratory (PNL) Single-Shell Tank Waste Characterization Support FY 89/90 Statement of Work (SOW), Rev. 1 dated March, 1990. Specific analyses for each sub-sample taken from a segment are delineated in Test Instructions prepared by the PNL Single-Shell Tank Waste Characterization Project Management Office (SST Project) in accordance with procedures contained in the SST Waste Characterization Procedure Compendium (PNL-MA-599). Analytical procedures used in the characterization activities are also included in PNL-MA-599. Core 9 included five segments although segment 1 did not have sufficient material for characterization. The five samplers were received from Westinghouse Hanford Company (WHC) on 11/21-22/89. Each segment was contained in a sampler and was enclosed in a shipping cask. The shipping cask was butted up to the 325-A hot cell and the sampler moved into the hot cell. The material in the sampler (i.e., the segment) was extruded from the sampler, limited physical characteristics assessed, and photographed. At this point samples were taken for particle size and volatile organic analyses. Each segment was then homogenized. Sub-samples were taken for required analyses as delineated in the appropriate Test Instruction. Table 1 includes sample numbers assigned to Core 9 segment materials being transferred from 325-A Hot Cell. Sample numbers 90-0298, 90-0299, 90-0302, and 90-0303 were included in Table 1 although no analyses were requested for these samples. Table 2 lists Core 9 sub-sample numbers per sample preparation method

Remote sensing data exploiration for geologic characterization of difficult targets : Laboratory Directed Research and Development project 38703 final report.

Energy Technology Data Exchange (ETDEWEB)

Costin, Laurence S.; Walker, Charles A.; Lappin, Allen R.; Hayat, Majeed M. (University of New Mexico, Albuquerque, NM); Ford, Bridget K.; Paskaleva, Biliana (University of New Mexico, Albuquerque, NM); Moya, Mary M.; Mercier, Jeffrey Alan (University of Arizona, Tucson, AZ); Stormont, John C. (University of New Mexico, Albuquerque, NM); Smith, Jody Lynn

2003-09-01

Characterizing the geology, geotechnical aspects, and rock properties of deep underground facility sites can enhance targeting strategies for both nuclear and conventional weapons. This report describes the results of a study to investigate the utility of remote spectral sensing for augmenting the geological and geotechnical information provided by traditional methods. The project primarily considered novel exploitation methods for space-based sensors, which allow clandestine collection of data from denied sites. The investigation focused on developing and applying novel data analysis methods to estimate geologic and geotechnical characteristics in the vicinity of deep underground facilities. Two such methods, one for measuring thermal rock properties and one for classifying rock types, were explored in detail. Several other data exploitation techniques, developed under other projects, were also examined for their potential utility in geologic characterization.

THE DEVELOPMENT OF THE YUCCA MOUNTAIN PROJECT FEATURE, EVENT, AND PROCESS (FEP) DATABASE

International Nuclear Information System (INIS)

Freeze, G.; Swift, P.; Brodsky, N.

2000-01-01

A Total System Performance Assessment for Site Recommendation (TSPA-SR) has recently been completed (CRWMS M andO, 2000b) for the potential high-level waste repository at the Yucca Mountain site. The TSPA-SR is an integrated model of scenarios and processes relevant to the postclosure performance of the potential repository. The TSPA-SR scenarios and model components in turn include representations of all features, events, and processes (FEPs) identified as being relevant (i.e., screened in) for analysis. The process of identifying, classifying, and screening potentially relevant FEPs thus provides a critical foundation for scenario development and TSPA analyses for the Yucca Mountain site (Swift et al., 1999). The objectives of this paper are to describe (a) the identification and classification of the comprehensive list of FEPs potentially relevant to the postclosure performance of the potential Yucca Mountain repository, and (b) the development, structure, and use of an electronic database for storing and retrieving screening information about the inclusion and/or exclusion of these Yucca Mountain FEPs in TSPA-SR. The FEPs approach to scenario development is not unique to the Yucca Mountain Project (YMP). General systematic approaches are summarized in NEA (1992). The application of the FEPs approach in several other international radioactive waste disposal programs is summarized in NEA ( 1999)

Fiscal Year 1999 memorandum of understanding for the TWRS characterization project

International Nuclear Information System (INIS)

HUNT, J.W.

1998-01-01

During fiscal year 1999, the level of success achieved by the Tank Waste Remediation System (TWRS) shall be determined by specific performance measures. These measures take the form of significant deliverables, one of which is the completion of Tank Characterization Reports (TCRS). In order to achieve success regarding the TCR performance deliverable, multiple organizations across TWRS must work together. Therefore, the requirements and expectations needed from each of these TWRS organizations were examined in order to gain an understanding of the performance necessary from each organization to achieve the end deliverable. This memorandum of understanding (MOU) documents the results of this review and establishes the performance criteria by which TWRS will assess its progress and success. These criteria have been determined based upon a TWRS Characterization Project budget of $42.1 million for fiscal year 1999; if this budget is changed or the currently identified workscope is modified, this MOU will need to be revised accordingly. This MOU is subdivided into six sections, where sections three through six each identify individual interfaces between TWRS organizations. The specific performance criteria related to each TWRS organizational interface are then delineated in the section, along with any additional goals or issues pertaining to that interface

Fiscal year 1998 memorandum of understanding for the TWRS characterization project

International Nuclear Information System (INIS)

Schreiber, R.D.

1998-01-01

During fiscal year 1998, the level of success achieved by the Tank Waste Remediation System (TWRS) shall be determined by specific performance measures. These measures take the form of significant deliverables, one of which is the completion of Tank Characterization Reports (TCRs). In order to achieve success regarding the TCR performance deliverable, multiple organizations across TWRS must work together. Therefore, the requirements and expectations needed from each of these TWRS organizations were examined in order to gain an understanding of the performance necessary from each organization to achieve the end deliverable. This memorandum of understanding (MOU) documents the results of this review and establishes the performance criteria by which TWRS will assess its progress and success. These criteria have been determined based upon a TWRS Characterization Project budget of $47.5 million for fiscal year 1998; if this budget is changed or the currently identified work scope is modified, this MOU will need to be revised accordingly. This MOU is subdivided into six sections, where sections three through six each identify individual interfaces between TWRS organizations. The specific performance criteria related to each TWRS organizational interface are then delineated in the section, along with any additional goals or issues pertaining to that interface

Qualification of Thermodynamic Data for Geochemical Modeling of Mineral-Water Interactions in Dilute Systems

International Nuclear Information System (INIS)

T. J. Wolery; C.F. Jove-Colon

2004-01-01

The purpose of this analysis report is to qualify the thermochemical database data0.ymp.R2 (DTN: MO0302SPATHDYN.000 [DIRS 161756], qualified by this report) and supporting calculations (DTNs: MO0302SPATHDYN.001 [DIRS 161886], and MO0303SPASPEQ2.000 [DIRS 162278]), which were originally documented in ''Data Qualification: Update and Revision of the Geochemical Thermodynamic Database, Data0.ymp'' (Steinborn et al. 2003 [DIRS 161956]). This original document still serves as the record of development of the data0.ymp.R2 database (DTN: MO0302SPATHDYN.000 [DIRS 161756]). The data0.ymp.R2 thermodynamic database (DTN: MO0302SPATHDYN.000 [DIRS 161756]) was developed for use with software code EQ3/6 (EQ3/6 V8.0, STN: 10813-8.0-00) (BSC 2003 [DIRS 162228]) and software code EQ6 (EQ6 V7.2bLV, STN: 10075-7.2bLV-02) (BSC 2002 [DIRS 159731]) to conduct geochemical modeling of mineral-fluid interactions involving aqueous solutions (ionic strengths of up to one molal; see Section 6.5) and temperatures of up to 300 C along the liquid-vapor saturation curve of pure water. The data0.ymp.R2 database (DTN: MO0302SPATHDYN.000 [DIRS 161756]) is an update of the previously qualified predecessor database data0.ymp.R0 (DTN: MO0009THRMODYN.001 [DIRS 152576]). The scope of this report is limited to qualification of the updates, as well as identification and evaluation of certain errors and discrepancies as discussed

Calibrated Properties Model

International Nuclear Information System (INIS)

Ahlers, C.F.; Liu, H.H.

2001-01-01

The purpose of this Analysis/Model Report (AMR) is to document the Calibrated Properties Model that provides calibrated parameter sets for unsaturated zone (UZ) flow and transport process models for the Yucca Mountain Site Characterization Project (YMP). This work was performed in accordance with the AMR Development Plan for U0035 Calibrated Properties Model REV00 (CRWMS M and O 1999c). These calibrated property sets include matrix and fracture parameters for the UZ Flow and Transport Model (UZ Model), drift seepage models, drift-scale and mountain-scale coupled-processes models, and Total System Performance Assessment (TSPA) models as well as Performance Assessment (PA) and other participating national laboratories and government agencies. These process models provide the necessary framework to test conceptual hypotheses of flow and transport at different scales and predict flow and transport behavior under a variety of climatic and thermal-loading conditions

Standard characterization of soils employed in the FAO/IAEA phosphate project

International Nuclear Information System (INIS)

Montange, D.; Zapata, F.

2002-01-01

In the frame of the FAO/IAEA networked research project, the agronomic effectiveness of natural and modified phosphate rock (PR) products was evaluated using nuclear and related techniques under a variety of soil, climate and management conditions. In addition to the local soil analyses, it was decided to make a standard characterization of the soils employed in the project to gather direct and comparable information on the relevant soil properties affecting the suitability of PRs for direct application and to better interpret the results from the agronomic evaluation, including the creation of a database for phosphate modelling. This paper describes the standard characterization of soils, that was mainly made at CIRAD, Montpellier, France. A total of 51 soil samples were analyzed from 15 countries including Belarus (1), Brazil (2), Chile (3), China (20), Cuba (2) Ghana (6), Hungary (2), Indonesia (3), Kenya (1), Malaysia (1), Poland (1), Romania (2), Russia (1), Thailand (3) and Venezuela (3). Methods of analyses used for the soil characterization included textural class, pH, chemical analysis for total N and P, and exchangeable elements (CEC, saturation). Available P was measured using 4 methods including Olsen, Bray II, Pi paper and Resin. Available P measurements using resin method were made at CENA, Piracicaba, Brazil. The soil P dynamics was described using the 32 P isotope exchange kinetic method at CEN Cadarache, France with the same soil samples. As a result of the worldwide distribution of the soils employed in the project, the results showed a very large diversity in each of the measured soil characteristics. The analysis of the data focused on the most representative tropical acid soils, i.e. Ultisols and Oxisols. Inceptisols have also been included because most of them were acid and located in the tropics and subtropics. Results are synthesized and analyzed with particular emphasis on: i) identification of the most relevant soil characteristics

Final work plan: Expedited Site Characterization of the IES Industries, Inc., Site at Marshalltown, Iowa. Ames Expedited Site Characterization Project, Version 1.0

Energy Technology Data Exchange (ETDEWEB)

1994-04-04

The overall goal of the Ames Laboratory Expedited Site Characterization (ESC) project is to evaluate and promote both innovative and state-of-the-practice site characterization and/or monitoring technologies. This will be accomplished by fielding both types of technologies together in the context of an expedited site characterization. The first site will be at a former manufactured gas plant (FMGP) in Marshalltown, Iowa. The project will field three areas of technology: geophysical, analytical, and data fusion. Geophysical technologies are designed to understand the subsurface geology to help predict fate and transport of the target contaminants. Analytical technologies/methods are designed to detect and quantify the target contaminants. Data fusion technology consists of software systems designed to rapidly integrate or fuse all site information into a conceptual site model that then becomes the decision making tool for the site team to plan subsequent sampling activity. Not all of the contaminants present can be located at the action level. Polynuclear aromatic hydrocarbons (PAHs) are the signature organics associated with the coal tar activities that took place at the site. As a result, PAHs were selected as the target compounds. Screening analytical instruments and nonintrusive geophysical techniques will be fielded to qualitatively map the spatial contaminant distribution. Soil gas surveys, immunoassay testing (IMA), innovative optical techniques, and passive organic sorbent sensors will be deployed along with the geophysical methods. Gas chromatography/mass spectrometry (GC/MS) instruments and a cone penetrometer system equipped with a laser-induced fluorescence (LIF) probe will quantitatively map the action level edges of the PAH plume(s). Samples will be taken both by the cone penetrometer test system (CPT) and the Geoprobe {reg_sign} sampler system.

Characterization of apparently balanced chromosomal rearrangements from the developmental genome anatomy project.

Science.gov (United States)

Higgins, Anne W; Alkuraya, Fowzan S; Bosco, Amy F; Brown, Kerry K; Bruns, Gail A P; Donovan, Diana J; Eisenman, Robert; Fan, Yanli; Farra, Chantal G; Ferguson, Heather L; Gusella, James F; Harris, David J; Herrick, Steven R; Kelly, Chantal; Kim, Hyung-Goo; Kishikawa, Shotaro; Korf, Bruce R; Kulkarni, Shashikant; Lally, Eric; Leach, Natalia T; Lemyre, Emma; Lewis, Janine; Ligon, Azra H; Lu, Weining; Maas, Richard L; MacDonald, Marcy E; Moore, Steven D P; Peters, Roxanna E; Quade, Bradley J; Quintero-Rivera, Fabiola; Saadi, Irfan; Shen, Yiping; Shendure, Jay; Williamson, Robin E; Morton, Cynthia C

2008-03-01

Apparently balanced chromosomal rearrangements in individuals with major congenital anomalies represent natural experiments of gene disruption and dysregulation. These individuals can be studied to identify novel genes critical in human development and to annotate further the function of known genes. Identification and characterization of these genes is the goal of the Developmental Genome Anatomy Project (DGAP). DGAP is a multidisciplinary effort that leverages the recent advances resulting from the Human Genome Project to increase our understanding of birth defects and the process of human development. Clinically significant phenotypes of individuals enrolled in DGAP are varied and, in most cases, involve multiple organ systems. Study of these individuals' chromosomal rearrangements has resulted in the mapping of 77 breakpoints from 40 chromosomal rearrangements by FISH with BACs and fosmids, array CGH, Southern-blot hybridization, MLPA, RT-PCR, and suppression PCR. Eighteen chromosomal breakpoints have been cloned and sequenced. Unsuspected genomic imbalances and cryptic rearrangements were detected, but less frequently than has been reported previously. Chromosomal rearrangements, both balanced and unbalanced, in individuals with multiple congenital anomalies continue to be a valuable resource for gene discovery and annotation.

Construction and characterization of the detection modules for the Muon Portal Project

Energy Technology Data Exchange (ETDEWEB)

Blancato, A.A.; Bonanno, D.L.; La Rocca, P.; Longhitano, F.; Lo Presti, D.; Parasole, O.; Pugliatti, C.; Riggi, F.; Russo, G.V.; Santagati, G. [Dipartimento di Fisica e Astronomia, Universita di Catania and INFN, Catania, (Italy); Bandieramonte, M.; Billotta, S.; Bonanno, G.; Garozzo, S.; Marano, D.; Riggi, S.; Romeo, G. [INAF, Osservatorio Astrofisico di Catania, (Italy); Fallica, P.G.; Romeo, M. [STMicroelectronics, Catania, (Italy)

2015-07-01

The Muon Portal Project is a joint initiative between research and industrial partners, aimed at the construction of a real size detector prototype (6 x 3 x 7 m{sup 3}) for the inspection of containers by the muon scattering technique, devised to search for hidden high-Z fissile materials and provide a full 3D tomography of the interior of the container in a scanning time of the order of minutes. The muon tracking detector is based on a set of 48 detection modules (size 1 m x 3 m), each built with 100 extruded scintillator strips, so as to provide four X-Y detection planes, two placed above and two below the container to be inspected. Two wavelength shifting (WLS) fibres embedded in each strip convey the emitted photons to Silicon Photomultipliers (SiPM) which act as photo-sensors. After a research and development phase, which led to the choice and test of the individual components, the construction of the full size detector has already started. The paper describes the results of the mass characterization of the photo-sensors and the construction and test measurements of the first detection modules of the Project. (authors)

Characterizing uncertain sea-level rise projections to support investment decisions

Science.gov (United States)

Lempert, Robert J.; Wikman-Svahn, Per; Keller, Klaus

2018-01-01

Many institutions worldwide are considering how to include uncertainty about future changes in sea-levels and storm surges into their investment decisions regarding large capital infrastructures. Here we examine how to characterize deeply uncertain climate change projections to support such decisions using Robust Decision Making analysis. We address questions regarding how to confront the potential for future changes in low probability but large impact flooding events due to changes in sea-levels and storm surges. Such extreme events can affect investments in infrastructure but have proved difficult to consider in such decisions because of the deep uncertainty surrounding them. This study utilizes Robust Decision Making methods to address two questions applied to investment decisions at the Port of Los Angeles: (1) Under what future conditions would a Port of Los Angeles decision to harden its facilities against extreme flood scenarios at the next upgrade pass a cost-benefit test, and (2) Do sea-level rise projections and other information suggest such conditions are sufficiently likely to justify such an investment? We also compare and contrast the Robust Decision Making methods with a full probabilistic analysis. These two analysis frameworks result in similar investment recommendations for different idealized future sea-level projections, but provide different information to decision makers and envision different types of engagement with stakeholders. In particular, the full probabilistic analysis begins by aggregating the best scientific information into a single set of joint probability distributions, while the Robust Decision Making analysis identifies scenarios where a decision to invest in near-term response to extreme sea-level rise passes a cost-benefit test, and then assembles scientific information of differing levels of confidence to help decision makers judge whether or not these scenarios are sufficiently likely to justify making such investments

Characterizing uncertain sea-level rise projections to support investment decisions.

Directory of Open Access Journals (Sweden)

Ryan L Sriver

Full Text Available Many institutions worldwide are considering how to include uncertainty about future changes in sea-levels and storm surges into their investment decisions regarding large capital infrastructures. Here we examine how to characterize deeply uncertain climate change projections to support such decisions using Robust Decision Making analysis. We address questions regarding how to confront the potential for future changes in low probability but large impact flooding events due to changes in sea-levels and storm surges. Such extreme events can affect investments in infrastructure but have proved difficult to consider in such decisions because of the deep uncertainty surrounding them. This study utilizes Robust Decision Making methods to address two questions applied to investment decisions at the Port of Los Angeles: (1 Under what future conditions would a Port of Los Angeles decision to harden its facilities against extreme flood scenarios at the next upgrade pass a cost-benefit test, and (2 Do sea-level rise projections and other information suggest such conditions are sufficiently likely to justify such an investment? We also compare and contrast the Robust Decision Making methods with a full probabilistic analysis. These two analysis frameworks result in similar investment recommendations for different idealized future sea-level projections, but provide different information to decision makers and envision different types of engagement with stakeholders. In particular, the full probabilistic analysis begins by aggregating the best scientific information into a single set of joint probability distributions, while the Robust Decision Making analysis identifies scenarios where a decision to invest in near-term response to extreme sea-level rise passes a cost-benefit test, and then assembles scientific information of differing levels of confidence to help decision makers judge whether or not these scenarios are sufficiently likely to justify making

An Aerial Radiological Survey of the Yucca Mountain Project Proposed Land Withdrawal and Adjacent Areas

International Nuclear Information System (INIS)

Craig Lyons, Thane Hendricks

2006-01-01

An aerial radiological survey of the Yucca Mountain Project (YMP) proposed land withdrawal was conducted from January to April 2006, and encompassed a total area of approximately 284 square miles (73,556 hectares). The aerial radiological survey was conducted to provide a sound technical basis and rigorous statistical approach for determining the potential presence of radiological contaminants in the Yucca Mountain proposed Land withdrawal area. The survey site included land areas currently managed by the Bureau of Land Management, the U.S. Air Force as part of the Nevada Test and Training Range or the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) as part of the Nevada Test Site (NTS). The survey was flown at an approximate ground speed of 70 knots (36 meters per second), at a nominal altitude of 150 ft (46 m) above ground level, along a set of parallel flight lines spaced 250 ft (76 m) apart. The flight lines were oriented in a north-south trajectory. The survey was conducted by the DOE NNSA/NSO Remote Sensing Laboratory-Nellis, which is located in Las Vegas, Nevada. The aerial survey was conducted at the request of the DOE Office of Civilian Radioactive Waste Management. The primary contaminant of concern was identified by YMP personnel as cesium-137 ( 137 Cs). Due to the proposed land withdrawal area's proximity to the historical Nuclear Rocket Development Station (NRDS) facilities located on the NTS, the aerial survey system required sufficient sensitivity to discriminate between dispersed but elevated 137 Cs levels from those normally encountered from worldwide fallout. As part of that process, the survey also measured and mapped the exposure-rate levels that currently existed within the survey area. The inferred aerial exposure rates of the natural terrestrial background radiation varied from less than 3 to 22 microroentgens per hour. This range of exposure rates was primarily due to the surface

Hydrogeological characterization on surface-based investigation phase in the Mizunami underground research laboratory project, in Japan

International Nuclear Information System (INIS)

Saegusa, Hiromitsu; Onoe, Hironori; Takeuchi, Shinji; Takeuchi, Ryuji; Ohyama, Takuya

2007-01-01

The Mizunami Underground Research Laboratory (MIU) project is being carried out by Japan Atomic Energy Agency in the Cretaceous Toki granite in the Tono area, central Japan. The MIU project is a purpose-built generic underground research laboratory project that is planned for a broad scientific study of the deep geological environment as a basis of research and development for geological disposal of nuclear wastes. One of the main goals of the MIU project is to establish comprehensive techniques for investigation, analysis, and assessment of the deep geological environment. The MIU project has three overlapping phases: Surface-based Investigation (Phase I), Construction (Phase II) and Operation (Phase III). Hydrogeological investigations using a stepwise process in Phase I have been carried out in order to obtain information on important properties such as, location of water conducting features, hydraulic conductivity and so on. Hydrogeological modeling and groundwater flow simulations in Phase I have been carried out in order to synthesize these investigation results, to evaluate the uncertainty of the hydrogeological model and to identify the main issues for further investigations. Using the stepwise hydrogeological characterization approach and combining the investigation with modeling and simulation, understanding of the hydrogeological environment has been progressively improved. (authors)

PERL - European research project on characterization of gaskets for bolted flange connections

International Nuclear Information System (INIS)

Kockelmann, H.; Hahn, R.

2004-01-01

Great progress was observed in the European standardization in the last years in the field of the design of floating type bolted flange connections. New design rules were developed (EN 1591) which include new definitions of gasket characteristics for the calculation of floating type flanged joints. In addition a new gasket testing standard was drafted (prEN 13555) which assures a comprehensive characterization of gaskets for bolted flanged joints. This draft standard contains some new features which were examined and validated within the European research project PERL (Pressure Equipment - Reduction of Leak Rate). The gasket testing strategy laid down in prEN 13555 is presented in this paper. Some testing results highlighten the measuring procedures and the evaluation of the gasket characteristics. (orig.)

Rock mass mechanical property estimations for the Yucca Mountain Site Characterization Project

International Nuclear Information System (INIS)

Lin, M.; Hardy, M.P.; Bauer, S.J.

1993-06-01

Rock mass mechanical properties are important in the design of drifts and ramps. These properties are used in evaluations of the impacts of thermomechanical loading of potential host rock within the Yucca Mountain Site Characterization Project. Representative intact rock and joint mechanical properties were selected for welded and nonwelded tuffs from the currently available data sources. Rock mass qualities were then estimated using both the Norwegian Geotechnical Institute (Q) and Geomechanics Rating (RMR) systems. Rock mass mechanical properties were developed based on estimates of rock mass quality, the current knowledge of intact properties, and fracture/joint characteristics. Empirical relationships developed to correlate the rock mass quality indices and the rock mass mechanical properties were then used to estimate the range of rock mass mechanical properties

Some Materials Degradation Issues in the U.S. High-Level Nuclear Waste Repository Study (The Yucca Mountain Project)

Energy Technology Data Exchange (ETDEWEB)

F. Hua; P. Pasupathi; N. Brown; K. Mon

2005-09-19

The safe disposal of radioactive waste requires that the waste be isolated from the environment until radioactive decay has reduced its toxicity to innocuous levels for plants, animals, and humans. All of the countries currently studying the options for disposing of high-level nuclear waste (HLW) have selected deep geologic formations to be the primary barrier for accomplishing this isolation. In U.S.A., the Nuclear Waste Policy Act of 1982 (as amended in 1987) designated Yucca Mountain in Nevada as the potential site to be characterized for high-level nuclear waste (HLW) disposal. Long-term containment of waste and subsequent slow release of radionuclides into the geosphere will rely on a system of natural and engineered barriers including a robust waste containment design. The waste package design consists of a highly corrosion resistant Ni-based Alloy 22 cylindrical barrier surrounding a Type 316 stainless steel inner structural vessel. The waste package is covered by a mailbox-shaped drip shield composed primarily of Ti Grade 7 with Ti Grade 24 structural support members. The U.S. Yucca Mountain Project has been studying and modeling the degradation issues of the relevant materials for some 20 years. This paper reviews the state-of-the-art understanding of the degradation processes based on the past 20 years studies on Yucca Mountain Project (YMP) materials degradation issues with focus on interaction between the in-drift environmental conditions and long-term materials degradation of waste packages and drip shields within the repository system during the 10,000 years regulatory period. This paper provides an overview of the current understanding of the likely degradation behavior of the waste package and drip shield in the repository after the permanent closure of the facility. The degradation scenario discussed in this paper include aging and phase instability, dry oxidation, general and localized corrosion, stress corrosion cracking and hydrogen induced

Some Materials Degradation Issues in the U.S. High-Level Nuclear Waste Repository Study (The Yucca Mountain Project)

International Nuclear Information System (INIS)

Hua, F.; Pasupathi, P.; Brown, N.; Mon, K.

2005-01-01

The safe disposal of radioactive waste requires that the waste be isolated from the environment until radioactive decay has reduced its toxicity to innocuous levels for plants, animals, and humans. All of the countries currently studying the options for disposing of high-level nuclear waste (HLW) have selected deep geologic formations to be the primary barrier for accomplishing this isolation. In U.S.A., the Nuclear Waste Policy Act of 1982 (as amended in 1987) designated Yucca Mountain in Nevada as the potential site to be characterized for high-level nuclear waste (HLW) disposal. Long-term containment of waste and subsequent slow release of radionuclides into the geosphere will rely on a system of natural and engineered barriers including a robust waste containment design. The waste package design consists of a highly corrosion resistant Ni-based Alloy 22 cylindrical barrier surrounding a Type 316 stainless steel inner structural vessel. The waste package is covered by a mailbox-shaped drip shield composed primarily of Ti Grade 7 with Ti Grade 24 structural support members. The U.S. Yucca Mountain Project has been studying and modeling the degradation issues of the relevant materials for some 20 years. This paper reviews the state-of-the-art understanding of the degradation processes based on the past 20 years studies on Yucca Mountain Project (YMP) materials degradation issues with focus on interaction between the in-drift environmental conditions and long-term materials degradation of waste packages and drip shields within the repository system during the 10,000 years regulatory period. This paper provides an overview of the current understanding of the likely degradation behavior of the waste package and drip shield in the repository after the permanent closure of the facility. The degradation scenario discussed in this paper include aging and phase instability, dry oxidation, general and localized corrosion, stress corrosion cracking and hydrogen induced

Development and characterization of semiconductor materials by ion beams. Final report of a co-ordinated research project

International Nuclear Information System (INIS)

2002-06-01

This CRP was recommended by the Consultants meeting on Ion Beam Techniques Applied to Semiconductor and Related Advanced Materials, held in April 1997 in Vienna. The consultants proposed to have a CRP in the field of application of MeV ion beams for the development and characterization of semiconductor materials. The CRP was approved and a first RCM was held in Vienna between 2-5 June 1998, in order to stimulate ideas and to promote collaborations among CRP participants. The goals and practical outcomes of the CRP were defined and several specific topics were identified including: optoelectronic characterization of semiconductor materials and devices by ion microbeams, characterization of thin films, defect transformations in semiconductors, light element analysis. One important recommendation was that sample exchanges among different laboratories be strongly encouraged. The participants presented individual activities on their projects, all subjects of research were identified and linked with approved individual projects. Collaboration among the participants was discussed and established. Some modifications to work plans were adopted. As proposed during the first RCM, the final RCM was held at the Ruder Boskovic Institute, Zagreb, Croatia, between 25 and 29 September 2000, with the purpose of reviewing/discussing the results achieved during the course of the CRP and to prepare a draft of the final report and associated publication. This document contains summary of the CRP and ten individual reports presented by participants. Each of the reports has been indexed separately

Vadose zone characterization project at the Hanford Tank Farms: U Tank Farm Report

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-05-01

The U.S. Department of Energy Grand Junction Office (DOE-GJO) was tasked by the DOE Richland Operations Office (DOE-RL) to perform a baseline characterization of the gamma-ray-emitting radionuclides that are distributed in the vadose zone sediments beneath and around the single-shell tanks (SSTs) at the Hanford Site. The intent of this characterization is to determine the nature and extent of the contamination, to identify contamination sources when possible, and to develop a baseline of the contamination distribution that will permit future data comparisons. This characterization work also allows an initial assessment of the impacts of the vadose zone contamination as required by the Resource Conservation and Recovery Act (RCRA). This characterization project involves acquiring information regarding vadose zone contamination with borehole geophysical logging methods and documenting that information in a series of reports. This information is presently limited to detection of gamma-emitting radionuclides from both natural and man-made sources. Data from boreholes surrounding each tank are compiled into individual Tank Summary Data Reports. The data from each tank in a tank farm are then compiled and summarized in a Tank Farm Report. This document is the Tank Farm Report for the U Tank Farm. Logging operations used high-purity germanium detection systems to acquire laboratory-quality assays of the gamma-emitting radionuclides in the sediments around and below the tanks. These assays were acquired in 59 boreholes that surround the U Tank Farm tanks. Logging of all boreholes was completed in December 1995, and the last Tank Summary Data Report for the U Tank Farm was issued in September 1996.

Geotechnical characterization of the North Ramp of the Exploratory Studies Facility: Yucca Mountain Site Characterization Project. Volume 2, NRG corehole data appendices

International Nuclear Information System (INIS)

Brechtel, C.E.; Lin, Ming; Martin, E.; Kessel, D.S.

1995-05-01

This report presents the results of the geological and geotechnical characterization of the Miocene volcanic tuff rocks of the Timber Mountain and Paintbrush groups that the tunnel boring machine will encounter during excavations of the Exploratory Studies Facility (ESF) North Ramp. The information in this report was developed to support the design of the ESF North Ramp. The ESF is being constructed by the DOE as part of the Yucca Mountain Project site characterization activities. The purpose of these activities is to evaluate the potential to locate the national high-level nuclear waste repository on land within and adjacent to the Nevada Test Site (NTS), Nye County, Nevada. This report was prepared as part of the Soil and Rock Properties Studies in accordance with the 8.3.1.14.2 Study Plan to Provide Soil and Rock Properties. This is volume 2 which contains NRG Corehole Data for each of the NRG Holes

Geotechnical characterization of the North Ramp of the Exploratory Studies Facility: Yucca Mountain Site Characterization Project. Volume 2, NRG corehole data appendices

Energy Technology Data Exchange (ETDEWEB)

Brechtel, C.E.; Lin, Ming; Martin, E. [Agapito Associates, Inc., Grand Junction, CO (United States); Kessel, D.S. [Sandia National Labs., Albuquerque, NM (United States)

1995-05-01

This report presents the results of the geological and geotechnical characterization of the Miocene volcanic tuff rocks of the Timber Mountain and Paintbrush groups that the tunnel boring machine will encounter during excavations of the Exploratory Studies Facility (ESF) North Ramp. The information in this report was developed to support the design of the ESF North Ramp. The ESF is being constructed by the DOE as part of the Yucca Mountain Project site characterization activities. The purpose of these activities is to evaluate the potential to locate the national high-level nuclear waste repository on land within and adjacent to the Nevada Test Site (NTS), Nye County, Nevada. This report was prepared as part of the Soil and Rock Properties Studies in accordance with the 8.3.1.14.2 Study Plan to Provide Soil and Rock Properties. This is volume 2 which contains NRG Corehole Data for each of the NRG Holes.

Memorandum of understanding for the TWRS characterization retrieval project

International Nuclear Information System (INIS)

JO, J.

1999-01-01

During fiscal year 1999, various programs and projects will require analyses from the 222-S Laboratory. In order to prioritize and successfully meet the analytical demands of all the customers, multiple organizations across the Tank Waste Remediation System (TWRS) must work together. One of the projects that will require analyses from the 222-S Laboratory is the retrieval project. Successful completion of retrieval project objectives requires cooperation among four TWRS organizations. The requirements and expectations regarding retrieval project analytical work were examined in order to define roles and responsibilities for each of these TWRS organizations. This memorandum of understanding (MOU) documents the results of this review and establishes the roles and responsibilities. This MOU is subdivided into three sections, the first of which is this introduction. Section 2 provides a summary of the overall roles and responsibilities with respect to retrieval project analytical work for the four TWRS organizations involved. The final section describes the individual interfaces involved in performing retrieval project analytical work, and discusses the roles and responsibilities with respect to each individual interface

Characterization of soil droughts in France and climate change. The ClimSec project: results and applications

International Nuclear Information System (INIS)

Soubeyroux, Jean-Michel; Blanchard, Michele; Dandin, Philippe; Kitova, Nadia; Martin, Eric; Vidal, Jean-Philippe

2012-01-01

The ClimSec project has studied the impact of climate change on drought and soil water over France by using a climatological reanalysis of the SAFRAN/ISBA/MODCOU suite (SIM) since 1958. Standardized drought indices for precipitation (SPI) and soil moisture (SSWI) have been defined for research purposes to characterize the various kinds of events. They were then adapted for operational hydrological monitoring and used to assess the exceptional drought of spring 2011. These indices were also calculated for future climate from the various regionalized climate projections available over France. Three particular experiments in socio-economic scenarios, climate models and down-scaling methods have been run to estimate the relative importance of the different uncertainties in drought evolution. The assessment of 21. century drought evolution shows a much earlier and more intense occurrence of changes for agricultural droughts linked to soil moisture deficits than for meteorological drought linked with precipitation deficits. Climate projections suggest that France could be affected on the second half of the 21. century by a quasi-continuous drought with a strong intensity, totally unknown in present climate. (authors)

NV/YMP RADIOLOGICAL CONTROL MANUAL

Energy Technology Data Exchange (ETDEWEB)

U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE; BECHTEL NEVADA

2004-11-01

This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) and the Yucca Mountain Office of Repository Development (YMORD). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations Part 835 (10 CFR 835), Occupational Radiation Protection. Programs covered by this manual are located at the Nevada Test Site (NTS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Pleasanton, California; and at Andrews Air Force Base, Maryland. In addition, field work by NNSA/NSO at other locations is also covered by this manual.

NV/YMP RADIOLOGICAL CONTROL MANUAL

International Nuclear Information System (INIS)

2004-01-01

This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) and the Yucca Mountain Office of Repository Development (YMORD). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations Part 835 (10 CFR 835), Occupational Radiation Protection. Programs covered by this manual are located at the Nevada Test Site (NTS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Pleasanton, California; and at Andrews Air Force Base, Maryland. In addition, field work by NNSA/NSO at other locations is also covered by this manual

Vandose Zone Characterization Project at the Hanford Tank Farms: SX Tank Farm Report

International Nuclear Information System (INIS)

Brodeur, J.R.; Koizumi, C.J.; Bertsch, J.F.

1996-09-01

The SX Tank Farm is located in the southwest portion of the 200 West Area of the Hanford Site. This tank farm consists of 15 single-shell tanks (SSTs), each with an individual capacity of 1 million gallons (gal). These tanks currently store high-level nuclear waste that was primarily generated from what was called the oxidation-reduction or open-quotes REDOXclose quotes process at the S-Plant facility. Ten of the 15 tanks are listed in Hanlon as open-quotes assumed leakersclose quotes and are known to have leaked various amounts of high-level radioactive liquid to the vadose zone sediment. The current liquid content of each tank varies, but the liquid from known leaking tanks has been removed to the extent possible. In 1994, the U.S. Department of Energy Richland Office (DOE-RL) requested the DOE Grand Junction Projects Office (GJPO), Grand Junction, Colorado, to perform a baseline characterization of contamination in the vadose zone at all the SST farms with spectral gamma-ray logging of boreholes surrounding the tanks. The SX Tank Farm geophysical logging was completed, and the results of this baseline characterization are presented in this report

Project Management Techniques

OpenAIRE

Mihalache Anita; Salagean Liana

2010-01-01

Project management is a technique that can aid in the planning, scheduling, and monitoring of complex projects characterized by numerous, non repetitive jobs called activities. Examples of projects that would use project management include: - developing a mass rapid – transit system for a metropolitan area; - organizing the relocation of a corporate headquarters; - planning the production of a concert, film, or play; - developing and marketing a new automobile; - constructing a high – rise of...

Prediction of Pseudo relative velocity response spectra at Yucca Mountain for underground nuclear explosions conducted in the Pahute Mesa testing area at the Nevada testing site

International Nuclear Information System (INIS)

Phillips, J.S.

1991-12-01

The Yucca Mountain Site Characterization Project (YMP), managed by the Office of Geologic Disposal of the Office of Civilian Radioactive Waste Management of the US Department of Energy, is examining the feasibility of siting a repository for commercial, high-level nuclear wastes at Yucca Mountain on and adjacent to the Nevada Test Site (NTS). This work, intended to extend our understanding of the ground motion at Yucca Mountain resulting from testing of nuclear weapons on the NTS, was funded by the Yucca Mountain project and the Military Applications Weapons Test Program. This report summarizes one aspect of the weapons test seismic investigations conducted in FY88. Pseudo relative velocity response spectra (PSRV) have been calculated for a large body of surface ground motions generated by underground nuclear explosions. These spectra have been analyzed and fit using multiple linear regression techniques to develop a credible prediction technique for surface PSRVs. In addition, a technique for estimating downhole PSRVs at specific stations is included. A data summary, data analysis, prediction development, prediction evaluation, software summary and FORTRAN listing of the prediction technique are included in this report

The STRIPA project. Annual report 1986

International Nuclear Information System (INIS)

1987-08-01

A summary of the Stripa Project phase 2 is given. The detailed informations describe crosshole techniques for the detection and characterization of fracture zones, the hydrological characterization of the Stripa site Part II, a three-dimensional migration experiment, borehole, shaft and tunnel sealing, the hydrogeochemical characterization of the Stripa groundwater and question of economy. A decision was taken in principale for an extension of the project into a third phase. (DG)

Experiences From NASA/Langley's DMSS Project

Science.gov (United States)

1996-01-01

There is a trend in institutions with high performance computing and data management requirements to explore mass storage systems with peripherals directly attached to a high speed network. The Distributed Mass Storage System (DMSS) Project at the NASA Langley Research Center (LaRC) has placed such a system into production use. This paper will present the experiences, both good and bad, we have had with this system since putting it into production usage. The system is comprised of: 1) National Storage Laboratory (NSL)/UniTree 2.1, 2) IBM 9570 HIPPI attached disk arrays (both RAID 3 and RAID 5), 3) IBM RS6000 server, 4) HIPPI/IPI3 third party transfers between the disk array systems and the supercomputer clients, a CRAY Y-MP and a CRAY 2, 5) a "warm spare" file server, 6) transition software to convert from CRAY's Data Migration Facility (DMF) based system to DMSS, 7) an NSC PS32 HIPPI switch, and 8) a STK 4490 robotic library accessed from the IBM RS6000 block mux interface. This paper will cover: the performance of the DMSS in the following areas: file transfer rates, migration and recall, and file manipulation (listing, deleting, etc.); the appropriateness of a workstation class of file server for NSL/UniTree with LaRC's present storage requirements in mind the role of the third party transfers between the supercomputers and the DMSS disk array systems in DMSS; a detailed comparison (both in performance and functionality) between the DMF and DMSS systems LaRC's enhancements to the NSL/UniTree system administration environment the mechanism for DMSS to provide file server redundancy the statistics on the availability of DMSS the design and experiences with the locally developed transparent transition software which allowed us to make over 1.5 million DMF files available to NSL/UniTree with minimal system outage

Project, construction and characterization of ionization chambers for use as standard systems in X and gamma radiation beams

International Nuclear Information System (INIS)

Perini, Ana Paula

2013-01-01

Ionization chambers present some advantages in relation to other dosimeters: easiness of handling, low energy dependence and high precision. The advantages associated to ionization chambers and the large number of diagnostic radiology exams and therapeutic treatments motivated the development of this PhD program. In this project ionization chambers were developed and characterized to be applied in diagnostic radiology and therapy beam dosimetry, with high precision and performance, in compliance with international recommendations. They were assembled in a simple way, utilizing low-cost national materials, so they can be reproduced and applied at calibration laboratories. The project of these ionization chambers presents some differences in relation to commercial ionization chambers, as the materials utilized and geometrical arrangements. Besides the development of the ionization chambers to be utilized in standard X-ray beam dosimetry as work standard systems, two graphite parallel-plate ionization chambers were developed and characterized to be applied as reference standard systems for determining the air kerma rates of gamma radiation sources. Comparing the air kerma rates determined with the reference standard of the Calibration Laboratory of IPEN, a Farmer ionization chamber, with the values of the air kerma rates obtained with the graphite ionization chambers, the maximum differences obtained were only 1.7% and 1.2% for the G1 and G2 graphite ionization chambers, respectively. Moreover, these ionization chambers presented correction factors close to 1.000, which is ideal for an ionization chamber be characterized as a reference standard system. (author)

YUCCA MOUNTAIN SITE CHARACTERIZATIONS PROJECT TUNNEL BORING MACHINE (TBM) SYSTEM SAFETY ANALYSIS

International Nuclear Information System (INIS)

1997-01-01

The purpose of this analysis is to systematically identify and evaluate hazards related to the tunnel boring machine (TBM) used in the Exploratory Studies Facility (ESF) at the Yucca Mountain Site Characterization Project. This process is an integral part of the systems engineering process; whereby safety is considered during planning, design, testing, and construction. Since the TBM is an ''as built'' system, the MandO is conducting the System Safety Analysis during the construction or assembly phase of the TBM. A largely qualitative approach was used since a radiological System Safety Analysis is not required. The risk assessment in this analysis characterizes the accident scenarios associated with the TBM in terms of relative risk and includes recommendations for mitigating all identified risks. The priority for recommending and implementing mitigation control features is: (1) Incorporate measures to reduce risks and hazards into the system/subsystem/component design, (2) add safety features and capabilities to existing designs, and (3) develop procedures and conduct training to increase worker awareness of potential hazards, on methods to reduce exposure to hazards, and on the actions required to avoid accidents or correct hazardous conditions. The scope of this analysis is limited to the TBM during normal operations, excluding hazards occurring during assembly and test of the TBM or maintenance of the TBM equipment

YUCCA MOUNTAIN SITE CHARACTERIZATIONS PROJECT TUNNEL BORING MACHINE (TBM) SYSTEM SAFETY ANALYSIS

Energy Technology Data Exchange (ETDEWEB)

N/A

1997-02-19

The purpose of this analysis is to systematically identify and evaluate hazards related to the tunnel boring machine (TBM) used in the Exploratory Studies Facility (ESF) at the Yucca Mountain Site Characterization Project. This process is an integral part of the systems engineering process; whereby safety is considered during planning, design, testing, and construction. Since the TBM is an ''as built'' system, the M&O is conducting the System Safety Analysis during the construction or assembly phase of the TBM. A largely qualitative approach was used since a radiological System Safety Analysis is not required. The risk assessment in this analysis characterizes the accident scenarios associated with the TBM in terms of relative risk and includes recommendations for mitigating all identified risks. The priority for recommending and implementing mitigation control features is: (1) Incorporate measures to reduce risks and hazards into the system/subsystem/component design, (2) add safety features and capabilities to existing designs, and (3) develop procedures and conduct training to increase worker awareness of potential hazards, on methods to reduce exposure to hazards, and on the actions required to avoid accidents or correct hazardous conditions. The scope of this analysis is limited to the TBM during normal operations, excluding hazards occurring during assembly and test of the TBM or maintenance of the TBM equipment.

Software quality assurance documentation for the release of NUFT 2.0 for HP platforms

International Nuclear Information System (INIS)

Fernandez, M.W.; Preckshot, G.G.; Johnson, G.L.

1998-01-01

This document is the Individual Software Plan (ISP) for version 2.0 of the Non-isothermal Unsaturated-saturated Flow and Transport (NUFT.) analysis computer program. This document addresses the applicable requirements of LLNL YMP procedure 033-YMP-QP 3.2, Section 4.2.1.1. The purpose of this ISP is to plan and organize the activities required to certify the NUFT code for quality affecting work involving problems that include cross drift analysis of the Yucca Mountain Repository facility. NUFT is software for application to the solution of a class of coupled mass and heat transport problems in porous geologic media including Yucca Mountain Repository Cross Drift Problem (YMRCDP- also known as the Enhanced Characterization of the Repository Block (ECRB)). Solution of this class of problems requires a suite of multiphase, multi-component models for numerical solution of non- isothermal flow and transport in porous media with applications to subsurface contaminant transport problems. NUFT is a suite of multiphase, multi-component models for numerical solution of non- isothermal flow and transport in porous media, with application to subsurface contaminant transport problems, and in particular, to the hydrology in and about the Yucca Mountain Repository Site. NUFI is acquired software, as defined by 033-YMP-QP 3.2, and a preliminary baseline of source code, electronic documentation, and paper documentation has been established as required by 033-YMP-QP 3.2, Section 4.1. NUFT runs on Sun Unix platforms, Solaris operating system version 5.5 and HP-UX with operating system version 10.20. The product to be qualified under this ISP is the version running on HP- UX. The HP version will be labeled Version 2.0h. The h is included to distinguish the HP version from possible future versions qualified for Sun or other platforms. The scope of the plans and procedures outlined in this ISP is limited to the effort required to qualify NUFT for the class of problems identified in

Conditions, factors and criteria for successful project implementation: generalization of experience of project management

Directory of Open Access Journals (Sweden)

Feraru Galina Sergeevna

2014-11-01

Full Text Available The article addresses issues characterizing features of project management contributing to their competitive advantage; shows the factors and criteria of success of projects and the main reasons for their failures, making the failed efforts of developers to create projects.

Closure development for high-level nuclear waste containers for the tuff repository

International Nuclear Information System (INIS)

Robitz, E.S. Jr.; McAninch, M.D. Jr.; Edmonds, D.P.; Babcock and Wilcox Co., Alliance, OH

1990-09-01

This report summarizes Phase 1 activities for closure development of the high-level nuclear waste package task for the tuff repository. Work was conducted under U.S. Department of Energy (DOE) Contract 9172105, administered through the Lawrence Livermore National Laboratory (LLNL), as part of the Yucca Mountain Project (YMP), funded through the DOE Office of Civilian Radioactive Waste Management (OCRWM). The goal of this phase was to select five closure processes for further evaluation in later phases of the program. A decision tree methodology was utilized to perform an objective evaluation of 15 potential closure processes. Information was gathered via a literature survey, industrial contacts, and discussions with project team members, other experts in the field, and the LLNL waste package task staff. The five processes selected were friction welding, electron beam welding, laser beam welding, gas tungsten arc welding, and plasma arc welding. These are felt to represent the best combination of weldment material properties and process performance in a remote, radioactive environment. Conceptual designs have been generated for these processes to illustrate how they would be implemented in practice. Homopolar resistance welding was included in the Phase 1 analysis, and developments in this process will be monitored via literature in Phases 2 and 3. Work was conducted in accordance with the YMP Quality Assurance Program. 223 refs., 20 figs., 9 tabs

Closure development for high-level nuclear waste containers for the tuff repository; Phase 1, Final report

Energy Technology Data Exchange (ETDEWEB)

Robitz, E.S. Jr.; McAninch, M.D. Jr.; Edmonds, D.P. [Babcock and Wilcox Co., Lynchburg, VA (USA). Nuclear Power Div.]|[Babcock and Wilcox Co., Alliance, OH (USA). Research and Development Div.

1990-09-01

This report summarizes Phase 1 activities for closure development of the high-level nuclear waste package task for the tuff repository. Work was conducted under U.S. Department of Energy (DOE) Contract 9172105, administered through the Lawrence Livermore National Laboratory (LLNL), as part of the Yucca Mountain Project (YMP), funded through the DOE Office of Civilian Radioactive Waste Management (OCRWM). The goal of this phase was to select five closure processes for further evaluation in later phases of the program. A decision tree methodology was utilized to perform an objective evaluation of 15 potential closure processes. Information was gathered via a literature survey, industrial contacts, and discussions with project team members, other experts in the field, and the LLNL waste package task staff. The five processes selected were friction welding, electron beam welding, laser beam welding, gas tungsten arc welding, and plasma arc welding. These are felt to represent the best combination of weldment material properties and process performance in a remote, radioactive environment. Conceptual designs have been generated for these processes to illustrate how they would be implemented in practice. Homopolar resistance welding was included in the Phase 1 analysis, and developments in this process will be monitored via literature in Phases 2 and 3. Work was conducted in accordance with the YMP Quality Assurance Program. 223 refs., 20 figs., 9 tabs.

Final report on the Background Soil Characterization Project at the Oak Ridge Reservation, Oak Ridge, Tennessee. Volume 1: Results of Field Sampling Program

Energy Technology Data Exchange (ETDEWEB)

Watkins, D.R.; Ammons, J.T.; Branson, J.L. [and others

1993-10-01

This report presents, evaluates, and documents data and results obtained in the Background Soil Characterization Project (BSCP). It is intended to be a stand-alone document for application and use in structuring and conducting remedial investigation and remedial action projects in the Environmental Restoration (ER) Program. The objectives of the BSCP consist of the following: determine background concentrations of organics, metals, and radionuclides in natural soils that are key to environmental restoration projects; provide remediation projects with 100% validated data on background concentrations, which are technically and legally defensible; and quantify baseline risks from background constituents for comparison of risks associated with contaminated sites.

Characterization of the radon source in North-Central Florida. Final report part 1 -- Final project report; Final report part 2 -- Technical report

International Nuclear Information System (INIS)

1997-01-01

This report contains two separate parts: Characterization of the Radon Source in North-Central Florida (final report part 1 -- final project report); and Characterization of the Radon Source in North-Central Florida (technical report). The objectives were to characterize the radon 222 source in a region having a demonstrated elevated indoor radon potential and having geology, lithology, and climate that are different from those in other regions of the U.S. where radon is being studied. Radon availability and transport in this region were described. Approaches for predicting the radon potential of lands in this region were developed

Bibliography of publications related to the Yucca Mountain Site Characterization Project prepared by U.S. Geological Survey personnel through April 1991

International Nuclear Information System (INIS)

Glanzman, V.M.

1991-01-01

Personnel of the US Geological Survey have participated in nuclear-waste management studies in the State of Nevada since the mid-1970's. A bibliography of publications prepared principally for the US Department of Energy Yucca Mountain Site Characterization Project (formerly Nevada Nuclear Waste Storage Investigations) through April 1991 contains 475 entries in alphabetical order. The listing includes publications prepared prior to the inception of the Nevada Nuclear Waste Storage Investigations Project in April 1977 and selected publications of interest to the Yucca Mountain region. 480 refs

Annual report on the Background Soil Characterization Project on the Oak Ridge Reservation, Oak Ridge, Tennessee: Results of Phase 1 investigation

International Nuclear Information System (INIS)

Watkins, D.R.; Goddard, P.L.; Hatmaker, T.L.; Hook, L.A.; Jackson, B.L.; Kimbrough, C.W.; Lee, S.Y.; Lietzke, D.A.; McGin, C.W.; Nourse, B.D.; Schmoyer, R.L.; Shaw, R.A.; Stinnette, S.E.; Switek, J.; Wright, J.C.; Ammons, J.T.; Branson, J.L.; Burgoa, B.B.

1993-05-01

Many constituents of potential concern for human health occur naturally at low concentrations in undisturbed soils. The Background soil Characterization Project (BSCP) was undertaken to provide background concentration data on potential contaminants in natural soils on the Oak Ridge Reservation (ORR). The objectives of the BSCP are to provide baseline data for contaminated site assessment and estimates of potential human health risk associated with background concentrations of hazardous and other constituents in native soils. This report presents, evaluates, and documents data and results obtained in Phase I of the project. It is intended to be a stand-alone document for application and use in structuring and conducting remedial investigation and remedial action projects in the Environmental Restoration (ER) Program

Annual report on the Background Soil Characterization Project on the Oak Ridge Reservation, Oak Ridge, Tennessee: Results of Phase 1 investigation

Energy Technology Data Exchange (ETDEWEB)

Watkins, D.R.; Goddard, P.L.; Hatmaker, T.L.; Hook, L.A.; Jackson, B.L.; Kimbrough, C.W.; Lee, S.Y.; Lietzke, D.A.; McGin, C.W.; Nourse, B.D.; Schmoyer, R.L.; Shaw, R.A.; Stinnette, S.E.; Switek, J.; Wright, J.C. [Oak Ridge National Lab., TN (United States); Ammons, J.T.; Branson, J.L.; Burgoa, B.B. [Tennessee Univ., Knoxville, TN (United States). Dept. of Plant and Soil Science; Lietzke, D.A. [Lietzke (David A.), Rutledge, TN (United States)

1993-05-01

Many constituents of potential concern for human health occur naturally at low concentrations in undisturbed soils. The Background soil Characterization Project (BSCP) was undertaken to provide background concentration data on potential contaminants in natural soils on the Oak Ridge Reservation (ORR). The objectives of the BSCP are to provide baseline data for contaminated site assessment and estimates of potential human health risk associated with background concentrations of hazardous and other constituents in native soils. This report presents, evaluates, and documents data and results obtained in Phase I of the project. It is intended to be a stand-alone document for application and use in structuring and conducting remedial investigation and remedial action projects in the Environmental Restoration (ER) Program.

Characterization of ceramics and semiconductors using nuclear techniques. Final report of a co-ordinated research project

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

With the aim of promoting research and facilitating more extensive application of nuclear techniques for material development, the IAEA established in 1994 a Co-ordinated Research Project (CRP) on Characterization of Ceramics and Semiconductors using Nuclear Techniques. This publication reviews and summarizes recent developments in this field and includes an assessment of the current status and trends in nuclear techniques in characterization of inorganic materials of technological importance. The TECDOC presents new achievements on ceramic superconductor behaviour under neutron induced defects, optimization of structure of mineral gels,m low temperature preparation of fine particles of ferrites, crystal luminescence of ceramic composites with improved plastic properties, thin film defects and detoxification of asbestos. The investigation of chemical composition, phase transitions and magnetic properties of ferrites by Moessbauer spectroscopy is largely developed. The document includes 18 individual contributions, each of them has been indexed and provided with an abstract Refs, figs, tabs

Characterization of ceramics and semiconductors using nuclear techniques. Final report of a co-ordinated research project

International Nuclear Information System (INIS)

1999-03-01

With the aim of promoting research and facilitating more extensive application of nuclear techniques for material development, the IAEA established in 1994 a Co-ordinated Research Project (CRP) on Characterization of Ceramics and Semiconductors using Nuclear Techniques. This publication reviews and summarizes recent developments in this field and includes an assessment of the current status and trends in nuclear techniques in characterization of inorganic materials of technological importance. The TECDOC presents new achievements on ceramic superconductor behaviour under neutron induced defects, optimization of structure of mineral gels,m low temperature preparation of fine particles of ferrites, crystal luminescence of ceramic composites with improved plastic properties, thin film defects and detoxification of asbestos. The investigation of chemical composition, phase transitions and magnetic properties of ferrites by Moessbauer spectroscopy is largely developed. The document includes 18 individual contributions, each of them has been indexed and provided with an abstract

Feature, event, and process screening and scenario development for the yucca mountain total system performance assessment

International Nuclear Information System (INIS)

Swift, P.; Barr, G.; Barnard, R.; Rechard, R.; Schenker, A.; Freeze, G.; Burck, P.

2001-01-01

Scenario development has two primary purposes in the design and documentation of postclosure performance assessments in a regulatory setting. First, scenario development ensures a sufficiently comprehensive consideration of the possible future states of the system. Second, scenario development identifies the important scenarios that must be considered in quantitative analyses of the total system performance assessment (TSPA). To ensure clear documentation of the treatment of potentially relevant future states of the system in the Yucca Mountain license application (LA), the US Department of Energy (DOE) has chosen to adopt a scenario development process based on the methodology developed by Cranwell et al. (1990) for the US Nuclear Regulatory Commission (NRC). Although the process, described below, has been modified somewhat as a result of experience gained in the last decade, the underlying methodology is consistent with that outlined by the DOE in the 1988 Site Characterization Plan for the Yucca Mountain Project (YMP) (U.S. DOE, 1988). The approach is fundamentally the same as that used in many performance assessments, including the most recent analysis of the Yucca Mountain repository by the NRC (Wescott et al., 1995). The approach has also been used by the DOE for the Waste Isolation Pilot Plant (WIPP) (U.S. DOE, 1996), by the Nuclear Energy Agency (NEA) of the Organisation for Economic Co-Operation and Development (OECD), and by other radioactive waste programs internationally. Section 2.0 of this report describes the scenario development process. Steps in the process are described in Section 2.1, and terms introduced in this section are defined in Section 2.2. The electronic database used to document the process is described in Section 3, and Section 4 provides a summary of the current status of the YMP scenario development work. Section 5 contains acknowledgments, and Section 6 contains a list of the references cited. (authors)

Second progress report on pre-test calculations for the large block test

International Nuclear Information System (INIS)

Lee, K.H.

1995-01-01

The US Department of Energy's (DOE) Yucca Mountain Site Characterization Project (YMP) is investigating the suitability of the Topopah Spring tuff in the thick vadose zone at Yucca Mountain, Nevada, as a host rock for permanent disposal of high-level radioactive waste. As part of the YMP, a group of field tests, called the Large Block Test (LBT), will be conducted on a large electrically heated block of Topopah Spring tuff. The block will be heated by electrical heaters. The goals of the LBT are to gain information on the coupled thermal-mechanical-hydrological-chemical processes that will be active in the near-field environment of a repository; to provide field data for testing and calibrating models; and to help in the development of measurement systems and techniques. In this second progress report, we present results of the final set of numerical modeling calculations performed in support of the LBT design. The results include block temperatures and heat fluxes across the surfaces. The results are applied primarily to the design of guard heaters to enforce adiabatic conditions along the block walls. Conduction-only runs are adequate to estimate the thermal behavior of the system, because earlier calculations showed that heat transfer in the block is expected to be dominated by conduction. In addition, conduction-only runs can be made at substantially shorter execution times than full hydrothermal runs. We also run a two-dimensional, hydrothermal, discrete fracture model, with 200-μm vertical fractures parallel to the heaters and occurring at a uniform spacing of 30 cm. The results show the development of distinct dryout and recondensation zones. The dryout zones are thickest at the fractures and thinnest in the matrix midway between the fractures

Hot-Gas Filter Ash Characterization Project

Energy Technology Data Exchange (ETDEWEB)

Swanson, M.L.; Hurley, J.P.; Dockter, B.A.; O`Keefe, C.A.

1997-07-01

Large-scale hot-gas filter testing over the past 10 years has revealed numerous cases of cake buildup on filter elements that has been difficult, if not impossible, to remove. At times, the cake can blind or bridge between candle filters, leading to filter failure. Physical factors, including particle-size distribution, particle shape, the aerodynamics of deposition, and system temperature, contribute to the difficulty in removing the cake, but chemical factors such as surface composition and gas-solid reactions also play roles in helping to bond the ash to the filters or to itself. This project is designed to perform the research necessary to determine the fuel-, sorbent-, and operations-related conditions that lead to blinding or bridging of hot-gas particle filters. The objectives of the project are threefold: (1) Determine the mechanisms by which a difficult-to-clean ash is formed and how it bridges hot-gas filters (2) Develop a method to determine the rate of bridging based on analyses of the feed coal and sorbent, filter properties, and system operating conditions and (3) Suggest and test ways to prevent filter bridging.

Characterizing opto-electret based paper speakers by using a real-time projection Moiré metrology system

Science.gov (United States)

Chang, Ya-Ling; Hsu, Kuan-Yu; Lee, Chih-Kung

2016-03-01

Advancement of distributed piezo-electret sensors and actuators facilitates various smart systems development, which include paper speakers, opto-piezo/electret bio-chips, etc. The array-based loudspeaker system possess several advantages over conventional coil speakers, such as light-weightness, flexibility, low power consumption, directivity, etc. With the understanding that the performance of the large-area piezo-electret loudspeakers or even the microfluidic biochip transport behavior could be tailored by changing their dynamic behaviors, a full-field real-time high-resolution non-contact metrology system was developed. In this paper, influence of the resonance modes and the transient vibrations of an arraybased loudspeaker system on the acoustic effect were measured by using a real-time projection moiré metrology system and microphones. To make the paper speaker even more versatile, we combine the photosensitive material TiOPc into the original electret loudspeaker. The vibration of this newly developed opto-electret loudspeaker could be manipulated by illuminating different light-intensity patterns. Trying to facilitate the tailoring process of the opto-electret loudspeaker, projection moiré was adopted to measure its vibration. By recording the projected fringes which are modulated by the contours of the testing sample, the phase unwrapping algorithm can give us a continuous phase distribution which is proportional to the object height variations. With the aid of the projection moiré metrology system, the vibrations associated with each distinctive light pattern could be characterized. Therefore, we expect that the overall acoustic performance could be improved by finding the suitable illuminating patterns. In this manuscript, the system performance of the projection moiré and the optoelectret paper speakers were cross-examined and verified by the experimental results obtained.

Process Knowledge Characterization of Radioactive Waste at the Classified Waste Landfill Remediation Project Sandia National Laboratories, Albuquerque, New Mexico

International Nuclear Information System (INIS)

DOTSON, PATRICK WELLS; GALLOWAY, ROBERT B.; JOHNSON JR, CARL EDWARD

1999-01-01

This paper discusses the development and application of process knowledge (PK) to the characterization of radioactive wastes generated during the excavation of buried materials at the Sandia National Laboratories/New Mexico (SNL/NM) Classified Waste Landfill (CWLF). The CWLF, located in SNL/NM Technical Area II, is a 1.5-acre site that received nuclear weapon components and related materials from about 1950 through 1987. These materials were used in the development and testing of nuclear weapon designs. The CWLF is being remediated by the SNL/NM Environmental Restoration (ER) Project pursuant to regulations of the New Mexico Environment Department. A goal of the CWLF project is to maximize the amount of excavated materials that can be demilitarized and recycled. However, some of these materials are radioactively contaminated and, if they cannot be decontaminated, are destined to require disposal as radioactive waste. Five major radioactive waste streams have been designated on the CWLF project, including: unclassified soft radioactive waste--consists of soft, compatible trash such as paper, plastic, and plywood; unclassified solid radioactive waste--includes scrap metal, other unclassified hardware items, and soil; unclassified mixed waste--contains the same materials as unclassified soft or solid radioactive waste, but also contains one or more Resource Conservation and Recovery Act (RCRA) constituents; classified radioactive waste--consists of classified artifacts, usually weapons components, that contain only radioactive contaminants; and classified mixed waste--comprises radioactive classified material that also contains RCRA constituents. These waste streams contain a variety of radionuclides that exist both as surface contamination and as sealed sources. To characterize these wastes, the CWLF project's waste management team is relying on data obtained from direct measurement of radionuclide activity content to the maximum extent possible and, in cases where

The DLR project Wirbelschleppe. Detecting, characterizing, controlling, attenuating, understanding, and predicting aircraft wake vortices

Energy Technology Data Exchange (ETDEWEB)

Holzaepfel, F. (ed.)

2008-07-01

This collection of reports presents an excerpt of the investigations that were performed in the framework of the DLR Projekt Wirbelschleppe. A similar sample of reports was presented as part of three dedicated wake vortex sessions accomplished at the 1{sup st} European Air and Space Conference (CEAS 2007) and Deutscher Luft- und Raumfahrtkongress 2007 in Berlin. The Projekt Wirbelschleppe was conducted in two phases in the time frame from 1999 to 2007 with the five contributing DLR Institutes: Institute of Atmospheric Physics, Institute of Aerodynamics and Flow Technology, Institute of Flight Systems, Institute of Flight Guidance, Institute of Robotics and Mechatronics and the Institute of Aeronautics and Astronautics of the University of Technology Berlin. The project unified a multitude of different aspects and disciplines of wake vortex research which can be characterized by four main themes: - minimization of wake vortices by measures at the aircraft; - development and demonstration of a system for wake vortex prediction and observation; - airborne wake vortex detection and active control; - integration of systems into air traffic control. The Projekt Wirbelschleppe greatly benefited from the European projects AWIATOR, ATC-Wake, Credos, C-Wake, Eurowake, FAR-Wake, FLYSAFE, I-Wake, S-Wake, WakeNet, WakeNet2-Europe, WakeNet3-Europe, and Wavenc. DLR's wake vortex activities will be continued in the Projekt Wetter and Fliegen (2008-2011): Because the current compilation represents only a limited extract of the accomplished work, it is completed by a list of references emerging from the project. (orig.)

Yucca Mountain Project bibliography, January--June 1989

International Nuclear Information System (INIS)

1990-01-01

Following a reorganization of the Office of Civilian Radioactive Waste Management, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project that was added to the Department of Energy's Energy Science and Technology Database from January 1990 through June 1990. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers, and articles are included in the sponsoring organization's list. Another section contains information about publications on the Energy Science and Technology Database that were not sponsored by the project but have some relevance to it

Site characterization report for the Basalt Waste Isolation Project

International Nuclear Information System (INIS)

1982-11-01

This Site Characterization Report documents the results of the site screening process, the preliminary site characterization data, the technical issues that need to be addressed, and the plans for resolving these issues

Environmental assessment for the Groundwater Characterization Project, Nevada Test Site, Nye County, Nevada

International Nuclear Information System (INIS)

1992-08-01

The US Department of Energy (DOE) proposes to conduct a program to characterize groundwater at the Nevada Test Site (NTS), Nye County, Nevada, in accordance with a 1987 DOE memorandum stating that all past, present, and future nuclear test sites would be treated as Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) sites (Memorandum from Bruce Green, Weapons Design and Testing Division, June 6, 1987). DOE has prepared an environmental assessment (DOE/EA-0532) to evaluate the environmental consequences associated with the proposed action, referred to as the Groundwater Characterization Project (GCP). This proposed action includes constructing access roads and drill pads, drilling and testing wells, and monitoring these wells for the purpose of characterizing groundwater at the NTS. Long-term monitoring and possible use of these wells in support of CERCLA, as amended by the Superfund Amendments and Reauthorization Act, is also proposed. The GCP includes measures to mitigate potential impacts on sensitive biological, cultural and historical resources, and to protect workers and the environment from exposure to any radioactive or mixed waste materials that may be encountered. DOE considers those mitigation measures related to sensitive biological, cultural and historic resources as essential to render the impacts of the proposed action not significant, and DOE has prepared a Mitigation Action Plan (MAP) that explains how such mitigations will be planned and implemented. Based on the analyses presented in the EA, DOE has determined that the proposed action is not 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, preparation of an environmental impact statement is not required and the Department is issuing this FONSI

Musiikilla iloa muistisairaiden vanhusten arkeen

OpenAIRE

Tiihonen, Jaana

2012-01-01

Opetus- ja kulttuuriministeriön (2010) taiteesta ja kulttuurista hyvinvointia -ehdotuksen toimintaohjelman kolme painopistealuetta ovat kulttuuri osallisuuden, yhteisöllisyyden, arjen toimintojen ja ympäristöjen edistäjänä, taide ja kulttuuri osana sosiaali- ja terveydenhuoltoa ja työhyvinvoinnin tukeminen taiteen ja kulttuurin keinoin. Muistisairaudet aiheuttavat vanhuksille eniten sosiaali- ja terveydenhuollonpalveluiden tarvetta ja ovat ympärivuorokautiseen pitkäaikaishoitoon joutumisen pä...

Status of volcanism studies for the Yucca Mountain Site Characterization Project

Energy Technology Data Exchange (ETDEWEB)

Crowe, B.; Perry, F.; Murrell, M.; Poths, J.; Valentine, G.A. [Los Alamos National Lab., NM (United States); Wells, S. [Univ. of California, Riverside, CA (United States); Bowker, L.; Finnegan, K. [Univ. of Nevada, Las Vegas, NV (United States); Geissman, J.; McFadden, L.

1995-02-01

Chapter 1 introduces the volcanism issue for the Yucca Mountain site and provides the reader with an overview of the organization, content, and significant conclusions of this report. The risk of future basaltic volcanism is the primary topic of concern including both events that intersect a potential repository and events that occur near or within the waste isolation system of a repository. Chapter 2 describes the volcanic history of the Yucca Mountain region (YMR) and emphasizes the Pliocene and Quaternary volcanic record, the interval of primary concern for volcanic risk assessment. The Lathrop Wells volcanic center is described in detail because it is the youngest basalt center in the YMR. Chapter 3 describes the tectonic setting of the YMR and presents and assesses the significance of multiple alternative tectonic models. Geophysical data are described for the YMR and are used as an aid to understand the distribution of basaltic volcanic centers. Chapter 4 discusses the petrologic and geochemical features of basaltic volcanism in the YMR, the southern Great Basin and the Basin and Range province. The long time of activity and characteristic small volume of the Postcaldera basalt of the YMR result in one of the lowest eruptive rates in a volcanic field in the southwest United States. Chapter 5 summarizes current concepts of the segregation, ascent, and eruption of basalt magma. Chapter 6 summarizes the history of volcanism studies (1979 through early 1994), including work for the Yucca Mountain Site Characterization Project and overview studies by the state of Nevada and the Nuclear Regulatory Commission. Chapter 7 summarizes probabilistic volcanic hazard assessment using a three-part conditional probability model. Chapter 8 describes remaining volcanism work judged to be needed to complete characterization studies for the YMR. Chapter 9 summarizes the conclusions of this volcanism status report.

Status of volcanism studies for the Yucca Mountain Site Characterization Project

International Nuclear Information System (INIS)

Crowe, B.; Perry, F.; Murrell, M.; Poths, J.; Valentine, G.A.; Wells, S.; Bowker, L.; Finnegan, K.; Geissman, J.; McFadden, L.

1995-02-01

Chapter 1 introduces the volcanism issue for the Yucca Mountain site and provides the reader with an overview of the organization, content, and significant conclusions of this report. The risk of future basaltic volcanism is the primary topic of concern including both events that intersect a potential repository and events that occur near or within the waste isolation system of a repository. Chapter 2 describes the volcanic history of the Yucca Mountain region (YMR) and emphasizes the Pliocene and Quaternary volcanic record, the interval of primary concern for volcanic risk assessment. The Lathrop Wells volcanic center is described in detail because it is the youngest basalt center in the YMR. Chapter 3 describes the tectonic setting of the YMR and presents and assesses the significance of multiple alternative tectonic models. Geophysical data are described for the YMR and are used as an aid to understand the distribution of basaltic volcanic centers. Chapter 4 discusses the petrologic and geochemical features of basaltic volcanism in the YMR, the southern Great Basin and the Basin and Range province. The long time of activity and characteristic small volume of the Postcaldera basalt of the YMR result in one of the lowest eruptive rates in a volcanic field in the southwest United States. Chapter 5 summarizes current concepts of the segregation, ascent, and eruption of basalt magma. Chapter 6 summarizes the history of volcanism studies (1979 through early 1994), including work for the Yucca Mountain Site Characterization Project and overview studies by the state of Nevada and the Nuclear Regulatory Commission. Chapter 7 summarizes probabilistic volcanic hazard assessment using a three-part conditional probability model. Chapter 8 describes remaining volcanism work judged to be needed to complete characterization studies for the YMR. Chapter 9 summarizes the conclusions of this volcanism status report

Advanced reservoir characterization for improved oil recovery in a New Mexico Delaware basin project

Energy Technology Data Exchange (ETDEWEB)

Martin, F.D.; Kendall, R.P.; Whitney, E.M. [Dave Martin and Associates, Inc., Socorro, NM (United States)] [and others

1997-08-01

The Nash Draw Brushy Canyon Pool in Eddy County, New Mexico is a field demonstration site in the Department of Energy Class III program. The basic problem at the Nash Draw Pool is the low recovery typically observed in similar Delaware fields. By comparing a control area using standard infill drilling techniques to a pilot area developed using advanced reservoir characterization methods, the goal of the project is to demonstrate that advanced technology can significantly improve oil recovery. During the first year of the project, four new producing wells were drilled, serving as data acquisition wells. Vertical seismic profiles and a 3-D seismic survey were acquired to assist in interwell correlations and facies prediction. Limited surface access at the Nash Draw Pool, caused by proximity of underground potash mining and surface playa lakes, limits development with conventional drilling. Combinations of vertical and horizontal wells combined with selective completions are being evaluated to optimize production performance. Based on the production response of similar Delaware fields, pressure maintenance is a likely requirement at the Nash Draw Pool. A detailed reservoir model of pilot area was developed, and enhanced recovery options, including waterflooding, lean gas, and carbon dioxide injection, are being evaluated.

Methodology and main results of seismic source characterization for the PEGASOS Project, Switzerland

International Nuclear Information System (INIS)

Coppersmith, K. J.; Youngs, R. R.; Sprecher, Ch.

2009-01-01

Under the direction of the National Cooperative for the Disposal of Radioactive Waste (NAGRA), a probabilistic seismic hazard analysis was conducted for the Swiss nuclear power plant sites. The study has become known under the name 'PEGASOS Project'. This is the first of a group of papers in this volume that describes the seismic source characterization methodology and the main results of the project. A formal expert elicitation process was used, including dissemination of a comprehensive database, multiple workshops for identification and discussion of alternative models and interpretations, elicitation interviews, feedback to provide the experts with the implications of their preliminary assessments, and full documentation of the assessments. A number of innovative approaches to the seismic source characterization methodology were developed by four expert groups and implemented in the study. The identification of epistemic uncertainties and treatment using logic trees were important elements of the assessments. Relative to the assessment of the seismotectonic framework, the four expert teams identified similar main seismotectonic elements: the Rhine Graben, the Jura / Molasse regions, Helvetic and crystalline subdivisions of the Alps, and the southern Germany region. In defining seismic sources, the expert teams used a variety of approaches. These range from large regional source zones having spatially-smoothed seismicity to smaller local zones, to account for spatial variations in observed seismicity. All of the teams discussed the issue of identification of feature-specific seismic sources (i.e. individual mapped faults) as well as the potential reactivation of the boundary faults of the Permo-Carboniferous grabens. Other important seismic source definition elements are the specification of earthquake rupture dimensions and the earthquake depth distribution. Maximum earthquake magnitudes were assessed for each seismic source using approaches that consider the

Methodological classification of innovative engineering projects

NARCIS (Netherlands)

Zwart, S.D.; de Vries, M.J.; Franssen, M.; Vermaas, P.E.; Kroes, P.; Meijers, A.W.M.

2016-01-01

In this chapter we report on and discuss our empirical classification of innovative engineering projects. Basic innovative engineering projects are characterized by their overall goal and accompanying method. On the basis of this goal and method, we classify engineering projects as all falling in

Characterization, Monitoring and Sensor Technology Integrated Program

International Nuclear Information System (INIS)

1993-01-01

This booklet contains summary sheets that describe FY 1993 characterization, monitoring, and sensor technology (CMST) development projects. Currently, 32 projects are funded, 22 through the OTD Characterization, Monitoring, and Sensor Technology Integrated Program (CMST-IP), 8 through the OTD Program Research and Development Announcement (PRDA) activity managed by the Morgantown Energy Technology Center (METC), and 2 through Interagency Agreements (IAGs). This booklet is not inclusive of those CMST projects which are funded through Integrated Demonstrations (IDs) and other Integrated Programs (IPs). The projects are in six areas: Expedited Site Characterization; Contaminants in Soils and Groundwater; Geophysical and Hydrogeological Measurements; Mixed Wastes in Drums, Burial Grounds, and USTs; Remediation, D ampersand D, and Waste Process Monitoring; and Performance Specifications and Program Support. A task description, technology needs, accomplishments and technology transfer information is given for each project

Evaluation of measurement reproducibility using the standard-sites data, 1994 Fernald field characterization demonstration project

International Nuclear Information System (INIS)

Rautman, C.A.

1996-02-01

The US Department of Energy conducted the 1994 Fernald (Ohio) field characterization demonstration project to evaluate the performance of a group of both industry-standard and proposed alternative technologies in describing the nature and extent of uranium contamination in surficial soils. Detector stability and measurement reproducibility under actual operating conditions encountered in the field is critical to establishing the credibility of the proposed alternative characterization methods. Comparability of measured uranium activities to those reported by conventional, US Environmental Protection Agency (EPA)-certified laboratory methods is also required. The eleven (11) technologies demonstrated included (1) EPA-standard soil sampling and laboratory mass-spectroscopy analyses, and currently-accepted field-screening techniques using (2) sodium-iodide scintillometers, (3) FIDLER low-energy scintillometers, and (4) a field-portable x-ray fluorescence spectrometer. Proposed advanced characterization techniques included (5) alpha-track detectors, (6) a high-energy beta scintillometer, (7) electret ionization chambers, (8) and (9) a high-resolution gamma-ray spectrometer in two different configurations, (10) a field-adapted laser ablation-inductively coupled plasma-atomic emission spectroscopy (ICP-AES) technique, and (11) a long-range alpha detector. Measurement reproducibility and the accuracy of each method were tested by acquiring numerous replicate measurements of total uranium activity at each of two ''standard sites'' located within the main field demonstration area. Meteorological variables including temperature, relative humidity. and 24-hour rainfall quantities were also recorded in conjunction with the standard-sites measurements

The fracture zone project - final report

International Nuclear Information System (INIS)

Andersson, Peter

1993-09-01

This report summarizes the work and the experiences gained during the fracture zone project at the Finnsjoen study site. The project is probably the biggest effort, so far, to characterize a major fracture zone in crystalline bedrock. The project was running between 1984-1990 involving a large number of geological, geohydrological, geochemical, and geomechanical investigation. The methods used for identification and characterization are reviewed and discussed in terms of applicability and possible improvements for future investigations. The discussion is exemplified with results from the investigation within the project. Flow and transport properties of the zone determined from hydraulic tests and tracer tests are discussed. A large number of numerical modelling efforts performed within the fracture zone project, the INTRAVAL project, and the SKB91-study are summarized and reviewed. Finally, occurrence of similar zones and the relevance of major low angle fracture zones in connection to the siting of an underground repository is addressed

THE BC CRIBS & TRENCHES GEOPHYSICAL CHARACTERIZATION PROJECT ONE STEP FORWARD IN HANFORDS CLEANUP PROCESS

Energy Technology Data Exchange (ETDEWEB)

BENECKE, MN.W.

2006-02-22

A geophysical characterization project was conducted at the BC Cribs and Trenches Area, located south of 200 East at the Hanford Site. The area consists of 26 waste disposal trenches and cribs, which received approximately 30 million gallons of liquid waste from the uranium recovery process and the ferrocyanide processes associated with wastes generated by reprocessing nuclear fuel. Waste discharges to BC Cribs contributed perhaps the largest liquid fraction of contaminants to the ground in the 200 Areas. The site also includes possibly the largest inventory of Tc-99 ever disposed to the soil at Hanford with an estimated quantity of 400 Ci. Other waste constituents included high volumes of nitrate and U-238. The geophysical characterization at the 50 acre site primarily included high resolution resistivity (HRR). The resistivity technique is a non-invasive method by which electrical resistivity data are collected along linear transects, and data are presented as continuous profiles of subsurface electrical properties. The transects ranged in size from about 400-700 meters and provided information down to depths of 60 meters. The site was characterized by a network of 51 HRR lines with a total of approximately 19.7 line kilometers of data collected parallel and perpendicular to the trenches and cribs. The data were compiled to form a three-dimensional representation of low resistivity values. Low resistivity, or high conductivity, is indicative of high ionic strength soil and porewater resulting from the migration of nitrate and other inorganic constituents through the vadose zone. High spatial density soil data from a single borehole, that included coincident nitrate concentrations, electrical conductivity, and Tc-99, were used to transform the electrical resistivity data into a nitrate plume. The plume was shown to extend laterally beyond the original boundaries of the waste site and, in one area, to depths that exceeded the characterization strategy. It is

THE BC CRIBS and TRENCHES GEOPHYSICAL CHARACTERIZATION PROJECT: ONE STEP FORWARD IN HANFORD'S CLEANUP PROCESS

International Nuclear Information System (INIS)

BENECKE, M.W.

2005-01-01

A geophysical characterization project was conducted at the BC Cribs and Trenches Area, located south of 200 East at the Hanford Site. The area consists of 26 waste disposal trenches and cribs, which received approximately 30 million gallons of liquid waste from the uranium recovery process and the ferrocyanide processes associated with wastes generated by reprocessing nuclear fuel. Waste discharges to BC Cribs contributed perhaps the largest liquid fraction of contaminants to the ground in the 200 Areas. The site also includes possibly the largest inventory of Tc-99 ever disposed to the soil at Hanford with an estimated quantity of 400 Ci. Other waste constituents included high volumes of nitrate and U-238. The geophysical characterization at the 50-acre site primarily included high resolution resistivity (HRR). The resistivity technique is a non-invasive method by which electrical resistivity data are collected along linear transects, and data are presented as continuous profiles of subsurface electrical properties. The transects ranged in size from about 400-700 meters and provided information down to depths of 60 meters. The site was characterized by a network of 51 HRR lines with a total of approximately 19.7 line kilometers of data collected parallel and perpendicular to the trenches and cribs. The data were compiled to form a three-dimensional representation of low resistivity values. Low resistivity, or high conductivity, is indicative of high ionic strength soil and porewater resulting from the migration of nitrate and other inorganic constituents through the vadose zone. High spatial density soil data from a single borehole, that included coincident nitrate concentrations, electrical conductivity. and Tc-99, were used to transform the electrical resistivity data into a nitrate plume. The plume was shown to extend laterally beyond the original boundaries of the waste site and, in one area, to depths that exceeded the characterization strategy

CLASSIFICATION OF THE MGR SITE WATER SYSTEM

International Nuclear Information System (INIS)

J.A. Ziegler

1999-01-01

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) site water system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

Classification of the MGR Assembly Transfer System

International Nuclear Information System (INIS)

S.E. Salzman

1999-01-01

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) assembly transfer system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

CLASSIFICATION OF THE MGR SITE OPERATIONS SYSTEM

International Nuclear Information System (INIS)

J.A. Ziegler

1999-01-01

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) site operations system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

CLASSIFICATION OF THE MGR SITE LAYOUT SYSTEM

International Nuclear Information System (INIS)

S.E. Salzman

1999-01-01

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) site layout system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

CLASSIFICATION OF THE MGR OFFSITE UTILITIES SYSTEM

International Nuclear Information System (INIS)

J.A. Ziegler

1999-01-01

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) offsite utilities system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

CLASSIFICATION OF THE MGR SUBSURFACE EXCAVATION SYSTEM

International Nuclear Information System (INIS)

R. Garrett

1999-01-01

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) subsurface excavation system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

Preliminary seismicity and focal mechanisms for the southern Great Basin of Nevada and California: January 1992 through September 1992

International Nuclear Information System (INIS)

Harmsen, S.C.

1994-01-01

The telemetered southern Great Basin seismic network (SGBSN) is operated for the Department of Energy's Yucca Mountain Project (YMP). The US Geological Survey, Branch of Earthquake and Landslide Hazards, maintained this network until September 30, 1992, at which time all operational and analysis responsibilities were transferred to the University of Nevada at Reno Seismological Laboratory (UNRSL). This report contains preliminary earthquake and chemical explosion hypocenter listings and preliminary earthquake focal mechanism solutions for USGS/SGBSN data for the period January 1, 1992 through September 30, 1992, 15:00 UTC

ENHANCED CHARACTERIZATION OF THE REPOSITORY BLOCK REQUIREMENTS DOCUMENT (ECRB-RD)

International Nuclear Information System (INIS)

G.M. Teraoka

1998-01-01

This Enhanced Characterization of the Repository Block Requirements Document (ECRB-RD) provides applicable design and construction requirements for the Enhanced Characterization of the Repository Block (ECRB) East-West Drift and its associated equipment. This document also identifies the applicable requirements from the Exploratory Studies Facilities Design Requirements (ESFDR) Document (YMPICM-00 19, Revision 2, ICN- 1) for design and construction of the ECRB East-West Drift, ground support, constructor support utilities and components. These requirements have been tailored specifically for the ECRB East-West Drift design and construction. The allocated requirements for the ECRB East-West Drift are in Sections III through VI. The requirements in sections III through VI contain requirement numbers from the ESFDR, Rev 2, ICN-1 for reference back to the ESFDR. Each requirement in the ECRB-RD also identifies a trace to the Site Design and Test Requirements Document (YMP/CM-0021, Rev. 2, ICN-1) and 10CFR60 similar to the style used in the ESFDR. These traces to 10CFR60 are consistent with the 1995 version of 10CFR60 used by the SD and TRD and the ESFDR. Those ESFDR requirements statements that were technically modified are identified as such and those that were derived as part of this allocation are also identified. An activity evaluation has been performed in accordance with QAP-2-0 and has determined that the QA program is applicable to this document. Therefore, the development of this document was performed in compliance with QAP-3-5, Revision 7, Development of Technical Documents and checked and reviewed in compliance with Section 5.3. This is consistent with the IOC from R. Stambaugh to M. Lugo on the subject of ECRB-RD, Revision 1, TDPP Applicability (LV.SEI.,RMS.03/98-0 12, Dated 3/12/98). The ECRB East-West Drift includes those excavated underground openings to support enhanced characterization testing activities for the repository block and provides potential

Final report on the Background Soil Characterization Project at the Oak Ridge Reservation, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Hatmaker, T.L.; Hook, L.A.; Jackson, B.L.

1993-10-01

The Background Soil Characterization Project (BSCP) will provide background concentration levels of selected metals, organic compounds, and radionuclides in soils from uncontaminated on-site areas at the Oak Ridge Reservation (ORR), and off-site in the western part of Roane County and the eastern part of Anderson County. The BSCP will establish a database, recommend how to use the data for contaminated site assessment, and provide estimates of the potential human health and environmental risks associated with the background level concentrations of potentially hazardous constituents. ORR background soil characterization data will be used for two purposes. The first application will be in differentiating between naturally occurring constituents and site-related contamination. This is a very important step in a risk assessment because if sufficient background data are not available, no constituent known to be a contaminant can be eliminated from the assessment even if the sampled concentration is measured at a minimum level. The second use of the background data will be in calculating baseline risks against which site-specific contamination risks can be compared

ERUPTION TO DOSE: COUPLING A TEPHRA DISPERSAL MODEL WITHIN A PERFORMANCE ASSESSMENT FRAMEWORK

International Nuclear Information System (INIS)

G. N. Keating, J. Pelletier

2005-01-01

The tephra dispersal model used by the Yucca Mountain Project (YMP) to evaluate the potential consequences of a volcanic eruption through the waste repository must incorporate simplifications in order to function within a large Monte-Carlo style performance assessment framework. That is, the explicit physics of the conduit, vent, and eruption column processes are abstracted to a 2-D, steady-state advection-dispersion model (ASHPLUME) that can be run quickly over thousands of realizations of the overall system model. Given the continuous development of tephra dispersal modeling techniques in the last few years, we evaluated the adequacy of this simplified model for its intended purpose within the YMP total system performance assessment (TSPA) model. We evaluated uncertainties inherent in model simplifications including (1) instantaneous, steady-state vs. unsteady eruption, which affects column height, (2) constant wind conditions, and (3) power-law distribution of the tephra blanket; comparisons were made to other models and published ash distributions. Spatial statistics are useful for evaluating differences in these model output vs. results using more complex wind, column height, and tephra deposition patterns. However, in order to assess the adequacy of the model for its intended use in TSPA, we evaluated the propagation of these uncertainties through FAR, the YMP ash redistribution model, which utilizes ASHPLUME tephra deposition results to calculate the concentration of nuclear waste-contaminated tephra at a dose-receptor population as a result of sedimentary transport and mixing processes on the landscape. Questions we sought to answer include: (1) what conditions of unsteadiness, wind variability, or departure from simplified tephra distribution result in significant effects on waste concentration (related to dose calculated for the receptor population)? (2) What criteria can be established for the adequacy of a tephra dispersal model within the TSPA

CCD characterization and measurements automation

International Nuclear Information System (INIS)

Kotov, I.V.; Frank, J.; Kotov, A.I.; Kubanek, P.; O'Connor, P.; Prouza, M.; Radeka, V.; Takacs, P.

2012-01-01

Modern mosaic cameras have grown both in size and in number of sensors. The required volume of sensor testing and characterization has grown accordingly. For camera projects as large as the LSST, test automation becomes a necessity. A CCD testing and characterization laboratory was built and is in operation for the LSST project. Characterization of LSST study contract sensors has been performed. The characterization process and its automation are discussed, and results are presented. Our system automatically acquires images, populates a database with metadata information, and runs express analysis. This approach is illustrated on 55 Fe data analysis. 55 Fe data are used to measure gain, charge transfer efficiency and charge diffusion. Examples of express analysis results are presented and discussed.

Determination of water movement in the unsaturated zone at Yucca Mountain using chloride, bromide, and chlorine isotopes as environmental tracers. Final report

International Nuclear Information System (INIS)

1994-01-01

This report, prepared by Hydro Geo Chem staff for Los Alamos National Laboratory, summarizes work conducted by the company under Subcontract 9-XG1-N3993-1. The ultimate objective of this work is to characterize the movement of subsurface water in the vicinity of Yucca Mountain, Nevada. Data produced under this contract is to be used by the US Department of Energy in its Yucca Mountain Site Characterization Project (YMP) to help determine hydrologic flows that may affect the performance of a potential nuclear waste repository. The data may be used in the licensing proceedings, and certain quality assurance procedures have thus been required. The work has focussed on measuring the distribution of environmental tracers-chlorine-36, chlorine, and bromine-and on evaluating the depth to which these conservative solutes have percolated in the unsaturated zone at Yucca Mountain. The following discussion summarizes progress made on the tasks outlined in the original Scope of Work. Details of this work and all data acquired by Hydro Geo Chem for this subcontract have been systematically organized in logbooks and laboratory notebooks. These documents have been structured to make it easy to trace the analytical history of a sample, from time of receipt to the final analytical results

Class III Mid-Term Project, "Increasing Heavy Oil Reserves in the Wilmington Oil Field Through Advanced Reservoir Characterization and Thermal Production Technologies"

Energy Technology Data Exchange (ETDEWEB)

Scott Hara

2007-03-31

The overall objective of this project was to increase heavy oil reserves in slope and basin clastic (SBC) reservoirs through the application of advanced reservoir characterization and thermal production technologies. The project involved improving thermal recovery techniques in the Tar Zone of Fault Blocks II-A and V (Tar II-A and Tar V) of the Wilmington Field in Los Angeles County, near Long Beach, California. A primary objective has been to transfer technology that can be applied in other heavy oil formations of the Wilmington Field and other SBC reservoirs, including those under waterflood. The first budget period addressed several producibility problems in the Tar II-A and Tar V thermal recovery operations that are common in SBC reservoirs. A few of the advanced technologies developed include a three-dimensional (3-D) deterministic geologic model, a 3-D deterministic thermal reservoir simulation model to aid in reservoir management and subsequent post-steamflood development work, and a detailed study on the geochemical interactions between the steam and the formation rocks and fluids. State of the art operational work included drilling and performing a pilot steam injection and production project via four new horizontal wells (2 producers and 2 injectors), implementing a hot water alternating steam (WAS) drive pilot in the existing steamflood area to improve thermal efficiency, installing a 2400-foot insulated, subsurface harbor channel crossing to supply steam to an island location, testing a novel alkaline steam completion technique to control well sanding problems, and starting on an advanced reservoir management system through computer-aided access to production and geologic data to integrate reservoir characterization, engineering, monitoring, and evaluation. The second budget period phase (BP2) continued to implement state-of-the-art operational work to optimize thermal recovery processes, improve well drilling and completion practices, and evaluate the

Final Technical Report: Characterizing Emerging Technologies.

Energy Technology Data Exchange (ETDEWEB)

King, Bruce Hardison [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hansen, Clifford [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Stein, Joshua [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Riley, Daniel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Gonzalez, Sigifredo [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2015-12-01

The Characterizing Emerging Technologies project focuses on developing, improving and validating characterization methods for PV modules, inverters and embedded power electronics. Characterization methods and associated analysis techniques are at the heart of technology assessments and accurate component and system modeling. Outputs of the project include measurement and analysis procedures that industry can use to accurately model performance of PV system components, in order to better distinguish and understand the performance differences between competing products (module and inverters) and new component designs and technologies (e.g., new PV cell designs, inverter topologies, etc.).

Multiteide Project: Multiparametric characterization of the activity of Teide-Pico Viejo volcanic system

Science.gov (United States)

Domínguez Cerdeña, Itahiza; Villasante-Marcos, Victor; Meletlidis, Stavros; Sainz-Maza, Sergio; Abella, Rafael; Torres, Pedro A.; Sánchez, Nieves; Luengo-Oroz, Natividad; José Blanco, María; García-Cañada, Laura; Pereda de Pablo, Jorge; Lamolda, Héctor; Moure, David; Del Fresno, Carmen; Finizola, Anthony; Felepto, Alicia

2017-04-01

Teide-Pico Viejo complex stands for one of the major natural volcanic hazards in the Canary Islands, due to the expected types of eruptions in the area and the high number of inhabitants in Tenerife Island. Therefore, it is necessary to have a volcanic alert system able to afford a precise assessment of the current state of the complex. For this purpose, the knowledge of the expected signals at each volcanic activity level is required. Moreover, the external effects that can affect the measurements shall be distinguished, external influences as the atmosphere are qualitatively known but have not been quantified yet. The objective of the project is to collect, analyze and jointly and continuously evaluate over time geophysical, geodetic, geochemical and meteorological data from the Teide-Pico Viejo complex and its surroundings. A continuous multiparametric network have been deployed in the area, which, together with the data provided by the Volcano Monitoring Network of the Instituto Geográfico Nacional (IGN) and data from other institutions will provide a comprehensive set of data with high resolution in both space and time. This multiparametric network includes a seismic array, two self-potential lines for continuous measurements, five magnetometers and two weather stations. The network will be complemented with 8 CGPS stations, one tiltmeter, 10 seismic stations, and four thermometric stations on the fumaroles of Teide volcano that IGN already manage in Tenerife. The data will be completed with the results from different repeated surveys of self potential, soil temperature and CO2 diffuse flux in several pre-established areas on top of Teide throughout the entire duration of project. During the project, new computation tools will be developed to study the correlation between the different parameters analyzed. The results obtained will characterize the possible seasonal fluctuations of each parameter and the variations related to meteorological phenomena. In

CLASSIFICATION OF THE MGR WASTE HANDLING BUILDING ELECTRICAL SYSTEM

International Nuclear Information System (INIS)

S.E. Salzman

1999-01-01

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) waste handling building electrical system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

CLASSIFICATION OF THE MGR DEFENSE HIGH-LEVEL WASTE DISPOSAL CONTAINER SYSTEM

International Nuclear Information System (INIS)

J.A. Ziegler

1999-01-01

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) defense high-level waste disposal container system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333PY ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

CLASSIFICATION OF THE MGR SITE COMPRESSED AIR SYSTEM

International Nuclear Information System (INIS)

J.A. Ziegler

1999-01-01

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) site compressed air system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

CLASSIFICATION OF THE MGR NON-FUEL COMPONENTS DISPOSAL CONTAINER SYSTEM

International Nuclear Information System (INIS)

J.A. Ziegler

1999-01-01

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) non-fuel components disposal container system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

CLASSIFICATION OF THE MGR SUBSURFACE VENTILATION SYSTEM

International Nuclear Information System (INIS)

R.J. Garrett

1999-01-01

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) subsurface ventilation system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P7 ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

CLASSIFICATION OF THE MGR OPERATIONS MONITORING AND CONTROL SYSTEM

International Nuclear Information System (INIS)

R.J. Garrett

1999-01-01

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) Operations Monitoring and Control System structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P7 ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

CLASSIFICATION OF THE MGR MAINTENANCE AND SUPPLY SYSTEM

International Nuclear Information System (INIS)

J.A. Ziegler

1999-01-01

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) maintenance and supply system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

CLASSIFICATION OF THE MGR EMERGENCY RESPONSE SYSTEM

International Nuclear Information System (INIS)

Zeigler, J.A.

1999-01-01

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) emergency response system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P7 ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

TWRS privatization support project waste characterization resource dictionary

International Nuclear Information System (INIS)

Patello, G.K.; Wiemers, K.D.

1996-09-01

A single estimate of waste characteristics for each underground storage tanks at the Hanford Site is not available. The information that is available was developed for specific programmatic objectives and varies in format and level of descriptive detail, depending on the intended application. This dictionary reflects an attempt to define what waste characterization information is available. It shows the relationship between the identified resource and the original data source and the inter-relationships among the resources; it also provides a brief description of each resource. Developed as a general dictionary for waste characterization information, this document is intended to make the user aware of potenially useful resources

Fuel Thermo-physical Characterization Project: Evaluation of Models to Calculate Thermal Diffusivity of Layered Composites

Energy Technology Data Exchange (ETDEWEB)

Burkes, Douglas [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Casella, Amanda J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gardner, Levi D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Casella, Andrew M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Huber, Tanja K. [Technische Universität München, Munich (Germany); Breitkreutz, Harald [Technische Universität München, Munich (Germany)

2015-02-11

The Office of Material Management and Minimization Fuel Thermo-physical Characterization Project at Pacific Northwest National Laboratory (PNNL) is tasked with using PNNL facilities and processes to receive irradiated low enriched uranium-molybdenum fuel plate samples and perform analyses in support of the Office of Material Management and Minimization Reactor Conversion Program. This work is in support of the Fuel Development Pillar that is managed by Idaho National Laboratory. A key portion of the scope associated with this project was to measure the thermal properties of fuel segments harvested from plates that were irradiated in the Advanced Test Reactor. Thermal diffusivity of samples prepared from the fuel segments was measured using laser flash analysis. Two models, one developed by PNNL and the other developed by the Technische Universität München (TUM), were evaluated to extract the thermal diffusivity of the uranium-molybdenum alloy from measurements made on the irradiated, layered composites. The experimental data of the “TC” irradiated fuel segment was evaluated using both models considering a three-layer and five-layer system. Both models are in acceptable agreement with one another and indicate that the zirconium diffusion barrier has a minimal impact on the overall thermal diffusivity of the monolithic U-Mo fuel.

THz transceiver characterization : LDRD project 139363 final report.

Energy Technology Data Exchange (ETDEWEB)

Nordquist, Christopher Daniel; Wanke, Michael Clement; Cich, Michael Joseph; Reno, John Louis; Fuller, Charles T.; Wendt, Joel Robert; Lee, Mark; Grine, Albert D.

2009-09-01

LDRD Project 139363 supported experiments to quantify the performance characteristics of monolithically integrated Schottky diode + quantum cascade laser (QCL) heterodyne mixers at terahertz (THz) frequencies. These integrated mixers are the first all-semiconductor THz devices to successfully incorporate a rectifying diode directly into the optical waveguide of a QCL, obviating the conventional optical coupling between a THz local oscillator and rectifier in a heterodyne mixer system. This integrated mixer was shown to function as a true heterodyne receiver of an externally received THz signal, a breakthrough which may lead to more widespread acceptance of this new THz technology paradigm. In addition, questions about QCL mode shifting in response to temperature, bias, and external feedback, and to what extent internal frequency locking can improve stability have been answered under this project.

Performance allocation traceable to regulatory criteria as applied to site characterization work at the Basalt Waste Isolation Project

International Nuclear Information System (INIS)

Deju, R.A.; Babad, H.; Bensky, M.S.; Jacobs, G.K.

1983-01-01

The Basalt Waste Isolation Project has developed a method for defining in detail the work required to demonstrate the feasibility of emplacing and providing for the safe isolation of nuclear wastes in a repository in the deep basalts at the Hanford Site near Richland, Washington. Criteria analysis allows the identification of areas of significant technical uncertainty or controversy that can be highlighted as issues. A preliminary analysis has been conducted, which, by identifying key radionuclides and allocating performance among the multiple barriers in a repository constructed in a basalt, allows the design and development testing activities at the Basalt Waste Isolation Project to be put into perspective. Application of sophisticated uncertainty analysis techniques will allow refinements in the analysis to be made and to further guide characterization and testing activities. Preliminary results suggest that a repository constructed in basalt will provide for the safe isolation of nuclear wastes in a cost-effective and reliable manner with a high degree of confidence

Headspace vapor characterization of Hanford Waste Tank SX-102: Results from samples collected on July 19, 1995. Tank Vapor Characterization Project

International Nuclear Information System (INIS)

McVeety, B.D.; Evans, J.C.; Clauss, T.W.; Pool, K.H.

1996-05-01

This report describes the results of vapor samples taken from the headspace of waste storage tank 241-SX-102 (Tank SX-102) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed under the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was open-quotes Vapor Sampling and Analysis Planclose quotes, and the sample job was designated S5046. Samples were collected by WHC on July 19, 1995, using the vapor sampling system (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace

Headspace vapor characterization of Hanford Waste Tank AX-103: Results from samples collected on June 21, 1995. Tank Vapor Characterization Project

International Nuclear Information System (INIS)

Ligotke, M.W.; Pool, K.H.; Clauss, T.W.

1996-05-01

This report describes the results of vapor samples taken from the headspace of waste storage tank 241-AX-103 (Tank AX-103) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was open-quotes Vapor Sampling and Analysis Planclose quotes, and the sample job was designated S5029. Samples were collected by WHC on June 21, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace

Headspace vapor characterization of Hanford Waste Tank AX-101: Results from samples collected on June 15, 1995. Tank Vapor Characterization Project

International Nuclear Information System (INIS)

Pool, K.H.; Clauss, T.W.; Evans, J.C.; McVeety, B.D.

1996-05-01

This report describes the results of vapor samples taken from the headspace of waste storage tank 241-AX-101 (Tank AX-101) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) under the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was open-quotes Vapor Sampling and Analysis Planclose quotes, and the sample job was designated S5028. Samples were collected by WHC on June 15, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace

The Stripa project annual report 1984

International Nuclear Information System (INIS)

1985-07-01

This is an autonomous OECD/NEA project relating to the final disposal of highly radioactive waste. Research is being performed in a granite formation 350 m below the ground surface. The first phase consists of three parts, namely hydrogeological and hydrogeochemical investigations in boreholes, tracer migration tests and large-scale tests of the behaviour of backfill material. The second phase includes the following investigations: detection and characterization of fracture zones, sealing of boreholes and shafts, hydrogoelogical characterization of the Stripa site and isotopic characterization of its groundwaters. The estimated cost of both phases is 111 MSEK and they are scheduled for completion in 1986. A summary of the progress of the project phase I and phase II is given in this report. (G.B.)

Mission Need Statement: Calcine Disposition Project Major Systems Acquisition Project

International Nuclear Information System (INIS)

J. T. Beck

2007-01-01

This document identifies the need to establish the Calcine Disposition Project to determine and implement the final disposition of calcine including characterization, retrieval, treatment (if necessary), packaging, loading, onsite interim storage pending shipment to a repository or interim storage facility, and disposition of related facilities

Proceedings of the DOE/Yucca Mountain Site Characterization Project Radionuclde Adsorption Workshop at Los Alamos National Laboratory, September 11--12, 1990

International Nuclear Information System (INIS)

Canepa, J.A.

1992-08-01

Los Alamos National Laboratory hosted a workshop on radionuclide adsorption for the Department of Energy (DOE)/Yucca Mountain Site Characterization Project on September 11 and 12, 1990. The purpose of the workshop was to respond to a recommendation by the Nuclear Waste Technical Review Board that the DOE organize a radionuclide adsorption workshop to be attended by the DOE and its contractors involved in the measurement and modeling of such adsorption. The workshop would have two general purposes: (a) to determine the applicability of available radionuclide adsorption data on tuff and models for predicting such adsorption under existing and postclosure conditions at Yucca Mountain and (b) to establish what additional radionuclide adsorption research and model development are needed. Individual projects are processed separately for the databases

Advanced Research Projects Agency on Materials Preparation and Characterization Research

Science.gov (United States)

Briefly summarized is research concerned with such topics as: Preparation of silica glass from amorphous silica; Glass structure by Raman ...ferroelectrics; Silver iodide crystals; Vapor phase growth; Refractory optical host materials; Hydroxyapatite ; Calcite; Characterization of single crystals with a double crystal spectrometer; Characterization of residual strain.

Results of pressurized-slot measurements in the G-Tunnel underground facility

International Nuclear Information System (INIS)

Zimmerman, R.M.; Mann, K.L.; Dodds, D.J.

1989-01-01

A rock-mechanics field-testing program is underway at Sandia National Laboratories (SNL) as part of the YMP. SNL has the responsibility for assessing the repository design and performance as well as characterizing the geomechanical behavior of the rock. SNL has conducted field experiments in G-Tunnel in Rainier Mesa at the NTS, where tuffs similar to those at Yucca Mountain, the potential repository site, are found. Later experiments are planned as part of the YMP Exploratory Shaft investigations at Yucca Mountain. Major geomechanical factors in repository developments are determinations of the stress state and the deformability of the rock mass (described by the modulus of deformation). One feature of SNL's rock-mechanics program was the development of a testing program for cutting thin slots in a jointed welded tuff and utilizing flatjacks for pressurizing these thin-slots on a relatively, large scale. Objectives in the pressurized-slot testing in G-Tunnel have been to apply and possibly improve methods for (1) utilizing the flatjack cancellation (FC) method for measuring stresses normal to the slot and (2) measuring the modulus of deformation of the jointed rock surrounding the slot. This paper discusses the results of field measurements in and around a single slot and evaluates potential applications and limitations. 10 refs., 1 fig., 4 tabs

Corrosion of copper-based materials in irradiated moist air systems

International Nuclear Information System (INIS)

Reed, D.T.; Van Konynenburg, R.A.

1991-06-01

The atmospheric corrosion of oxygen-free copper (CDA-102), 70/30 copper-nickel (CDA-715), and 7% aluminum bronze (CDA-613) in an irradiated moist air environment was investigated. Experiments were performed in both dry and 40% RH (at sign 90 degree C) air at temperatures of 90 and 150 degree C. Initial corrosion rates were determined based on a combination of weight gain and weight loss measurements. Corrosion products observed were identified. These experiments support efforts by the Yucca Mountain Project (YMP) to evaluate possible metallic barrier materials for nuclear waste containers. 8 refs., 1 fig., 2 tabs

DATA QUALIFICATION REPORT: MINERALOGY DATA FOR USE ON THE YUCCA MOUNTAIN PROJECT

International Nuclear Information System (INIS)

T.L. Steinborn

2002-01-01

This DQR uses the technical assessment methods according to Attachment 2 of AP-SIII.2QY Rev. 0, ICN 3, to qualify DTN LADB831321AN98.002. The data addressed in this DQR have been cited in CRWMS M andO (2000b) to support the Site Recommendation in determining the suitability of Yucca Mountain as a repository for high level nuclear waste. CRWMS M andO (2000b) refers to mineral analyses that are unqualified. Within the context of this DQR, the term mineral analyses includes: (1) the determination of the identity of specific crystalline phases from the Yucca Mountain Site by X-ray diffraction (XRD) analysis, as well as, (2) determination of mineral abundance as a percentage of the total mineral content of samples collected from drill core, side wall core and drill cuttings. These data are used among other purposes to define the spatial distribution of minerals at the Yucca Mountain Site, for correlation with geologic properties, and may be used as input in developing both unsaturated and saturated zone flow and transport models for the YMP Total System Performance Assessment. This DQR evaluates the unqualified data within DTNs within the context of supporting such kinds of studies on the YMP. The unqualified data considered in this DQR were identified and directly used in CRWMS M andO (2000b) in which the mineral analyses are used to create three-dimensional representations of mineral distributions. The purpose of this DQR is to recommend data that can be cited as qualified for use in technical products to support the License Application. The qualified data were placed in new DTNs generated as a result of the evaluation. The appropriateness and limitations (if any) of the data with respect to intended use are addressed in this DQR. In accordance with Attachment 1 of procedure AP-3.15Q, Rev. 3, ICN 2, ''Managing Technical Product Inputs'', it has been determined that the unqualified mineral abundance data for core material are not used in the direct calculation of

Yucca Mountain Biological Resources Monitoring Program

International Nuclear Information System (INIS)

1992-01-01

The US Department of Energy (DOE) is required by the Nuclear Waste Policy Act of 1982 (as amended in 1987) to study and characterize Yucca Mountain as a possible site for a geologic repository for high-level nuclear waste. During site characterization, the DOE will conduct a variety of geotechnical, geochemical, geological, and hydrological studies to determine the suitability of Yucca Mountain as a repository. To ensure that site characterization activities (SCA) do not adversely affect the Yucca Mountain area, an environmental program has been implemented to monitor and mitigate potential impacts and to ensure that activities comply with applicable environmental regulations. This report describes the activities and accomplishments during fiscal year 1991 (FY91) for six program areas within the Terrestrial Ecosystem component of the YMP environmental program. The six program areas are Site Characterization Activities Effects, Desert Tortoises, Habitat Reclamation, Monitoring and Mitigation, Radiological Monitoring, and Biological Support

Yucca Mountain Biological Resources Monitoring Program; Annual report, FY91

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-01-01

The US Department of Energy (DOE) is required by the Nuclear Waste Policy Act of 1982 (as amended in 1987) to study and characterize Yucca Mountain as a possible site for a geologic repository for high-level nuclear waste. During site characterization, the DOE will conduct a variety of geotechnical, geochemical, geological, and hydrological studies to determine the suitability of Yucca Mountain as a repository. To ensure that site characterization activities (SCA) do not adversely affect the Yucca Mountain area, an environmental program has been implemented to monitor and mitigate potential impacts and to ensure that activities comply with applicable environmental regulations. This report describes the activities and accomplishments during fiscal year 1991 (FY91) for six program areas within the Terrestrial Ecosystem component of the YMP environmental program. The six program areas are Site Characterization Activities Effects, Desert Tortoises, Habitat Reclamation, Monitoring and Mitigation, Radiological Monitoring, and Biological Support.

Environmental assessment for the Groundwater Characterization Project, Nevada Test Site, Nye County, Nevada; Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-08-01

The US Department of Energy (DOE) proposes to conduct a program to characterize groundwater at the Nevada Test Site (NTS), Nye County, Nevada, in accordance with a 1987 DOE memorandum stating that all past, present, and future nuclear test sites would be treated as Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) sites (Memorandum from Bruce Green, Weapons Design and Testing Division, June 6, 1987). DOE has prepared an environmental assessment (DOE/EA-0532) to evaluate the environmental consequences associated with the proposed action, referred to as the Groundwater Characterization Project (GCP). This proposed action includes constructing access roads and drill pads, drilling and testing wells, and monitoring these wells for the purpose of characterizing groundwater at the NTS. Long-term monitoring and possible use of these wells in support of CERCLA, as amended by the Superfund Amendments and Reauthorization Act, is also proposed. The GCP includes measures to mitigate potential impacts on sensitive biological, cultural and historical resources, and to protect workers and the environment from exposure to any radioactive or mixed waste materials that may be encountered. DOE considers those mitigation measures related to sensitive biological, cultural and historic resources as essential to render the impacts of the proposed action not significant, and DOE has prepared a Mitigation Action Plan (MAP) that explains how such mitigations will be planned and implemented. Based on the analyses presented in the EA, DOE has determined that the proposed action is not 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, preparation of an environmental impact statement is not required and the Department is issuing this FONSI.

Yucca Mountain site characteriztion project bibliography. Progress Report, 1994--1995

International Nuclear Information System (INIS)

1996-08-01

Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project which was added to the Department of Energy's Energy Science and Technology Database from January 1, 1994, through December 31, 1995. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers, and articles are included in the sponsoring organization's list. Another section contains information about publications on the Energy Science and Technology database which were not sponsored by the project but have some relevance to it

Yucca Mountain site characteriztion project bibliography. Progress Report, 1994--1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-08-01

Following a reorganization of the Office of Civilian Radioactive Waste Management in 1990, the Yucca Mountain Project was renamed Yucca Mountain Site Characterization Project. The title of this bibliography was also changed to Yucca Mountain Site Characterization Project Bibliography. Prior to August 5, 1988, this project was called the Nevada Nuclear Waste Storage Investigations. This bibliography contains information on this ongoing project which was added to the Department of Energy`s Energy Science and Technology Database from January 1, 1994, through December 31, 1995. The bibliography is categorized by principal project participating organization. Participant-sponsored subcontractor reports, papers, and articles are included in the sponsoring organization`s list. Another section contains information about publications on the Energy Science and Technology database which were not sponsored by the project but have some relevance to it.

Headspace vapor characterization of Hanford Waste Tank 241-T-110: Results from samples collected on August 31, 1995. Tank Vapor Characterization Project

International Nuclear Information System (INIS)

McVeety, B.D.; Thomas, B.L.; Evans, J.C.

1996-05-01

This report describes the results of vapor samples taken from the headspace of waste storage tank 241-T-110 (Tank T-110) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was open-quotes Vapor Sampling and Analysis Planclose quotes, and the sample job was designated S5056. Samples were collected by WHC on August 31, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace

Headspace vapor characterization of Hanford Waste Tank 241-TX-111: Results from samples collected on October 12, 1995. Tank Vapor Characterization Project

International Nuclear Information System (INIS)

Pool, K.H.; Clauss, T.W.; Evans, J.C.

1996-06-01

This report describes the results of vapor samples taken from the headspace of waste storage tank 241-TX-111 (Tank TX-111) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was open-quotes Vapor Sampling and Analysis Planclose quotes, and the sample job was designated S5069. Samples were collected by WHC on October 12, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace

Headspace vapor characterization of Hanford Waste Tank 241-SX-109: Results from samples collected on August 1, 1995. Tank Vapor Characterization Project

International Nuclear Information System (INIS)

Pool, K.H.; Clauss, T.W.; Evans, J.C.

1996-05-01

This report describes the results of vapor samples taken from the headspace of waste storage tank 241-SX-109 (Tank SX-109) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was open-quotes Vapor Sampling and Analysis Planclose quotes, and the sample job was designated S5048. Samples were collected by WHC on August 1, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace

Headspace vapor characterization of Hanford Waste Tank 241-SX-104: Results from samples collected on July 25, 1995. Tank Vapor Characterization Project

International Nuclear Information System (INIS)

Thomas, B.L.; Clauss, T.W.; Evans, J.C.

1996-05-01

This report describes the results of vapor samples taken from the headspace of waste storage tank 241-SX-104 (Tank SX-104) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was open-quotes Vapor Sampling and Analysis Planclose quotes, and the sample job was designated S5049. Samples were collected by WHC on July 25, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace

Headspace vapor characterization of Hanford Waste Tank 241-S-112: Results from samples collected on July 11, 1995. Tank Vapor Characterization Project

International Nuclear Information System (INIS)

Clauss, T.W.; Pool, K.H.; Evans, J.C.

1996-05-01

This report describes the results of vapor samples taken from the headspace of waste storage Tank 241-S-112 (Tank S-112) at the Hanford. Pacific Northwest National Laboratory (PNNL) is contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was open-quotes Vapor Sampling and Analysis Planclose quotes, and the sample job was designated S5044. Samples were collected by WHC on July 11, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace

Headspace vapor characterization of Hanford Waste Tank 241-SX-105: Results from samples collected on July 26, 1995. Tank Vapor Characterization Project

International Nuclear Information System (INIS)

Pool, K.H.; Clauss, T.W.; Evans, J.C.

1996-05-01

This report describes the results of vapor samples taken from the headspace of waste storage tank 241-SX-105 (Tank SX-105) at the Hanford Site in Washington State. Pacific Northwest National Laboratory (PNNL) contracted with Westinghouse Hanford Company (WHC) to provide sampling devices and analyze samples for inorganic and organic analytes collected from the tank headspace and ambient air near the tank. The analytical work was performed by the PNNL Vapor Analytical Laboratory (VAL) by the Tank Vapor Characterization Project. Work performed was based on a sample and analysis plan (SAP) prepared by WHC. The SAP provided job-specific instructions for samples, analyses, and reporting. The SAP for this sample job was open-quotes Vapor Sampling and Analysis Planclose quotes, and the sample job was designated S5047. Samples were collected by WHC on July 26, 1995, using the Vapor Sampling System (VSS), a truck-based sampling method using a heated probe inserted into the tank headspace

Phenotypic and genotypic characterization of Thai isolates of Plasmodium falciparum after an artemisinin resistance containment project.

Science.gov (United States)

Thita, Thunyapit; Jadsri, Pimrat; Thamkhantho, Jarupatr; Ruang-Areerate, Toon; Suwandittakul, Nantana; Sitthichot, Naruemon; Mahotorn, Kittiya; Tan-Ariya, Peerapan; Mungthin, Mathirut

2018-05-15

In Thailand, artemisinin-based combination therapy (ACT) has been used to treat uncomplicated falciparum malaria since 1995. Unfortunately, artemisinin resistance has been reported from Thailand and other Southeast Asian countries since 2003. Malarone ® , a combination of atovaquone-proguanil (ATQ-PG), has been used to cease artemisinin pressure in some areas along Thai-Cambodia border, as part of an artemisinin resistance containment project since 2009. This study aimed to determine genotypes and phenotypes of Plasmodium falciparum isolates collected from the Thai-Cambodia border after the artemisinin resistance containment project compared with those collected before. One hundred and nine of P. falciparum isolates collected from Thai-Cambodia border from Chanthaburi and Trat provinces during 1988-2016 were used in this study. Of these, 58 isolates were collected after the containment. These parasite isolates were characterized for in vitro antimalarial sensitivities including chloroquine (CQ), quinine (QN), mefloquine (MQ), piperaquine (PPQ), artesunate (AS), dihydroartemisinin (DHA), ATQ and PG and genetic markers for drug resistance including the Kelch13 (k13), Plasmodium falciparum chloroquine resistance transporter (pfcrt), P. falciparum multidrug resistance 1 (pfmdr1) and cytochrome b (cytb) genes. Mean CQ, QN, MQ, PPQ and AS IC 50 s of the parasite isolates collected from 2009 to 2016 exhibited significantly higher than those of parasites collected before 2009. Approximately 57% exhibited in vitro MQ resistance. Approximately 94% of the isolates collected from 2009 to 2016 contained the pfmdr1 184F allele. Mutations of the k13 gene were detected in approximately 90% of the parasites collected from 2009 to 2016 which were significantly higher than the parasite isolates collected before. No ATQ-resistant genotype and phenotype of P. falciparum were found among the isolates collected after the containment project. Although the containment project had been

Characterization of projected DWPF glasses heat treated to simulate canister centerline cooling

International Nuclear Information System (INIS)

Marra, S.L.; Jantzen, C.M.

1992-05-01

Liquid high-level nuclear waste will be immobilized at the Savannah River Site (SRS) by vitrification in borosilicate glass. The glass will be produced and poured into stainless steel canisters in the Defense Waste Processing Facility (DWPF). Eventually these canistered waste forms will be sent to a geologic repository for final disposal. In order to assure acceptability by the repository, the Department of Energy has defined requirements which DWPF canistered waste forms must meet. These requirements are the Waste Acceptance Preliminary Specifications (WAPS). The WAPS require DWPF to identify the crystalline phases expected to be present in the final glass product. Knowledge of the thermal history of the borosilicate glass during filling and cooldown of the canister is necessary to determine the amount and type of crystalline phases present in the final glass product. Glass samples of seven projected DWPF compositions were cooled following the same temperature profile as that of glass at the centerline of the full-scale DWPF canister. The glasses were characterized by x-ray diffraction and scanning electron microscopy to identify the crystalline phases present The volume percents of each crystalline phase present were determined by quantitative x-ray diffraction. The Product Consistency Test (PCI) was used to determine the durability of the heat-treated glasses

The Collaborative Project Owner in Theory and Practice

DEFF Research Database (Denmark)

Frederiksen, Signe Hedeboe; Svejvig, Per

is complex characterized by information asymmetry and potential mistrust. Studies also show that top managers may actually be reluctant to play an active role during the project life cycle. In this paper, we examine how the involvement of project owners unfolds in the project process, when given explicit...

Characterization of federated oil fractions used for the PTAC project to study the petroleum fraction-specific toxicity to soils

International Nuclear Information System (INIS)

Wang, Z.; Jokuty, P.; Fingas, M.; Sigouin, L.

2001-01-01

In 1998, the Petroleum Technology Alliance of Canada (PTAC) and the Canadian Association of Petroleum Producers (CAPP) launched an important research project for the oil and gas industry entitled A Fraction-Specific Toxicity and Derivation of Recommended Soil Quality Guidelines for Crude Oil in Agricultural Soils. The objective was to generate useful and relevant data that could be used to develop soil quality guidelines for petroleum hydrocarbon residuals in agricultural soils. The oil used in the study was Federated crude oil which was fractionated into four fractions using a distillation method. The fraction-based approach was used to support ecologically-relevant, risk-based, soil quality criteria for the protection of environmental health. This paper presented the nominal carbon number and boiling point ranges of these fractions and described the distillation procedures for producing the fractions from the Federated crude oil. The paper also presented the detailed chemical characterization results of each distillation fraction. The toxicity of the crude oil mixture to plants and soil invertebrates was also assessed using standardized toxicity tests. Tests were also conducted to assess the toxicity of fractions of the crude oil and the toxic interactions of the fractions responsible for a significant proportion of the toxicity. Phase 2 of the project was designed to determine if hydrocarbon residuals exceeding 1000 μg/g and weathered for short or long periods of time, posed an ecotoxicological risk or impaired soil physical, chemical and biological properties such that productivity of the agricultural soils was compromised. The objectives of phase 2 were to amend differently textured soils in field plots at sites with fresh crude oil and to monitor their toxicity to terrestrial organisms using laboratory-based ecotoxicity tests. The study showed that because of the nature of the chemical composition of hydrocarbons (such as boiling points, nominal carbon range

Sähköinen asiointi tavaraliikennelupahakemuksen toimintaprosessissa

OpenAIRE

Laitakari, Pauliina

2012-01-01

Korvausta vastaan suoritettavaan tavarankuljetukseen tarvitaan voimassaoleva tavaraliikennelupa, jonka myöntää Elinkeino-, liikenne- ja ympäristökeskus. Opinnäytetyön toimeksiantajana on Pohjois-Pohjanmaan Elinkeino-, liikenne- ja ympäristökeskus. Työ tehdään liikenne ja infrastruktuuri –vastuualueen lupapalvelut-yksikköön. Opinnäytetyön aiheena on sähköinen asiointi tavaraliikenneluvan toimintaprosessissa. Lakimuutosten myötä lisääntyneet työtehtävät vaativat toiminnan tehostamista ja tämän ...

Farkkujen elinkaari

OpenAIRE

Järvinen, Janica

2011-01-01

Tässä opinnäytetyössä tutkitaan farkkujen elinkaarta ja siihen liittyviä ympäristönäkökohtia. Tutkimuksen kohteena on myös M.A.S.I Company Oy:n toiminnan soveltuminen ympäristömerkinnän kriteereiden mukaiseksi. Tutkimus tehtiin kyselyiden, haastatteluiden, keskustelujen ja teoreettisen tutkimuksen avulla. Opinnäytetyön teoriaosuudessa tarkastellaan aluksi puuvillaa kuituna ja sen tuotantoa aina viljelystä kankaan kudontaan. Työssä edetään puuvillakankaiden esikäsittelyosiosta farkkujen va...

Vihreiden arvojen vaikutus matkailijoiden ostopäätökseen Rukan ja Kuusamon alueella

OpenAIRE

Mustonen, Tiia

2011-01-01

Opinnäytetyöni tavoitteena oli selvittää vaikuttavatko vihreät arvot Rukan ja Kuusamon alueen matkailijoiden ostopäätökseen. Tekeekö siis ympäristömerkki tuotteesta houkuttelevamman kuin tavanomaisesta tuotteesta? Viitekehys koostuu kahdesta osa-alueesta, matkailusta ja ostokäyttäytymisestä. Tarkempia aihekokonaisuuksia ovat matkailun vaikutukset, kestävä kehitys ja ympäristömerkit. Ostokäyttäytymisessä olen keskittynyt erityisesti matkailualan kuluttajakäyttäytymiseen. Työni on määr...

Data Qualification Report: Precipitation Chloride Data for Use on the Yucca Mountain Project

International Nuclear Information System (INIS)

C. Wilson

2000-01-01

The data covered by this qualification report have been cited in analysis/model reports (AMRs) to support the Site Recommendation in determining the suitability of Yucca Mountain as a repository for high level nuclear waste. Those analyses cited both qualified and unqualified hydrochemical data. This report evaluates unqualified precipitation chloride data based on the pedigree of the data and within the context of supporting analyses on the Yucca Mountain Project (YMP). The following AMRs use the unqualified chloride data considered in this report: (1) AMR S0040, ''Geochemical and Isotopic Constraints on Groundwater Flow Directions, Mixing and Recharge at Yucca Mountain'' (ANL-NBS-HS-000021) (Kwicklis 2000)--an analysis of groundwater recharge rates, flow directions and velocities, and mixing proportions of water from different source areas based on groundwater geochemical and isotopic data. (2) AMR U0085, ''Analysis of Geochemical Data for the Unsaturated Zone'' (ANL-NBS-HS-000017) (Fabryka-Martin 2000)--identifies fluid geochemical parameters for the unsaturated zone, local precipitation, and surface water; discusses the occurrence and origins of fracture minerals; and presents a thermal history of the unsaturated zone. These data are being evaluated for inclusion in technical products to include AMRs and Process Modeling Reports (PMRs) that support the Site Recommendation and that may also be used to support the License Application. A finding that the precipitation chloride data are qualified means that the data are adequate for generalized use and can be appropriately used in a wide variety of applications, so long as consideration is given to limitations on the accuracy, precision and representativeness of the data for an intended use in a technical product

Human Genome Project

Energy Technology Data Exchange (ETDEWEB)

Block, S. [The MITRE Corporation, McLean, VA (US). JASON Program Office; Cornwall, J. [The MITRE Corporation, McLean, VA (US). JASON Program Office; Dally, W. [The MITRE Corporation, McLean, VA (US). JASON Program Office; Dyson, F. [The MITRE Corporation, McLean, VA (US). JASON Program Office; Fortson, N. [The MITRE Corporation, McLean, VA (US). JASON Program Office; Joyce, G. [The MITRE Corporation, McLean, VA (US). JASON Program Office; Kimble, H. J. [The MITRE Corporation, McLean, VA (US). JASON Program Office; Lewis, N. [The MITRE Corporation, McLean, VA (US). JASON Program Office; Max, C. [The MITRE Corporation, McLean, VA (US). JASON Program Office; Prince, T. [The MITRE Corporation, McLean, VA (US). JASON Program Office; Schwitters, R. [The MITRE Corporation, McLean, VA (US). JASON Program Office; Weinberger, P. [The MITRE Corporation, McLean, VA (US). JASON Program Office; Woodin, W. H. [The MITRE Corporation, McLean, VA (US). JASON Program Office

1998-01-04

The study reviews Department of Energy supported aspects of the United States Human Genome Project, the joint National Institutes of Health/Department of Energy program to characterize all human genetic material, to discover the set of human genes, and to render them accessible for further biological study. The study concentrates on issues of technology, quality assurance/control, and informatics relevant to current effort on the genome project and needs beyond it. Recommendations are presented on areas of the genome program that are of particular interest to and supported by the Department of Energy.

Site characterization report for the basalt waste isolation project. Volume III

International Nuclear Information System (INIS)

1982-11-01

The reference location for a repository in basalt for the terminal storage of nuclear wastes on the Hanford Site and the candidate horizons within this reference repository location have been identified and the preliminary characterization work in support of the site screening process has been completed. Fifteen technical questions regarding the qualification of the site were identified to be addressed during the detailed site characterization phase of the US Department of Energy-National Waste Terminal Storage Program site selection process. Resolution of these questions will be provided in the final site characterization progress report, currently planned to be issued in 1987, and in the safety analysis report to be submitted with the License Application. The additional information needed to resolve these questions and the plans for obtaining the information have been identified. This Site Characterization Report documents the results of the site screening process, the preliminary site characterization data, the technical issues that need to be addressed, and the plans for resolving these issues. Volume 3 contains chapters 13 through 19: site issues and plans; geoengineering and repository design issues and plans; waste package and site geochemistry issues and plans; performance-assessment issues and plans; site characterization program; quality assurance; and identification of alternate sites

Natural analogue synthesis report, TDR-NBS-GS-000027 REV00 ICN02

International Nuclear Information System (INIS)

Simmons, A.; Nieder-Westermann, G.; Stuckless, J.; Dobson, P.; Unger, A.J.A.; Kwicklis, E.; Lichtner, P.; Carey, B.; Wolde, G.; Murrel, M.; Kneafsey, T.J.; Meijer, A.; Faybishenko, B.

2002-01-01

The purpose of this report is to present analogue studies and literature reviews designed to provide qualitative and quantitative information to test and provide added confidence in process models abstracted for performance assessment (PA) and model predictions pertinent to PA. This report provides updates to studies presented in the Yucca Mountain Site Description (CRWMS M and O 2000 [151945], Section 13) and new examples gleaned from the literature, along with results of quantitative studies conducted specifically for the Yucca Mountain Site Characterization Project (YMP). The intent of the natural analogue studies was to collect corroborative evidence from analogues to demonstrate additional understanding of processes expected to occur during postclosure at a potential Yucca Mountain repository. The report focuses on key processes by providing observations and analyses of natural and anthropogenic (human-induced) systems to improve understanding and confidence in the operation of these processes under conditions similar to those that could occur in a nuclear waste repository. The process models include those that represent both engineered and natural barrier processes. A second purpose of this report is to document the various applications of natural analogues to geologic repository programs, focusing primarily on the way analogues have been used by the YMP. This report is limited to providing support for PA in a confirmatory manner and to providing corroborative inputs for process modeling activities. Section 1.7 discusses additional limitations of this report. Key topics for this report are analogues to emplacement drift degradation, waste form degradation, waste package degradation, degradation of other materials proposed for the engineered barrier, seepage into drifts, radionuclide flow and transport in the unsaturated zone (UZ), analogues to coupled thermal-hydrologic-mechanical-chemical processes, saturated zone (SZ) transport, impact of radionuclide

Natural Analogue Synthesis Report

Energy Technology Data Exchange (ETDEWEB)

A. M. Simmons

2002-05-01

The purpose of this report is to present analogue studies and literature reviews designed to provide qualitative and quantitative information to test and provide added confidence in process models abstracted for performance assessment (PA) and model predictions pertinent to PA. This report provides updates to studies presented in the ''Yucca Mountain Site Description'' (CRWMS M and O 2000 [151945], Section 13) and new examples gleaned from the literature, along with results of quantitative studies conducted specifically for the Yucca Mountain Site Characterization Project (YMP). The intent of the natural analogue studies was to collect corroborative evidence from analogues to demonstrate additional understanding of processes expected to occur during postclosure at a potential Yucca Mountain repository. The report focuses on key processes by providing observations and analyses of natural and anthropogenic (human-induced) systems to improve understanding and confidence in the operation of these processes under conditions similar to those that could occur in a nuclear waste repository. The process models include those that represent both engineered and natural barrier processes. A second purpose of this report is to document the various applications of natural analogues to geologic repository programs, focusing primarily on the way analogues have been used by the YMP. This report is limited to providing support for PA in a confirmatory manner and to providing corroborative inputs for process modeling activities. Section 1.7 discusses additional limitations of this report. Key topics for this report are analogues to emplacement drift degradation, waste form degradation, waste package degradation, degradation of other materials proposed for the engineered barrier, seepage into drifts, radionuclide flow and transport in the unsaturated zone (UZ), analogues to coupled thermal-hydrologic-mechanical-chemical processes, saturated zone (SZ) transport

Natural analogue synthesis report, TDR-NBS-GS-000027 rev00 icn02

Energy Technology Data Exchange (ETDEWEB)

Simmons, A.; Nieder-Westermann, G.; Stuckless, J.; Dobson, P.; Unger, A.J.A.; Kwicklis, E.; Lichtner, P.; Carey, B.; Wolde, G.; Murrel,M.; Kneafsey, T.J.; Meijer, A.; Faybishenko, B.

2002-04-01

The purpose of this report is to present analogue studies and literature reviews designed to provide qualitative and quantitative information to test and provide added confidence in process models abstracted for performance assessment (PA) and model predictions pertinent to PA. This report provides updates to studies presented in the Yucca Mountain Site Description (CRWMS M&O 2000 [151945], Section 13) and new examples gleaned from the literature, along with results of quantitative studies conducted specifically for the Yucca Mountain Site Characterization Project (YMP). The intent of the natural analogue studies was to collect corroborative evidence from analogues to demonstrate additional understanding of processes expected to occur during postclosure at a potential Yucca Mountain repository. The report focuses on key processes by providing observations and analyses of natural and anthropogenic (human-induced) systems to improve understanding and confidence in the operation of these processes under conditions similar to those that could occur in a nuclear waste repository. The process models include those that represent both engineered and natural barrier processes. A second purpose of this report is to document the various applications of natural analogues to geologic repository programs, focusing primarily on the way analogues have been used by the YMP. This report is limited to providing support for PA in a confirmatory manner and to providing corroborative inputs for process modeling activities. Section 1.7 discusses additional limitations of this report. Key topics for this report are analogues to emplacement drift degradation, waste form degradation, waste package degradation, degradation of other materials proposed for the engineered barrier, seepage into drifts, radionuclide flow and transport in the unsaturated zone (UZ), analogues to coupled thermal-hydrologic-mechanical-chemical processes, saturated zone (SZ) transport, impact of radionuclide release

Progress report on pre-test calculations for the large block test

International Nuclear Information System (INIS)

Lee, K.H.

1995-01-01

The U.S. Department of Energy's (DOE) Yucca Mountain Site Characterization Project (YMP) is investigating the suitability of the Topopah Spring tuff in the thick vadose zone at Yucca Mountain, Nevada, as a host rock for permanent disposal of high-level radioactive waste. As part of the YMP, a group of field tests, referred to as the Large Block Test (LBT), will be conducted on a large electrically heated block of Topopah Spring tuff, isolated at Fran Ridge, Nevada Test Site. The block, which will be 3 x 3 m in horizontal dimensions and 4.5 m in height, will be heated by electrical heaters. The goals of the LBT axe to gain information on the coupled thermal-mechanical-hydrological-chemical processes active in the near-field environment of a repository; to provide field data for testing and calibrating models; and to help the development of measurement systems and techniques. This progress report presents results of on-going numerical modeling calculations carried out in support of the LBT design. An equivalent continuum model with an upper boundary temperature of 60 degrees C was used to simulate the hydrothermal response of the block to heating over a one-year period. The total heating power was started at 1500 W and later reduced to maintain an approximately uniform temperature of 138-140 degrees C. For a homogeneous bulk permeability case, the results show the formation of a distinct dry-out zone in and around the heater plane, and well-developed condensation zones above and below the heater plane. For a heterogeneous permeability distribution, the condensation zone above the heater plane was not well developed. This difference in results suggests that water saturation changes might be sensitive to changes in bulk permeability distribution. Rock temperatures were almost unaffected by permeability distribution. Heat flow was dominated by conduction. No liquid flow through the top of the block was predicted

Final project report for NEET pulsed ion beam project

Energy Technology Data Exchange (ETDEWEB)

Kucheyev, S. O. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2018-01-11

The major goal of this project was to develop and demonstrate a novel experimental approach to access the dynamic regime of radiation damage formation in nuclear materials. In particular, the project exploited a pulsed-ion-beam method in order to gain insight into defect interaction dynamics by measuring effective defect interaction time constants and defect diffusion lengths. This project had the following four major objectives: (i) the demonstration of the pulsed ion beam method for a prototypical nuclear ceramic material, SiC; (ii) the evaluation of the robustness of the pulsed beam method from studies of defect generation rate effects; (iii) the measurement of the temperature dependence of defect dynamics and thermally activated defect-interaction processes by pulsed ion beam techniques; and (iv) the demonstration of alternative characterization techniques to study defect dynamics. As we describe below, all these objectives have been met.

Computer systems and software description for gas characterization system

International Nuclear Information System (INIS)

Vo, C.V.

1997-01-01

The Gas Characterization System Project was commissioned by TWRS management with funding from TWRS Safety, on December 1, 1994. The project objective is to establish an instrumentation system to measure flammable gas concentrations in the vapor space of selected watch list tanks, starting with tank AN-105 and AW-101. Data collected by this system is meant to support first tank characterization, then tank safety. System design is premised upon Characterization rather than mitigation, therefore redundancy is not required

Management system information of characterization of the dismantling project of Jose Cabrera; Sistema de Gestion de la informacion de caracterizacion del proyecto de desmantelamiento de la CN Jose Cabrera

Energy Technology Data Exchange (ETDEWEB)

Gimeno Blesa, M. E.; Martin Palomo, N.; Gomez Rodriguez, C. A.

2011-07-01

In the proposed dismantling and decommissioning of the Jose Cabrera NPP is designed and implemented a database of physical and radiological inventory, which provides a powerful tool to optimize the storage, monitoring and control of the characterization data. The database is a useful and reliable management system characterization information that facilitates access and information processing, and ensures their integrity and traceability along of the dismantling project.

Characterizing near-surface CO2 conditions before injection - Perspectives from a CCS project in the Illinois Basin, USA

Science.gov (United States)

Locke, R.A.; Krapac, I.G.; Lewicki, J.L.; Curtis-Robinson, E.

2011-01-01

The Midwest Geological Sequestration Consortium is conducting a large-scale carbon capture and storage (CCS) project in Decatur, Illinois, USA to demonstrate the ability of a deep saline formation to store one million tonnes of carbon dioxide (CO2) from an ethanol facility. Beginning in early 2011, CO2 will be injected at a rate of 1,000 tonnes/day for three years into the Mount Simon Sandstone at a depth of approximately 2,100 meters. An extensive Monitoring, Verification, and Accounting (MVA) program has been undertaken for the Illinois Basin Decatur Project (IBDP) and is focused on the 0.65 km2 project site. Goals include establishing baseline conditions to evaluate potential impacts from CO2 injection, demonstrating that project activities are protective of human health and the environment, and providing an accurate accounting of stored CO2. MVA efforts are being conducted pre-, during, and post- CO2 injection. Soil and net CO2 flux monitoring has been conducted for more than one year to characterize near-surface CO2 conditions. More than 2,200 soil CO2 flux measurements have been manually collected from a network of 118 soil rings since June 2009. Three ring types have been evaluated to determine which type may be the most effective in detecting potential CO 2 leakage. Bare soil, shallow-depth rings were driven 8 cm into the ground and were prepared to minimize surface vegetation in and near the rings. Bare soil, deep-depth rings were prepared similarly, but were driven 46 cm. Natural-vegetation, shallow-depth rings were driven 8 cm and are most representative of typical vegetation conditions. Bare-soil, shallow-depth rings had the smallest observed mean flux (1.78 ??mol m-2 s-1) versus natural-vegetation, shallow-depth rings (3.38 ??mol m-2 s-1). Current data suggest bare ring types would be more sensitive to small CO2 leak signatures than natural ring types because of higher signal to noise ratios. An eddy covariance (EC) system has been in use since June

Virtual environmental applications for buried waste characterization technology evaluation report

International Nuclear Information System (INIS)

1995-05-01

The project, Virtual Environment Applications for Buried Waste Characterization, was initiated in the Buried Waste Integrated Demonstration Program in fiscal year 1994. This project is a research and development effort that supports the remediation of buried waste by identifying and examining the issues, needs, and feasibility of creating virtual environments using available characterization and other data. This document describes the progress and results from this project during the past year

Virtual environmental applications for buried waste characterization technology evaluation report

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-05-01

The project, Virtual Environment Applications for Buried Waste Characterization, was initiated in the Buried Waste Integrated Demonstration Program in fiscal year 1994. This project is a research and development effort that supports the remediation of buried waste by identifying and examining the issues, needs, and feasibility of creating virtual environments using available characterization and other data. This document describes the progress and results from this project during the past year.

FY17 Status Report on the Computing Systems for the Yucca Mountain Project TSPA-LA Models.

Energy Technology Data Exchange (ETDEWEB)

Appel, Gordon John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hadgu, Teklu [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Appel, Gordon John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Reynolds, John Thomas [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Garland, Jason P. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-10-01

Sandia National Laboratories (SNL) continued evaluation of total system performance assessment (TSPA) computing systems for the previously considered Yucca Mountain Project (YMP). This was done to maintain the operational readiness of the computing infrastructure (computer hardware and software) and knowledge capability for total system performance assessment (TSPA) type analysis, as directed by the National Nuclear Security Administration (NNSA), DOE 2010. This work is a continuation of the ongoing readiness evaluation reported in Lee and Hadgu (2014), Hadgu et al. (2015) and Hadgu and Appel (2016). The TSPA computing hardware (CL2014) and storage system described in Hadgu et al. (2015) were used for the current analysis. One floating license of GoldSim with Versions 9.60.300, 10.5, 11.1 and 12.0 was installed on the cluster head node, and its distributed processing capability was mapped on the cluster processors. Other supporting software were tested and installed to support the TSPA- type analysis on the server cluster. The current tasks included preliminary upgrade of the TSPA-LA from Version 9.60.300 to the latest version 12.0 and address DLL-related issues observed in the FY16 work. The model upgrade task successfully converted the Nominal Modeling case to GoldSim Versions 11.1/12. Conversions of the rest of the TSPA models were also attempted but program and operational difficulties precluded this. Upgrade of the remaining of the modeling cases and distributed processing tasks is expected to continue. The 2014 server cluster and supporting software systems are fully operational to support TSPA-LA type analysis.

Managing externally financed projects: the Integrated Primary Health Care Project in Bolivia.

Science.gov (United States)

Homedes, N

2001-12-01

Bolivia is one of the poorest countries in Latin America. Health indicators are very poor, communicable diseases are prevalent and, coupled with malnutrition, remain the major killers of children under 5 years old. The Integrated Primary Health Care Project (PROISS) was a US$39 million project executed by the Ministry of Health (MOH), 50% financed by the World Bank and aimed at improving primary health care in the four largest Bolivian municipalities. The implementation of the project started in 1990 and ended in 1997. During implementation it went through three distinct phases: Phase 1 (1990-94) was a period characterized by conflict and confusion; Phase 2 (1995-mid-1996) documented major improvements in coverage and service quality; and Phase 3 (mid-1996-97) witnessed the decline of the project. This paper explores the factors that contributed to the success and the decline of the project, draws lessons for project managers and international agencies involved in the definition and implementation of social sector projects, and discusses the unlikelihood that externally financed projects can have a sustainable impact on the development of the health sector of recipient countries.

Final Hanford Site Transuranic (TRU) Waste Characterization Quality Assurance Project Plan

International Nuclear Information System (INIS)

GREAGER, T.M.

1999-01-01

The Transuranic Waste Characterization Quality Assurance Program Plan required each US Department of Energy (DOE) site that characterizes transuranic waste to be sent the Waste Isolation Pilot Plan that addresses applicable requirements specified in the QAPP

Myoglobin structure and function: A multiweek biochemistry laboratory project.

Science.gov (United States)

Silverstein, Todd P; Kirk, Sarah R; Meyer, Scott C; Holman, Karen L McFarlane

2015-01-01

We have developed a multiweek laboratory project in which students isolate myoglobin and characterize its structure, function, and redox state. The important laboratory techniques covered in this project include size-exclusion chromatography, electrophoresis, spectrophotometric titration, and FTIR spectroscopy. Regarding protein structure, students work with computer modeling and visualization of myoglobin and its homologues, after which they spectroscopically characterize its thermal denaturation. Students also study protein function (ligand binding equilibrium) and are instructed on topics in data analysis (calibration curves, nonlinear vs. linear regression). This upper division biochemistry laboratory project is a challenging and rewarding one that not only exposes students to a wide variety of important biochemical laboratory techniques but also ties those techniques together to work with a single readily available and easily characterized protein, myoglobin. © 2015 International Union of Biochemistry and Molecular Biology.

Site characterization report for the basalt waste isolation project. Volume II

Energy Technology Data Exchange (ETDEWEB)

None

1982-11-01

The reference location for a repository in basalt for the terminal storage of nuclear wastes on the Hanford Site and the candidate horizons within this reference repository location have been identified and the preliminary characterization work in support of the site screening process has been completed. Fifteen technical questions regarding the qualification of the site were identified to be addressed during the detailed site characterization phase of the US Department of Energy-National Waste Terminal Storage Program site selection process. Resolution of these questions will be provided in the final site characterization progress report, currently planned to be issued in 1987, and in the safety analysis report to be submitted with the License Application. The additional information needed to resolve these questions and the plans for obtaining the information have been identified. This Site Characterization Report documents the results of the site screening process, the preliminary site characterization data, the technical issues that need to be addressed, and the plans for resolving these issues. Volume 2 contains chapters 6 through 12: geochemistry; surface hydrology; climatology, meteorology, and air quality; environmental, land-use, and socioeconomic characteristics; repository design; waste package; and performance assessment.

Site characterization report for the basalt waste isolation project. Volume II

International Nuclear Information System (INIS)

1982-11-01

The reference location for a repository in basalt for the terminal storage of nuclear wastes on the Hanford Site and the candidate horizons within this reference repository location have been identified and the preliminary characterization work in support of the site screening process has been completed. Fifteen technical questions regarding the qualification of the site were identified to be addressed during the detailed site characterization phase of the US Department of Energy-National Waste Terminal Storage Program site selection process. Resolution of these questions will be provided in the final site characterization progress report, currently planned to be issued in 1987, and in the safety analysis report to be submitted with the License Application. The additional information needed to resolve these questions and the plans for obtaining the information have been identified. This Site Characterization Report documents the results of the site screening process, the preliminary site characterization data, the technical issues that need to be addressed, and the plans for resolving these issues. Volume 2 contains chapters 6 through 12: geochemistry; surface hydrology; climatology, meteorology, and air quality; environmental, land-use, and socioeconomic characteristics; repository design; waste package; and performance assessment

Yucca Mountain biological resources monitoring program; Annual report FY92

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-02-01

The US Department of Energy (DOE) is required by the Nuclear Waste Policy Act of 1982 (as amended in 1987) to study and characterize Yucca Mountain as a potential site for a geologic repository for high-level nuclear waste. During site characterization, the DOE will conduct a variety of geotechnical, geochemical, geological, and hydrological studies to determine the suitability of Yucca Mountain as a potential repository. To ensure that site characterization activities (SCA) do not adversely affect the environment at Yucca Mountain, an environmental program has been implemented to monitor and mitigate potential impacts and ensure activities comply with applicable environmental regulations. This report describes the activities and accomplishments of EG&G Energy Measurements, Inc. (EG&G/EM) during fiscal year 1992 (FY92) for six program areas within the Terrestrial Ecosystem component of the YMP environmental program. The six program areas are Site Characterization Effects, Desert Tortoises, Habitat Reclamation, Monitoring and Mitigation, Radiological Monitoring, and Biological Support.

Yucca Mountain biological resources monitoring program

International Nuclear Information System (INIS)

1993-02-01

The US Department of Energy (DOE) is required by the Nuclear Waste Policy Act of 1982 (as amended in 1987) to study and characterize Yucca Mountain as a potential site for a geologic repository for high-level nuclear waste. During site characterization, the DOE will conduct a variety of geotechnical, geochemical, geological, and hydrological studies to determine the suitability of Yucca Mountain as a potential repository. To ensure that site characterization activities (SCA) do not adversely affect the environment at Yucca Mountain, an environmental program has been implemented to monitor and mitigate potential impacts and ensure activities comply with applicable environmental regulations. This report describes the activities and accomplishments of EG ampersand G Energy Measurements, Inc. (EG ampersand G/EM) during fiscal year 1992 (FY92) for six program areas within the Terrestrial Ecosystem component of the YMP environmental program. The six program areas are Site Characterization Effects, Desert Tortoises, Habitat Reclamation, Monitoring and Mitigation, Radiological Monitoring, and Biological Support

WORKSHOP ON DEVELOPMENT OF RADIONUCLIDE GETTERS FOR THE YUCCA MOUNTAIN WASTE REPOSITORY: PROCEEDINGS

International Nuclear Information System (INIS)

K.C. Holt

2006-01-01

One of the important that the U.S. Department of Energy (DOE) is currently undertaking is the development of a high-level nuclear waste repository to be located at Yucca Mountain, Nevada. Concern is generated by the Yucca Mountain Project (YMP) is due to potential releases as groundwater contamination, as described in the Total System Performance Assessment (TSPA). The dose to an off-site individual using this groundwater for drinking and irrigation is dominated by four radionuclides: Tc-99, I-127, Np-237, and U-238. Ideally, this dose would be limited to a single radionuclide, U-238; in other words, YMP would resemble a uranium ore body, a common geologic feature in the Western U.S. For this reason and because of uncertainties in the behavior of Tc-99, I-127, and Np-237, it would be helpful to limit the amount of Tc, I, and Np leaving the repository, which would greatly increase the confidence in the long-term performance of YMP. An approach to limiting the migration of Tc, I, and Np that is complementary to the existing YMP repository design plans is to employ sequestering agents or ''getters'' for these radionuclides such that their migration is greatly hindered, thus decreasing the amount of radionuclide leaving the repository. Development of such getters presents a number of significant challenges. The getter must have a high affinity and high selectivity for the radionuclide in question since there is approximately a 20- to 50-fold excess of other fission products and a 1000-fold excess of uranium in addition to the ions present in the groundwater. An even greater challenge is that the getters must function over a period greater than the half-life of the radionuclide (greater than 5 half-lives would be ideal). Typically, materials with a high affinity for Tc, I, or Np are not sufficiently durable. For example, strong-base ion exchange resins have a very high affinity for TcO 4 - but are not expected to be durable. On the other hand, durable materials, such as

WORKSHOP ON DEVELOPMENT OF RADIONUCLIDE GETTERS FOR THE YUCCA MOUNTAIN WASTE REPOSITORY

Energy Technology Data Exchange (ETDEWEB)

K.C. Holt

2006-03-13

One of the important that the U.S. Department of Energy (DOE) is currently undertaking is the development of a high-level nuclear waste repository to be located at Yucca Mountain, Nevada. Concern is generated by the Yucca Mountain Project (YMP) is due to potential releases as groundwater contamination, as described in the Total System Performance Assessment (TSPA). The dose to an off-site individual using this groundwater for drinking and irrigation is dominated by four radionuclides: Tc-99, I-127, Np-237, and U-238. Ideally, this dose would be limited to a single radionuclide, U-238; in other words, YMP would resemble a uranium ore body, a common geologic feature in the Western U.S. For this reason and because of uncertainties in the behavior of Tc-99, I-127, and Np-237, it would be helpful to limit the amount of Tc, I, and Np leaving the repository, which would greatly increase the confidence in the long-term performance of YMP. An approach to limiting the migration of Tc, I, and Np that is complementary to the existing YMP repository design plans is to employ sequestering agents or ''getters'' for these radionuclides such that their migration is greatly hindered, thus decreasing the amount of radionuclide leaving the repository. Development of such getters presents a number of significant challenges. The getter must have a high affinity and high selectivity for the radionuclide in question since there is approximately a 20- to 50-fold excess of other fission products and a 1000-fold excess of uranium in addition to the ions present in the groundwater. An even greater challenge is that the getters must function over a period greater than the half-life of the radionuclide (greater than 5 half-lives would be ideal). Typically, materials with a high affinity for Tc, I, or Np are not sufficiently durable. For example, strong-base ion exchange resins have a very high affinity for TcO{sub 4}{sup -} but are not expected to be durable. On the other

Implementing information systems with project teams using ethnographic-action research

NARCIS (Netherlands)

Hartmann, Timo; Fischer, Martin; Haymaker, John

2009-01-01

Architecture, engineering, and construction (AEC) projects are characterized by a large variation in requirements and work routines. Therefore, it is difficult to develop and implement information systems to support projects. To address these challenges, this paper presents a project-centric

Preparation and Characterization of Myosin Proteins.

Science.gov (United States)

Caldwell, Elizabeth; Eftink, Maurice R.

1985-01-01

Students complete five experimental projects at the end of a senior-level biochemistry course which involves the isolation and characterization of myosin and its water-soluble subfragments. Procedures used and results obtained are provided for such projects as viscosity and ATPase measurements and gel electrophoresis experiments. (JN)

Polarization Characterization of a Multi-Moded Feed Structure

Data.gov (United States)

National Aeronautics and Space Administration — The Polarization Characterization of a Multi-Moded Feed Structure projects characterize the polarization response of a multi-moded feed horn as an innovative...

Characterizing Process-Based River and Floodplain Restoration Projects on Federal Lands in Oregon, and Assessing Catalysts and Barriers to Implementation

Science.gov (United States)

Bianco, S.; Jones, J. A.; Gosnell, H.

2017-12-01

Process-based restoration, a new approach to river and floodplain management, is being implemented on federal lands across Oregon. These management efforts are aimed at promoting key physical processes in order to improve river ecological function, create diverse habitat, and increase biological productivity for ESA-listed bull trout and spring Chinook salmon. Although the practice is being disseminated across the Pacific Northwest, it remains unclear what is driving aquatic and riparian ecosystem restoration towards this process-based approach and away from form-based methods such as Rosgen's Natural Channel Design. The technical aspects of process-based restoration have been described in the literature (ex. Beechie et al. 2010), but little is known about the practice from a social science perspective, and few case studies exist to assess the impact of these efforts. We combine semi-structured qualitative interviews with management experts and photogrammetric analysis to better understand how complex social processes and changing ideas about aquatic ecosystems are manifesting on the ground in federal land management. This study characterizes process-based river and floodplain restoration projects on federal lands in Oregon, and identifies catalysts and barriers to its implementation. The Deer Creek Floodplain Enhancement project serves as a case study for photogrammetric analysis. To characterize long-term changes at Deer Creek, geomorphic features were mapped and classified using orthoimage mosaics developed from a time series of historic aerial photographs dating back to 1954. 3D Digital Elevation Models (3D-DEMs) were created of portions of the modified sections of Deer Creek and its floodplain immediately before and after restoration using drone-captured aerial photography and a photogrammetric technique called Structure from Motion. These 3D-DEMs have enabled extraction of first-order geomorphic variables to compare pre- and post-project conditions. This

Modeling needs assessment for Hanford Tank Farm Operations. Vadose Zone Characterization Project at the Hanford Tank Farms

International Nuclear Information System (INIS)

1996-04-01

This report presents the results of a modeling-needs assessment conducted for Tank Farm Operations at the Hanford Site. The goal of this project is to integrate geophysical logging and subsurface transport modeling into a broader decision-based framework that will be made available to guide Tank Farm Operations in implementing future modeling studies. In support of this goal, previous subsurface transport modeling studies were reviewed, and stakeholder surveys and interviews were completed (1) to identify regulatory, stakeholder, and Native American concerns and the impacts of these concerns on Tank Farm Operations, (2) to identify technical constraints that impact site characterization and modeling efforts, and (3) to assess how subsurface transport modeling can best be used to support regulatory, stakeholder, Native American, and Tank Farm Operations needs. This report is organized into six sections. Following an introduction, Section 2.0 discusses background issues that relate to Tank Farm Operations. Section 3.0 summarizes the technical approach used to appraise the status of modeling and supporting characterization. Section 4.0 presents a detailed description of how the technical approach was implemented. Section 5.0 identifies findings and observations that relate to implementation of numerical modeling, and Section 6.0 presents recommendations for future activities

An international peer review of the biosphere modelling programme of the US Department of Energy's Yucca mountain site characterization project. Report of the IAEA International Review Team

International Nuclear Information System (INIS)

2001-04-01

The United States Department of Energy (DOE) has a project for characterizing the site of a facility for disposing of radioactive waste located at Yucca Mountain Nevada, USA (the Yucca Mountain Site Characterization Project). This Project has developed an approach for assessing the future potential impact of any releases of radionuclides to the biosphere from a potential disposal facility sited at Yucca Mountain The DOE requested the International Atomic Energy Agency (IAEA) to organize an independent international expert review of the assessment methodology being used in its biosphere modelling programme. The IAEA accepted the request in the context of its statutory obligation to provide for the application of its established international standards of safety for the protection of health, at the request of a State, to any of that State's activities in the field of atomic energy. The terms of reference of the peer review were to review the biosphere assessment methodology being used for the total system performance assessment of the potential disposal facility. The main purpose was to analyze critically the proposed rationale and methodology and to identify consistencies and inconsistencies between methods being used in the frame of the Project and those established in international standards or in international programmes such as the IAEA's Biosphere Modelling and Assessment Programme (BIOMASS). This report presents the consensus view of the international experts convened by the IAEA for carrying out the review

1995 project of the year Hanford Environmental compliance project nomination

Energy Technology Data Exchange (ETDEWEB)

Kelly, J.R.

1996-02-01

The completion of the Hanford Environmental Compliance (HEC) Project in December 1995 brought to a successful close a long line of major contributions to environmental cleanup. Not since the early days of the Hanford Site during and shortly after World War 11 had such a large group of diverse construction activities, with a common goal, been performed at Hanford. Key to this success was the unique combination of 14 subprojects under the HEC Project which afforded the flexibility to address evolving subproject requirements. This strategy resulted in the accomplishment of the HEC Project stakeholders` objectives on an aggressive schedule, at a $33 million cost savings to the customer. The primary objectives of the HEC Project were to upgrade selected Hanford Site facilities and systems to bring them into compliance with current environmental standards and regulations. The HEC Project contributed significantly towards the Hanford site compliance with Clean Water Act, Resource Conservation and Recovery Act (RCRA) and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requirements. It provided, in part, those construction activities required to comply with those requirements in the areas of liquid and solid waste treatment and disposal, waste characterization, and groundwater monitoring.

1995 project of the year Hanford Environmental compliance project nomination

International Nuclear Information System (INIS)

Kelly, J.R.

1996-02-01

The completion of the Hanford Environmental Compliance (HEC) Project in December 1995 brought to a successful close a long line of major contributions to environmental cleanup. Not since the early days of the Hanford Site during and shortly after World War 11 had such a large group of diverse construction activities, with a common goal, been performed at Hanford. Key to this success was the unique combination of 14 subprojects under the HEC Project which afforded the flexibility to address evolving subproject requirements. This strategy resulted in the accomplishment of the HEC Project stakeholders' objectives on an aggressive schedule, at a $33 million cost savings to the customer. The primary objectives of the HEC Project were to upgrade selected Hanford Site facilities and systems to bring them into compliance with current environmental standards and regulations. The HEC Project contributed significantly towards the Hanford site compliance with Clean Water Act, Resource Conservation and Recovery Act (RCRA) and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) requirements. It provided, in part, those construction activities required to comply with those requirements in the areas of liquid and solid waste treatment and disposal, waste characterization, and groundwater monitoring

Hotelliasiakkaiden suhtautuminen ekologisuuteen hotellipalveluissa : case Original Sokos Hotel Rikala

OpenAIRE

Laakkonen, Jenna

2015-01-01

Matkailualan jatkuva kasvaminen ja ihmisten ympäristötietoisuuden lisääntyminen vaativat majoitusalaa ekologisempiin toimintatapoihin. Majoitusliikkeillä onkin tärkeä rooli toimia edelläkävijöinä vastuullisuuden ja kestävän kehityksen mukaisesti, sillä luonnonvarojen käyttö on mittavaa suhteessa muuhun palvelualaan. Ympäristöystävälli-syyden arvostuksen noustessa yritykset ovat huomanneet ekologisuuden tuovan säästöjen lisäksi merkittävää kil-pailuetua. Tämän kvantitatiivisen opinnäytetyö...

Overview of the current CRWMS repository design

International Nuclear Information System (INIS)

Daniel, R.B.; Teraoka, G.M.

1998-01-01

This paper summarizes the current design for a potential geologic repository for spent fuels and high-level wastes at Yucca Mountain, Nevada. The objective of the paper is to present the key design features of the Mined Geologic Disposal System (MGDS) surface facilities and MGDS subsurface facilities. The paper describes the following: surface layout; waste handling operations design; subsurface design; and the underground transport and emplacement design. A more detailed presentation of key features is provided in the ''Reference design description for a geologic repository'' which is located on the YMP Homepage at www.ymp.gov

CODESYS-oppimisympäristö

OpenAIRE

Fearon, Aleksei

2016-01-01

Tämän opinnäytetyön tarkoituksena oli suunnitella ja rakentaa CODESYS-ympäristöön pohjautuva harjoituskokoonpano. Suunniteltu laitteisto rakennettiin käyttäen kolmea erilaista logiikkayksikköä. Käytetyissä logiikoissa oli käyttöjärjestelmän lisäksi taustalla toimiva CODESYS-ympäristö. Logiikoina käytettiin Nexcom APPC1530 paneeli-PC:tä, Nexcom Nise91 Linux -konetta ja Raspberry Pi -minitietokonetta. Työssä tutkittiin CODESYS-ohjelmointiympäristöä, sen ominaisuuksia ja käyttökohteita. Opin...

City of Austin: Green habitat learning project. A green builder model home project

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

The purpose of the Year 14 UCETF project was to design and construct a residential structure that could serve as a demonstration facility, training site, and testing and monitoring laboratory for issues related to the implementation of sustainable building practices and materials. The Model Home Project builds on the previous and existing efforts, partially funded by the UCETF, of the City of Austin Green Builder Program to incorporate sustainable building practices into mainstream building activities. The Green Builder Program uses the term {open_quotes}green{close_quotes} as a synonym for sustainability. In the research and analysis that was completed for our earlier reports in Years 12 and 13, we characterized specific elements that we associate with sustainability and, thus, green building. In general, we refer to a modified life cycle assessment to ascertain if {open_quotes}green{close_quotes} building options reflect similar positive cyclical patterns found in nature (i.e. recyclability, recycled content, renewable resources, etc.). We additionally consider economic, human health and synergistic ecological impacts associated with our building choices and characterize the best choices as {open_quotes}green.{close_quotes} Our ultimate goal is to identify and use those {open_quotes}green{close_quotes} materials and processes that provide well for us now and do not compromise similar benefits for future generations. The original partnership developed for this project shifted during the year from a project stressing advanced (many prototypical) {open_quotes}green{close_quotes} building materials and techniques in a research and demonstration context, to off-the-shelf but underutilized {open_quotes}green{close_quotes} materials in the practical social context of using {open_quotes}green{close_quotes} technologies for low income housing. That project, discussed in this report, is called the Green Habitat Learning Project.

Evaluation of Features, Events, and Processes (FEP) for the Biosphere Model

International Nuclear Information System (INIS)

J. J. Tappen

2003-01-01

The purpose of this revision of ''Evaluation of the Applicability of Biosphere-Related Features, Events, and Processes (FEPs)'' (BSC 2001) is to document the screening analysis of biosphere-related primary FEPs, as identified in ''The Development of Information Catalogued in REV00 of the YMP FEP Database'' (Freeze et al. 2001), in accordance with the requirements of the final U.S. Nuclear Regulatory Commission (NRC) regulations at 10 CFR Part 63. This database is referred to as the Yucca Mountain Project (YMP) FEP Database throughout this document. Those biosphere-related primary FEPs that are screened as applicable will be used to develop the conceptual model portion of the biosphere model, which will in turn be used to develop the mathematical model portion of the biosphere model. As part of this revision, any reference to the screening guidance or criteria provided either by Dyer (1999) or by the proposed NRC regulations at 64 FR 8640 has been removed. The title of this revision has been changed to more accurately reflect the purpose of the analyses. In addition, this revision will address Item Numbers 19, 20, 21, 25, and 26 from Attachment 2 of ''U.S. Nuclear Regulatory Commission/U.S. Department of Energy Technical Exchange and Management Meeting on Total System Performance Assessment and Integration (August 6 through 10, 2001)'' (Reamer 2001). This Scientific Analysis Report (SAR) does not support the current revision to the YMP FEP Database (Freeze et al. 2001). Subsequent to the release of the YMP FEP Database (Freeze et al. 2001), a series of reviews was conducted on both the FEP processes used to support Total System Performance Assessment for Site Recommendation and to develop the YMP FEP Database. In response to observations and comments from these reviews, particularly the NRC/DOE TSPA Technical Exchange in August 2001 (Reamer 2001), several Key Technical Issue (KTI) Agreements were developed. ''The Enhanced Plan for Features, Events and Processes

Evaluation of Features, Events, and Processes (FEP) for the Biosphere Model

Energy Technology Data Exchange (ETDEWEB)

J. J. Tappen

2003-02-16

The purpose of this revision of ''Evaluation of the Applicability of Biosphere-Related Features, Events, and Processes (FEPs)'' (BSC 2001) is to document the screening analysis of biosphere-related primary FEPs, as identified in ''The Development of Information Catalogued in REV00 of the YMP FEP Database'' (Freeze et al. 2001), in accordance with the requirements of the final U.S. Nuclear Regulatory Commission (NRC) regulations at 10 CFR Part 63. This database is referred to as the Yucca Mountain Project (YMP) FEP Database throughout this document. Those biosphere-related primary FEPs that are screened as applicable will be used to develop the conceptual model portion of the biosphere model, which will in turn be used to develop the mathematical model portion of the biosphere model. As part of this revision, any reference to the screening guidance or criteria provided either by Dyer (1999) or by the proposed NRC regulations at 64 FR 8640 has been removed. The title of this revision has been changed to more accurately reflect the purpose of the analyses. In addition, this revision will address Item Numbers 19, 20, 21, 25, and 26 from Attachment 2 of ''U.S. Nuclear Regulatory Commission/U.S. Department of Energy Technical Exchange and Management Meeting on Total System Performance Assessment and Integration (August 6 through 10, 2001)'' (Reamer 2001). This Scientific Analysis Report (SAR) does not support the current revision to the YMP FEP Database (Freeze et al. 2001). Subsequent to the release of the YMP FEP Database (Freeze et al. 2001), a series of reviews was conducted on both the FEP processes used to support Total System Performance Assessment for Site Recommendation and to develop the YMP FEP Database. In response to observations and comments from these reviews, particularly the NRC/DOE TSPA Technical Exchange in August 2001 (Reamer 2001), several Key Technical Issue (KTI) Agreements were developed

Development of a Methodology for Hydrogeological Characterization of Faults: Progress of the Project in Berkeley, California

Science.gov (United States)

Goto, J.; Moriya, T.; Yoshimura, K.; Tsuchi, H.; Karasaki, K.; Onishi, T.; Ueta, K.; Tanaka, S.; Kiho, K.

2010-12-01

The Nuclear Waste Management Organization of Japan (NUMO), in collaboration with Lawrence Berkeley National Laboratory (LBNL), has carried out a project to develop an efficient and practical methodology to characterize hydrologic property of faults since 2007, exclusively for the early stage of siting a deep underground repository. A preliminary flowchart of the characterization program and a classification scheme of fault hydrology based on the geological feature have been proposed. These have been tested through the field characterization program on the Wildcat Fault in Berkeley, California. The Wildcat Fault is a relatively large non-active strike-slip fault which is believed to be a subsidiary of the active Hayward Fault. Our classification scheme assumes the contrasting hydrologic features between the linear northern part and the split/spread southern part of the Wildcat Fault. The field characterization program to date has been concentrated in and around the LBNL site on the southern part of the fault. Several lines of electrical and reflection seismic surveys, and subsequent trench investigations, have revealed the approximate distribution and near-surface features of the Wildcat Fault (see also Onishi, et al. and Ueta, et al.). Three 150m deep boreholes, WF-1 to WF-3, have been drilled on a line normal to the trace of the fault in the LBNL site. Two vertical holes were placed to characterize the undisturbed Miocene sedimentary formations at the eastern and western sides of the fault (WF-1 and WF-2 respectively). WF-2 on the western side intersected the rock formation, which was expected only in WF-1, and several of various intensities. Therefore, WF-3, originally planned as inclined to penetrate the fault, was replaced by the vertical hole further to the west. It again encountered unexpected rocks and faults. Preliminary results of in-situ hydraulic tests suggested that the transmissivity of WF-1 is ten to one hundred times higher than WF-2. The monitoring

RESEARCH ON COMPLEX, LARGE INDUSTRIAL PROJECTS IN TRANSNATIONAL ENVIRONMENT

Directory of Open Access Journals (Sweden)

Florin POPESCU

2016-12-01

Full Text Available More and more projects from different industrial sectors developed in transnational environment are becoming more characterized as "complex". In recent years, there has been much discussion and controversy about the complexity of the projects, and, despite what has been written and said in various papers, journals and professional conferences, more confusion than clarification was created, complexity of projects being interpreted differently from one author to another. Most of the literature studied is based on linear, analytical and rational approach, focusing on the size of project management planning and control and actually less on projects that are characterized as taking place and grow into a dynamic socio-human environment in a continuous change. This study represents a critical review of existing theoretical models found in literature, highlighting their limitations. The output of this literature study represents an integration of different approaches concerning complexity under one umbrella to provide a common understanding of the evolution of this concept.

The CONNECT project

DEFF Research Database (Denmark)

Assaf, Yaniv; Alexander, Daniel C; Jones, Derek K

2013-01-01

Of Neuroimagers for the Non-invasive Exploration of brain Connectivity and Tracts) project aimed to combine tractography and micro-structural measures of the living human brain in order to obtain a better estimate of the connectome, while also striving to extend validation of these measurements. This paper...... summarizes the project and describes the perspective of using micro-structural measures to study the connectome.......In recent years, diffusion MRI has become an extremely important tool for studying the morphology of living brain tissue, as it provides unique insights into both its macrostructure and microstructure. Recent applications of diffusion MRI aimed to characterize the structural connectome using...

Towards a Collaborative Open Environment of Project-Centred Learning

DEFF Research Database (Denmark)

Bongio, Aldo; van Bruggen, Jan; Ceri, Stefano

Nowadays, engineering studies are characterized by high mobility of students, lecturers and workforce and by the dynamics of multinational companies where “classes” or “students’ teams” composed of persons with different competencies and backgrounds, working together in projects to solve complex ...... environment. This paper proposes a COOPER framework and shows its approaches to address the various research challenges. This work is partially supported by EU/IST FP6 STREP project COOPER (contract number IST-2005-027073).......Nowadays, engineering studies are characterized by high mobility of students, lecturers and workforce and by the dynamics of multinational companies where “classes” or “students’ teams” composed of persons with different competencies and backgrounds, working together in projects to solve complex...

Legacy sample disposition project. Volume 2: Final report

International Nuclear Information System (INIS)

Gurley, R.N.; Shifty, K.L.

1998-02-01

This report describes the legacy sample disposition project at the Idaho Engineering and Environmental Laboratory (INEEL), which assessed Site-wide facilities/areas to locate legacy samples and owner organizations and then characterized and dispositioned these samples. This project resulted from an Idaho Department of Environmental Quality inspection of selected areas of the INEEL in January 1996, which identified some samples at the Test Reactor Area and Idaho Chemical Processing Plant that had not been characterized and dispositioned according to Resource Conservation and Recovery Act (RCRA) requirements. The objective of the project was to manage legacy samples in accordance with all applicable environmental and safety requirements. A systems engineering approach was used throughout the project, which included collecting the legacy sample information and developing a system for amending and retrieving the information. All legacy samples were dispositioned by the end of 1997. Closure of the legacy sample issue was achieved through these actions

Phase 1 Characterization sampling and analysis plan West Valley demonstration project.

Energy Technology Data Exchange (ETDEWEB)

Johnson, R. L. (Environmental Science Division)

2011-06-30

The Phase 1 Characterization Sampling and Analysis Plan (CSAP) provides details about environmental data collection that will be taking place to support Phase 1 decommissioning activities described in the Phase 1 Decommissioning Plan for the West Valley Demonstration Project, Revision 2 (Phase I DP; DOE 2009). The four primary purposes of CSAP data collection are: (1) pre-design data collection, (2) remedial support, (3) post-remediation status documentation, and (4) Phase 2 decision-making support. Data collection to support these four main objectives is organized into two distinct data collection efforts. The first is data collection that will take place prior to the initiation of significant Phase 1 decommissioning activities (e.g., the Waste Management Area [WMA] 1 and WMA 2 excavations). The second is data collection that will occur during and immediately after environmental remediation in support of remediation activities. Both data collection efforts have a set of well-defined objectives that encompass the data needs of the four main CSAP data collection purposes detailed in the CSAP. The main body of the CSAP describes the overall data collection strategies that will be used to satisfy data collection objectives. The details of pre-remediation data collection are organized by WMA. The CSAP contains an appendix for each WMA that describes the details of WMA-specific pre-remediation data collection activities. The CSAP is intended to expand upon the data collection requirements identified in the Phase 1 Decommissioning Plan. The CSAP is intended to tightly integrate with the Phase 1 Final Status Survey Plan (FSSP). Data collection described by the CSAP is consistent with the FSSP where appropriate and to the extent possible.

Corrective Action Decision Document for Corrective Action Unit 168: Area 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada, Rev. No.: 2 with Errata Sheet

Energy Technology Data Exchange (ETDEWEB)

Wickline, Alfred

2006-12-01

disposal cells contained within the landfill boundaries. (3) No COCs were identified at CAS 25-19-02. (4) Radiological surveys at CAS 25-23-02 identified 13 railroad cars that exceeded the NV/YMP Radiological Control Manual limits for free release. Six railroad cars were below these limits and therefore met the free-release criteria. (5) An In-Situ Object Counting System survey taken at CAS 25-23-02 identified two railroad cars possibly containing fuel fragments; both exceeded the NV/YMP Radiological Control Manual free release criteria. (6) Corrective Action Site 25-23-18 contains total petroleum hydrocarbons-diesel-range organics, Aroclor-1260, uranium-234, uranium-235, strontium-90, and cesium-137 that exceed PALs. (7) Radiological surveys at CAS 25-34-01 indicate that there were no total contamination readings that exceeded the NV/YMP Radiological Control Manual limits for free release. (8) Radiological surveys at CAS 25-34-02 indicate that there were no total contamination readings that exceeded the NV/YMP Radiological Control Manual limits for free release. (9) Radiological surveys at CAS 25-23-13 identified six pieces of equipment that exceed the NV/YMP Radiological Control Manual limits for free release. (10) Corrective Action Site 25-99-16 was not investigated. A review of historical documentation and current site conditions showed that no further characterization was required to select the appropriate corrective action. (11) Corrective Action Site 26-08-01 contains hydrocarbon-contaminated soil at concentrations exceeding the PAL. The contamination is at discrete locations associated with asphalt debris. (12) Corrective Action Site 26-17-01 contains total petroleum hydrocarbons-diesel-range organics and Aroclor-1260 exceeding the PALs. (13) Radiological surveys at CAS 26-19-02 identified metallic debris that exceeded the NV/YMP Radiological Control Manual limits for free release. Concentrations of radiological or chemical constituents in soil did not exceed PALs.

SYSTEMS SAFETY ANALYSIS FOR FIRE EVENTS ASSOCIATED WITH THE ECRB CROSS DRIFT

International Nuclear Information System (INIS)

R. J. Garrett

2001-01-01

The purpose of this analysis is to systematically identify and evaluate fire hazards related to the Yucca Mountain Site Characterization Project (YMP) Enhanced Characterization of the Repository Block (ECRB) East-West Cross Drift (commonly referred to as the ECRB Cross-Drift). This analysis builds upon prior Exploratory Studies Facility (ESF) System Safety Analyses and incorporates Topopah Springs (TS) Main Drift fire scenarios and ECRB Cross-Drift fire scenarios. Accident scenarios involving the fires in the Main Drift and the ECRB Cross-Drift were previously evaluated in ''Topopah Springs Main Drift System Safety Analysis'' (CRWMS M and O 1995) and the ''Yucca Mountain Site Characterization Project East-West Drift System Safety Analysis'' (CRWMS M and O 1998). In addition to listing required mitigation/control features, this analysis identifies the potential need for procedures and training as part of defense-in-depth mitigation/control features. The inclusion of this information in the System Safety Analysis (SSA) is intended to assist the organization(s) (e.g., Construction, Environmental Safety and Health, Design) responsible for these aspects of the ECRB Cross-Drift in developing mitigation/control features for fire events, including Emergency Refuge Station(s). This SSA was prepared, in part, in response to Condition/Issue Identification and Reporting/Resolution System (CIRS) item 1966. The SSA is an integral part of the systems engineering process, whereby safety is considered during planning, design, testing, and construction. A largely qualitative approach is used which incorporates operating experiences and recommendations from vendors, the constructor and the operating contractor. The risk assessment in this analysis characterizes the scenarios associated with fires in terms of relative risk and includes recommendations for mitigating all identified hazards. The priority for recommending and implementing mitigation control features is: (1) Incorporate

Characterization of Most Promising Sequestration Formations in the Rocky Mountain Region (RMCCS)

Energy Technology Data Exchange (ETDEWEB)

McPherson, Brian; Matthews, Vince

2013-09-30

The primary objective of the “Characterization of Most Promising Carbon Capture and Sequestration Formations in the Central Rocky Mountain Region” project, or RMCCS project, is to characterize the storage potential of the most promising geologic sequestration formations within the southwestern U.S. and the Central Rocky Mountain region in particular. The approach included an analysis of geologic sequestration formations under the Craig Power Station in northwestern Colorado, and application or extrapolation of those local-scale results to the broader region. A ten-step protocol for geologic carbon storage site characterization was a primary outcome of this project.

Tank characterization project (TWRS) process engineering data management plan

International Nuclear Information System (INIS)

Adams, M.R.

1997-01-01

The Tank Characterization Data Management (TCDM) system provides customers and users with data and information of known and acceptable quality when they are needed, in the form they are needed, and at a reasonable cost. The TCDM mission will be accomplished by the following: (1) maintaining and managing tank characterization data and information based on business needs and objectives including transfer of ownership to future contractors; (2) capturing data where it originates and entering it only once to control data consistency, electronic data and information management shall be emphasized to the extent practicable; (3) establishing data quality standards, and managing and certifying databases and data sources against these standards to maintain the proper level of data and information quality consistent with the importance of the data and information, data obtained at high cost with significant implications to decision making regarding tank safety and/or disposal will be maintained and managed at the highest necessary levels of quality; (4) establishing and enforcing data management standards for the Tank Characterization Database (TCD) and supporting data sources including providing mechanisms for discovering and correcting data errors before they propagate; (5) emphasizing electronic data sharing with all authorized users, customers, contractors, and stakeholders to the extent practicable; (6) safeguarding data and information from unauthorized alteration or destruction; (7) providing standards for electronic information deliverables to subcontractors and vendors to achieve uniformity in electronic data management; and (8) investing in new technology (hardware and/or software) as prudent and necessary to accomplish the mission in an efficient and effective manner

A Remote Characterization System for subsurface mapping of buried waste sites

International Nuclear Information System (INIS)

Sandness, G.A.; Bennett, D.W.; Martinson, L.

1992-06-01

This paper describes a development project that will provide new technology for characterizing hazardous waste burial sites. The project is a collaborative effort by five of the national laboratories, involving the development and demonstration of a remotely controlled site characterization system. The Remote Characterization System (RCS) includes a unique low-signature survey vehicle, a base station, radio telemetry data links, satellite-based vehicle tracking, stereo vision, and sensors for non-invasive inspection of the surface and subsurface

Characterizing Cross-Professional Collaboration in Research and Development Projects in Secondary Education

Science.gov (United States)

Schenke, Wouter; van Driel, Jan H.; Geijsel, Femke P.; Sligte, Henk W.; Volman, Monique L. L.

2016-01-01

Collaboration between practitioners and researchers can increasingly be observed in research and development (R&D) projects in secondary schools. This article presents an analysis of cross-professional collaboration between teachers, school leaders and educational researchers and/or advisers as part of R&D projects in terms of three…

Myoglobin Structure and Function: A Multiweek Biochemistry Laboratory Project

Science.gov (United States)

Silverstein, Todd P.; Kirk, Sarah R.; Meyer, Scott C.; Holman, Karen L. McFarlane

2015-01-01

We have developed a multiweek laboratory project in which students isolate myoglobin and characterize its structure, function, and redox state. The important laboratory techniques covered in this project include size-exclusion chromatography, electrophoresis, spectrophotometric titration, and FTIR spectroscopy. Regarding protein structure,…

Ground Characterization Studies in Canakkale Pilot Site of LIQUEFACT Project

Science.gov (United States)

Ozcep, F.; Oztoprak, S.; Aysal, N.; Bozbey, I.; Tezel, O.; Ozer, C.; Sargin, S.; Bekin, E.; Almasraf, M.; Cengiz Cinku, M.; Ozdemir, K.

2017-12-01

The our aim is to outline the ground characterisation studies in Canakkale test site. Study is based on the EU H2020 LIQUEFACT project entitled "Liquefact: Assessment and mitigation of liquefaction potential across Europe: a holistic approach to protect structures / infrastructures for improved resilience to earthquake-induced liquefaction disasters". Objectives and extent of ground characterization for Canakkale test site includes pre-existing soil investigation studies and complementary field studies. There were several SPT and geophysical tests carried out in the study area. Within the context of the complementary tests, six (6) study areas in the test site were chosen and complementary tests were carried out in these areas. In these areas, additional boreholes were opened and SPT tests were performed. It was decided that additional CPT (CPTU and SCPT) and Marchetti Dilatometer (DMT) tests should be carried out within the scope of the complementary testing. Seismic refraction, MASW and micro tremor measurements had been carried out in pre-existing studies. Shear wave velocities obtained from MASW measurements were evaluated to the most rigorous level. These tests were downhole seismic, PS-logging, seismic refraction, 2D-ReMi, MASW, micro tremor (H/V Nakamura method), 2D resistivity and resonance acoustic profiling (RAP). RAP is a new technique which will be explained briefly in the relevant section. Dynamic soil properties had not been measured in pre-existing studies, therefore these properties were investigated within the scope of the complementary tests. Selection of specific experimental tests of the complementary campaign was based on cost-benefit considerations Within the context of complementary field studies, dynamic soil properties were measured using resonant column and cyclic direct shear tests. Several sieve analyses and Atterberg Limits tests which were documented in the pre-existing studies were evaluated. In the complementary study carried out

Fuel Thermo-physical Characterization Project. Fiscal Year 2014 Final Report

Energy Technology Data Exchange (ETDEWEB)

Burkes, Douglas [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Casella, Andrew M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buck, Edgar C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Casella, Amanda J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Edwards, Matthew K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); MacFarlan, Paul J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Pool, Karl N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Slonecker, Bruce D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Smith, Frances N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Steen, Franciska H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-03-15

The Office of Material Management and Minimization (M3) Reactor Conversion Fuel Thermo-Physical Characterization Project at Pacific Northwest National Laboratory (PNNL) was tasked with using PNNL facilities and processes to receive irradiated low enriched uranium–molybdenum (LEU-Mo) fuel plate samples and perform analysis in support of the M3 Reactor Conversion Program. This work is in support of the M3 Reactor Conversion Fuel Development Pillar that is managed by Idaho National Laboratory. The primary research scope was to determine the thermo-physical properties as a function of temperature and burnup. Work conducted in Fiscal Year (FY) 2014 complemented measurements performed in FY 2013 on four additional irradiated LEU-Mo fuel plate samples. Specifically, the work in FY 2014 investigated the influence of different processing methods on thermal property behavior, the absence of aluminum alloy cladding on thermal property behavior for additional model validation, and the influence of higher operating surface heat flux / more aggressive irradiation conditions on thermal property behavior. The model developed in FY 2013 and refined in FY 2014 to extract thermal properties of the U-Mo alloy from the measurements conducted on an integral fuel plate sample (i.e., U-Mo alloy with a thin Zr coating and clad in AA6061) continues to perform very well. Measurements conducted in FY 2014 on samples irradiated under similar conditions compare well to measurements performed in FY 2013. In general, there is no gross influence of fabrication method on thermal property behavior, although the difference in LEU-Mo foil microstructure does have a noticeable influence on recrystallization of grains during irradiation. Samples irradiated under more aggressive irradiation conditions, e.g., higher surface heat flux, revealed lower thermal conductivity when compared to samples irradiated at moderate surface heat fluxes, with the exception of one sample. This report documents thermal

Diversity of Cortico-descending Projections

DEFF Research Database (Denmark)

Innocenti, Giorgio M; Caminiti, Roberto; Rouiller, Eric M

2018-01-01

The axonal composition of cortical projections originating in premotor, supplementary motor (SMA), primary motor (a4), somatosensory and parietal areas and descending towards the brain stem and spinal cord was characterized in the monkey with histological tract tracing, electron microscopy (EM) a...

SCANDICIN YMPÄRISTÖOHJELMAN TUNTEMUKSEN PARANTAMINEN SCANDIC KAJANUKSESSA

OpenAIRE

Hintta, Hanna

2010-01-01

Tämä opinnäytetyö on toiminnallinen opinnäytetyö, jonka tarkoituksena oli antaa Scandic Kajanuksen käyttöön sähköisen materiaalin lisäksi paperinen tietolähde Scandicin ympäristöohjelmasta. Scandicin vakituiset työntekijät suorittavat ympäristökoulutuksen Scandicin Intranetissä, mutta harjoittelijoilta, osa-aikaisilta ja vuokratyövoimalta ei edellytetä koulutuksen suorittamista. He ovat kuitenkin merkittävä osa työyhteisöä ja vaikuttavat jokapäiväisellä työllään Scandicin tuloksiin kestävän k...

CLASSIFICATION OF THE MGR MUCK HANDLING SYSTEM

International Nuclear Information System (INIS)

R. Garrett

1999-01-01

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) muck handling system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description (QARD) (DOE 1998). This QA classification incorporates the current MGR design and the results of the ''Preliminary Preclosure Design Basis Event Calculations for the Monitored Geologic Repository (CRWMS M and O 1998a)

Ekologisuus Ilosaarirock-festivaalin rakentamisessa

OpenAIRE

Shemeikka, Karri

2012-01-01

Ekologisuus, ympäristötyö ja -teot ovat asioita, joilla on suuri vaikutus tämän päivän yritysten toimintaan. Niillä on myös tärkeä vaikutus siihen, millaisen julkisuuskuvan yritys luo sidosryhmiinsä ja yhteiskuntaan. Tämän opinnäytetyön tarkoituksena oli selvittää, miten kesällä 2011 Ilosaarirockin rakentamisessa mukana olleet palkalliset ja vapaaehtoiset työntekijät näkevät ekologisuuden osana tapahtuman tuotantoa. Lisäksi selvitettiin millaiseksi he kokevat ympäristöteot oman työsuorituksen...

Polytope projects

CERN Document Server

Iordache, Octavian

2013-01-01

How do you know what works and what doesn't? This book contains case studies highlighting the power of polytope projects for complex problem solving. Any sort of combinational problem characterized by a large variety of possibly complex constructions and deconstructions based on simple building blocks can be studied in a similar way. Although the majority of case studies are related to chemistry, the method is general and equally applicable to other fields for engineering or science.

Enhanced project management tool

Science.gov (United States)

Hsu, Chen-Jung (Inventor); Patel, Hemil N. (Inventor); Maluf, David A. (Inventor); Moh Hashim, Jairon C. (Inventor); Tran, Khai Peter B. (Inventor)

2012-01-01

A system for managing a project that includes multiple tasks and a plurality of workers. Input information includes characterizations based upon a human model, a team model and a product model. Periodic reports, such as one or more of a monthly report, a task plan report, a schedule report, a budget report and a risk management report, are generated and made available for display or further analysis or collection into a customized report template. An extensible database allows searching for information based upon context and upon content. Seven different types of project risks are addressed, including non-availability of required skill mix of workers. The system can be configured to exchange data and results with corresponding portions of similar project analyses, and to provide user-specific access to specified information.

Nuclear power: Financing big projects

International Nuclear Information System (INIS)

Raabe, G.

1992-01-01

Since the early seventies, the Dresdner Bank AG has been intensively engaged in financing nuclear power plants, e.g., the Muelheim-Kaerlich Nuclear Power Station currently down because of legal technicaltities. The bank has also been involved in other large-scale projects in the energy sector and, in addition, has conceptually accompanied the stages of the nuclear fuel cycle, such as enrichment, fuel element fabrication, and reprocessing. However, for political reasons it has not been possible to carry out these projects and finance them in the Federal Republic. With appropriate modifications, these financial models can also be transferred to international projects; after all, the enrichment sector has always been characterized by trilateral ventures. (orig.) [de

Spectroscopic and Physical Characterization of Functionalized Au Nanoparticles: A Multiweek Experimental Project

Science.gov (United States)

Masson, Jean-Francois; Yockell-Lelièvre, Hélène

2014-01-01

A term project was introduced in teaching advanced spectroscopy and notions of nanotechnology to chemistry students at the graduate level (M.Sc. and Ph.D.). This project could also be suited for an honor's thesis at the undergraduate level. Students were assigned a unique combination of nanoparticle synthesis (13 nm Au nanospheres, ~100 nm…

Project Work in Networked Distance Education

DEFF Research Database (Denmark)

Knudsen, Morten; Helbo, Jan; Jensen, Lars Peter

2000-01-01

devoted to courses and the other half to project work. A computer conference system, LuvitÒ provides facilities for the courses, as well as structured synchronous and asynchronous communication. Eight times per year two-day seminars are held at the university for intensive lectures, project work......Problem oriented project work has been the foundation for the educational system at Aalborg University since its start 25 years ago. The duration of each student project is one semester, and the students spend half of their time working on the project in groups of typically 5-6 persons....... As the experience since then has proven this to be a very successful innovation in higher education [1], it seems to be an obvious idea also to base our new distance educations on the project study form. Traditionally, however, distance education has been characterized by one-way communication and self...

Technology evaluation report for the Buried Waste Robotics Program Subsurface Mapping Project

International Nuclear Information System (INIS)

Griebenow, B.E.

1992-01-01

This document presents a summary of the work performed in support of the Buried Waste Robotics Program Subsurface Mapping Project. The project objective was to demonstrate the feasibility of remotely characterizing buried waste sites. To fulfill this objective, a remotely-operated vehicle, equipped with several sensors, was deployed at the Idaho National Engineering Laboratory. Descriptions of the equipment and areas involved in the project are included in this report. Additionally, this document provides data that was obtained during characterization operations at the Cold Test Pit and the Subsurface Disposal Area, both at the Idaho National Engineering Laboratory's Radioactive Waste Management Complex, and at the Idaho Chemical Processing Plant. The knowledge gained from the experience, that can be applied to the next generation remote-characterization system, is extensive and is presented in this report

Total-system performance assessment for Yucca Mountain -- SNL second iteration (TSPA-1993); Executive summary

Energy Technology Data Exchange (ETDEWEB)

Wilson, M.L.; Barnard, R.W. [Sandia National Labs., Albuquerque, NM (United States); Gauthier, J.H. [Sandia National Labs., Albuquerque, NM (United States)]|[Spectra Research, Inc. (United States)] [and others

1994-04-01

Sandia National Laboratories has completed the second iteration of the periodic total-system performance assessments (TSPA-93) for the Yucca Mountain Site Characterization Project (YMP). Scenarios describing expected conditions (aqueous and gaseous transport of contaminants) and low-probability events (human-intrusion drilling and volcanic intrusion) are modeled. The hydrologic processes modeled include estimates of the perturbations to ambient conditions caused by heating of the repository resulting from radioactive decay of the waste. TSPA-93 incorporates significant new detailed process modeling, including two- and three-dimensional modeling of thermal effects, groundwater flow in the saturated-zone aquifers, and gas flow in the unsaturated zone. Probabilistic analyses are performed for aqueous and gaseous flow and transport, human intrusion, and basaltic magmatic activity. Results of the calculations lead to a number of recommendations concerning studies related to site characterization. Primary among these are the recommendations to obtain better information on percolation flux at Yucca Mountain, on the presence or absence of flowing fractures, and on physical and chemical processes influencing gaseous flow. Near-field thermal and chemical processes, and waste-container degradation are also areas where additional investigations may reduce important uncertainties. Recommendations for repository and waste-package design studies are: (1) to evaluate the performance implications of large-size containers, and (2) to investigate in more detail the implications of high repository thermal power output on the adjacent host rock and on the spent fuel.

Total-system performance assessment for Yucca Mountain -- SNL second iteration (TSPA-1993)

International Nuclear Information System (INIS)

Wilson, M.L.; Barnard, R.W.; Gauthier, J.H.

1994-04-01

Sandia National Laboratories has completed the second iteration of the periodic total-system performance assessments (TSPA-93) for the Yucca Mountain Site Characterization Project (YMP). Scenarios describing expected conditions (aqueous and gaseous transport of contaminants) and low-probability events (human-intrusion drilling and volcanic intrusion) are modeled. The hydrologic processes modeled include estimates of the perturbations to ambient conditions caused by heating of the repository resulting from radioactive decay of the waste. TSPA-93 incorporates significant new detailed process modeling, including two- and three-dimensional modeling of thermal effects, groundwater flow in the saturated-zone aquifers, and gas flow in the unsaturated zone. Probabilistic analyses are performed for aqueous and gaseous flow and transport, human intrusion, and basaltic magmatic activity. Results of the calculations lead to a number of recommendations concerning studies related to site characterization. Primary among these are the recommendations to obtain better information on percolation flux at Yucca Mountain, on the presence or absence of flowing fractures, and on physical and chemical processes influencing gaseous flow. Near-field thermal and chemical processes, and waste-container degradation are also areas where additional investigations may reduce important uncertainties. Recommendations for repository and waste-package design studies are: (1) to evaluate the performance implications of large-size containers, and (2) to investigate in more detail the implications of high repository thermal power output on the adjacent host rock and on the spent fuel

The LCO Follow-up and Characterization Network and AgentNEO Citizen Science Project

Science.gov (United States)

Lister, Tim; Greenstreet, Sarah; Gomez, Edward; Christensen, Eric J.; Larson, Stephen M.

2017-10-01

The LCO NEO Follow-up Network is using the telescopes of the Las Cumbres Observatory (LCO) and a web-based target selection, scheduling and data reduction system to confirm NEO candidates and characterize radar-targeted known NEOs. Starting in July 2014, the LCO NEO Follow-up Network has observed over 4,500 targets and reported more than 25,000 astrometric and photometric measurements to the Minor Planet Center.The LCO NEO Follow-up Network's main aims are to perform confirming follow-up of the large number of NEO candidates and to perform characterization measurements of radar targets to obtain light curves and rotation rates. The NEO candidates come from the NEO surveys such as Catalina, PanSTARRS, ATLAS, NEOWISE and others. In particular, we are targeting objects in the Southern Hemisphere, where the LCO NEO Follow-up Network is the largest resource for NEO observations.The first phase of the LCO Network comprises nine 1-meter and seven 0.4-meter telescopes at site at McDonald Observatory (Texas), Cerro Tololo (Chile), SAAO (South Africa) and Siding Spring Observatory (Australia). The network has been fully operational since 2014 May, and observations are being executed remotely and robotically. Additional 0.4-meter telescopes will be deployed in 2017 and 2x1-meter telescopes for a site at Ali Observatory, Tibet are planned for 2018-2019.We have developed web-based software called NEOexchange which automatically downloads and aggregates NEO candidates from the Minor Planet Center's NEO Confirmation Page, the Arecibo and Goldstone radar target lists and the NASA lists. NEOexchange allows the planning and scheduling of observations on the LCO Telescope Network and the tracking of the resulting blocks and generated data. We have extended the NEOexchange software to include automated scheduling and moving object detection, with the results presented to the user via the website.We will present results from the LCO NEO Follow-up Network and from the development of the

Workshop on development of radionuclide getters for the Yucca Mountain waste repository: proceedings.

Energy Technology Data Exchange (ETDEWEB)

Moore, Robert Charles; Lukens, Wayne W. (Lawrence Berkeley National Laboratory)

2006-03-01

The proposed Yucca Mountain repository, located in southern Nevada, is to be the first facility for permanent disposal of spent reactor fuel and high-level radioactive waste in the United States. Total Systems Performance Assessment (TSPA) analysis has indicated that among the major radionuclides contributing to dose are technetium, iodine, and neptunium, all of which are highly mobile in the environment. Containment of these radionuclides within the repository is a priority for the Yucca Mountain Project (YMP). These proceedings review current research and technology efforts for sequestration of the radionuclides with a focus on technetium, iodine, and neptunium. This workshop also covered issues concerning the Yucca Mountain environment and getter characteristics required for potential placement into the repository.

Cost-Effective Cementitious Material Compatible with Yucca Mountain Repository Geochemistry

Energy Technology Data Exchange (ETDEWEB)

Dole, LR

2004-12-17

The current plans for the Yucca Mountain (YM) repository project (YMP) use steel structures to stabilize the disposal drifts and connecting tunnels that are collectively over 100 kilometers in length. The potential exist to reduce the underground construction cost by 100s of millions of dollars and improve the repository's performance. These economic and engineering goals can be achieved by using the appropriate cementitious materials to build out these tunnels. This report describes the required properties of YM compatible cements and reviews the literature that proves the efficacy of this approach. This report also describes a comprehensive program to develop and test materials for a suite of underground construction technologies.

Predictions of tracer transport in interwell tracer tests at the C-Hole complex. Yucca Mountain site characterization project report milestone 4077

International Nuclear Information System (INIS)

Reimus, P.W.

1996-09-01

This report presents predictions of tracer transport in interwell tracer tests that are to be conducted at the C-Hole complex at the Nevada Test Site on behalf of the Yucca Mountain Site Characterization Project. The predictions are used to make specific recommendations about the manner in which the tracer test should be conducted to best satisfy the needs of the Project. The objective of he tracer tests is to study flow and species transport under saturated conditions in the fractured tuffs near Yucca Mountain, Nevada, the site of a potential high-level nuclear waste repository. The potential repository will be located in the unsaturated zone within Yucca Mountain. The saturated zone beneath and around the mountain represents the final barrier to transport to the accessible environment that radionuclides will encounter if they breach the engineered barriers within the repository and the barriers to flow and transport provided by the unsaturated zone. Background information on the C-Holes is provided in Section 1.1, and the planned tracer testing program is discussed in Section 1.2

Plans for characterization of salt sites

International Nuclear Information System (INIS)

Heim, G.E.; Matthews, S.C.; Kircher, J.F.; Kennedy, R.K.

1983-01-01

This basic salt site characterization program has been designed to provide the data required to support the design, performance assessment, and licensing of each of the principal project elements: the repository, the shafts, and the surface facilities. The work has been sequenced to meet the design and licensing schedule. It is anticipated that additional characterization activities will be performed to address site-specific considerations and to provide additional information to address questions which arise during the evaluation of characterization data. 3 figures, 3 tables

The Columbia River Protection Supplemental Technologies Quality Assurance Project Plan

Energy Technology Data Exchange (ETDEWEB)

Fix, N. J.

2008-03-12

Pacific Northwest National Laboratory researchers are working on the Columbia River Protection Supplemental Technologies Project. This project is a U. S. Department of Energy, Office of Environmental Management-funded initiative designed to develop new methods, strategies, and technologies for characterizing, modeling, remediating, and monitoring soils and groundwater contaminated with metals, radionuclides, and chlorinated organics. This Quality Assurance Project Plan provides the quality assurance requirements and processes that will be followed by the Technologies Project staff.

Design Theory Projectability

DEFF Research Database (Denmark)

Baskerville, Richard; Pries-Heje, Jan

2014-01-01

design science research is materially prescriptive, it requires a different perspective in developing the breadth of applications of design theories. In this paper we propose different concepts that embody forms of general technological knowledge The concept of projectability, developed originally......Technological knowledge has been characterized as having a scope that is specific to a particular problem. However, the information systems community is exploring forms of design science research that provide a promising avenue to technological knowledge with broader scope: design theories. Because...... as a means of distinguishing realized generalizations from unrealized generalizations, helps explain how design theories, being prescriptive, possess a different form of applicability. The concept of entrenchment describes the use of a theory in many projections. Together these concepts provide a means...

Mexican participation in the AMS project

Science.gov (United States)

Menchaca-Rocha, A.; Buenerd, M.; Cabrera, J. I.; Canizal, C.; Esquivel, O.; Núñez, R.; Plascencia, J. C.; Reyes, T.; Villoro, M. F.

2001-05-01

Optical characterization of hydrophobic silica aerogel SP-25 for the RICH, and a scheme to generate particle-ID conditions on TOF and Tracker amplitude data are reported, as part of a Mexican effort to contribute to the AMS Project. .

Characterization of low-level waste from the industrial sector, and near-term projection of waste volumes and types

International Nuclear Information System (INIS)

MacKenzie, D.R.

1988-01-01

A telephone survey of low-level waste generators has been carried out in order to make useful estimates of the volume and nature of the waste which the generators will be shipping for disposal when the compacts and states begin operating new disposal facilities. Emphasis of the survey was on the industrial sector, since there has been little information available on characteristics of industrial LLW. Ten large industrial generators shipping to Richland, ten shipping to Barnwell, and two whose wastes had previously been characterized by BNL were contacted. The waste volume shipped by these generators accounted for about two-thirds to three-quarters of the total industrial volume. Results are given in terms of the categories of LLW represented and of the chemical characteristics of the different wastes. Estimates by the respondents of their near-term waste volume projections are presented

Characterization of low-level waste from the industrial sector, and near-term projection of waste volumes and types

International Nuclear Information System (INIS)

MacKenzie, D.R.

1988-01-01

A telephone survey of low-level waste generators has been carried out in order to make useful estimates of the volume and nature of the waste which the generators are shipping for disposal when the compacts and states begin operating new disposal facilities. Emphasis of the survey was on the industrial sector, since there has been little information available on characteristics of industrial LLW. Ten large industrial generators shipping to Richland, ten shipping to Barnwell, and two whose wastes had previously been characterized by BNL were contacted. The waste volume shipped by these generators accounted for about two-thirds to three-quarters of the total industrial volume. Results are given in terms of the categories of LLW represented and of the chemical characteristics of the different wastes. Estimates by the respondents of their near-term waste volume projections are presented

Yucca Mountain Project technical status report (TSR), October 1989--March 1990

International Nuclear Information System (INIS)

1990-01-01

This Yucca Mountain Project Technical Status Report (TSR) on site characterization is the second in a series of reports that will be issued at approximately six-month intervals during site characterization. In addition, progress made toward the initiation and conduct of new site characterization activities is included. For this report, information on the technical progress made by Yucca Mountain Project participating organizations has been compiled covering the period from October 1989, through March 31, 1990. The status report consists of three sections: an introductory section; a section on the status of site characterization, which includes preparatory activities, sites programs, repository design, seals system design, waste package design, and performance assessment; and a reference section, which provides a complete listing of all published documents cited in the text. 59 refs

Hydrometric, Hydrochemical, and Hydrogeophysical Runoff Characterization Across Multiple Land Covers in the Agua Salud Project, Panama

Science.gov (United States)

Litt, Guy Finley

As the Panama Canal Authority faces sensitivity to water shortages, managing water resources becomes crucial for the global shipping industry's security. These studies address knowledge gaps in tropical water resources to aid hydrological model development and validation. Field-based hydrological investigations in the Agua Salud Project within the Panama Canal Watershed employed multiple tools across a variety of land covers to investigate hydrological processes. Geochemical tracers informed where storm runoff in a stream comes from and identified electrical conductivity (EC) as an economical, high sample frequency tracer during small storms. EC-based hydrograph separation coupled with hydrograph recession rate analyses identified shallow and deep groundwater storage-discharge relationships that varied by season and land cover. A series of plot-scale electrical resistivity imaging geophysical experiments coupled with rainfall simulation characterized subsurface flow pathway behavior and quantified respectively increasing infiltration rates across pasture, 10 year old secondary succession forest, teak (tectona grandis), and 30 year old secondary succession forest land covers. Additional soil water, groundwater, and geochemical studies informed conceptual model development in subsurface flow pathways and groundwater, and identified future research needs.

Role of Hydrogeology in Professional Environmental Projects

Science.gov (United States)

The purpose of this presentation is to acquaint hydrogeology students how hydrogeological principles are applied in environmental engineering projects. This presentation outlines EPA's Superfund processes of site characterization, feasibility studies, and remediation processes.

Design and testing of a perimeter of increment threshold by projection

OpenAIRE

García Domene, María del Carmen; Luque Cobija, María José; Fez Saiz, Dolores de

2017-01-01

In the present study, we have designed and tested a perimeter for the detection of damage in the chromatic mechanisms using a video projector. To this purpose, we have characterized pixel to pixel a video projector, to account for the inhomogeneities in the projection. We have measured the tristimulus values of the projector primaries as a function of digital level, at 49 locations of the projection screen and, from them, we have arrived to a characterization model which reduces the color dif...

Resins characterization strategy at Kozloduy Nuclear Power Plant

International Nuclear Information System (INIS)

Fenoy, A.; González, R.; Molleda, P.; Sánchez, L.; Herrera, J.

2013-01-01

The Consortium ENSA- Gas Natural Fenosa Engineering has a contract with Kozloduy Nuclear Power Plant (KNPP) for the retrieval and conditioning of the resins. Before that, the project deals with resins characterization to verify the fulfillment the Bulgarian authorities’ requirements. The project includes all the resins generated during the operation of the BACKGROUND Resins characterization strategy at Kozloduy Nuclear Power Plant units 1, 2, 3 and 4, which were stored into six big dimensions tanks: four low tanks and two intermediate tanks. They only have a manhole above for tanks access. The methodology and the progress of the work are presented

Results from Nevada Nuclear Waste Storage Investigations (NNWSI) Series 3 spent fuel dissolution tests

International Nuclear Information System (INIS)

Wilson, C.N.

1990-06-01

The dissolution and radionuclide release behavior of spent fuel in groundwater is being studied by the Yucca Mountain Project (YMP), formerly the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. Specimens prepared from pressurized water reactor fuel rod segments were tested in sealed stainless steel vessels in Nevada Test Site J-13 well water at 85 degree C and 25 degree C. The test matrix included three specimens of bare-fuel particles plus cladding hulls, two fuel rod segments with artificially defected cladding and water-tight end fittings, and an undefected fuel rod section with watertight end fittings. Periodic solution samples were taken during test cycles with the sample volumes replenished with fresh J-13 water. Test cycles were periodically terminated and the specimens restarted in fresh J-13 water. The specimens were run for three cycles for a total test duration of 15 months. 22 refs., 32 figs., 26 tabs

A desk evaluation review of project POL/5/006 plant breeding using induced mutations. Project desk evaluation

International Nuclear Information System (INIS)

1993-01-01

Projects POL/5/006 was initiated in 1985 to assist the Government of Poland in improving the mutation breeding efforts in the country to promote the development of new and higher yielding crop varieties. The difficult economic situation in the country at this time restricted the procurement of special equipment, spare parts and supplies from abroad and, therefore, impeded research and development work in this field. The project was implemented using a distinctive approach and design characterized by having six recipient institutions and the establishment of one central gamma-irradiation facility to be made available to all participating institutions for mutation induction. The project was formally closed in 1989. The review of project POL/5/006 was undertaken in accord with the expressed wishes of the Board of Governors for selected ex-post evaluations of completed projects. The main purpose of the review was to ascertain if the project objectives were achieved, and to determine what impact the technical assistance provided may have had on continued post-project and current plant breeding programmes in Poland

A desk evaluation review of project POL/5/006 plant breeding using induced mutations. Project desk evaluation

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-09-14

Projects POL/5/006 was initiated in 1985 to assist the Government of Poland in improving the mutation breeding efforts in the country to promote the development of new and higher yielding crop varieties. The difficult economic situation in the country at this time restricted the procurement of special equipment, spare parts and supplies from abroad and, therefore, impeded research and development work in this field. The project was implemented using a distinctive approach and design characterized by having six recipient institutions and the establishment of one central gamma-irradiation facility to be made available to all participating institutions for mutation induction. The project was formally closed in 1989. The review of project POL/5/006 was undertaken in accord with the expressed wishes of the Board of Governors for selected ex-post evaluations of completed projects. The main purpose of the review was to ascertain if the project objectives were achieved, and to determine what impact the technical assistance provided may have had on continued post-project and current plant breeding programmes in Poland.

Project management tool

Science.gov (United States)

Maluf, David A. (Inventor); Bell, David G. (Inventor); Gurram, Mohana M. (Inventor); Gawdiak, Yuri O. (Inventor)

2009-01-01

A system for managing a project that includes multiple tasks and a plurality of workers. Input information includes characterizations based upon a human model, a team model and a product model. Periodic reports, such as a monthly report, a task plan report, a budget report and a risk management report, are generated and made available for display or further analysis. An extensible database allows searching for information based upon context and upon content.

Hydrological flow analysis at Yucca Mountain, Nevada. Final report

International Nuclear Information System (INIS)

1995-01-01

This final report, prepared by Hydro Geo Chem staff for Los Alamos National Laboratory, summarizes work conducted by the company under Subcontract 52OHHOOI 5-3G, which was terminated by LANL effective 7 February 1995 for practical reasons, in that responsibilities for all tasks in the Statement of Work had been transitioned to LANL employees. The ultimate objective of this work is to characterize the movement of subsurface water in the vicinity of Yucca Mountain, Nevada. Data produced under this contract is to be used by the U.S. Department of Energy in its Yucca Mountain Site Characterization Project (YMP) to help determine hydrologic flows that may affect the performance of a potential nuclear waste,, repository. The data may be used in the licensing proceedings, and certain quality assurance procedures have thus been required. The work has focused on measuring the distribution of environmental tracers- chlorine-36, chlorine, and bromine-and on evaluating the depth to which these conservative solutes have percolated in the unsaturated zone at Yucca Mountain. The period of performance for the original Subcontract was I October 1994 to 31 December 1996. Obviously, we have not completed, nor are we expected to complete, all of the scope of work in the Subcontract. The following discussion summarizes progress made on the tasks outlined in the Statement of Work for this Subcontract Details of this work and all data acquired by Hydro Geo Chem for this Subcontract have, been systematically organized in logbooks and - laboratory notebooks (Appendices A and B). These documents have been structured to make it easy to trace the analytical history of a sample, from time of receipt to the final analytical results. The current status of this work and its relevance for the Yucca Mountain Project are described in a LANL report co-authored by Hydro Geo Chem staff

Borehole Tool for the Comprehensive Characterization of Hydrate-bearing Sediments

KAUST Repository

Dai, Sheng; Santamarina, Carlos

2018-01-01

Reservoir characterization and simulation require reliable parameters to anticipate hydrate deposits responses and production rates. The acquisition of the required fundamental properties currently relies on wireline logging, pressure core testing, and/or laboratory ob-servations of synthesized specimens, which are challenged by testing capabilities and in-nate sampling disturbances. The project reviews hydrate-bearing sediments, properties, and inherent sampling effects, albeit lessen with the developments in pressure core technology, in order to develop robust correlations with index parameters. The resulting information is incorporated into a tool for optimal field characterization and parameter selection with un-certainty analyses. Ultimately, the project develops a borehole tool for the comprehensive characterization of hydrate-bearing sediments at in situ, with the design recognizing past developments and characterization experience and benefited from the inspiration of nature and sensor miniaturization.

Borehole Tool for the Comprehensive Characterization of Hydrate-bearing Sediments

KAUST Repository

Dai, Sheng

2018-02-01

Reservoir characterization and simulation require reliable parameters to anticipate hydrate deposits responses and production rates. The acquisition of the required fundamental properties currently relies on wireline logging, pressure core testing, and/or laboratory ob-servations of synthesized specimens, which are challenged by testing capabilities and in-nate sampling disturbances. The project reviews hydrate-bearing sediments, properties, and inherent sampling effects, albeit lessen with the developments in pressure core technology, in order to develop robust correlations with index parameters. The resulting information is incorporated into a tool for optimal field characterization and parameter selection with un-certainty analyses. Ultimately, the project develops a borehole tool for the comprehensive characterization of hydrate-bearing sediments at in situ, with the design recognizing past developments and characterization experience and benefited from the inspiration of nature and sensor miniaturization.

Borehole Tool for the Comprehensive Characterization of Hydrate-bearing Sediments

Energy Technology Data Exchange (ETDEWEB)

Dai, Sheng [Georgia Inst. of Technology, Atlanta, GA (United States); Santamarina, J. Carlos [Georgia Inst. of Technology, Atlanta, GA (United States); King Abdullah Univ. of Science and Technology (KAUST), Thuwal (Saudi Arabia)

2017-12-30

Reservoir characterization and simulation require reliable parameters to anticipate hydrate deposits responses and production rates. The acquisition of the required fundamental properties currently relies on wireline logging, pressure core testing, and/or laboratory observations of synthesized specimens, which are challenged by testing capabilities and innate sampling disturbances. The project reviews hydrate-bearing sediments, properties, and inherent sampling effects, albeit lessen with the developments in pressure core technology, in order to develop robust correlations with index parameters. The resulting information is incorporated into a tool for optimal field characterization and parameter selection with uncertainty analyses. Ultimately, the project develops a borehole tool for the comprehensive characterization of hydrate-bearing sediments at in situ, with the design recognizing past developments and characterization experience and benefited from the inspiration of nature and sensor miniaturization.

Multi-method characterization of low-level radioactive waste at two Sandia National Laboratories environmental restoration sites

International Nuclear Information System (INIS)

Johnson, C.E. Jr.; Galloway, R.B.; Dotson, P.W.

1999-01-01

This paper discusses the application of multiple characterization methods to radioactive wastes generated by the Sandia National Laboratories/New Mexico (SNL/NM) Environmental Restoration (ER) Project during the excavation of buried materials at the Classified Waste Landfill (CWLF) and the Radioactive Waste Landfill (RWL). These waste streams include nuclear weapon components and other refuse that are surface contaminated or contain sealed radioactive sources with unknown radioactivity content. Characterization of radioactive constituents in RWL and CWLF waste has been problematic, due primarily to the lack of documented characterization data prior to burial. A second difficulty derives from the limited information that ER project personnel have about weapons component design and testing that was conducted in the early days of the Cold War. To reduce the uncertainties and achieve the best possible waste characterization, the ER Project has applied both project-specific and industry-standard characterization methods that, in combination, serve to define the types and quantities of radionuclide constituents in the waste. The resulting characterization data have been used to develop waste profiles for meeting disposal site waste acceptance criteria

Yoga Meditation Practitioners Exhibit Greater Gray Matter Volume and Fewer Reported Cognitive Failures: Results of a Preliminary Voxel-Based Morphometric Analysis

Directory of Open Access Journals (Sweden)

Brett Froeliger

2012-01-01

Full Text Available Hatha yoga techniques, including physical postures (asanas, breathing exercises (pranayama, and meditation, involve the practice of mindfulness. In turn, yoga meditation practices may induce the state of mindfulness, which, when evoked recurrently through repeated practice, may accrue into trait or dispositional mindfulness. Putatively, these changes may be mediated by experience-dependent neuroplastic changes. Though prior studies have identified differences in gray matter volume (GMV between long-term mindfulness practitioners and controls, no studies to date have reported on whether yoga meditation is associated with GMV differences. The present study investigated GMV differences between yoga meditation practitioners (YMP and a matched control group (CG. The YMP group exhibited greater GM volume in frontal, limbic, temporal, occipital, and cerebellar regions; whereas the CG had no greater regional greater GMV. In addition, the YMP group reported significantly fewer cognitive failures on the Cognitive Failures Questionnaire (CFQ, the magnitude of which was positively correlated with GMV in numerous regions identified in the primary analysis. Lastly, GMV was positively correlated with the duration of yoga practice. Results from this preliminary study suggest that hatha yoga practice may be associated with the promotion of neuroplastic changes in executive brain systems, which may confer therapeutic benefits that accrue with repeated practice.

Characterization of leaky faults

International Nuclear Information System (INIS)

Shan, Chao.

1990-05-01

Leaky faults provide a flow path for fluids to move underground. It is very important to characterize such faults in various engineering projects. The purpose of this work is to develop mathematical solutions for this characterization. The flow of water in an aquifer system and the flow of air in the unsaturated fault-rock system were studied. If the leaky fault cuts through two aquifers, characterization of the fault can be achieved by pumping water from one of the aquifers, which are assumed to be horizontal and of uniform thickness. Analytical solutions have been developed for two cases of either a negligibly small or a significantly large drawdown in the unpumped aquifer. Some practical methods for using these solutions are presented. 45 refs., 72 figs., 11 tabs

THE MODEL OF FORMATION A PORTFOLIO OF THE INTERNATIONAL ACTIVITIES PROJECTS OF HEI

Directory of Open Access Journals (Sweden)

Сергей Васильевич РУДЕНКО

2016-02-01

Full Text Available The paper discusses an approach to assessing the project's value of the university international activities, based on the method of expert assessments and fuzzy-multiple method. Evaluating the effectiveness of the university-based project approach is a key factor in its competitiveness. The necessity substantiated of projects valuation of the university international activities. The concept is based on the matrices evaluation value product, process, international activities and development. For integral evaluation value of the university international activities project, we propose viewed from the standpoint of efficiency of all its results. These results can be roughly characterized by the following benchmarks: educational, scientific, technical, political, economic and social. In turn, key benchmarks characterized by its parameters, which estimate conducted by experts. Rating value of the university international activities project is to define the integral indicator of the value of the project. The proposed approach to determining the value of the international activities university projects, based on expert assessments and methods of fuzzy set theory will evaluate the effectiveness of these projects and implement the optimal choice.

Digface characterization test plan (remote testing)

International Nuclear Information System (INIS)

Croft, K.; Hyde, R.; Allen, S.

1993-08-01

The objective of the Digface Characterization (DFC) Remote Testing project is to remotely deploy a sensor head (Mini-Lab) across a digface to determine if it can characterize the contents below the surface. The purpose of this project is to provide a robotics technology that allows removal of workers from hazards, increases speed of operations, and reduces life cycle costs compared to alternate methods and technologies. The Buried Waste Integrated Demonstration (BWID) is funding the demonstration, testing, and evaluation of DFC. This document describes the test plan for the DFC remote deployment demonstration for the BWID. The purposes of the test plan are to establish test parameters so that the demonstration results are deemed useful and usable and perform the demonstration in a safe manner and within all regulatory requirements

Spent nuclear fuel project technical databook

Energy Technology Data Exchange (ETDEWEB)

Reilly, M.A.

1998-07-22

The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values.

Spent nuclear fuel project technical databook

International Nuclear Information System (INIS)

Reilly, M.A.

1998-01-01

The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values

Geology, Surficial, Neuse River Basin Mapping Project Core Locations �Äö?Ñ?¨ Ongoing project in Middle Coastal Plain to characterize geomorphology, surficial geology, and shallow aquifers and confining units; Excel spread sheet with core names, coordinates, and data co, Published in 2006, 1:24000 (1in=2000ft) scale, North Carolina Department of Environment and Natural Resources (DENR).

Data.gov (United States)

NSGIC State | GIS Inventory — Geology, Surficial dataset current as of 2006. Neuse River Basin Mapping Project Core Locations �Äö?Ñ?¨ Ongoing project in Middle Coastal Plain to characterize...

The International Stripa Project: an overview

International Nuclear Information System (INIS)

Fairhurst, C.; Gera, F.; Gnirk, P.; Gray, M.; Stillborg, B.

1993-01-01

The International Stripa Project was a a cooperative research and development project among several member countries of the Nuclear Energy Agency of the Organization for Economic Cooperation and Development. The scientific and technical objectives of the project were to investigate several aspects of technology concerned with the feasibility and safety of disposal of long-lived, heat-generating radioactive waste at depth in granitic rocks. In particular, the Stripa Project addressed: 1) the development of instruments and procedures to characterize candidate repository sites; 2) the understanding and modelling of groundwater flow and solute transport in fractured crystalline rock; and 3) the design of engineered barriers capable of contributing to waste isolation by restricting groundwater flow in proximity to the waste containers and in the surrounding host rock. This overview summarizes the work focussed on natural barriers and engineered barriers. (author)

Preparation, Characterization, and Selectivity Study of Mixed-Valence Sulfites

Science.gov (United States)

Silva, Luciana A.; de Andrade, Jailson B.

2010-01-01

A project involving the synthesis of an isomorphic double sulfite series and characterization by classical inorganic chemical analyses is described. The project is performed by upper-level undergraduate students in the laboratory. This compound series is suitable for examining several chemical concepts and analytical techniques in inorganic…

CCD characterization and measurements automation

Czech Academy of Sciences Publication Activity Database

Kotov, I.V.; Frank, J.; Kotov, A.I.; Kubánek, Petr; O´Connor, P.; Prouza, Michael; Radeka, V.; Takacs, P.

2012-01-01

Roč. 695, Dec (2012), 188-192 ISSN 0168-9002 R&D Projects: GA MŠk ME09052 Institutional research plan: CEZ:AV0Z10100502 Keywords : CCD * characterization * test automation Subject RIV: BN - Astronomy, Celestial Mechanics, Astrophysics Impact factor: 1.142, year: 2012

Summer Student Project: GEM Simulation and Gas Mixture Characterization

CERN Document Server

Oviedo Perhavec, Juan Felipe

2013-01-01

Abstract This project is a numerical simulation approach to Gas Electron Multiplier (GEM) detectors design. GEMs are a type of gaseous ionization detector that have proposed as an upgrade for CMS muon endcap. The main advantages of this technology are high spatial and time resolution and outstanding aging resistance. In this context, fundamental physical behavior of a Gas Electron Multiplier (GEM) is analyzed using ANSYS and Garfield++ software coupling. Essential electron transport properties for several gas mixtures were computed as a function of varying electric and magnetic field using Garfield++ and Magboltz.

ICT and the Project Studies at Roskilde University, Denmark

DEFF Research Database (Denmark)

Nielsen, Jørgen Lerche; Ou, Tie

2004-01-01

needs for qualification and reform. With distinctive philosophy and approach in education, studies at Roskilde University are organized as project work characterized by problem orientation, participant direction, exemplarity, interdisciplinarity and collaborative learning. The paper addresses how...... the increasing application of ICT is changing the educational environments at Roskilde University and, consequently, facilitating and challenging the project studies. The discussion is mainly based on an empirical research in which we observed a group of students and participated in their project work. The data...

Report on materials characterization center workshop on stress corrosion cracking for the Salt Repository Project, December 16-17, 1986, Seattle, Washington: Workshop summary

International Nuclear Information System (INIS)

Merz, M.D.; Shannon, D.W.

1986-09-01

The Materials Characterization Center (MCC) at Pacific Northwest Laboratory (PNL) conducted a Workshop on Stress Corrosion Cracking for the Salt Repository Project on December 16 and 17, 1986 in Seattle, Washington. The workshop was held to formulate recommendations for addressing stress corrosion cracking (SCC) in a salt repository. It was attended by 24 representatives from major laboratories, universities, and industry. This report presents the recommendations of the workshop, along with the agenda, list of participants, questions and comments, summaries of working groups on low-strength steel and alternate materials, and materials handed out by the speakers

The Yucca Mountain Project Prototype Testing Program

International Nuclear Information System (INIS)

1989-10-01

The Yucca Mountain Project is conducting a Prototype Testing Program to ensure that the Exploratory Shaft Facility (ESF) tests can be completed in the time available and to develop instruments, equipment, and procedures so the ESF tests can collect reliable and representative site characterization data. This report summarizes the prototype tests and their status and location and emphasizes prototype ESF and surface tests, which are required in the early stages of the ESF site characterization tests. 14 figs

Afraid to Start Because the Outcome is Uncertain?: Social Site Characterization as a Tool for Informing Public Engagement Efforts

Science.gov (United States)

Wade, S.; Greenberg, S.

2009-01-01

This paper introduces the concept of social site characterization as a parallel effort to technical site characterization to be used in evaluating and planning carbon dioxides capture and storage (CCS) projects. Social site characterization, much like technical site characterization, relies on a series of iterative investigations into public attitudes towards a CCS project and the factors that will shape those views. This paper also suggests ways it can be used to design approaches for actively engaging stakeholders and communities in the deployment of CCS projects. This work is informed by observing the site selection process for FutureGen and the implementation of research projects under the Regional Carbon Sequestration Partnership Program. ?? 2009 Elsevier Ltd. All rights reserved.

Modeling high-temperature superconductors and metallic alloys on the Intel IPSC/860

Science.gov (United States)

Geist, G. A.; Peyton, B. W.; Shelton, W. A.; Stocks, G. M.

Oak Ridge National Laboratory has embarked on several computational Grand Challenges, which require the close cooperation of physicists, mathematicians, and computer scientists. One of these projects is the determination of the material properties of alloys from first principles and, in particular, the electronic structure of high-temperature superconductors. While the present focus of the project is on superconductivity, the approach is general enough to permit study of other properties of metallic alloys such as strength and magnetic properties. This paper describes the progress to date on this project. We include a description of a self-consistent KKR-CPA method, parallelization of the model, and the incorporation of a dynamic load balancing scheme into the algorithm. We also describe the development and performance of a consolidated KKR-CPA code capable of running on CRAYs, workstations, and several parallel computers without source code modification. Performance of this code on the Intel iPSC/860 is also compared to a CRAY 2, CRAY YMP, and several workstations. Finally, some density of state calculations of two perovskite superconductors are given.

Plan for Characterization of K Basin Spent Nuclear Fuel (SNF) and Sludge (OCRWM)

International Nuclear Information System (INIS)

TRIMBLE, D.J.

2000-01-01

This is an update of the plan for the characterization of spent nuclear fuel (SNF) and sludge stored in the Hanford K West and K East Basins. The purpose of the characterization program is to provide fuel and sludge data in support of the SNF Project in the effort to remove the fuel from the K Basins and place it into dry storage. Characterization of the K Basin fuel and sludge was initiated in 1994 and has been guided by the characterization plans (Abrefah 1994, Lawrence 1995a, Lawrence 1995b) and the characterization program management plan (PMP) (Lawrence 1995c, Lawrence 1998, Trimble 1999). The fuel characterization was completed in 1999. Summaries of these activities were documented by Lawrence (1999) and Suyama (1999). Lawrence (1999) is a summary report providing a road map to the detailed documentation of the fuel characterization. Suyama (1999) provides a basis for the limited characterization sample size as it relates to supporting design limits and the operational safety envelope for the SNF Project. The continuing sludge characterization is guided by a data quality objective (DQO) (Makenas 2000) and a sampling and analysis plan (SAP) (Baker, Welsh and Makenas 2000) The original intent of the characterization program was ''to provide bounding behavior for the fuel'' (Lawrence 1995a). To accomplish this objective, a fuel characterization program was planned that would provide data to augment data from the literature. The program included in-situ examinations of the stored fuel and laboratory testing of individual elements and small samples of fuel (Lawrence 1995a). Some of the planned tests were scaled down or canceled due to the changing needs of the SNF Project. The fundamental technical basis for the process that will be used to place the K Basin fuel into dry storage was established by several key calculations. These calculations characterized nominal and bounding behavior of fuel in Multi-Canister Overpacks (MCOs) during processing and storage

Reproduction of the Yucca Mountain Project TSPA-LA Uncertainty and Sensitivity Analyses and Preliminary Upgrade of Models

Energy Technology Data Exchange (ETDEWEB)

Hadgu, Teklu [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Nuclear Waste Disposal Research and Analysis; Appel, Gordon John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States). Nuclear Waste Disposal Research and Analysis

2016-09-01

Sandia National Laboratories (SNL) continued evaluation of total system performance assessment (TSPA) computing systems for the previously considered Yucca Mountain Project (YMP). This was done to maintain the operational readiness of the computing infrastructure (computer hardware and software) and knowledge capability for total system performance assessment (TSPA) type analysis, as directed by the National Nuclear Security Administration (NNSA), DOE 2010. This work is a continuation of the ongoing readiness evaluation reported in Lee and Hadgu (2014) and Hadgu et al. (2015). The TSPA computing hardware (CL2014) and storage system described in Hadgu et al. (2015) were used for the current analysis. One floating license of GoldSim with Versions 9.60.300, 10.5 and 11.1.6 was installed on the cluster head node, and its distributed processing capability was mapped on the cluster processors. Other supporting software were tested and installed to support the TSPA-type analysis on the server cluster. The current tasks included verification of the TSPA-LA uncertainty and sensitivity analyses, and preliminary upgrade of the TSPA-LA from Version 9.60.300 to the latest version 11.1. All the TSPA-LA uncertainty and sensitivity analyses modeling cases were successfully tested and verified for the model reproducibility on the upgraded 2014 server cluster (CL2014). The uncertainty and sensitivity analyses used TSPA-LA modeling cases output generated in FY15 based on GoldSim Version 9.60.300 documented in Hadgu et al. (2015). The model upgrade task successfully converted the Nominal Modeling case to GoldSim Version 11.1. Upgrade of the remaining of the modeling cases and distributed processing tasks will continue. The 2014 server cluster and supporting software systems are fully operational to support TSPA-LA type analysis.

DEPLOYMENT OF INNOVATIVE CHARACTERIZATION TECHNOLOGIES AND IMPLEMENTATION OF THE MARSSIM PROCESS AT RADIOLOGICALLY CONTAMINATED SITES.

Energy Technology Data Exchange (ETDEWEB)

KALB,P.D.; MILIAN,L.; LUCKETT,L.; WATTERS,D.; MILLER,K.M.; GOGOLAK,C.

2001-05-01

The success of this Accelerated Site Technology Deployment (ASTD) project is measured on several levels. First, the deployment of this innovative approach using in situ characterization, portable field laboratory measurements, and implementation of MARSSIM was successfully established for all three phases of D and D characterization, i.e., pre-job scoping, on-going disposition of waste, and final status surveys upon completion of the activity. Unlike traditional D and D projects, since the Brookhaven Graphite Research Reactor Decommissioning Project (BGRR-DP) is operating on an accelerated schedule, much of the work is being carried out simultaneously. Rather than complete a full characterization of the facility before D and D work begins, specific removal actions require characterization as the activity progresses. Thus, the need for rapid and cost-effective techniques for characterization is heightened. Secondly, since the approach used for this ASTD project was not thoroughly proven prior to deployment, a large effort was devoted to demonstrating technical comparability to project managers, regulators and stakeholders. During the initial phases, large numbers of replicate samples were taken and analyzed by conventional baseline techniques to ensure that BGRR-DP quality assurance standards were met. ASTD project staff prepared comparisons of data gathered using ISOCS and BetaScint with traditional laboratory methods and presented this information to BGRR-DP staff and regulators from EPA Region II, NYS Department of Environmental Conservation, and the Suffolk County Board of Health. As the results of comparability evaluations became available, approval for these methods was received and the techniques associated with in situ characterization, portable field laboratory measurements, and implementation of MARSSIM were gradually integrated into BGRR-DP procedures.

DEPLOYMENT OF INNOVATIVE CHARACTERIZATION TECHNOLOGIES AND IMPLEMENTATION OF THE MARSSIM PROCESS AT RADIOLOGICALLY CONTAMINATED SITES

International Nuclear Information System (INIS)

KALB, P.D.; MILIAN, L.; LUCKETT, L.; WATTERS, D.; MILLER, K.M.; GOGOLAK, C.

2001-01-01

The success of this Accelerated Site Technology Deployment (ASTD) project is measured on several levels. First, the deployment of this innovative approach using in situ characterization, portable field laboratory measurements, and implementation of MARSSIM was successfully established for all three phases of D and D characterization, i.e., pre-job scoping, on-going disposition of waste, and final status surveys upon completion of the activity. Unlike traditional D and D projects, since the Brookhaven Graphite Research Reactor Decommissioning Project (BGRR-DP) is operating on an accelerated schedule, much of the work is being carried out simultaneously. Rather than complete a full characterization of the facility before D and D work begins, specific removal actions require characterization as the activity progresses. Thus, the need for rapid and cost-effective techniques for characterization is heightened. Secondly, since the approach used for this ASTD project was not thoroughly proven prior to deployment, a large effort was devoted to demonstrating technical comparability to project managers, regulators and stakeholders. During the initial phases, large numbers of replicate samples were taken and analyzed by conventional baseline techniques to ensure that BGRR-DP quality assurance standards were met. ASTD project staff prepared comparisons of data gathered using ISOCS and BetaScint with traditional laboratory methods and presented this information to BGRR-DP staff and regulators from EPA Region II, NYS Department of Environmental Conservation, and the Suffolk County Board of Health. As the results of comparability evaluations became available, approval for these methods was received and the techniques associated with in situ characterization, portable field laboratory measurements, and implementation of MARSSIM were gradually integrated into BGRR-DP procedures

Measurement techniques for radiological characterization of contaminated sites

Energy Technology Data Exchange (ETDEWEB)

Loos, M

1996-09-18

Once the decision is taken to characterize a contaminated site, appropriate measurement techniques must be selected. The choice will depend on the available information, on the nature and extent of the contamination, as well as on available resources (staff and budget). Some techniques are described on the basis of examples of characterization projects (e.g. Olen area in Belgium).

OECD Halden reactor project

International Nuclear Information System (INIS)

1979-01-01

This is the nineteenth annual Report on the OECD Halden Reactor Project, describing activities at the Project during 1978, the last year of the 1976-1978 Halden Agreement. Work continued in two main fields: test fuel irradiation and fuel research, and computer-based process supervision and control. Project research on water reactor fuel focusses on various aspects of fuel behavior under normal, and off-normal transient conditions. In 1978, participating organisations continued to submit test fuel for irradiation in the Halden boiling heavy-water reactor, in instrumented test assemblies designed and manufactured by the Project. Work included analysis of the impact of fuel design and reactor operating conditions on fuel cladding behavior. Fuel performance modelling included characterization of thermal and mechanical behavior at high burn-up, of fuel failure modes, and improvement of data qualification procedures to reduce and quantify error bands on in-reactor measurements. Instrument development yielded new or improved designs for measuring rod temperature, internal pressure, axial neutron flux shape determination, and for detecting cladding defects. Work on computer-based methods of reactor supervision and control included continued development of a system for predictive core surveillance, and of special mathematical methods for core power distribution control

CLASSIFICATION OF THE MGR WASTE HANDLING BUILDING VENTILATION SYSTEM

International Nuclear Information System (INIS)

J.A. Ziegler

2000-01-01

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) waste handling building ventilation system structures, systems and components (SSCs) performed by the MGR Preclosure Safety and Systems Engineering Section. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 2000). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 2000). This QA classification incorporates the current MGR design and the results of the ''Design Basis Event Frequency and Dose Calculation for Site Recommendation'' (CRWMS M andO 2000a) and ''Bounding Individual Category 1 Design Basis Event Dose Calculation to Support Quality Assurance Classification'' (Gwyn 2000)

Subharmonic projections for a quantum Markov semigroup

International Nuclear Information System (INIS)

Fagnola, Franco; Rebolledo, Rolando

2002-01-01

This article introduces a concept of subharmonic projections for a quantum Markov semigroup, in view of characterizing the support projection of a stationary state in terms of the semigroup generator. These results, together with those of our previous article [J. Math. Phys. 42, 1296 (2001)], lead to a method for proving the existence of faithful stationary states. This is often crucial in the analysis of ergodic properties of quantum Markov semigroups. The method is illustrated by applications to physical models

Tank 241-A-104 tank characterization plan

International Nuclear Information System (INIS)

Schreiber, R.D.

1994-01-01

This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, WHC 222-S Laboratory, and PNL 325 Analytical Chemistry Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of auger samples from tank 241-A-104. This Tank Characterization Plan will identify characterization objectives pertaining to sample collection, hot cell sample isolation, and laboratory analytical evaluation and reporting requirements in addition to reporting the current contents and status of the tank as projected from historical information

Projection correlation between two random vectors.

Science.gov (United States)

Zhu, Liping; Xu, Kai; Li, Runze; Zhong, Wei

2017-12-01

We propose the use of projection correlation to characterize dependence between two random vectors. Projection correlation has several appealing properties. It equals zero if and only if the two random vectors are independent, it is not sensitive to the dimensions of the two random vectors, it is invariant with respect to the group of orthogonal transformations, and its estimation is free of tuning parameters and does not require moment conditions on the random vectors. We show that the sample estimate of the projection correction is [Formula: see text]-consistent if the two random vectors are independent and root-[Formula: see text]-consistent otherwise. Monte Carlo simulation studies indicate that the projection correlation has higher power than the distance correlation and the ranks of distances in tests of independence, especially when the dimensions are relatively large or the moment conditions required by the distance correlation are violated.

Understanding Project Based Production through Socio-technical Modularity

DEFF Research Database (Denmark)

Thuesen, Christian Langhoff

This paper develops an approach for understanding Project Based Production. This form of production is characterized by unique deliverables, high complexity, high value, high risk, profound uncertainty and many stakeholders and is increasingly important the postmodern society. Common to the pract......This paper develops an approach for understanding Project Based Production. This form of production is characterized by unique deliverables, high complexity, high value, high risk, profound uncertainty and many stakeholders and is increasingly important the postmodern society. Common...... to the practices of PBP and other production practices is the goal of balancing the dilemma between creativity and productivity. In response to industrialized production, the concept of modularity gained popularity for addressing this dilemma by exploring product, process and organization structures. However...... with the starting point in system theory and a strong bias towards industrial production, the predominant understanding of modularity faces difficulty in explaining practices of Project Based Production in both social – technical and dynamic – stable aspects. Illustrated by a case the paper addresses this gap...

DebriSat - A Planned Laboratory-Based Satellite Impact Experiment for Breakup Fragment Characterizations

Science.gov (United States)

Liou, Jer-Chyi; Clark, S.; Fitz-Coy, N.; Huynh, T.; Opiela, J.; Polk, M.; Roebuck, B.; Rushing, R.; Sorge, M.; Werremeyer, M.

2013-01-01

The goal of the DebriSat project is to characterize fragments generated by a hypervelocity collision involving a modern satellite in low Earth orbit (LEO). The DebriSat project will update and expand upon the information obtained in the 1992 Satellite Orbital Debris Characterization Impact Test (SOCIT), which characterized the breakup of a 1960 s US Navy Transit satellite. There are three phases to this project: the design and fabrication of DebriSat - an engineering model representing a modern, 60-cm/50-kg class LEO satellite; conduction of a laboratory-based hypervelocity impact to catastrophically break up the satellite; and characterization of the properties of breakup fragments down to 2 mm in size. The data obtained, including fragment size, area-to-mass ratio, density, shape, material composition, optical properties, and radar cross-section distributions, will be used to supplement the DoD s and NASA s satellite breakup models to better describe the breakup outcome of a modern satellite.

Cutting-edge characterization technologies for D and D

International Nuclear Information System (INIS)

Bossart, S.J.; Kasper, K.M.

1998-01-01

The US Department of Energy's (DOE's) Office of Science and Technology (OST) has been developing and demonstrating technologies to improve methods used to characterize the presence and quantity of contaminants. As a part of OST, the Deactivation and Decommissioning (D and D) Focus Area has been developing and demonstrating innovative technologies for facility characterization to reduce costs associated with this important D and D activity. Characterization activities are an essential and substantial part of D and D. An initial scoping survey must be done to identify personnel hazards and to develop a decommissioning plan. Detailed characterization data must be collected to determine the type and magnitude of contaminants to begin decontamination and dismantlement activities. Surveys must be done during decontamination activities to determine the effectiveness of the decontamination efforts. A final status survey is required, and a confirmatory survey may also be required to document the end-state of a facility. These extensive characterization efforts contribute substantially to the overall cost of a D and D project. Through its Large-Scale Demonstration Program, the D and D Focus Area has been demonstrating many innovative technologies to improve D and D characterization processes. During the large-scale demonstration projects, innovative characterization technologies are evaluated alongside competing baseline technologies. Innovative technology summary reports are being generated on all of these technologies. When they are completed, they will be available through the DOE Office of Science and Technology's Homepage at http://em-52.em.doe.gov/idf/ost/pubs.htm

Plans for characterization of salt sites in the United States of America

International Nuclear Information System (INIS)

Heim, G.E.; Matthews, S.C.; Kircher, J.F.; Kennedy, R.K.

1984-02-01

The characterization plans presented in this paper are considered to be basic in nature and are the minimum program that meets project needs. The proposed basic program can be applied to any of the salt sites under consideration. It has been designed to provide the data required to support the design, performance assessment, and licensing of each of the principal project elements: the repository, the shafts, and the surface facilities. The work has been sequenced to meet the design and licensing schedule. It is anticipated that additional characterization activities will be performed to address site-specific considerations and to provide additional information to address questions which arise during the evaluation of characterization data. The information obtained during the characterization program will be incorporated into: the site characterization plan, the site recommendation report, the environmental impact statement, and the construction authorization application

Contracts for field projects and supporting research on enhanced oil recovery. Progress review number 87

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-10-01

Approximately 30 research projects are summarized in this report. Title of the project, contract number, company or university, award amount, principal investigators, objectives, and summary of technical progress are given for each project. Enhanced oil recovery projects include chemical flooding, gas displacement, and thermal recovery. Most of the research projects though are related to geoscience technology and reservoir characterization.

Characterization of solar cells

Energy Technology Data Exchange (ETDEWEB)

Haerkoenen, J.; Tuominen, E.; Nybergh, K.; Ezer, Y.; Yli-Koski, M.; Sinkkonen, J. [Helsinki Univ. of Technology, Otaniemi (Finland). Dept. of Electrical and Communications Engineering

1998-10-01

Photovoltaic research in the Electron Physics Laboratory started in 1993, when laboratory joined the national TEKES/NEMO 2 research program. Since the beginning of the project, characterization as well as experimentally orientated development of the fabrication process of the solar cells were carried out parallery. The process development research started by the initiatives of the Finnish industry. At the moment a large amount of the laboratory personnel works on solar cell research and the financing comes mainly from external projects. The funding for the research has come from TEKES, Ministry of Education, Finnish Academy, GETA graduate school, special equipment grants of the university, and from the laboratory

The Palmottu analogue project

International Nuclear Information System (INIS)

Ahonen, L.; Blomqvist, R.; Suksi, J.

1993-01-01

The report gives a summary of the results of investigations carried out in 1992 at the Palmottu natural analogue study site, which is a small U-Th mineralization in Nummi-Pusula, southwestern Finland. Additionally, the report includes several separate articles dealing with various aspects of the Palmottu Analogue Project: (1) deep groundwater flow, (2) interpretation of hydraulic connections, (3) characterization of groundwater colloids, (4) uranium mineral-groundwater equilibrium, (5) water-rock interaction and (6) modelling of in situ matrix diffusion. The Palmottu Analogue Project aims at a more profound understanding of radionuclide transport processes in fractured crystalline bedrock. The essential factors controlling transport are groundwater flow and interaction between water and rock. Accordingly, the study includes (1) structural interpretations partly based on geophysical measurements, (2) hydrological studies including hydraulic drill-hole measurements, (3) flow modelling, (4) hydrogeochemical characterization of groundwater, uranium chemistry and colloid chemistry, (5) mineralogical studies, (6) geochemical interpretation and modelling, (7) studies of radionuclide mobilization and retardation including matrix diffusion, and (8) modelling of uranium series data. Palaeohydrogeological aspects, due to the anticipated future glaciation of the Fennoscandian Shield, are of special interest. Quaternary sediments are studied to gain information on post-glacial migration in the overburden. (orig.)

Programming a real code in a functional language (part 1)

Energy Technology Data Exchange (ETDEWEB)

Hendrickson, C.P.

1991-09-10

For some, functional languages hold the promise of allowing ease of programming massively parallel computers that imperative languages such as Fortran and C do not offer. At LLNL, we have initiated a project to write the physics of a major production code in Sisal, a functional language developed at LLNL in collaboration with researchers throughout the world. We are investigating the expressibility of Sisal, as well as its performance on a shared-memory multiprocessor, the Y-MP. An interesting aspect of the project is that Sisal modules can call Fortran modules, and are callable by them. This eliminates the rewriting of 80% of the production code that would not benefit from parallel execution. Preliminary results indicate that the restrictive nature of the language does not cause problems in expressing the algorithms we have chosen. Some interesting aspects of programming in a mixed functional-imperative environment have surfaced, but can be managed. 8 refs.

NNWSI environmental characterization prior to the exploratory shaft

International Nuclear Information System (INIS)

Bertram, S.G.; Everett, J.J.

1982-01-01

The primary objective of the environmental characterization is to ensure that the site characterization and selection are in compliance with the National Environmental Policy Act (NEPA) and with applicable federal, state and local environmental laws and regulations. This paper describes the overview of the screening area and the Yucca Mountain biological and archaeological field studies. No further environmetal data will be collected for the 970 km 2 screening area because the NNWSI Project has selected the Yucca Mountain location for site characterization

Time-Frequency Analysis and Hermite Projection Method Applied to Swallowing Accelerometry Signals

Directory of Open Access Journals (Sweden)

Ervin Sejdić

2010-01-01

Full Text Available Fast Hermite projections have been often used in image-processing procedures such as image database retrieval, projection filtering, and texture analysis. In this paper, we propose an innovative approach for the analysis of one-dimensional biomedical signals that combines the Hermite projection method with time-frequency analysis. In particular, we propose a two-step approach to characterize vibrations of various origins in swallowing accelerometry signals. First, by using time-frequency analysis we obtain the energy distribution of signal frequency content in time. Second, by using fast Hermite projections we characterize whether the analyzed time-frequency regions are associated with swallowing or other phenomena (vocalization, noise, bursts, etc.. The numerical analysis of the proposed scheme clearly shows that by using a few Hermite functions, vibrations of various origins are distinguishable. These results will be the basis for further analysis of swallowing accelerometry to detect swallowing difficulties.

Projective geometry for polarization in geometric quantization

International Nuclear Information System (INIS)

Campbell, P.; Dodson, C.T.J.

1976-12-01

It is important to know the extent to which the procedure of geometric quantization depends on a choice of polarization of the symplectic manifold that is the classical phase space. Published results have so far been restricted to real and transversal polarizations. Here we also consider these cases by presenting a formulation in terms of projective geometry. It turns out that there is a natural characterization of real transversal polarizations and maps among them using projective concepts. We give explicit constructions for Rsup(2n)

[Earth Science Technology Office's Computational Technologies Project