Elucidating the effects of solar panel waste glass substitution on the physical and mechanical characteristics of clay bricks.

Science.gov (United States)

Lin, Kae-Long; Huang, Long-Sheng; Shie, Je-Lueng; Cheng, Ching-Jung; Lee, Ching-Hwa; Chang, Tien-Chin

2013-01-01

This study deals with the effect of solar panel waste glass on fired clay bricks. Brick samples were heated to temperatures which varied from 700-1000 degrees C for 6 h, with a heating rate of 10 degrees C min(-1). The material properties of the resultant material were then determined, including speciation variation, loss on ignition, shrinkage, bulk density, 24-h absorption rate, compressive strength and salt crystallization. The results indicate that increasing the amount of solar panel waste glass resulted in a decrease in the water absorption rate and an increase in the compressive strength of the solar panel waste glass bricks. The 24-h absorption rate and compressive strength of the solar panel waste glass brick made from samples containing 30% solar panel waste glass sintered at 1000 degrees C all met the Chinese National Standard (CNS) building requirements for first-class brick (compressive strengths and water absorption of the bricks were 300 kg cm(-2) and 10% of the brick, respectively). The addition of solar panel waste glass to the mixture reduced the degree of firing shrinkage. The salt crystallization test and wet-dry tests showed that the addition of solar panel waste glass had highly beneficial effects in that it increased the durability of the bricks. This indicates that solar panel waste glass is indeed suitable for the partial replacement of clay in bricks.

Minutes of the Tank Waste Science Panel meeting September 13--14, 1990

International Nuclear Information System (INIS)

Strachan, D.M.; Morgan, L.G.

1991-02-01

The third meeting of the Tank Waste Science Panel was held September 13--14, 1990. Science Panel members were briefed on the August 5, 1990, gas release from tank 241-101-SY (commonly denoted 101-SY), synthetic waste experiments to investigate gas generation and crust behavior in the tank, computer simulations of the thermal behavior of the waste in the tank, and calculations of gas generation based on radiolytic chemistry in alkaline solutions. Data from tanks 103-SY and 103-AN were presented, but it was decided not to divert attention from tank 101-SY at this time by taking additional samples from 103-SY or 103-AN. Science Panel members recommended that multiple groups begin a concerted experimental effort to understand the chemical and physical mechanisms involved in the tank. The understanding, along with the tank model, can then be used to determine the effectiveness of a particular mitigation method before using the method in tank 101-SY. 1 tab

Minutes of the Tank Waste Science Panel meeting July 9--1, 1991

International Nuclear Information System (INIS)

Strachan, D.M.

1992-04-01

The fifth meeting of the Tank Waste Science Panel was held July 9--11, 1991, in Atlanta, Georgia. The subject areas included the generation, retention, and release of gases from Tank 241-SY-101 and the chemistry of ferrocyanide wastes

Proceedings of the ninth annual DOE low-level waste management forum: executive summary, technical and special session summaries, attendees

International Nuclear Information System (INIS)

Anon.

1988-01-01

This first volume of proceedings contains summaries of each of six technical sessions as well as three special sessions held during the conference. The six technical sessions were: Disposal technology and facility development (15 papers); Institutional and regulatory issues (10); Performance assessment (14); Waste characterization and verification (7); Site closure and stabilization (6); and Waste treatment (8). The three special sessions were: 1) Review of criteria for guidance on alternative disposal technology; 2) Hazardous waste regulatory update; and 3) Challenges to meeting the 1993 deadline. All papers have been indexed for inclusion on the Energy Data Base

Scope and approach to management of mixed wastes: introduction to the session

International Nuclear Information System (INIS)

Ausmus, B.S.

1986-01-01

Mixed wastes are those that are termed both radioactive and chemically hazardous based on regulatory criteria in the United States. Historically, mixed wastes that could be classified as radioactive wastes were treated, stored, and disposed under statutes governing radioactive wastes. In recent years, it has become apparent that: (a) hazardous wastes are generated in nuclear facilities; (b) many wastes are both radioactive and chemically hazardous; and (c) the management of chemically hazardous wastes and mixed wastes requires reexamination of current waste treatment/disposal methods and development/implementation of modified methods. The purpose of this session is to discuss specific aspects of the mixed waste management problems and to provide a forum for discussion of the technical and institutional barriers to problem solutions. The paper addresses several mixed waste problems and current approaches to their solutions, including: (1) mixed waste management in fuel cycle facilities; (2) mixed waste management in a US Dept. of Energy production facility; and (3) mixed wastes impacts on 10CFR61 compliance. Technical and institutional approaches to mixed waste management are explored in three areas: (1) alternatives for treatment prior to shallow land disposal; (2) potential benefits of recovery of strategic/critical materials from mixed wastes; and (3) shallow land disposal system compatibilities/problems

Thermomechanical analysis of underground excavations in the vicinity of a nuclear waste isolation panel

International Nuclear Information System (INIS)

St John, C.M.

1987-06-01

This report summarizes the results of a series of analyses of excavations in the vicinity of waste emplacement panels. Specific consideration is given to the access drifts running between adjacent emplacement panels, the drift intersection at the entrance to the emplacement panels, and the waste emplacement excavations. Both horizontal and vertical emplacement models are considered, but greater emphasis is placed on the former. Three numerical modeling procedures were used in this study: a finite-element model was used for three-dimensional stress analysis of the tunnel intersection, a model based on the closed-form solution for point heat sources was used to predict temperatures and stresses in the vicinity of the emplacement panel, and simple two-dimensional boundary-element models were used to predict temperatures and stresses around excavations of various shapes. The results of two-dimensional stress analyses were postprocessed to determine the extent to which the strength of a rock mass, containing a set of vertical joints, was exceeded. The results presented in this report do not indicate that there will be any particular stability problems at the tunnel intersection investigated. Further, the effect of waste emplacement within the adjacent panels is to decrease the vertical rock stresses and increase the horizontal rock stresses at the intersection. These stress changes will tend to enhance the stability of larger-span excavations, including the tunnel intersection and the alcoves necessary for horizontal emplacement of waste canisters. The relatively high horizontal stresses experienced by the access were identified as a potential concern. However, evaluation of recent data on the thermomechanical properties of the rock mass modeled here has indicated that the stress changes will not be as severe as stated herein

Concepts for operational period panel seal design at the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Hansen, F.D.; Lin, M.S.; Van Sambeek, L.L.

1993-07-01

Concepts for underground panel or drift seals at the Waste Isolation Pilot Plant are developed to satisfy sealing requirements of the operational period. The concepts are divided into two groups. In the ''NOW'' group, design concepts are considered in which a sleeve structure is installed in the panel access immediately after excavation and before waste is emplaced. In the ''LATER'' group, no special measures are taken during excavation or before waste emplacement; the seal is installed at a later date, perhaps up to 35 years after the drift is excavated. Three concepts are presented in both the NOW and LATER groups. A rigid sleeve, a yielding sleeve, and steel rings with inflatable tubes are proposed as NOW concepts. One steel ring concept and two concrete monoliths are proposed for seals emplaced in older drifts. Advantages and disadvantages are listed for each concept. Based on the available information, it appears most feasible to recommend a LATER concept using a concrete monolith as a preferred seal for the operational period. Each concept includes the potential of remedial grout and/or construction of a chamber that could be used for monitoring leakage from a closed panel during the operational period. Supporting in situ demonstrations of elements of the concepts are recommended

Nuclear Waste Education Project

International Nuclear Information System (INIS)

1989-01-01

In summary, both the Atlanta and Albuquerque pilot seminars achieved the Nuclear Waste Education Project's goal of informing citizens on both the substance and the process of nuclear waste policy so that they can better participate in future nuclear waste decisions. Nuclear waste issues are controversial, and the seminars exposed the nature of the controversy, and utilized the policy debates to create lively and provocative sessions. The format and content of any citizen education curriculum must be made to fit the particular goal that has been chosen. If the Department of Energy and the LWVEF decide to continue to foster an informed dialogue among presenters and participants, the principles of controversial issues education would serve this goal well. If, however, the Department of Energy and/or the LWVEF decide to go beyond imparting information and promoting a lively discussion of the issues, towards some kind of consensus-building process, it would be appropriate to integrate more interactive sessions into the format. As one evaluator wrote, ''In-depth participation in finding solutions or establishing policy -- small group discussion'' would have been preferable to the plenary sessions that mostly were in the form of lectures and expert panel discussion. The evaluator continued by saying, ''Since these [small group discussions] would require more time commitment, they might be part of follow-up workshops focused on particular topics.''

Theory, practice, and history in critical GIS: Reports on an AAG panel session

Science.gov (United States)

Wilson, M.W.; Poore, B.S.

2009-01-01

Extending a special session held at the 2008 annual meeting of the Association of American Geographers in Boston, this commentary collection highlights elements of the critical GIS research agenda that are particularly pressing. Responding to a Progress report on critical GIS written by David O'Sullivan in 2006, these six commentaries discuss how different interpretations of 'critical' are traced through critical GIS research. Participants in the panel session discussed the need for a continued discussion of a code of ethics in GIS use in the context of ongoing efforts to alter or remake the software and its associated practices, of neo-geographies and volunteered geographies. There were continued calls for hope and practical ways to actualize this hope, and a recognition that critical GIS needs to remain relevant to the technology. This 'relevance' can be variously defined, and in doing so, researchers should consider their positioning vis-??-vis the technology. Throughout the commentaries collected here, a question remains as to what kind of work disciplinary sub-fields such as critical GIS and GIScience perform. This is a question about language, specifically the distance that language can create among practitioners and theoreticians, both in the case of critical GIS and more broadly throughout GIScience.

1994 Panel 1 Utilization Plan

International Nuclear Information System (INIS)

1994-01-01

The Waste Isolation Pilot Plant (WIPP) is intended to receive, handle, and permanently dispose of transuranic (TRU) waste. To fulfill this mission, the U.S. Department of Energy (DOE) constructed a full-scale facility to demonstrate both technical and operational principles of the permanent isolation of TRU waste. The WIPP consists of surface and underground facilities. Panel 1 is situated in the underground facility horizon which is located approximately 2,150 feet below the surface in the predominantly halite Salado Formation. The Panel 1 Utilization Plan provides a strategy for the optimum use of Panel 1 which is consistent with the priorities established by the DOE to accomplish the WIPP mission. These priorities, which include maintaining personnel safety, conducting performance assessment, and continued operational enhancements, are the guiding premise for the decisions on the planned usage of the WIPP underground facility. The continuation of ongoing investigations along with the planned testing and training to be carried out in Panel 1 will enhance the current knowledge and understanding of the operational and geotechnical aspects of the panel configuration. This enhancement will ultimately lead to safer, more efficient, and more cost-effective methods of operation. Excavation of the waste storage area began in May 1986 with the mining of entries to Panel 1. The original design for the waste storage rooms at the WIPP provided a limited period of time during which to mine the openings and to emplace waste. Each panel, consisting of seven storage rooms, was scheduled to be mined and filled in less than 5 years. Panel 1 was developed to receive waste for a demonstration phase that was scheduled to start in October 1988. The demonstration phase was deferred, and the experimental test program was modified to use contact-handled (CH) transuranic waste in bin-scale tests, planned for Room 1, Panel 1

Panel discussion. Session 1

International Nuclear Information System (INIS)

Rodgers, B.R.

1986-01-01

An attempt is made to identify problems that need research and development work in order to advance low-level radioactive waste technology and to put the industry in a better position in five to ten years, or even twenty-five years from now. Attention is focused on disposal methods, operating procedures, the effects of the establishment of the state compact, and de minimis criteria

Peer review panel summary report for technical determination of mixed waste incineration off-gas systems for Rocky Flats

International Nuclear Information System (INIS)

1992-01-01

A Peer Review Panel was convened on September 15-17, 1992 in Boulder, Co. The members of this panel included representatives from DOE, EPA, and DOE contractors along with invited experts in the fields of air pollution control and waste incineration. The primary purpose of this review panel was to make a technical determination of a hold, test and release off gas capture system should be implemented in the proposed RF Pland mixed waste incineration system; or if a state of the art continuous air pollution control and monitoring system should be utilized as the sole off-gas control system. All of the evaluations by the panel were based upon the use of the fluidized bed unit proposed by Rocky Flats and cannot be generalized to other systems

DELPHI expert panel evaluation of Hanford high level waste tank failure modes and release quantities

Energy Technology Data Exchange (ETDEWEB)

Dunford, G.L.; Han, F.C.

1996-09-30

The Failure Modes and Release Quantities of the Hanford High Level Waste Tanks due to postulated accident loads were established by a DELPHI Expert Panel consisting of both on-site and off-site experts in the field of Structure and Release. The Report presents the evaluation process, accident loads, tank structural failure conclusion reached by the panel during the two-day meeting.

Requirements for the safe management of radioactive waste. Proceedings of a seminar held in Vienna, 28-31 August 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

This publication contains the proceedings of the Seminar on Requirements for the Safe Management of Radioactive Waste held from 28 to 31 August 1995 in Vienna. The Seminar summarizes the experience gained up to date in the safe management of radioactive waste. The papers were presented by outstanding invited speakers from Member States. It is expected that the outcome of the presentations and discussions of the broad set of issues on radioactive waste management included in this publication will be used in the preparation process of the Convention on the Safe Management of Radioactive Waste. The information provided in this publication has been arranged as follows: The first part includes the opening statement and three topical presentations in the opening session and the paper on radioactive waste management as part of the environmental protection. The second, third and fourth parts include papers dealing with planning for safety, experience in the safe management of radioactive waste and radioactive waste management issues, respectively. The fifth part contains the summaries of the three sessions, including the respective panel discussions, provided by the chairman of each session. Finally, the sixth part incorporates statements by panelists and is a summary of the panel discussions provided by the respective chairmen on three topics: ``Implications of Treating Spent Fuel as High Level Waste``, ``Residues from Past Activities and Accidents`` and ``Exclusion, Exemption and Clearance of Materials from Nuclear Regulatory Control``. Refs, figs and tabs.

The consequences of disposal of low-level radioactive waste from the Fernald Environmental Management Project: Report of the DOE/Nevada Independent Panel

International Nuclear Information System (INIS)

Crowe, B.; Hansen, W.; Waters, R.; Sully, M.; Levitt, D.

1998-04-01

The Department of Energy (DOE) convened a panel of independent scientists to assess the performance impact of shallow burial of low-level radioactive waste from the Fernald Environmental Management Project, in light of a transportation incident in December 1997 involving this waste stream. The Fernald waste has been transported to the Nevada Test Site and disposed in the Area 5 Radioactive Waste Management Site (RWMS) since 1993. A separate DOE investigation of the incident established that the waste has been buried in stress-fractured metal boxes, and some of the waste contained excess moisture (high-volumetric water contents). The Independent Panel was charged with determining whether disposition of this waste in the Area 5 RWMS has impacted the conclusions of a previously completed performance assessment in which the site was judged to meet required performance objectives. To assess the performance impact on Area 5, the panel members developed a series of questions. The three areas addressed in these questions were (1) reduced container integrity, (2) the impact of reduced container integrity on subsidence of waste in the disposal pits and (3) excess moisture in the waste. The panel has concluded that there is no performance impact from reduced container integrity--no performance is allocated to the container in the conservative assumptions used in performance assessment. Similarly, the process controlling post-closure subsidence results primarily from void space within and between containers, and the container is assumed to degrade and collapse within 100 years

Recycling acetic acid from polarizing film of waste liquid crystal display panels by sub/supercritical water treatments.

Science.gov (United States)

Wang, Ruixue; Chen, Ya; Xu, Zhenming

2015-05-19

Waste liquid crystal display (LCD) panels mainly contain inorganic materials (glass substrate) and organic materials (polarizing film and liquid crystal). The organic materials should be removed first since containing polarizing film and liquid crystal is to the disadvantage of the indium recycling process. In the present study, an efficient and environmentally friendly process to obtain acetic acid from waste LCD panels by sub/supercritical water treatments is investigated. Furthermore, a well-founded reaction mechanism is proposed. Several highlights of this study are summarized as follows: (i) 99.77% of organic matters are removed, which means the present technology is quite efficient to recycle the organic matters; (ii) a yield of 78.23% acetic acid, a quite important fossil energy based chemical product is obtained, which can reduce the consumption of fossil energy for producing acetic acid; (iii) supercritical water acts as an ideal solvent, a requisite reactant as well as an efficient acid-base catalyst, and this is quite significant in accordance with the "Principles of Green Chemistry". In a word, the organic matters of waste LCD panels are recycled without environmental pollution. Meanwhile, this study provides new opportunities for alternating fossil-based chemical products for sustainable development, converting "waste" into "fossil-based chemicals".

Minutes of the Tank Waste Science Panel meeting, November 11--13, 1991

Energy Technology Data Exchange (ETDEWEB)

Strachan, D.M. (comp.)

1992-04-01

The sixth meeting of the Tank Waste Science Panel was held November 11--13, 1991, in Pasco and Richland, Washington. Participating scientists presented the results of recent work on various aspects of issues relating to the generation and release of gases from Tank 241-SY-101 and the presence of ferrocyanide in other tanks at Hanford. Results are discussed.

Minutes of the Tank Waste Science Panel meeting, November 11--13, 1991

International Nuclear Information System (INIS)

Strachan, D.M.

1992-04-01

The sixth meeting of the Tank Waste Science Panel was held November 11--13, 1991, in Pasco and Richland, Washington. Participating scientists presented the results of recent work on various aspects of issues relating to the generation and release of gases from Tank 241-SY-101 and the presence of ferrocyanide in other tanks at Hanford. Results are discussed

Incorporation of waste and fiber kaolin caroa panels in Medium Density Fiberboard - MDF

International Nuclear Information System (INIS)

Bezerra, A.F.C.; Santana, L.N.L.; Neves, G.A.; Carvalho, L.H. de; Lopes, F.F.M.

2012-01-01

Medium-density panels are composites molded under high temperature and pressure which have physical and mechanical properties similar to those of solid wood. Their composition includes eucalyptus grandis fibers and pinus elliotii fibers, but other fibers can be used such as caroa fibers. The goal of this work was to manufacture panels which kaolin waste and caroa fibers and compare their physical, chemical and mechanical of these panels with a others. Both residue and the fibers were characterized by: differential thermal analysis, thermal gravimetric analysis and Xray diffraction. Through the process of pressing the test specimens were fabricated, test samples were evaluated by three point bending, internal bond, water absorption and swelling in thickness. The samples have low levels of thickness swelling, flexural strength and higher tensile and absorption content relative to commercial MDF. (author)

Waste Isolation Pilot Plant supplementary roof support system underground storage area, Panel 1, Room 1

International Nuclear Information System (INIS)

1991-10-01

WIPP is designed to provide a full-scale facility to demonstrate the technical and operational principles for permanent isolation of defense-generated transuranic waste. It is also designed to provide a facility in which studies and experiments can be conducted. Bin Scale Tests are being planned as part of the WIPP Test Phase Performance Assessment Program described in the WIPP Test Phase Plan: Performance Assessment (DOE 1990 b). These Tests are anticipated to be conducted over a period of up to seven years. Room 1 of Panel 1 of the Underground Storage Area is to be used as the location of the Bin-Scale Tests to investigate the generation of gas from the waste that is proposed to be stored at the WIPP in the near future. The original design for the waste storage rooms in Panel 1 provided for a limited period of time during which to mine the openings and to emplace waste. Room 1 was initially mined to rough dimensions in 1986. Information obtained from the Site and Preliminary Design Validation (SPDV) program showed that the rooms would remain stable without ground support and that creep closure would not adversely affect equipment clearances during at least five years following excavation

Session Introduction

Science.gov (United States)

Eliane Lessner, Co-Chair:

2009-03-01

A panel discussion session providing a worldwide assessment of the status and experiences of women in physics, paying attention to the different cultures and environments they work in and to how the age of the physicist affects their perspective. We will hear about women physicists in Korea in particular and Asia in general, in Egypt in particular and Africa in general, and in the Caribbean. Six invited speakers will present analyses of the progress being made in promoting women in physics from their personal experiences and as assessed from their participation in the Third International Conference on Women In Physics (ICWIP2008) convened in Seoul, Korea in October 2008. From Albania to Zimbabwe, with representation of all the continents, ICWIP2008 congregated 283 women and men physicists from 57 countries to share the participants' scientific accomplishments and evaluate international progress in improving the status of women in physics. This three-hour session is organized jointly by the Committee on the Status of Women in Physics of the APS (CSWP) and the Forum on International Physics of the APS (FIP). Audience participation in the panel discussion will be strongly encouraged.

Minutes of the Tank Waste Science Panel meeting, July 20, 1990: Hanford Tank Safety Project

International Nuclear Information System (INIS)

Strachan, D.M.; Morgan, L.G.

1991-02-01

The second meeting of the Tank Waste Science Panel was held July 20, 1990. Science Panel members discussed the prioritization of various analyses to be performed on core samples from tank 101-SY, and were asked to review and comment on the draft Westinghouse Hanford Company document ''Analytical Chemistry Plan.'' They also reviewed and discussed the initial contributions to the report titled Chemical and Physical Processes in Tank 101-SY: A Preliminary Report. Science Panel members agreed that a fundamental understanding of the physical and chemical processes in the tank is essential, and strongly recommended that no remediation measures be taken until there is a better understanding of the chemical and physical phenomena that result in the episodic gas release from tank 101-SY. 1 ref

Waste Photovoltaic Panels for Ultrapure Silicon and Hydrogen through the Low-Temperature Magnesium Silicide.

Czech Academy of Sciences Publication Activity Database

Dytrych, Pavel; Bumba, Jakub; Kaštánek, František; Fajgar, Radek; Koštejn, Martin; Šolcová, Olga

Roč. 56, č. 45 ( 2017 ), s. 12863-12869 ISSN 0888-5885 R&D Projects: GA ČR GA15-14228S Institutional support: RVO:67985858 Keywords : magnesium silicide * waste photovoltaic panels * ultrapure silicon Subject RIV: CI - Industrial Chemistry, Chemical Engineering OBOR OECD: Chemical process engineering Impact factor: 2.843, year: 2016

Technological process and optimum design of organic materials vacuum pyrolysis and indium chlorinated separation from waste liquid crystal display panels

Energy Technology Data Exchange (ETDEWEB)

Ma, En; Xu, Zhenming, E-mail: zmxu@sjtu.edu.cn

2013-12-15

Highlights: • The vacuum pyrolysis–vacuum chlorinated separation system was proposed to recover the waste LCD panel. • The system can recycle the whole waste LCD panels efficiently without negative effects to environment. • The 82.03% of the organic materials was reclaimed. All pyrolysis products can be utilized by a reasonable way. • The separation of indium was optimized by the central composite design (CCD) under response surface methodology (RSM). • The recovery ratio of indium was further increased to 99.97%. -- Abstract: In this study, a technology process including vacuum pyrolysis and vacuum chlorinated separation was proposed to convert waste liquid crystal display (LCD) panels into useful resources using self-design apparatuses. The suitable pyrolysis temperature and pressure are determined as 300 °C and 50 Pa at first. The organic parts of the panels were converted to oil (79.10 wt%) and gas (2.93 wt%). Then the technology of separating indium was optimized by central composite design (CCD) under response surface methodology (RSM). The results indicated the indium recovery ratio was 99.97% when the particle size is less than 0.16 mm, the weight percentage of NH{sub 4}Cl to glass powder is 50 wt% and temperature is 450 °C. The research results show that the organic materials, indium and glass of LCD panel can be recovered during the recovery process efficiently and eco-friendly.

New directions in theory - the panel

International Nuclear Information System (INIS)

Miller, G.A.; British Columbia Univ., Vancouver

1990-01-01

This is a personalized summary of the panel session of 7 July, 1989. The intent of the session was to discuss important questions in few particle theory. The vigorous participation of the audience was sought and received. (orig.)

Topical Session on Materials Management

International Nuclear Information System (INIS)

2002-01-01

At its second meeting, in Paris, 5-7 December 2001, the WPDD held two topical sessions on the D and D Safety Case and on the Management of Materials from D and D, respectively. This report documents the topical session on the management of materials. Presentations during the topical session covered key aspects of the management of materials and meant to provide an exchange of information and experience, including: Experience and lessons learnt from VLLW and non-radioactive material management in Spain and Germany with special attention to recycling (How specific solutions came about? Are there 'generic' examples for wider adoption?); Risk assessment of recycling and non-recycling: a CPD study; Waste acceptance issues within different national contexts (What constraints are there on the waste receiving body and what flexibility can the latter have? What constraints does this impose on D and D implementers? What about wastes are without current solution? What needs to be done? What about large items and 'difficult' waste in general?); Radiological characterisation of materials during decommissioning, particularly difficult situations - large volumes, large items,.. wastes, heterogeneous streams (What examples of established practice? What are the approaches or aspects that set the regulatory requirements? How can the flow rates be large but the answers acceptable? How much is needed to be known for later action, e. g., disposal, release, protection of worker, etc.); Radiological characterisation of buildings as they stand, in order to allow conventional demolition (What are strategies for optimisation of characterisation? How much needs to be known to take action later? e.g. for storage, disposal, release, cost estimation and ALARA? What needs to be done in advance and after decommissioning/dismantling?). At the end of each presentation time was allotted for discussion of the paper. Integral to the Topical Session was a facilitated plenary discussion on the topical

Topical Session on 'Addressing Issues Raised by Stakeholders: Impacts on Process, Content and Behaviour in Waste Organisations'

International Nuclear Information System (INIS)

2004-01-01

At its 5. meeting in June 2004, the FSC held a topical session aimed at reviewing how organisations are adapting to the new outreach and decision-making context. Eleven organisations from eight countries provided the relevant information, which are collected in these proceedings. Learning and adapting to societal requirements - and organising institutions accordingly - is one of the main aspects of the future programme of work of the FSC. This topical session on 'Addressing Issues Raised by Stakeholders: Impacts on Process, Content and Behaviour in Waste Organisations' provides useful material for future initiatives as well as a source of information to interested stakeholders and practitioners. It focused on how regulators and implementers responded and are restructuring to respond to stakeholders' concerns, issues and needs regarding radioactive waste management

Reporting session of UWTF operation. Compilation of documents

International Nuclear Information System (INIS)

Shimizu, Kaoru; Togashi, Akio; Irinouchi, Shigenori

1999-07-01

This is the compilation of the papers and OHP transparencies presented, as well as discussions and comments, on the occasion of UWTF reporting session. UWTF stands for The Second Uranium Waste Treatment Facility, which was constructed for compression of metallic wastes and used filters, which are parts of uranium bearing solid wastes generated from Tokai Works, Japan Nuclear Cycle Development Institute. UWTF has been processing wastes since June 4 1998. In the session, based on the one year experience of UWTF operation, the difficulties met and the suggestions to the waste sources are mainly discussed. A brief summary of the UWTF construction, description of waste treatment process, and operation report of fiscal year 1998 are attached. (A. Yamamoto)

Update on Canada's nuclear fuel waste management program

International Nuclear Information System (INIS)

Allan, C.J.

1992-09-01

The Canadian Nuclear Fuel Waste Management Program (CNFWMP) was launched in 1978 as a joint initiative by the governments of Canada and Ontario. Under the program, AECL has been developing and assessing a generic concept to dispose of nuclear fuel waste in plutonic rock of the Canadian Shield. The disposal concept has been referred for review under the Environmental Assessment and Review Process. AECL will submit an Environmental Impact Statement (EIS) to an Environmental Assessment Panel, which was appointed in late 1989. Hearings will be held in areas that have a particular interest in the concept and its application. At the end of the review, the Panel will make recommendations as to the acceptability of the concept and the course of future action. The federal government will decide on the next steps to be taken. In the spring of 1990 public open houses were held to tell prospective participants how to enter the process. Sessions designed to assist the Panel in determining the scope of the EIS took place in the autumn of 1990. In June 1991 the Panel issued for comment a set of draft guidelines for the EIS. More than 30 groups and individuals submitted comments. The final guidelines were issued in March 1992, and AECL expects to submit its EIS to the Panel in 1993. If the concept review is completed by 1995 and if the concept is approved, disposal could begin some time after 2025. (L.L.) (12 refs.)

Hanford Tank Safety Project: Minutes of the Tank Waste Science Panel meeting, February 7--8, 1991

Energy Technology Data Exchange (ETDEWEB)

Strachan, D.M. [comp.

1991-06-01

The Tank Waste Science Panel met February 7--8, 1991, to review the latest data from the analyses of the October 24, 1990, gas release from Tank 241-SY-101 (101-SY) at Hanford; discuss the results of work being performed in support of the Hanford Tank Safety Project; and be briefed on the ferrocyanide issues included in the expanded scope of the Science Panel. The shapes of the gas release curves from the past three events are similar and correlate well with changes in waste level, but the correlation between the released volume of gas and the waste height is not as good. An analysis of the kinetics of gas generation from waste height measurements in Tank 101-SY suggests that the reaction giving rise to the gases in the tank is independent of the gas pressure and independent of the physical processes that give rise to the episodic release of the gases. Tank waste height data were also used to suggest that a floating crust formed early in the history of the tank and that the current crust is being made thicker in the eastern sector of the tank by repeated upheaval of waste slurry onto the surface. The correlation between the N{sub 2}O and N{sub 2} generated in the October release appears to be 1:1, suggesting a single mechanistic pathway. Analysis of other gas generation ratios, however, suggests that H{sub 2} and N{sub 2}O are evolved together, whereas N{sub 2} is from the air. If similar ratios are observed in planned radiolysis experiments are Argonne National Laboratory, radiolysis would appear to be generating most of the gases in Tank 101-SY. Data from analysis of synthetic waste crust using a dynamic x-ray diffractometer suggest that, in air, organics are being oxidized and liberating CO{sub 2} and NO{sub x}. Experiments at Savannah River Laboratory indicate that irradiation of solutions containing NO{sub 3} and organics can produce N{sub 2}O.

Minutes of the Tank Waste Science Panel meeting, November 11--13, 1991. Hanford Tank Safety Project

Energy Technology Data Exchange (ETDEWEB)

Strachan, D.M. [comp.

1992-04-01

The sixth meeting of the Tank Waste Science Panel was held November 11--13, 1991, in Pasco and Richland, Washington. Participating scientists presented the results of recent work on various aspects of issues relating to the generation and release of gases from Tank 241-SY-101 and the presence of ferrocyanide in other tanks at Hanford. Results are discussed.

Detailed design report for an operational phase panel-closure system

International Nuclear Information System (INIS)

1996-01-01

Under contract to Westinghouse Electric Corporation (Westinghouse), Waste Isolation Division (WID), IT Corporation has prepared a detailed design of a panel-closure system for the Waste Isolation Pilot Plant (WIPP). Preparation of this detailed design of an operational-phase closure system is required to support a Resource Conservation and Recovery Act (RCRA) Part B permit application and a non-migration variance petition. This report describes the detailed design for a panel-closure system specific to the WIPP site. The recommended panel-closure system will adequately isolate the waste-emplacement panels for at least 35 years. This report provides detailed design and material engineering specifications for the construction, emplacement, and interface-grouting associated with a panel-closure system at the WIPP repository, which would ensure that an effective panel-closure system is in place for at least 35 years. The panel-closure system provides assurance that the limit for the migration of volatile organic compounds (VOC) will be met at the point of compliance, the WIPP site boundary. This assurance is obtained through the inherent flexibility of the panel-closure system

The 1996 meeting of the national technical workgroup on mixed waste thermal treatment

International Nuclear Information System (INIS)

1996-01-01

The National Technical Workgroup on Mixed Waste Thermal Treatment held its annual meeting in Atlanta Georgia on March 12-14, 1996. The National Technical Workgroup (NTW) and this meeting were sponsored under an interagency agreement between EPA and DOE. The 1996 Annual Meeting was hosted by US DOE Oak Ridge Operations in conjunction with Lockheed Martin Energy Systems - Center for Waste Management. A new feature of the annual meeting was the Permit Writer Panel Session which provided an opportunity for the state and federal permit writers to discuss issues and potential solutions to permitting mixed waste treatment systems. In addition, there was substantial discussion on the impacts of the Waste Combustion Performance Standards on mixed waste thermal treatment which are expected to proposed very soon. The 1996 meeting also focussed on two draft technical resource documents produced by NTW on Waste Analysis Plans and Compliance Test Procedures. Issues discussed included public involvement, waste characterization, and emission issues

Toxicity assessment and feasible recycling process for amorphous silicon and CIS waste photovoltaic panels.

Science.gov (United States)

Savvilotidou, Vasiliki; Antoniou, Alexandra; Gidarakos, Evangelos

2017-01-01

End-of-Life (EoL) photovoltaic (P/V) modules, which are recently included in the 2012/19/EU recast, require sound and sustainable treatment. Under this perspective, this paper deals with 2nd generation P/V waste modules, known as thin-film, via applying chemical treatment techniques. Two different types of modules are examined: (i) tandem a-Si:H/μc-Si:H panel and, (ii) Copper-Indium-Selenide (CIS) panel. Panels' pretreatment includes collection, manual dismantling and shredding; pulverization and digestion are further conducted to identify their chemical composition. A variety of elements is determined in the samples leachates' after both microwave-assisted total digestion and Toxicity Characteristic Leaching Procedure (TCLP test) using Inductively Coupled Plasma Mass Spectroscopy (ICP-MS) analysis. The analysis reveals that several elements are detected in the two of panels, with no sample exceeds the TCLP test. Concentrations of precious and critical metals are also measured, which generates great incentives for recovery. Then, further experiments, for P/V recycling investigation, are presented using different acids or acid mixtures under a variety of temperatures and a stable S/L ratio, with or without agitation, in order to determine the optimal recycling conditions. The results verify that chemical treatment in P/V shredded samples is efficient since driving to ethylene-vinyl acetate (EVA) resin's dissolution, as well as valuable structural materials recovery (P/V glass, ribbons, cells, P/V intermediate layers). Among the solvents used, sulfuric acid and lactic acid demonstrate the most efficient and strongest performance on panels' treatment at gentle temperatures providing favorably low energy requirements. Copyright © 2016 Elsevier Ltd. All rights reserved.

The radioactive waste management conference

International Nuclear Information System (INIS)

Fareeduddin, S.; Hirling, J.

1983-01-01

The international conference on radioactive waste management was held in Seattle, Washington, from 16 to 20 May 1983. The response was gratifying, reflecting world-wide interest: it was attended by 528 participants from 29 Member States of the IAEA and eight international organizations. The conference programme was structured to permit reviews and presentation of up-to-date information on five major topics: - waste management policy and its implementation: national and international approaches; legal, economic, environmental, and social aspects (four sessions with 27 papers from 16 countries and four international organizations); - handling, treatment, and conditioning of wastes from nuclear facilities, nuclear power plants and reprocessing plants, including the handling and treatment of gaseous wastes and wastes of specific types (five sessions with 35 papers); - storage and underground disposal of radioactive wastes: general, national concepts, underground laboratories, and designs of repositories for high-level, and low- and intermediate-level waste disposal (five sessions with 35 papers); - environmental and safety assessment of waste management systems: goals methodologies, assessments for geological repositories, low- and intermediate-level wastes, and mill tailings (four sessions with 26 papers); - radioactive releases to the environment from nuclear operations: status and perspectives, environmental transport processes, and control of radioactive waste disposal into the environment (three sessions with 23 papers)

Summary review of rock mechanics workshop on radioactive waste disposal

International Nuclear Information System (INIS)

Carter, N.L.; Goodman, R.E.; Merrill, R.H.

1977-01-01

Presentations, critiques and recommendations for the disposal of commercial radioactive waste based upon an analysis of the information presented at the Rock Mechanics Review/Workshop, Denver, Colorado, December 16-17, 1976 are summarized. The workshop, comprised of both formal and informal sessions, with about 50 participants, was hosted by RE/SPEC Inc. and Dr. Paul F. Gnirk, President and was sponsored by the Office of Waste Isolation (OWI), led by Dr. William C. McClain. The panel of reviewers, responsible for this report, consisted of Neville L. Carter, Richard E. Goodman, and Robert H. Merrill. These panel members were selected not only on the basis of their experience in various aspects of Rock Mechanics and Mining Engineering but also because they have had no previous active participation in problems concerning disposal of radioactive waste. By way of a general comment, the review panel was very favorably impressed with the Rock Mechanics research efforts, supported by OWI, on this problem and with the level of technical competence of those carrying out the research. Despite the rather preliminary nature of the results presented and the youth of the program itself, it is clear that the essential ingredients for a successful program are at hand, especially as regards disposal in natural salt formations. These include laboratory studies of appropriate rock deformation, numerical analyses of thermal and mechanical stresses around openings, and in situ field tests. We shall comment on each of these three major areas in turn. We shall then offer recommendations for their improvement, and, finally, we shall make more general recommendations for future considerations of the OWI radioactive waste disposal program

Risk-based decisionmaking (Panel)

Energy Technology Data Exchange (ETDEWEB)

Smith, T.H.

1995-12-31

By means of a panel discussion and extensive audience interaction, explore the current challenges and progress to date in applying risk considerations to decisionmaking related to low-level waste. This topic is especially timely because of the proposed legislation pertaining to risk-based decisionmaking and because of the increased emphasis placed on radiological performance assessments of low-level waste disposal.

Puncture panel optimization

International Nuclear Information System (INIS)

Glass, R.E.; Longenbaugh, R.S.

1986-01-01

Sandia National Laboratories developed the TRansUranic PACkage Transporter (TRUPACT) to transport defense contact-handled transuranic wastes. The package has been designed to meet the normal and hypothetical accident conditions in 10CFR71 which includes the demonstrated ability to survive a 1-meter drop onto a mild steel pin. The puncture protection is provided by puncture resistant panels. In conjunction with the development of TRUPACT, a series of experiments has been conducted to reduce the weight of the puncture resistant panels. The initial scoping tests resulted in a preliminary design incorporating 30 layers of Kevlar. This design has been shown to meet the regulatory puncture test. To reduce the weight of this panel, subscale tests were conducted on panels utilizing Kevlar yarns with varying mass per unit length (denier) as well as different resins. This paper reviews the testing undertaken in the original panel development and discusses the results obtained from the recent subscale and full-scale optimization tests

1979 New Mexico legislative session: energy issues and legislation

International Nuclear Information System (INIS)

Barsumian, L.; Vandevender, S.G.

1979-10-01

This report is an account of the energy legislation and associated issues considered during the 1979 session of the 34th New Mexico Legislature. The session's major issue was the federal study of a proposed nuclear Waste Isolation Pilot Plant (WIPP) in New Mexico. A large proportion of time and effort was spent on resolving the state's formal position toward the federal project. However, other energy concerns were also significant even though they were neither as controversial nor as visible as the primary issue. The two most important laws enacted were the Radioactive Waste Consultation Act and the Radioactive Waste Transportation Act. The Legislature considered 47 other energy-related bills, of which 17 were enacted

Integrated thermal treatment systems study. Internal review panel report

International Nuclear Information System (INIS)

Cudahy, J.; Escarda, T.; Gimpel, R.

1995-04-01

The U.S. Department of Energy (DOE) Office of Technology Development (OTD) commissioned two studies to evaluate nineteen thermal treatment technologies for treatment of DOE mixed low-level waste. These studies were called the Integrated Thermal Treatment System (ITTS) Phase I and Phase II. With the help of the DOE Office of Environmental Management (EM) Mixed Waste Focus Group, OTD formed an ITTS Internal Review Panel to review and comment on the ITTS studies. This Panel was composed of scientists and engineers from throughout the DOE complex, the U.S. Environmental Protection Agency, the California EPA, and private experts. The Panel met from November 15-18, 1994 to review the ITTS studies and to make recommendations on the most promising thermal treatment systems for DOE mixed low-level wastes and on research and development necessary to prove the performance of the technologies. This report describes the findings and presents the recommendations of the Panel

DOE model conference on waste management and environmental restoration

International Nuclear Information System (INIS)

1990-01-01

Reports dealing with current topics in waste management and environmental restoration were presented at this conference in six sessions. Session 1 covered the ''Hot Topics'' including regulations and risk assessment. Session 2 dealt with waste reduction and minimization; session 3 dealt with waste treatment and disposal. Session 4 covered site characterization and analysis. Environmental restoration and associated technologies wee discussed in session 5 and 6. Individual papers have been cataloged separately

Insights from the panel review process

International Nuclear Information System (INIS)

Searborn, B.

1998-01-01

The environmental review process for nuclear waste management and disposal was unusual in that the Panel was asked to examine a concept rather than a specific project at a specific site. The Panel was charged with commenting on the safety and acceptability of the AECL concept, examining criteria for determining the safety and acceptability of any concept for managing nuclear fuel waste, and examining future steps which should be taken. In short, it was asked to provide policy advice to governments. The Panel concluded that safety is a key part, but only one part, of acceptability, and that safety must be viewed from both a technical and a social perspective. It judged that safety of the AECL concept had been adequately demonstrated from a technical perspective, but not from a social perspective. It also concluded that the AECL concept does not have the required level of public acceptability to be adopted as Canada's approach for managing nuclear fuel wastes. The paper examines in some detail the various aspects of the public concerns surrounding the nuclear cycle in general, and the safety of the proposals put forward by AECL for nuclear fuel waste management in particular. It notes the differences between those who look at safety from a technical perspective, and those who look at safety from a social perspective. And it lists the concerns related to acceptability in addition to the key factor of safety. After outlining the Panel's recommendations to governments on future steps to be taken, the paper discusses the extent to which the recommendations respond to the public's concerns. It stresses the importance of Aboriginal participation; of the creation of a new agency to deal with the full range of activities, technical and social, related to long-term management; of the public and decision-makers having more than one viable option to choose from; and of the essentiality of an inter-active process of public participation at all stages of decision-making. Finally

Biomass and waste to energy. Financial incentives for renewables. Altener workshop

International Nuclear Information System (INIS)

Van Halen, C.; Kwant, K.W.

1996-12-01

The title workshop was organised by Novem in cooperation with its partners in the Altener Waste for Energy (WfE) network, and AFB-Nett (Agricultural and Forestry Biomass Network). Almost 100 participants from 13 European countries attended the workshop. The aim of the workshop was to explore the industrial potential, to discuss mutual differences and financial barriers that appear still to be present. The morning session of the workshop included country presentations of existing national financial incentives to support renewable energy. In the afternoon session three 'Dutch cases' were presented, followed by a presentation of the results of a European comparison, commissioned by Novem. The second part of the afternoon was reserved for an 'in-depth' plenary panel discussion, e.g. on best practices, new instruments, potential and need for harmonization

Session V: Management of Radioactive Waste and Damaged Fuel. Session V-A: Generation and Management of Materials and Waste

International Nuclear Information System (INIS)

Blommaert, W.; Cheng Hui

2013-01-01

Mitigation of the Chernobyl accident consequences stressed the attention on the huge volumes and the variety of wastes resulting from the accident (almost all long- lived and alfa containing radioactive waste). The accident and the mitigation of the consequences clearly demonstrated the level of unpreparedness for such accident, the absence of experience in the management of huge amounts of contaminated materials, as well as the lack of storage /disposal capacity. This resulted in a ''not organized storage for not organized waste''. Hence, large amounts of contaminated materials are being stored under conditions that do not fully comply with present international safety requirements. During mitigation and clean-up operations after the Chernobyl accident, disposal facilities were constructed. Some of them are located in areas with high water table and hence (potentially) result in contamination of groundwater. For this reason some of them will require re-disposal, requiring itself a comprehensive safety assessment. On the other hand, the Chernobyl accident resulted, during the early phase of the accident, in the creation of a special governmental ''brainstorming'' commission on the decision making process, with a clear allocation of responsibilities and with full power. Later on, considered options for the management of different ''Chernobyl'' waste types (solid, liquid, fuel,) were provided in the National Policy and Strategy. Attention was drawn to the fact that pre-operational work is a time and cost consuming process. Up to now there is no decision on geological disposal. The development of facilities on the ''Vector site'' in the exclusion zone of Chernobyl is going on. The Vector operation covers retrieval operation of radioactive waste, characterization activities, processing activities, transport and storage/disposal of the radioactive waste in the exclusion zone. National legislation does not take into account the peculiarity of the ''Chernobyl'' waste and

Industrial waste utilization in the panels production for high buildings facade and socle facing

Science.gov (United States)

Vitkalova, Irina; Torlova, Anastasiya; Pikalov, Evgeniy; Selivanov, Oleg

2018-03-01

The research presents comprehensive utilization of such industrial waste as galvanic sludge, broken window glass as functional additives for producing ceramics for facade and socle paneling in high-rise construction. The basic charge component is low-plasticity clay, which does not allow producing high-quality products if used without any functional additives. The application of the mentioned above components broadens the resource base, reduces production cost and the mass of the products in comparison with the currently used facing ceramics. The decrease of product mass helps to reduce the load on the basement and to use ceramic material in high-rise construction more effectively. Additional advantage of the developed composition is the reducing of production energy intensity due to comparatively low pressing pressure and firing temperature thus reducing the overall production cost. The research demonstrates the experimental results of determining density, compressive strength, water absorption, porosity and frost resistance of the produced ceramic material. These characteristics prove that the material can be applied for high buildings outdoor paneling. Additional research results prove ecologic safety of the produced ceramic material.

DOE model conference on waste management and environmental restoration

Energy Technology Data Exchange (ETDEWEB)

1990-01-01

Reports dealing with current topics in waste management and environmental restoration were presented at this conference in six sessions. Session 1 covered the Hot Topics'' including regulations and risk assessment. Session 2 dealt with waste reduction and minimization; session 3 dealt with waste treatment and disposal. Session 4 covered site characterization and analysis. Environmental restoration and associated technologies wee discussed in session 5 and 6. Individual papers have been cataloged separately.

Session Report - S. Voinis (Andra)

International Nuclear Information System (INIS)

Voinis, Sylvie

2014-01-01

The session addressed key issues related to the industrial feasibility of construction. It covered the implementer and regulator points of view. The conclusions derive from three presentations completed by the outcomes of six WG. At the Morsleben Repository, Germany, the licensing of the closure of the repository has been initiated by BfS. The closure concept is based on extensive backfilling with salt concrete complemented by seals. In order to demonstrate the feasibility of constructing such a seal structure an in-situ experiment is performed in a drift of the repository. In the UK, the framework for implementing geological disposal of the higher activity radioactive waste is described in the White Paper published by the UK Government in June 2008. The process to site a facility will be staged and based on voluntarism and partnership with local communities. This process is in its early stage. The paper outlines the work being undertaken by the NDA. In canada, Ontario Power Generation (OPG) has submitted information required for a CNSC licence to prepare the site and construct a DGR for the disposal of low and intermediate level waste from the operation of their nuclear power reactors. That submission includes an Environmental Impact Statement (EIS), as required for a Panel Review under the Canadian Environmental Assessment Act (CEAA), and the information required for a licence application under the NSCA Regulations. Discussions between the proponent and the regulator in the pre-licensing phase, clarified CNSC expectations for the characterization of the site and for the development of the EIS and application. They also helped to ensure that OPG understood these expectations. Outcomes WG session-1: - Start with construction but during operational phase: Simultaneous construction and operation activities. - Need for technical requirements/criteria: So that it can be judged whether 'products' meet the requirements; LT safety issues to be considered during

Lean production design using value stream mapping and ergonomics approach for waste elimination on buffing panel upright process

Science.gov (United States)

Suryoputro, M. R.; Sari, A. D.; Burhanudin, R.; Sugarindra, M.

2017-12-01

This study discussed the implementation of ergonomics and value stream mapping issues to reduce the existing waste in the process of buffing upright panel in the XYZ music manufacturing company. Aimed to identify the 9 waste based on the identification in terms of production processes and ergonomic factors, namely environmental health and safety, defects, overproduction, waiting, not utilizing employee knowledge skill and ability, transportation, inventory, motion, and excess process. In addition, ergonomics factors were identified, for example posture using REBA, job safety analysis, and physical workload. This study results indicated that the process is having 21.4% of the potential dangers that could not be accepted and thus potentially lead to lost time. Continued with the physical workload, the score of % cardiovascular load value is still below 30%, which means that the physical workload is normal and allows the addition of work. Meanwhile, in the calculation of posture investigation, the REBA resulted that there was a motion waste identified on the edge buff machine and ryoto with the score of 10 and 8. In conclusion, the results shown that there were 20 overall waste produced, then thus waste were reduced based on the identification and discussion of proposed improvements.

Panel reports of the first session of the workshop on coal for California

Energy Technology Data Exchange (ETDEWEB)

Davidson, Karen R.

1980-05-01

The panel reports are the result of a five-day workshop held at the Pajaro Dunes Conference Center, Watsonville, California, October 1-6, 1978. The workshop was conducted by JPL, under the sponsorship of the US Department of Energy and the California Energy Commission. The purpose of the exercise was to assay the opinions of a broad range of groups in order to identify what people perceive to be the problems associated with increased coal use in California. Representatives from utilities, industry, mining companies, citizens groups, and the academic community were divided into seven panels, each of which prepared a report. Representatives of government agencies attended as observers. The panels examined end-uses of coal in California, mine-mouth conversion, advanced concepts and use of Alaskan coal, environmental effects, public acceptance, finance, and legislation and regulation.

Quantification of landfill methane using modified Intergovernmental Panel on Climate Change's waste model and error function analysis.

Science.gov (United States)

Govindan, Siva Shangari; Agamuthu, P

2014-10-01

Waste management can be regarded as a cross-cutting environmental 'mega-issue'. Sound waste management practices support the provision of basic needs for general health, such as clean air, clean water and safe supply of food. In addition, climate change mitigation efforts can be achieved through reduction of greenhouse gas emissions from waste management operations, such as landfills. Landfills generate landfill gas, especially methane, as a result of anaerobic degradation of the degradable components of municipal solid waste. Evaluating the mode of generation and collection of landfill gas has posted a challenge over time. Scientifically, landfill gas generation rates are presently estimated using numerical models. In this study the Intergovernmental Panel on Climate Change's Waste Model is used to estimate the methane generated from a Malaysian sanitary landfill. Key parameters of the model, which are the decay rate and degradable organic carbon, are analysed in two different approaches; the bulk waste approach and waste composition approach. The model is later validated using error function analysis and optimum decay rate, and degradable organic carbon for both approaches were also obtained. The best fitting values for the bulk waste approach are a decay rate of 0.08 y(-1) and degradable organic carbon value of 0.12; and for the waste composition approach the decay rate was found to be 0.09 y(-1) and degradable organic carbon value of 0.08. From this validation exercise, the estimated error was reduced by 81% and 69% for the bulk waste and waste composition approach, respectively. In conclusion, this type of modelling could constitute a sensible starting point for landfills to introduce careful planning for efficient gas recovery in individual landfills. © The Author(s) 2014.

Radioactive waste management at the Hanford Reservation

International Nuclear Information System (INIS)

Anon.

1979-01-01

During some 30 years of plutonium production, the Hanford Reservation has accumulated large quantities of low- and high-level radioactive wastes. The high-level wastes have been stored in underground tanks, and the low-level wastes have been percolated into the soil. In recent years some programs for solidification and separation of the high-level wastes have been initiated. The Hanford waste-management system was studied by a panel of the Committee on Radioactive Waste Management of the National Academy of Sciences. The panel concluded that Hanford waste-management practices were adequate at present and for the immediate future but recommended increased research and development programs related to long-term isolation of the wastes. The panel also considered some alternatives for on-site disposal of the wastes. The Hanford Reservation was originally established for the production of plutonium for military purposes. During more than 30 years of operation, large volumes of high- and low-level radioactive wastes have been accumulated and contained at the site. The Management of these wastes has been the subject of controversy and criticism. To obtain a true technical evaluation of the Hanford waste situation, the Energy Research and Development Administration (now part of the Department of Energy) issued a contract to the National Academy of Sciences and the National Research Councilto conduct an independent review and evaluation of the Hanford waste-management practices and plans. A panel of the Committee on Radioactive Waste Management (CRWM) of the National Academy of Sciences conducted this study between the summer of 1976 and the summer of 1977. This article is a summary of the final report of that panel

Pyrolysis characteristics and pyrolysis products separation for recycling organic materials from waste liquid crystal display panels

Energy Technology Data Exchange (ETDEWEB)

Wang, Ruixue; Xu, Zhenming, E-mail: zmxu@sjtu.edu.cn

2016-01-25

Highlights: • Pyrolysis characteristics are conducted for a better understanding of LCDs pyrolysis. • Optimum design is developed which is significant to guide the further industrial process. • Acetic acid and TPP are recycled and separated. - Abstract: Waste liquid crystal display (LCD) panels mainly contain inorganic materials (glass substrate with indium-tin oxide film), and organic materials (polarizing film and liquid crystal). The organic materials should be removed beforehand since the organic matters would hinder the indium recycling process. In the present study, pyrolysis process is used to remove the organic materials and recycle acetic as well as and triphenyl phosphate (TPP) from waste LCD panels in an environmental friendly way. Several highlights of this study are summarized as follows: (i) Pyrolysis characteristics and pyrolysis kinetics analysis are conducted which is significant to get a better understanding of the pyrolysis process. (ii) Optimum design is developed by applying Box–Behnken Design (BBD) under response surface methodology (RSM) for engineering application which is significant to guide the further industrial recycling process. The oil yield could reach 70.53 wt% and the residue rate could reach 14.05 wt% when the pyrolysis temperature is 570 °C, nitrogen flow rate is 6 L min{sup −1} and the particle size is 0.5 mm. (iii) Furthermore, acetic acid and TPP are recycled, and then separated by rotary evaporation, which could reduce the consumption of fossil energy for producing acetic acid, and be reused in electronics manufacturing industry.

Pyrolysis characteristics and pyrolysis products separation for recycling organic materials from waste liquid crystal display panels

International Nuclear Information System (INIS)

Wang, Ruixue; Xu, Zhenming

2016-01-01

Highlights: • Pyrolysis characteristics are conducted for a better understanding of LCDs pyrolysis. • Optimum design is developed which is significant to guide the further industrial process. • Acetic acid and TPP are recycled and separated. - Abstract: Waste liquid crystal display (LCD) panels mainly contain inorganic materials (glass substrate with indium-tin oxide film), and organic materials (polarizing film and liquid crystal). The organic materials should be removed beforehand since the organic matters would hinder the indium recycling process. In the present study, pyrolysis process is used to remove the organic materials and recycle acetic as well as and triphenyl phosphate (TPP) from waste LCD panels in an environmental friendly way. Several highlights of this study are summarized as follows: (i) Pyrolysis characteristics and pyrolysis kinetics analysis are conducted which is significant to get a better understanding of the pyrolysis process. (ii) Optimum design is developed by applying Box–Behnken Design (BBD) under response surface methodology (RSM) for engineering application which is significant to guide the further industrial recycling process. The oil yield could reach 70.53 wt% and the residue rate could reach 14.05 wt% when the pyrolysis temperature is 570 °C, nitrogen flow rate is 6 L min"−"1 and the particle size is 0.5 mm. (iii) Furthermore, acetic acid and TPP are recycled, and then separated by rotary evaporation, which could reduce the consumption of fossil energy for producing acetic acid, and be reused in electronics manufacturing industry.

Proceedings: special panel on geothermal model intercomparison study

Energy Technology Data Exchange (ETDEWEB)

1980-12-17

Separate abstracts were prepared for five papers. Two papers were abstracted previously for EDB. Five panel responses to the project, three workshop session summaries, and conclusions drawn are also included in this report. (MHR)

Stressed skin panels

Energy Technology Data Exchange (ETDEWEB)

Anon

2001-07-01

Advantages and disadvantages of stressed skin panels, also known as structural insulated panels (SIPs), are discussed as material and labour-saving alternatives to traditional stick framing. Stressed skin panels are manufactured 'sandwich' assemblies with a rigid insulating polystyrene foam core, whose interior and exterior surfaces are bonded into panels. The skins distribute and carry the structural loading while the bonded foam core provides insulation and keeps the two skins aligned. Since there are fewer framing members, there is little thermal bridging and the R-value remains high. SIPs are usually manufactured in four feet by eight feet panels, although some manufacturers can produce panels up to eight feet by forty feet. SIPs are resource efficient as they use less wood than conventional framing (about 25 per cent less); can structurally cover large spans, requiring less supplementary framing. Use of SIPs eliminate the need for headers over small openings; provide the ability to nail anywhere; create less scrap and waste; lessen vulnerability to unfavourable weather and other job-site hazards, can reduce delays, and often can produce significant savings in material and labour costs. Limitations include the more complex approaches to plumbing and electrical systems, although this can be minimized by designers by incorporating much of the plumbing and electrical work on interior (non-panel) walls. Most stressed skin panels require one-half inch interior gypsum drywall. If become wet, stressed skin panels take a long time to dry out and may harbour mold growth. Larger stressed-skin panels used in floors and roofs, may require cranes or other machinery for handling because of their weight. Although not without some environmental impact, overall, stressed skin panels are judged to be a resource-efficient building technology with significant energy-efficiency benefits and distinct advantages over stick framing. 3 photos.

Safe Management and disposal of nuclear waste. Volume 3

International Nuclear Information System (INIS)

1993-01-01

These proceedings of the international conference Safewaste 93, volume 3 are divided into three poster sessions bearing on: poster session P-1: Radioactive waste management and actinide burning; poster session P-2: Safety aspects of radioactive waste disposal; poster session P-3: Transport and disposal

International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13), Paris – March 4-7, 2013: Closing Session. Summary of Sustainability of Advanced Fuel Cycles Panel Session II

International Nuclear Information System (INIS)

Cameron, R.

2013-01-01

Sustainability was discussed in terms of the social, environment and economic perspectives, which arise from the original Brundtland definition of sustainability. The panel presented their perspectives of the need to move towards a sustainable future, involving better use of uranium, reductions in high-level radioactive waste, safe, secure and economic operation of nuclear reactors and the fuel cycle. In all cases, it was considered that sustainability in the long-term must involve fast reactors and a closed nuclear fuel cycle, although both Korea and the IAEA pointed out that these are clearly national decisions and there will not be a single solution for all countries

The Radioactive Waste Management at Studsvik

Energy Technology Data Exchange (ETDEWEB)

Hedlund, R; Lindskog, A

1966-04-15

The report was originally prepared as a contribution to the discussions in an IAEA panel on economics of radioactive waste management held in Vienna from 13 - 17 December 1965. It contains the answers and comments to the questions of a questionnaire for the panel concerning the various operations associated with the management (collection, transport, treatment, discharge, storage, and operational monitoring) of: - radioactive liquid wastes, except high-level effluents from reactor fuel recovering operations; - solid wastes, except those produced from treatment of high level wastes; - gaseous wastes produced from treatment of the foregoing liquid and solid wastes; - equipment decontamination facilities and radioactive laundries.

The Radioactive Waste Management at Studsvik

International Nuclear Information System (INIS)

Hedlund, R.; Lindskog, A.

1966-04-01

The report was originally prepared as a contribution to the discussions in an IAEA panel on economics of radioactive waste management held in Vienna from 13 - 17 December 1965. It contains the answers and comments to the questions of a questionnaire for the panel concerning the various operations associated with the management (collection, transport, treatment, discharge, storage, and operational monitoring) of: - radioactive liquid wastes, except high-level effluents from reactor fuel recovering operations; - solid wastes, except those produced from treatment of high level wastes; - gaseous wastes produced from treatment of the foregoing liquid and solid wastes; - equipment decontamination facilities and radioactive laundries

Evaluation and review of alternative waste forms for immobilization of high level radioactive wastes

International Nuclear Information System (INIS)

1980-01-01

The objective of this study was to review the relative merits and potential of 15 (fifteen) alternative waste forms being considered for the solidification and disposal of radioactive wastes. The relative merits of 4 (four) alternative pre-solidification processing approaches were also assessed in this study. A Peer Review Panel composed of 8 (eight) scientists and engineers representing independent, non-DOE laboratories from industry, government, and universities and the disciplines of materials science, ceramics, glass, metallurgy, and geology conducted the review. A numerical rating of alternative waste forms was arrived at individually by the panel members taking into consideration 9 (nine) scientific and 9 (nine) engineering parameters affecting the long term performance and production of waste forms. At a meeting on May 9, 1980, a group ranking for the alternative forms was achieved by averaging the individual scores and discussing the available data base. Three final ranking lists comparing: (A) Present Scientific Merits or Least Risk for Use Today; and (B) Research Priority; and (C) Present and Potential Engineering Practicality were prepared by the Panel. Each waste form in the lists is assigned a value of either (1) Top Rank, (2) Intermediate Rank, or (3) Bottom Rank. A discussion of the relative strengths and weaknesses of the alternative waste forms and recommendations for future program directions is presented in the body of the accompanying Peer Review Panel report

Estimating national landfill methane emissions: an application of the 2006 Intergovernmental Panel on Climate Change Waste Model in Panama.

Science.gov (United States)

Weitz, Melissa; Coburn, Jeffrey B; Salinas, Edgar

2008-05-01

This paper estimates national methane emissions from solid waste disposal sites in Panama over the time period 1990-2020 using both the 2006 Intergovernmental Panel on Climate Change (IPCC) Waste Model spreadsheet and the default emissions estimate approach presented in the 1996 IPCC Good Practice Guidelines. The IPCC Waste Model has the ability to calculate emissions from a variety of solid waste disposal site types, taking into account country- or region-specific waste composition and climate information, and can be used with a limited amount of data. Countries with detailed data can also run the model with country-specific values. The paper discusses methane emissions from solid waste disposal; explains the differences between the two methodologies in terms of data needs, assumptions, and results; describes solid waste disposal circumstances in Panama; and presents the results of this analysis. It also demonstrates the Waste Model's ability to incorporate landfill gas recovery data and to make projections. The former default method methane emissions estimates are 25 Gg in 1994, and range from 23.1 Gg in 1990 to a projected 37.5 Gg in 2020. The Waste Model estimates are 26.7 Gg in 1994, ranging from 24.6 Gg in 1990 to 41.6 Gg in 2020. Emissions estimates for Panama produced by the new model were, on average, 8% higher than estimates produced by the former default methodology. The increased estimate can be attributed to the inclusion of all solid waste disposal in Panama (as opposed to only disposal in managed landfills), but the increase was offset somewhat by the different default factors and regional waste values between the 1996 and 2006 IPCC guidelines, and the use of the first-order decay model with a time delay for waste degradation in the IPCC Waste Model.

Environmental Kuznets Curve in China: New evidence from dynamic panel analysis

International Nuclear Information System (INIS)

Li, Tingting; Wang, Yong; Zhao, Dingtao

2016-01-01

This paper applies a panel of 28 provinces of China from 1996 to 2012 to study the impacts of economic development, energy consumption, trade openness, and urbanization on the carbon dioxide, waste water, and waste solid emissions. By estimating a dynamic panel model with the system Generalized Method of Moments (GMM) estimator and an autoregressive distributed lag (ARDL) model with alternative panel estimators, respectively, we find that the Environmental Kuznets Curve (EKC) hypothesis is well supported for all three major pollutant emissions in China across different models and estimation methods. Our study also confirms positive effects of energy consumption on various pollutant emissions. In addition, we find some evidence that trade and urbanization may deteriorate environmental quality in the long run, albeit not in the short run. From policy perspective, our estimation results bode well for Chinese government's goal of capping greenhouse emissions by 2030 as outlined in the recent China-US climate accord, while containing energy consumption and harm effects from expanding trade and urbanization remains some environmental challenges that China faces. - Highlights: •We apply dynamic panel estimations to study the EKC hypothesis with Chinese panel data. •Our study covers three indicators: carbon dioxide, waste water, and waste solid emissions. •We find robust support for the EKC hypothesis for all three indicators of pollution. •Energy consumption has significantly positive effects on all three pollutant emissions. •Trade and urbanization may have harmful environmental impacts in the long run.

IAEA Meeting to Highlight Technologies to Safely Manage Radioactive Waste

International Nuclear Information System (INIS)

2014-01-01

The two-day Forum was divided into four sessions that follow the journey of radioactive waste from its generation to final disposal: The first session provided an overview of the peaceful uses of nuclear technologies, the radioactive waste they generate, and of integrated management approaches adapted to various waste classes, as well as associated economic, security and safeguards considerations; The second session developed the steps required to manage radioactive waste before its disposal; The third illustrated disposal solutions for radioactive waste that must remain under regulatory control; and The fourth and final session focused on how evolving nuclear technologies, such as better use of nuclear fuel, innovative fuels and advanced reactors and fuel cycles, could affect future waste management needs

Session: What do we know about cumulative or population impacts

Energy Technology Data Exchange (ETDEWEB)

Kerlinger, Paul; Manville, Al; Kendall, Bill

2004-09-01

This session at the Wind Energy and Birds/Bats workshop consisted of a panel discussion followed by a discussion/question and answer period. The panelists were Paul Kerlinger, Curry and Kerlinger, LLC, Al Manville, U.S. Fish and Wildlife Service, and Bill Kendall, US Geological Service. The panel addressed the potential cumulative impacts of wind turbines on bird and bat populations over time. Panel members gave brief presentations that touched on what is currently known, what laws apply, and the usefulness of population modeling. Topics addressed included which sources of modeling should be included in cumulative impacts, comparison of impacts from different modes of energy generation, as well as what research is still needed regarding cumulative impacts of wind energy development on bird and bat populations.

Business challenges for the young generation. Panel Discussion

International Nuclear Information System (INIS)

Margolis, Robert; Shoop, Undine; Umstadter, Karl; Plies, Christina; Allen, Todd; Sackett, John; Klein, Dale; Gates, W. Gary; Simmons, Sonja

2001-01-01

This special panel session will capture the views of senior professionals on how to address the need to attract new talent to the nuclear profession. Young professionals will express their views on how to attract new talent to the nuclear profession. (authors)

In-Situ Testing and Performance Assessment of a Redesigned WIPP Panel Closure - 13192

Energy Technology Data Exchange (ETDEWEB)

Klein, Thomas [URS-Professional Solutions, 4021 National Parks Highway Carlsbad, NM 88220 (United States); Patterson, Russell [Department of Energy-Carlsbad Field Office, 4021 National Parks Highway Carlsbad, NM 88220 (United States); Camphouse, Chris; Herrick, Courtney; Kirchner, Thomas; Malama, Bwalya; Zeitler, Todd [Sandia National Laboratories-Carlsbad, 4100 National Parks Highway Carlsbad, NM 88220 (United States); Kicker, Dwayne [SM Stoller Corporation-Carlsbad, 4100 National Parks Highway Carlsbad, NM (United States)

2013-07-01

There are two primary regulatory requirements for Panel Closures at the Waste Isolation Pilot Plant (WIPP), the nation's only deep geologic repository for defense related Transuranic (TRU) and Mixed TRU waste. The Federal requirement is through 40 CFR 191 and 194, promulgated by the U.S. Environmental Protection Agency (EPA). The state requirement is regulated through the authority of the Secretary of the New Mexico Environment Department (NMED) under the New Mexico Hazardous Waste Act (HWA), New Mexico Statutes Annotated (NMSA) 1978, chap. 74-4-1 through 74-4-14, in accordance with the New Mexico Hazardous Waste Management Regulations (HWMR), 20.4.1 New Mexico Annotated Code (NMAC). The state regulations are implemented for the operational period of waste emplacement plus 30 years whereas the federal requirements are implemented from the operational period through 10,000 years. The 10,000 year federal requirement is related to the adequate representation of the panel closures in determining long-term performance of the repository. In Condition 1 of the Final Certification Rulemaking for 40 CFR Part 194, the EPA required a specific design for the panel closure system. The U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) has requested, through the Planned Change Request (PCR) process, that the EPA modify Condition 1 via its rulemaking process. The DOE has also requested, through the Permit Modification Request (PMR) process, that the NMED modify the approved panel closure system specified in Permit Attachment G1. The WIPP facility is carved out of a bedded salt formation 655 meters below the surface of southeast New Mexico. Condition 1 of the Final Certification Rulemaking specifies that the waste panels be closed using Option D which is a combination of a Salado mass concrete (SMC) monolith and an isolation/explosion block wall. The Option D design was also accepted as the panel closure of choice by the NMED. After twelve years of waste handling

Peer Review of the Waste Package Material Performance Interim Report

International Nuclear Information System (INIS)

J. A. Beavers; T. M. Devine, Jr.; G. S. Frankel; R. H. Jones; R. G. Kelly; R. M. Latanision; J. H. Payer

2001-01-01

At the request of the U.S. Department of Energy, Bechtel SAIC Company, LLC, formed the Waste Package Materials Performance Peer Review Panel (the Panel) to review the technical basis for evaluating the long-term performance of waste package materials in a proposed repository at Yucca Mountain, Nevada. This is the interim report of the Panel; a final report will be issued in February 2002. In its work to date, the Panel has identified important issues regarding waste package materials performance. In the remainder of its work, the Panel will address approaches and plans to resolve these issues. In its review to date, the Panel has not found a technical basis to conclude that the waste package materials are unsuitable for long-term containment at the proposed Yucca Mountain Repository. Nevertheless, significant technical issues remain unsettled and, primarily because of the extremely long life required for the waste packages, there will always be some uncertainty in the assessment. A significant base of scientific and engineering knowledge for assessing materials performance does exist and, therefore, the likelihood is great that uncertainty about the long-term performance can be substantially reduced through further experiments and analysis

Experimental investigation to evaluate the potential environmental hazards of photovoltaic panels

Energy Technology Data Exchange (ETDEWEB)

Tammaro, Marco, E-mail: marco.tammaro@enea.it [ENEA, Italian National Agency for New Technologies, Energy and the Environment, Centre of Research of Portici Naples (Italy); Salluzzo, Antonio, E-mail: antonio.salluzzo@enea.it [ENEA, Italian National Agency for New Technologies, Energy and the Environment, Centre of Research of Portici Naples (Italy); Rimauro, Juri, E-mail: juri.rimauro@enea.it [ENEA, Italian National Agency for New Technologies, Energy and the Environment, Centre of Research of Portici Naples (Italy); Schiavo, Simona, E-mail: simona.schiavo@unina.it [University “Federico II” of Naples Via Università 100, 80055 Portici (Italy); Manzo, Sonia, E-mail: sonia.manzo@enea.it [ENEA, Italian National Agency for New Technologies, Energy and the Environment, Centre of Research of Portici Naples (Italy)

2016-04-05

Highlights: • We measure the metals released in the leaching solution by samples of PV panels. • We measure the environmental effects by a battery of ecotoxicological tests. • The experimental data are compared with the European and Italian benchmark limits. • We assess the potential emissions of metals from future PV waste. • Experimental results show that the photovoltaic panels present an environmental risk. - Abstract: Recently the potential environmental hazard of photovoltaic modules together with their management as waste has attracted the attention of scientists. Particular concern is aroused by the several metals contained in photovoltaic panels whose potential release in the environment were scarcely investigated. Here, for the first time, the potential environmental hazard of panels produced in the last 30 years was investigated through the assessment of up to 18 releasable metals. Besides, the corresponding ecotoxicological effects were also evaluated. Experimental data were compared with the current European and Italian law limits for drinking water, discharge on soil and landfill inert disposal in order to understand the actual pollution load. Results showed that less than 3% of the samples respected all law limits and around 21% was not ecotoxic. By considering the technological evolutions in manufacturing, we have shown that during the years crystalline silicon panels have lower tendency to release hazardous metals with respect to thin film panels. In addition, a prediction of the amounts of lead, chromium, cadmium and nickel releasable from next photovoltaic waste was performed. The prevision up to 2050 showed high amounts of lead (30 t) and cadmium (2.9 t) releasable from crystalline and thin film panels respectively.

Topical Session on Liabilities identification and long-term management at national level - Topical Session held during the 36. Meeting of the RWMC

International Nuclear Information System (INIS)

2003-01-01

These proceedings cover a topical session that was held at the March 2003 meeting of the Radioactive Waste Management Committee. The topical session focused on liability assessment and management for decommissioning of all types of nuclear installations, including decontamination of historic sites and waste management, as applicable. The presentations covered the current, national situations. The first oral presentation, from Switzerland, set the scene by providing a broad coverage of the relevant issues. The subsequent presentations - five from Member countries and one from the EC - described additional national positions and the evolving EC proposed directives. Each oral presentation was followed by a brief period of Q and As for clarification only. A plenary discussion took place on the ensemble of presentations and a Rapporteur provided a report on points made and lessons learnt. Additionally, written contributions were provided by RWMC delegates from several other countries. These are included in the proceedings as are the papers from the oral sessions, and the Rapporteur's report. These papers are not intended to be exhaustive, but to give an informed glimpse of NEA countries' approaches to liability identification and management in the context of nuclear facilities decommissioning and dismantling

INC93: international nuclear congress. Technical sessions summaries

International Nuclear Information System (INIS)

Boulton, J.

1993-01-01

The conference dealt mainly with safety, environmental and human aspects of nuclear energy, including waste management. This volume consists of summaries of the technical sessions contained in Volumes 2 and 3. The individual papers have also been abstracted separately for INIS, with the summaries abridged

INC93: international nuclear congress. Technical sessions summaries

Energy Technology Data Exchange (ETDEWEB)

Boulton, J

1994-12-31

The conference dealt mainly with safety, environmental and human aspects of nuclear energy, including waste management. This volume consists of summaries of the technical sessions contained in Volumes 2 and 3. The individual papers have also been abstracted separately for INIS, with the summaries abridged.

IOC-WMO Intergovernmental WOCE panel. First session

International Nuclear Information System (INIS)

1990-10-01

Ocean currents are an important mechanism by which the present-day climate system moves heat and salt from one latitude band to another. Meteorologists have long been able to quantify the large scale atmospheric circulation by mapping surface pressure. It is only in the coming decade that advances in satellite altimetry, deep floats and surface drifters will permit the design of programmes to determine the ocean circulation in a global and a quantitative sense. The World Ocean Circulation Experiment (WOCE) is such a programme. The WOCE Implementation Plan, also published in 1986, established the elements of the WOCE Field Programme that are necessary to achieve those scientific goals. Core project working groups and scientific panels ensure that the most effective balance of tools such as hydrography, subsurface floats, satellites and moorings are deployed to meet the scientific objective. WOCE is closely related to the International Geosphere Biosphere Programme (IGBP) and the World Climate Research Programme (WCRP). Various aspects of global climate change science are encompassed by WOCE. The heat balance of the earth involves incoming energy, mainly radiation received through the tropics, and outgoing energy, radiated fairly uniformly around the globe. A large amount (more than half) of the total heat flux is moved laterally across the globe by the oceans. Sea surface temperature is now determined globally by satellite. The Joint Global Ocean Flux Study is addressing the global carbon cycle. Tracers such as tritium, freon, have helped to qualitatively describe ocean sections. Drifting buoys have helped to describe surface ocean circulation and ALACE floats (pop-up) are describing intermediate layer circulation. Precision satellite radar altimetry has helped demonstrate the variability of ocean currents on a global scale

Managing Radioactive Waste. Problems and Challenges in a Globalizing World

International Nuclear Information System (INIS)

2010-09-01

Many countries are at a crossroads in terms of maintaining their energy supply. The existing resources of fossil fuels are dwindling, and global warming makes their use increasingly problematic. Nuclear power is now often regarded inevitable for future sustainability, energy security, and economic prosperity. There are, however, still unsolved problems regarding nuclear power. The fact that no country has established a final waste repository for spent nuclear fuel throws fundamental doubt on nuclear energy expansion. Also, the processes of globalization have transformed the nuclear industry towards increased privatization, concentration, and internationalization. This leads to uncertainties regarding the responsibility for nuclear waste management. In these circumstances is it of greatest importance that scholars from different disciplines, as well as policy makers and practitioners within the field, meet to share experiences. This conference had the general objective of producing knowledge about the challenges caused by global developmental trends, and what the management of nuclear waste implies for contemporary and future social development. Over 100 persons attended the conferences. Papers available at the conference site have been separately indexed. Several contributions were also made as PP-presentation, which are available at the site, among others the Keynote Speeches: Waiting for the Nuclear Renaissance: Exploring the Nexus of Expansion and Disposal in Europe (Jane Dawson); Applying the Risk Governance Framework: Institutional Requirements for Dealing with Nuclear Waste (Ortwin Renn); Learning to Listen: The Long Road to Legitimating Radioactive Waste Management Policies (Frans Berkhout); The Nuclear Waste Debate is Irrational but We Need Not Panic (Frank von Hippel). The conference was divided into the following sessions: Session A: Political characteristics matters; Session B: Radioactivity, geology, society. On a problem definition of HLW

Managing Radioactive Waste. Problems and Challenges in a Globalizing World

Energy Technology Data Exchange (ETDEWEB)

2010-09-15

Many countries are at a crossroads in terms of maintaining their energy supply. The existing resources of fossil fuels are dwindling, and global warming makes their use increasingly problematic. Nuclear power is now often regarded inevitable for future sustainability, energy security, and economic prosperity. There are, however, still unsolved problems regarding nuclear power. The fact that no country has established a final waste repository for spent nuclear fuel throws fundamental doubt on nuclear energy expansion. Also, the processes of globalization have transformed the nuclear industry towards increased privatization, concentration, and internationalization. This leads to uncertainties regarding the responsibility for nuclear waste management. In these circumstances is it of greatest importance that scholars from different disciplines, as well as policy makers and practitioners within the field, meet to share experiences. This conference had the general objective of producing knowledge about the challenges caused by global developmental trends, and what the management of nuclear waste implies for contemporary and future social development. Over 100 persons attended the conferences. Papers available at the conference site have been separately indexed. Several contributions were also made as PP-presentation, which are available at the site, among others the Keynote Speeches: Waiting for the Nuclear Renaissance: Exploring the Nexus of Expansion and Disposal in Europe (Jane Dawson); Applying the Risk Governance Framework: Institutional Requirements for Dealing with Nuclear Waste (Ortwin Renn); Learning to Listen: The Long Road to Legitimating Radioactive Waste Management Policies (Frans Berkhout); The Nuclear Waste Debate is Irrational but We Need Not Panic (Frank von Hippel). The conference was divided into the following sessions: Session A: Political characteristics matters; Session B: Radioactivity, geology, society. On a problem definition of HLW

Evaluation and review of alternative waste forms for immobilization of high level radioactive wastes

International Nuclear Information System (INIS)

1979-01-01

Objective was to review the relative merits and potential of eleven alternative waste forms being considered for the solidification and disposal of radioactive wastes. A numerical rating of the alternative waste forms was arrived at individually by peer review panel members taking into consideration nine scientific and nine engineering parameters affecting the long-term performance and production of waste forms. A group rating for the alternative forms was achieved by averaging the individiual scores and discussing the available data base. Three final ranking lists comparing: (A) Present Scientific Merits or Least Risk for Use Today; (B) Research Priority; and (3) Present and Potential Engineering Practicality were prepared by the Panel. Each waste form in the lists is assigned a value of either (1) Top Rank, (2) Intermediate Rank, or is assigned a value of either (1) Top Rank, (2) Intermediate Rank, or (3) Bottom Rank. Relative strengths and weaknesses of the alternative waste forms and recommendations for future program directions are discussed

Gender-specific Regulatory Challenges to Product Approval: a panel discussion.

Science.gov (United States)

McGregor, Alyson J; Barr, Helen; Greenberg, Marna R; Safdar, Basmah; Wildgoose, Peter; Wright, David W; Hollander, Judd E

2014-12-01

On May 13, 2014, a 1-hour panel discussion session titled "Gender-specific Regulatory Challenges to Product Approval" was held during the Academic Emergency Medicine consensus conference, "Gender-specific Research in Emergency Medicine: Investigate, Understand, and Translate How Gender Affects Patient Outcomes." The session sought to bring together leaders in emergency medicine (EM) research, authors, and reviewers in EM research publications, as well as faculty, fellows, residents, and students engaged in research and clinical practice. A panel was convened involving a representative from the Office of Women's Health of the U.S. Food and Drug Administration, two pharmaceutical executives, and a clinical EM researcher. The moderated discussion also involved audience members who contributed significantly to the dialogue. Historical background leading up to the session along with the main themes of the discussion are reproduced in this article. These revolve around sex- and gender-specific research, statistical analysis of sex and gender, clinical practice, financial costs associated with pharmaceutical development, adaptive design, and specific recommendations on the regulatory process as it affects the specialty of EM. © 2014 by the Society for Academic Emergency Medicine.

Photovoltaic panels, the waste of the future

International Nuclear Information System (INIS)

Levilly, Ronan

2014-01-01

In use for some years now as alternative means of generating electricity, photovoltaic panels contain heavy metals, end-of-life management of which is already raising questions. The collection and treatment sector is beginning to structure itself by developing new processes, the impacts of which in terms of chemical risks remain to be defined. (author)

Scientific conference proceedings. Session 3

International Nuclear Information System (INIS)

Bartosek, V.

1985-01-01

The Radiochemical Technology session met at UJV Rez on June 7, 1985 to hear 13 papers of which 11 were incorporated in INIS. The papers inform of results attained in the field of processing liquid radioactive wastes from nuclear power plants, processing spent nuclear fuel using the fluoride process, of the separation of fission products by dicarbolide extraction, the chemistry of complex uranium compounds, etc. The cooperation of UJV with VUJE and VUCHZ is also dealt with. (E.S.)

The Atomic Safety and Licensing Board Panel

International Nuclear Information System (INIS)

1998-01-01

Through the Atomic Energy Act, Congress made is possible for the public to get a full and fair hearing on civilian nuclear matters. Individuals who are directly affected by any licensing action involving a facility producing or utilizing nuclear materials may participate in a formal hearing, on the record, before independent judges on the Atomic Safety and Licensing Board Panel (ASLBP or Panel). Frequently, in deciding whether a license, permit, amendment, or extension should be granted to a particular applicant, the Panel members must be more than mere umpires. If appropriate, they are authorized to go beyond the issues the parties place before them in order to identify, explore, and resolve significant questions involving threats to the public health and safety that come to a board's attention during the proceedings. This brochure explains the purpose of the panel. Also addressed are: type of hearing handled; method of public participation; formality of hearings; high-level waste; other panel responsibilities and litigation technology

LLW Forum meeting report, October 20--22, 1997

International Nuclear Information System (INIS)

Norris, C.; Brown, H.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-10-01

The Low-Level Radioactive Waste Forum met in Annapolis, Maryland, on October 20--22, 1997. Twenty-six Forum Participants, Alternate Forum Participants, and meeting designees representing 22 compacts and states participated. A report on the meeting is given under the following subtitles: New developments in states and compacts; Discussion with NRC Commissioner McGaffigan; Regulatory issues session; Executive session; LLW forum business session; DOE low-level waste management program; Transportation of radioactive waste; Environmental equity: Title VI; Congressional studies on Ward Valley Site; Implementation of DOE's strategy for waste management; Relicensing Envirocare; Draft agreement for uniform application of manifesting procedures; CRCPD report; Panel: Future of low-level radioactive waste management; Agenda planning: February 1998; Resolutions; and Attendance

Safety Assessment of Radioactive waste Repositories

International Nuclear Information System (INIS)

1991-01-01

It is planned to dispose of high-level radioactive wastes in deep geological formations. To access the long-term safety of radioactive waste disposal systems, mathematical models are used to describe groundwater flow, chemistry and potential radionuclide migration through these formations. Establishing the validity of such models is important in order to obtain the necessary confidence in the safety of the disposal method. The papers in these proceedings of the GEOVAL'90 Symposium describe the current state of knowledge on the validation of geosphere flow and transport models. This symposium, divided into five sessions, contains 65 technical papers: session 1 - Necessity of validation. Session 2 - Progress in validation of flow and transport models in orystalline rock, unsaturated media, salt media or clay. Session 3 - Progress in validation of geochemical models. Session 4 - Progress in validation of coupled thermo-hydro-mechanical effects. Session 5 - Validation strategy

Sensory analysis of characterising flavours: evaluating tobacco product odours using an expert panel.

Science.gov (United States)

Krüsemann, Erna J Z; Lasschuijt, Marlou P; de Graaf, C; de Wijk, René A; Punter, Pieter H; van Tiel, Loes; Cremers, Johannes W J M; van de Nobelen, Suzanne; Boesveldt, Sanne; Talhout, Reinskje

2018-05-23

Tobacco flavours are an important regulatory concept in several jurisdictions, for example in the USA, Canada and Europe. The European Tobacco Products Directive 2014/40/EU prohibits cigarettes and roll-your-own tobacco having a characterising flavour. This directive defines characterising flavour as 'a clearly noticeable smell or taste other than one of tobacco […]'. To distinguish between products with and without a characterising flavour, we trained an expert panel to identify characterising flavours by smelling. An expert panel (n=18) evaluated the smell of 20 tobacco products using self-defined odour attributes, following Quantitative Descriptive Analysis. The panel was trained during 14 attribute training, consensus training and performance monitoring sessions. Products were assessed during six test sessions. Principal component analysis, hierarchical clustering (four and six clusters) and Hotelling's T-tests (95% and 99% CIs) were used to determine differences and similarities between tobacco products based on odour attributes. The final attribute list contained 13 odour descriptors. Panel performance was sufficient after 14 training sessions. Products marketed as unflavoured that formed a cluster were considered reference products. A four-cluster method distinguished cherry-flavoured, vanilla-flavoured and menthol-flavoured products from reference products. Six clusters subdivided reference products into tobacco leaves, roll-your-own and commercial products. An expert panel was successfully trained to assess characterising odours in cigarettes and roll-your-own tobacco. This method could be applied to other product types such as e-cigarettes. Regulatory decisions on the choice of reference products and significance level are needed which directly influences the products being assessed as having a characterising odour. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2018. All rights reserved. No commercial use

Session II-D. Systems

International Nuclear Information System (INIS)

Hall, R.J.

1981-01-01

The objectives of the Systems Task in the NWTS Program include: development of program requirements, allocation of the requirements to subsystems or tasks, integration of the task activities towards meeting the overall requirements, and assessment of progress towards achievement of the program mission. The Systems Task also includes a number of ancillary activities which are necessary to the program but which do not logically fall into other work-breakdown structure elements. Activities in the Systems Task, which in the NWTS Program are conducted at both the program and project levels, are generally grouped under the heading systems engineering and include identification of requirements, development of a baseline, integration of the system, baseline control, functional analyses, trade-off studies, and system analyses. The following papers in this session address some of the activities and progress that was achieved in the Systems Task in FY 1981: (1) waste isolation system alternatives: a cost comparison; (2) BWIP technical integration and control; (3) BWIP performance evaluation process: a criteria based method; (4) impacts of waste age; (5) systems studies of subseabed disposal; and (6) systems studies of waste transportation

Experience with citizens panels

International Nuclear Information System (INIS)

Selwyn, J.

2002-01-01

In May 1999, 200 delegates attended a four-day UK Consensus Conference on radioactive waste management, which was organised by the UK Centre for Economic and Environmental Development (UK CEED) and supported by the government, industry and environmental groups. The event brought together a Citizens' Panel of fifteen people, randomly selected to represent a cross section of the British public, together with the major players in the debate. The four-day conference saw the panel cross-examine expert witnesses from organisations such as NIREX, British Nuclear Fuels Limited, the Ministry of Defence, Greenpeace and Friends of the Earth. The findings of their investigations were put together in a report containing detailed recommendations for government and industry and presented to the Minister on the final day. (author)

MO-F-201-01: Panel Member

Energy Technology Data Exchange (ETDEWEB)

Evans, J. [Virginia Commonwealth University (United States)

2016-06-15

The goal of this session is to provide guidance to medical physicists undergoing the American Board of Radiology certification process in therapeutic medical physics. This panel discussion will focus on parts 2 (computer-based) and 3 (oral) of the examination. Unlike the latter portions of the exam which are specialty-driven, part 1 is universal for all medical physics fields and will not be addressed. This session is structured into different topics that aim to guide the participants on how to successfully prepare for the board exams. The subjects of discussion will include timing and strategies for exam preparation, crucial differences in preparing for the clinical computer-based exam versus the oral exam, what study tools are currently available for each, etc. The panel discussion format will allow the speakers to collectively present their experience and advice relating to each topic and foment audience participation. Learning Objectives: Know the main differences between what is expected for parts 2 and 3 Know different resources for test preparation Know how to formulate a plan to best study for each part based on the specific skill set the two parts require Know how to best present his/her answers during the oral examination – demeanor, answer structure, etc.

MO-F-201-02: Panel Member

Energy Technology Data Exchange (ETDEWEB)

Padilla, L. [Virginia Commonwealth University (United States)

2016-06-15

The goal of this session is to provide guidance to medical physicists undergoing the American Board of Radiology certification process in therapeutic medical physics. This panel discussion will focus on parts 2 (computer-based) and 3 (oral) of the examination. Unlike the latter portions of the exam which are specialty-driven, part 1 is universal for all medical physics fields and will not be addressed. This session is structured into different topics that aim to guide the participants on how to successfully prepare for the board exams. The subjects of discussion will include timing and strategies for exam preparation, crucial differences in preparing for the clinical computer-based exam versus the oral exam, what study tools are currently available for each, etc. The panel discussion format will allow the speakers to collectively present their experience and advice relating to each topic and foment audience participation. Learning Objectives: Know the main differences between what is expected for parts 2 and 3 Know different resources for test preparation Know how to formulate a plan to best study for each part based on the specific skill set the two parts require Know how to best present his/her answers during the oral examination – demeanor, answer structure, etc.

MO-F-201-03: Panel Member

Energy Technology Data Exchange (ETDEWEB)

Studenski, M. [University of Miami (United States)

2016-06-15

The goal of this session is to provide guidance to medical physicists undergoing the American Board of Radiology certification process in therapeutic medical physics. This panel discussion will focus on parts 2 (computer-based) and 3 (oral) of the examination. Unlike the latter portions of the exam which are specialty-driven, part 1 is universal for all medical physics fields and will not be addressed. This session is structured into different topics that aim to guide the participants on how to successfully prepare for the board exams. The subjects of discussion will include timing and strategies for exam preparation, crucial differences in preparing for the clinical computer-based exam versus the oral exam, what study tools are currently available for each, etc. The panel discussion format will allow the speakers to collectively present their experience and advice relating to each topic and foment audience participation. Learning Objectives: Know the main differences between what is expected for parts 2 and 3 Know different resources for test preparation Know how to formulate a plan to best study for each part based on the specific skill set the two parts require Know how to best present his/her answers during the oral examination – demeanor, answer structure, etc.

MO-F-201-04: Panel Member

Energy Technology Data Exchange (ETDEWEB)

McNutt, T. [Johns Hopkins University (United States)

2016-06-15

The goal of this session is to provide guidance to medical physicists undergoing the American Board of Radiology certification process in therapeutic medical physics. This panel discussion will focus on parts 2 (computer-based) and 3 (oral) of the examination. Unlike the latter portions of the exam which are specialty-driven, part 1 is universal for all medical physics fields and will not be addressed. This session is structured into different topics that aim to guide the participants on how to successfully prepare for the board exams. The subjects of discussion will include timing and strategies for exam preparation, crucial differences in preparing for the clinical computer-based exam versus the oral exam, what study tools are currently available for each, etc. The panel discussion format will allow the speakers to collectively present their experience and advice relating to each topic and foment audience participation. Learning Objectives: Know the main differences between what is expected for parts 2 and 3 Know different resources for test preparation Know how to formulate a plan to best study for each part based on the specific skill set the two parts require Know how to best present his/her answers during the oral examination – demeanor, answer structure, etc.

MO-E-BRB-02: Panel Member

Energy Technology Data Exchange (ETDEWEB)

Larner, J. [University of Virginia (United States)

2016-06-15

In this interactive session, lung SBRT patient cases will be presented to highlight real-world considerations for ensuring safe and accurate treatment delivery. An expert panel of speakers will discuss challenges specific to lung SBRT including patient selection, patient immobilization techniques, 4D CT simulation and respiratory motion management, target delineation for treatment planning, online treatment alignment, and established prescription regimens and OAR dose limits. Practical examples of cases, including the patient flow thought the clinical process are presented and audience participation will be encouraged. This panel session is designed to provide case demonstration and review for lung SBRT in terms of (1) clinical appropriateness in patient selection, (2) strategies for simulation, including 4D and respiratory motion management, and (3) applying multi imaging modality (4D CT imaging, MRI, PET) for tumor volume delineation and motion extent, and (4) image guidance in treatment delivery. Learning Objectives: Understand the established requirements for patient selection in lung SBRT Become familiar with the various immobilization strategies for lung SBRT, including technology for respiratory motion management Understand the benefits and pitfalls of applying multi imaging modality (4D CT imaging, MRI, PET) for tumor volume delineation and motion extent determination for lung SBRT Understand established prescription regimes and OAR dose limits.

MO-E-BRB-03: Panel Member

Energy Technology Data Exchange (ETDEWEB)

Salter, B. [University Utah (United States)

2016-06-15

In this interactive session, lung SBRT patient cases will be presented to highlight real-world considerations for ensuring safe and accurate treatment delivery. An expert panel of speakers will discuss challenges specific to lung SBRT including patient selection, patient immobilization techniques, 4D CT simulation and respiratory motion management, target delineation for treatment planning, online treatment alignment, and established prescription regimens and OAR dose limits. Practical examples of cases, including the patient flow thought the clinical process are presented and audience participation will be encouraged. This panel session is designed to provide case demonstration and review for lung SBRT in terms of (1) clinical appropriateness in patient selection, (2) strategies for simulation, including 4D and respiratory motion management, and (3) applying multi imaging modality (4D CT imaging, MRI, PET) for tumor volume delineation and motion extent, and (4) image guidance in treatment delivery. Learning Objectives: Understand the established requirements for patient selection in lung SBRT Become familiar with the various immobilization strategies for lung SBRT, including technology for respiratory motion management Understand the benefits and pitfalls of applying multi imaging modality (4D CT imaging, MRI, PET) for tumor volume delineation and motion extent determination for lung SBRT Understand established prescription regimes and OAR dose limits.

MO-E-BRB-01: Panel Member

Energy Technology Data Exchange (ETDEWEB)

Benedict, S. [University of California Davis Medical Center (United States)

2016-06-15

In this interactive session, lung SBRT patient cases will be presented to highlight real-world considerations for ensuring safe and accurate treatment delivery. An expert panel of speakers will discuss challenges specific to lung SBRT including patient selection, patient immobilization techniques, 4D CT simulation and respiratory motion management, target delineation for treatment planning, online treatment alignment, and established prescription regimens and OAR dose limits. Practical examples of cases, including the patient flow thought the clinical process are presented and audience participation will be encouraged. This panel session is designed to provide case demonstration and review for lung SBRT in terms of (1) clinical appropriateness in patient selection, (2) strategies for simulation, including 4D and respiratory motion management, and (3) applying multi imaging modality (4D CT imaging, MRI, PET) for tumor volume delineation and motion extent, and (4) image guidance in treatment delivery. Learning Objectives: Understand the established requirements for patient selection in lung SBRT Become familiar with the various immobilization strategies for lung SBRT, including technology for respiratory motion management Understand the benefits and pitfalls of applying multi imaging modality (4D CT imaging, MRI, PET) for tumor volume delineation and motion extent determination for lung SBRT Understand established prescription regimes and OAR dose limits.

MO-F-201-01: Panel Member

International Nuclear Information System (INIS)

Evans, J.

2016-01-01

The goal of this session is to provide guidance to medical physicists undergoing the American Board of Radiology certification process in therapeutic medical physics. This panel discussion will focus on parts 2 (computer-based) and 3 (oral) of the examination. Unlike the latter portions of the exam which are specialty-driven, part 1 is universal for all medical physics fields and will not be addressed. This session is structured into different topics that aim to guide the participants on how to successfully prepare for the board exams. The subjects of discussion will include timing and strategies for exam preparation, crucial differences in preparing for the clinical computer-based exam versus the oral exam, what study tools are currently available for each, etc. The panel discussion format will allow the speakers to collectively present their experience and advice relating to each topic and foment audience participation. Learning Objectives: Know the main differences between what is expected for parts 2 and 3 Know different resources for test preparation Know how to formulate a plan to best study for each part based on the specific skill set the two parts require Know how to best present his/her answers during the oral examination – demeanor, answer structure, etc.

MO-F-201-04: Panel Member

International Nuclear Information System (INIS)

McNutt, T.

2016-01-01

The goal of this session is to provide guidance to medical physicists undergoing the American Board of Radiology certification process in therapeutic medical physics. This panel discussion will focus on parts 2 (computer-based) and 3 (oral) of the examination. Unlike the latter portions of the exam which are specialty-driven, part 1 is universal for all medical physics fields and will not be addressed. This session is structured into different topics that aim to guide the participants on how to successfully prepare for the board exams. The subjects of discussion will include timing and strategies for exam preparation, crucial differences in preparing for the clinical computer-based exam versus the oral exam, what study tools are currently available for each, etc. The panel discussion format will allow the speakers to collectively present their experience and advice relating to each topic and foment audience participation. Learning Objectives: Know the main differences between what is expected for parts 2 and 3 Know different resources for test preparation Know how to formulate a plan to best study for each part based on the specific skill set the two parts require Know how to best present his/her answers during the oral examination – demeanor, answer structure, etc.

Radioactive waste management. Introductory statement of the 3rd scientific forum during the 44th session of the IAEA General Conference. Vienna, 19 September 2000

International Nuclear Information System (INIS)

ElBaradei, M.

2000-01-01

The document reproduces the text of the introductory statement made by the Director General of the IAEA at the 3rd scientific forum organized during the 44th session of the IAEA General Conference, Vienna, 19 september 2000, on the management of radioactive waste. He emphasized the following aspects: progress made in technology and public acceptance, global challenges, international co-operation, building a stronger framework

Nuclear fuel cycle issues and challenges. Scientific forum during the 48th Regular Session of the IAEA General Conference. Session summaries and reports

International Nuclear Information System (INIS)

2004-01-01

The three sessions of the forum focused on: Advanced Fuel Cycles and Reactor Concepts; Waste and Spent Fuel Management Issues; and Research Reactor Fuel Cycle and Related Issues. Twelve detailed presentations were made by leading experts, followed by panellists' comments and discussion with participants

Nuclear fuel waste policy in Canada

International Nuclear Information System (INIS)

Brown, P.A.; Letourneau, C.

1999-01-01

The 1996 Policy Framework for Radioactive Waste established the approach in Canada for dealing with all radioactive waste, and defined the respective roles of Government and waste producers and owners. The Policy Framework sets the stage for the development of institutional and financial arrangements to implement long-term waste management solutions in a safe, environmentally sound, comprehensive, cost-effective and integrated manner. For nuclear fuel waste, a 10-year environmental review of the concept to bury nuclear fuel waste bundles at a depth of 500 m to 1000 m in stable rock of the Canadian Shield was completed in March 1998. The Review Panel found that while the concept was technically safe, it did not have the required level of public acceptability to be adopted at this time as Canada's approach for managing its nuclear fuel waste. The Panel recommended that a Waste Management Organization be established at arm's length from the nuclear industry, entirely funded by the waste producers and owners, and that it be subject to oversight by the Government. In its December 1998 Response to the Review Panel, the Government of Canada provided policy direction for the next steps towards developing Canada's approach for the long-term management of nuclear fuel waste. The Government chose to maintain the responsibility for long-term management of nuclear fuel waste close with the producers and owners of the waste. This is consistent with its 1996 Policy Framework for Radioactive Waste. This approach is also consistent with experience in many countries. In addition, the federal government identified the need for credible federal oversight. Cabinet directed the Minister of NRCan to consult with stakeholders, including the public, and return to ministers within 12 months with recommendations on means to implement federal oversight. (author)

Report from the UK consensus conference on radioactive waste management, May 1999

International Nuclear Information System (INIS)

Hiett, A.

2000-01-01

A Consensus Conference took place in the UK in May 1999 to address the issue of Radioactive Waste Management. Sixteen members of the public were invited, at random, to take part in the conference, and initially were unaware of the topic. After two preparation weekends, the citizen's panel held a two day conference at which they cross examined expert 'witnesses' on issues which they felt to be relevant to the topic. The remit of the panel was as follows: ''The Consensus Conference is to focus on the effective and publicly acceptable long term management of nuclear waste in the UK, both civil and military, concentrating particularly on intermediate and high level waste. This will be considered by the citizens' panel in their capacity as members of the public, taking into account what they see as the relevant issues''. Following the conference itself, the panel produced a report on their findings and conclusions. Retrievability was just one of the many areas that the panel covered. In relation to the area of public acceptance for long term management of radioactive waste, the recommendations of the panel were as follows: ''In conclusion the panel was unanimous that in order for a solution to be publicly acceptable, the waste MUST remain accessible and monitorable to give future generations a chance to deal with the problem if/when a solution is found''. (author)

Retrievable surface storage: interim storage of solidified high-level waste

International Nuclear Information System (INIS)

LaRiviere, J.R.; Nelson, D.C.

1976-01-01

Studies have been conducted on retrievable-surface-storage concepts for the interim storage of solidified high-level wastes. These studies have been reviewed by the Panel on Engineered Storage, convened by the Committee on Radioactive Waste Management of the National Research Council-National Academy of Sciences. The Panel has concluded that ''retrievable surface storage is an acceptable interim stage in a comprehensive system for managing high-level radioactive wastes.'' The scaled storage cask concept, which was recommended by the Panel on Engineered Storage, consists of placing a canister of waste inside a carbon-steel cask, which in turn is placed inside a thick concrete cylinder. The waste is cooled by natural convection air flow through an annulus between the cask and the inner wall of the concrete cylinder. The complete assembly is placed above ground in an outdoor storage area

TWRS vadose zone contamination issue expert panel report

Energy Technology Data Exchange (ETDEWEB)

Shafer, D.S.

1997-05-01

When members were first canvassed for participation in the Vadose Zone Expert Panel the stated purpose for convening the Panel was to review a controversial draft report, the SX Tank Farm Report. This report was produced by a DOE Grand Junction Project Office (GJPO) contractor, RUST Geotech, now MACTEC-ERS, for the DOE Richland Office (DOERL). Three meetings were planned for June, July and August, 1995 to review the draft report and to complete a Panel report by mid-September. The Expert Panel has found its efforts confounded by various non-technical issues. The Expert Panel has chosen to address some of the non-technical issues in this Preface rather than to dilute the technical discussion that follows in the body of this independent expert panel status report (Panel Report). Rather than performing a straightforward manuscript review, the Panel was asked to resolve conflicting interpretations of gamma-ray logging measurements performed in vadose zone boreholes (drywells) surrounding the high-level radioactive wastes of the SX tank farm. There are numerous and complex technical issues that must be evaluated before the vertical and radial extent of contaminant migration at the SX tank farm can be accurately assessed. When the Panel first met in early June, 1996, it quickly became apparent that the scientific and technical issues were obscured by policy and institutional affairs which have polarized discussion among various segments of the Hanford organization. This situation reflects the kinds of institutional problems described separately in reports by the National Research Council of the National Academy of Sciences (NAS/NRC), The Hanford Tanks Environmental Impacts and Policy Choices and BmTiers to Science: Technical Management of the Department of Energy Environmental Remediation Program. The Vadose Zone Characterization Program, appears to be caught between conflicting pressures and organizational mandates, some imposed from outside DOE-RL and some self

Evaluation of proposed panel closure modifications at WIPP

Energy Technology Data Exchange (ETDEWEB)

Allen, Lawrence E.; Silva, Matthew K.; Channell, James K.; Abel, John F.; Morgan, Dudley R.

2001-12-31

A key component in the design of the WIPP repository is the installation of concrete structures as panel seals in the intake and exhaust drifts after a panel has been filled with waste containers. As noted in the EPA final rule, the panel seal closure system is intended to block brine flow between the waste panels at the WIPP. On April 17, 2001, the DOE proposed seven modifications to the EPA concerning the design of the panel closure system. EPA approval of these modifications is necessary since the details of the panel design are specified in EPA’s final rule as a condition for WIPP certification. However, the EPA has not determined whether a rulemaking would be required for these proposed design modifications. On September 4, 2001, the DOE withdrew the request, noting that it would be resubmitted on a future date. The Environmental Evaluation Group (EEG) contracted with two engineers, Dr. John Abel and Dr. Rusty Morgan, to evaluate the proposed modifications. The EEG has accepted the conclusions and recommendations from these two experts: 1) replacement of Salado Mass Concrete with a generic salt-based concrete; 2) replacement of the explosion wall with a construction wall; 3) replacement of freshwater grouting with salt-based grouting; 4) option to allow surface or underground mixing; and 5) option to allow up to one year for completion of closure. The proposed modification to allow local carbonate river rock as aggregate is acceptable pending demonstration that no problems will exist in the resulting concrete. The proposed modification to give the contractor discretion in removal of steel forms is not supported. Instead, several recommendations are made to specifically reduce the number of forms left, thereby reducing potential migration pathways.

Experimental investigation to evaluate the potential environmental hazards of photovoltaic panels.

Science.gov (United States)

Tammaro, Marco; Salluzzo, Antonio; Rimauro, Juri; Schiavo, Simona; Manzo, Sonia

2016-04-05

Recently the potential environmental hazard of photovoltaic modules together with their management as waste has attracted the attention of scientists. Particular concern is aroused by the several metals contained in photovoltaic panels whose potential release in the environment were scarcely investigated. Here, for the first time, the potential environmental hazard of panels produced in the last 30 years was investigated through the assessment of up to 18 releasable metals. Besides, the corresponding ecotoxicological effects were also evaluated. Experimental data were compared with the current European and Italian law limits for drinking water, discharge on soil and landfill inert disposal in order to understand the actual pollution load. Results showed that less than 3% of the samples respected all law limits and around 21% was not ecotoxic. By considering the technological evolutions in manufacturing, we have shown that during the years crystalline silicon panels have lower tendency to release hazardous metals with respect to thin film panels. In addition, a prediction of the amounts of lead, chromium, cadmium and nickel releasable from next photovoltaic waste was performed. The prevision up to 2050 showed high amounts of lead (30t) and cadmium (2.9t) releasable from crystalline and thin film panels respectively. Copyright © 2015 Elsevier B.V. All rights reserved.

Foaming of CRT panel glass powder with Na2CO3

DEFF Research Database (Denmark)

Petersen, Rasmus Rosenlund; König, Jakob; Smedskjær, Morten Mattrup

melt, while Na2O becomes incorporated into the glass structure. We have quantified the melt expansion through density measurements and the Na2O incorporation is indicated by the decrease of the glass transition temperature (Tg) of the final foam glass. The glass foaming quality depends on the foaming......Recycling of cathode ray tube (CRT) glass remains a challenging task. The CRT glass consists of four glass types fused together: Funnel-, neck-, frit- and panel glass. The three former glasses contain toxic lead oxide, and therefore have a low recycling potential. The latter on the other hand...... is lead-free, but since barium and strontium oxide are present, panel glass is incompatible with most common recycling methods. However, foam glass production is a promising approach for the recycling of panel glass waste, since the process parameters can be changed according to the glass waste...

Solidification of high-level radioactive wastes. Final report

International Nuclear Information System (INIS)

1979-06-01

A panel on waste solidification was formed at the request of the Nuclear Regulatory Commission to study the scientific and technological problems associated with the conversion of liquid and semiliquid high-level radioactive wastes into a stable form suitable for transportation and disposition. Conclusions reached and recommendations made are as follows. Many solid forms described in this report could meet standards as stringent as those currently applied to the handling, storage, and transportation of spent fuel assemblies. Solid waste forms should be selected only in the context of the total radioactive waste management system. Many solid forms are likely to be satisfactory for use in an appropriately designed system, The current United States policy of deferring the reprocessing of commercial reactor fuel provides additional time for R and D solidification technology for this class of wastes. Defense wastes which are relatively low in radioactivity and thermal power density can best be solidified by low-temperature processes. For solidification of fresh commercial wastes that are high in specific activity and thermal power density, the Panel recommends that, in addition to glass, the use of fully-crystalline ceramics and metal-matrix forms be actively considered. Preliminary analysis of the characteristics of spent fuel pins indicates that they may be eligible for consideration as a waste form. Because the differences in potential health hazards to the public resulting from the use of various solid form and disposal options are likely to be small, the Panel concludes that cost, reliability, and health hazards to operating personnel will be major considerations in choosing among the options that can meet safety requiremens. The Panel recommends that responsibility for all radioactive waste management operations (including solidification R and D) should be centralized

Panel discussion on 'Government and industry social responsibility towards potential communities hosting radioactive waste management sites'

International Nuclear Information System (INIS)

Cragg, W.; Storey, K.; Cooper, H.; McIntyre, J.; Brown, P.

2006-01-01

'Full text:' In healthy democracies, support from local communities for industrial/development projects is highly desirable. What are the respective roles of the various stakeholder sectors, i.e. governments, industry, and communities around industrial projects, including waste management facilities, and how can they interact with sustainable development in mind? Should the private sector be involved in public policy? Should the public sector have an active role in providing funding complementing the notion of the Polluter pays principle? Should communities have a greater role in overseeing the activities of industry and be enabled to do so? Should communities be empowered to increase their role in decision-making processes? Are there trends emerging in this area? Are there improvements to be made? The Not-in-My-Backyard (NIMBY) reflex is not e thical . Thoughtful review is required when considering the right or the desirability to develop. Each of the invited panel members will briefly approach this issue from the perspective of their respective sector. A discussion period will ensue which hopefully will provide insight into how diverse sectors can work together to ensure the establishment of radioactive waste management facilities in communities which support such projects based on local and national values. (author)

USE OF CANDEIA’S (Eremanthus erythropappus WASTE WOOD

Directory of Open Access Journals (Sweden)

Rosimeire Cavalcante dos Santos

2008-09-01

Full Text Available The candeia (Eremanthus erythropappus is a native forest species with multiple uses and specially utilized as essential oils source. The use of the candeia´s waste wood after oil extraction for particle panels production becomes a viable alternative, avoiding environmental problems and increasing the availability of these products in the consuming market. This work verified the viability of producing wood-cement panels using waste wood generated after the extraction of candeia’s oil, in association with pinus and eucalipto woods. The experiment was installed according to a completely randomized design with three repetitions. The treatments were arranged according to a factorial 2 x 3 scheme (two wooden species and three replacement percentages of the woods by candeia’s waste. The results of the physical and mechanical property tests showed high potentiality of candeia waste wood, after oil extraction, in association with pinus and eucalipto wood for manufacturing wood-cement panels.

Does industrial waste taxation contribute to reduction of landfilled waste? Dynamic panel analysis considering industrial waste category in Japan.

Science.gov (United States)

Sasao, Toshiaki

2014-11-01

Waste taxes, such as landfill and incineration taxes, have emerged as a popular option in developed countries to promote the 3Rs (reduce, reuse, and recycle). However, few studies have examined the effectiveness of waste taxes. In addition, quite a few studies have considered both dynamic relationships among dependent variables and unobserved individual heterogeneity among the jurisdictions. If dependent variables are persistent, omitted variables cause a bias, or common characteristics exist across the jurisdictions that have introduced waste taxes, the standard fixed effects model may lead to biased estimation results and misunderstood causal relationships. In addition, most existing studies have examined waste in terms of total amounts rather than by categories. Even if significant reductions in total waste amounts are not observed, some reduction within each category may, nevertheless, become evident. Therefore, this study analyzes the effects of industrial waste taxation on quantities of waste in landfill in Japan by applying the bias-corrected least-squares dummy variable (LSDVC) estimators; the general method of moments (difference GMM); and the system GMM. In addition, the study investigates effect differences attributable to industrial waste categories and taxation types. This paper shows that industrial waste taxes in Japan have minimal, significant effects on the reduction of final disposal amounts thus far, considering dynamic relationships and waste categories. Copyright © 2014 Elsevier Ltd. All rights reserved.

A multi-criteria decision analysis assessment of waste paper management options.

Science.gov (United States)

Hanan, Deirdre; Burnley, Stephen; Cooke, David

2013-03-01

The use of Multi-criteria Decision Analysis (MCDA) was investigated in an exercise using a panel of local residents and stakeholders to assess the options for managing waste paper on the Isle of Wight. Seven recycling, recovery and disposal options were considered by the panel who evaluated each option against seven environmental, financial and social criteria. The panel preferred options where the waste was managed on the island with gasification and recycling achieving the highest scores. Exporting the waste to the English mainland for incineration or landfill proved to be the least preferred options. This research has demonstrated that MCDA is an effective way of involving community groups in waste management decision making. Copyright © 2012 Elsevier Ltd. All rights reserved.

Underground nuclear waste storage backed

International Nuclear Information System (INIS)

Long, J.R.

1978-01-01

Latest to hold hearings on nuclear waste disposal problems is the Senate Commerce Subcommittee on Science, Technology and Space. Testimonies by John M. Deutch, Rustum Roy (presenting results of National Research Council panel on waste solidification), and Darleane C. Hoffman are summarized

Session 1984-85. Radioactive waste. Minutes of evidence, Monday 17 June 1985. Nuclear Industry Radioactive Waste Executive

International Nuclear Information System (INIS)

1985-01-01

The Environment Select Committee of the House of Commons received a memorandum from the Nuclear Industry Radioactive Waste Executive, on the management and disposal of radioactive waste arising in the UK, under the headings: introduction; the structure of NIREX; the nature of radioactive waste; plans for the disposal of low and intermediate level wastes. Representatives of NIREX were examined on the subject of the memorandum and the minutes of evidence are recorded. (U.K.)

Incorporation of waste and fiber kaolin caroa panels in Medium Density Fiberboard - MDF; Incorporacao de residuos de caulim e fibras de caroa em paineis de media densidade- MDF

Energy Technology Data Exchange (ETDEWEB)

Bezerra, A.F.C.; Santana, L.N.L.; Neves, G.A.; Carvalho, L.H. de; Lopes, F.F.M., E-mail: anaflavia.dema@yahoo.com.br [Universidade Federal de Campina Grande (UFCG), PB (Brazil)

2012-07-01

Medium-density panels are composites molded under high temperature and pressure which have physical and mechanical properties similar to those of solid wood. Their composition includes eucalyptus grandis fibers and pinus elliotii fibers, but other fibers can be used such as caroa fibers. The goal of this work was to manufacture panels which kaolin waste and caroa fibers and compare their physical, chemical and mechanical of these panels with a others. Both residue and the fibers were characterized by: differential thermal analysis, thermal gravimetric analysis and Xray diffraction. Through the process of pressing the test specimens were fabricated, test samples were evaluated by three point bending, internal bond, water absorption and swelling in thickness. The samples have low levels of thickness swelling, flexural strength and higher tensile and absorption content relative to commercial MDF. (author)

Proceedings of the international symposium on radioactive waste disposal: Health and environmental criteria and standards

International Nuclear Information System (INIS)

Hultcrantz, K.

1999-04-01

The co-organisers of the International Symposium on Health and Environmental Criteria and Standards for Radioactive Waste Disposal are pleased to present these proceedings. This Symposium succeeded in bringing together a wide range of participants and perspectives in order to address in a common forum the technical and non-technical issues related to long-term storage of radioactive waste. The papers presented herein reflect both the diversity of the participants and the complexity of the issues addressed. The sessions, panels, and papers developed for the symposium focused on some of the daunting challenges posed by long-term isolation and storage of high level radioactive waste. Panel sessions addressed the basic principles of criteria and standards, the context of the risks involved, and an overview of relevant philosophical, social, and ethical issues. Paper sessions considered national laws, policies and experiences; criteria formulation; environmental protection; compliance; human intrusion; and fundamental philosophical, social, and ethical issues. The presentations stimulated lively discussion and debate, and the contributors received valuable feedback. The interplay between technical and social aspects reflected in some papers and in the discussion highlights the changing role of the public in radioactive waste issues. The average citizen has become more aware of and more involved in radioactive waste matters in recent years. Solutions that were previously analysed through a technological lens are now being viewed in a much broader perspective that better addresses the concerns of local communities as well as national and international interests. Public involvement must begin earlier, last longer, and improve in quality so as to create an ongoing dialogue and debate rather than cycles of dictates and discord. The symposium has offered suggestions as to how government, industry, and the public can foster a broader dialogue on the formulation and

Waste management, decommissioning and environmental restoration for Canada's nuclear activities. Proceedings

International Nuclear Information System (INIS)

2011-01-01

The Canadian Nuclear Society conference on Waste Management, Decommissioning and Environmental Restoration for Canada's Nuclear Activities was held in Toronto, Ontario, Canada on September 11-14, 2011. The conference provided a forum for discussion of the status and proposed future directions of technical, regularly, environmental, social and economic aspects of radioactive waste management, nuclear facility decommissioning, and environmental restoration activities for Canadian nuclear facilities. The conference included both plenary sessions and sessions devoted to more detailed technical issues. The plenary sessions were focussed on three broad themes: the overall Canadian program; low and intermediate waste; and, international perspectives. Topics of the technical sessions included: OPG's deep geologic repository for low and intermediate level waste; stakeholder interactions; decommissioning projects; uranium mine waste management; used fuel repository - design and safety assessment; federal policies, programs and oversight; regulatory considerations; aboriginal traditional knowledge; geological disposal - CRL site classification; geological disposal - modelling and engineered barriers; Port Hope Area Initiative; waste characterization; LILWM - treatment and processing; decommissioning projects and information management; international experience; environmental remediation; fuel cycles and waste processing.

78 FR 63168 - Judges Panel of the Malcolm Baldrige National Quality Award

Science.gov (United States)

2013-10-23

... INFORMATION CONTACT: Robert Fangmeyer, Acting Director, Baldrige Performance Excellence Program, National... Baldrige National Quality Award AGENCY: National Institute of Standards and Technology, Department of... Quality Award (Judges Panel) will meet in closed session Monday through Friday, November 4-8, 2013, 8:30 a...

Proceedings of the seventh annual participants' information meeting. DOE Low-Level Waste Management Program

International Nuclear Information System (INIS)

1986-02-01

The Seventh Annual Department of Energy (DOE) Low-Level Waste Management Program (LLWMP) Participants' Information Meeting was held September 10-13, 1985 in Las Vegas, Nevada. The purpose of the meeting was to provide a forum for exchange of information on low-level radioactive waste management activities, requirements, and plans. Attendees included representatives from the DOE Nuclear Energy and Defense Low-Level Waste Management Programs, interim operations offices and their contractor operators; representatives from the US Nuclear Regulatory Commission, US Environmental Protection Agency, US Geological Survey, and their contractors; representatives of states and regions responsible for development of new commercial low-level waste disposal facilities; representatives of Great Britain, France, and Canada; representatives of utilities, private contractors, and parties concerned with low-level waste management issues. The meeting was organized by topical areas to allow for the exchange of information and the promotion of discussion on specific aspects of low-level waste management. Plenary sessions were held at the start and conclusion of the meeting while seven concurrent topical sessions were held during the intervening day and a half. Session chairmen from each of these concurrent sessions presented a summary of the discussion and conclusions resulting from their respective sessions at the final plenary session

Management of radioactive waste at the Oak Ridge National Laboratory: a technical review

International Nuclear Information System (INIS)

1985-01-01

This review was performed for the US Department of Energy by a panel of the Board on Radioactive Waste Management under the National Research Council's Commission on Physical Sciences, Mathematics, and Resources. In summary, ORNL's waste management practices have kept offsite doses low; some of the practices are temporary and improvised - they may not be as satisfactory in the future; reducing anticipated future releases will be difficult because the limited number of candidate waste disposal locations are characterized by topographic peculiarities; and a major ORNL accomplishment has been the demonstration that hydrofracture can be a successful method of disposal for at least low- and intermediate-level waste. The panel obtained its information over a 2-year period by examining a large body of technical literature, by making six visits to the Oak Ridge National Laboratory, and through briefings by representatives of government agencies and their subcontractors. Chapter 2 contains the charge to the panel. Chapters 3, 4, and 5 describe the site, the waste that is present, and the methods used to handle it. Chapters 6 through 10 treat the manner in which the performance of the waste-handling system is monitored, the criteria against which performance is assessed, the panel's assessment of performance, and consideration of alternative methods for future handling of radioactive waste. Chapter 11 contains a brief comparison of ORNL with other sites. The panel's principal conclusions and recommendations are summarized below and treated in detail in subsequent chapters. In general, the conclusions and recommendations considered by the panel to be the most important are provided first. 123 refs., 30 figs., 24 tabs

Technical viability and development needs for waste forms and facilities

Energy Technology Data Exchange (ETDEWEB)

Pegg, I.; Gould, T.

1996-05-01

The objective of this breakout session was to provide a forum to discuss technical issues relating to plutonium-bearing waste forms and their disposal facilities. Specific topics for discussion included the technical viability and development needs associated with the waste forms and/or disposal facilities. The expected end result of the session was an in-depth (so far as the limited time would allow) discussion of key issues by the session participants. The session chairs expressed allowance for, and encouragement of, alternative points of view, as well as encouragement for discussion of any relevant topics not addressed in the paper presentations. It was not the intent of this session to recommend or advocate any one technology over another.

Manpower Requirements and Education in Nuclear Science: An International Perspective Nuclear Science Manpower and Education Panel

International Nuclear Information System (INIS)

Zeisler, R.; Clark, S.B.; Parry, S.J.; Choppin, G.R.; Danesi, P.R.; Rossbach, M.; Williamson, C.; and others

2005-01-01

The MARC-VI conference served as an excellent setting for a session organized to present and discuss the problems in nuclear science manpower and education. A panel discussion and contributed papers reflected the world-wide situation. Major points of the panel discussion are presented. As a result, a resolution on the current situation of nuclear chemistry and radiochemistry was drafted and endorsed by the conference attendees. (author)

Eco-dialysis: the financial and ecological costs of dialysis waste products: is a 'cradle-to-cradle' model feasible for planet-friendly haemodialysis waste management?

Science.gov (United States)

Piccoli, Giorgina Barbara; Nazha, Marta; Ferraresi, Martina; Vigotti, Federica Neve; Pereno, Amina; Barbero, Silvia

2015-06-01

Approximately 2 million chronic haemodialysis patients produce over 2,000,000 tons of waste per year that includes about 600,000 tons of potentially hazardous waste. The aim of the present study was to analyse the characteristics of the waste that is produced through chronic haemodialysis in an effort to identify strategies to reduce its environmental and financial impact. The study included three dialysis machines and disposables for bicarbonate dialysis, haemodiafiltration (HFR) and lactate dialysis. Hazardous waste is defined as waste that comes into contact with bodily fluids. The weight and cost of waste management was evaluated by various policies of differentiation, ranging from a careful-optimal differentiation to a careless one. The amount of time needed for optimal management was recorded in 30 dialysis sessions. Non-hazardous materials were assessed for potential recycling. The amount of plastic waste that is produced per dialysis session ranges from 1.5 to 8 kg (from 1.1 to 8 kg of potentially hazardous waste), depending upon the type of dialysis machine and supplies, differentiation and emptying policies. The financial cost of waste disposal is high, and is mainly related to hazardous waste disposal, with costs ranging from 2.2 to 16 Euro per session (2.7-21 USD) depending on the waste management policy. The average amount of time needed for careful, optimal differentiation disposal is approximately 1 minute for a haemodialysis session and 2 minutes for HFR. The ecological cost is likewise high: less than one-third of non-hazardous waste (23-28%) is potentially recyclable, while the use of different types of plastic, glues, inks and labels prevents the remaining materials from being recycled. Acknowledging the problem of waste management in dialysis could lead to savings of hundreds of millions of Dollars and to the reuse and recycling of hundreds of tons of plastic waste per year on a world-wide scale with considerable financial and ecological savings

Waste management '76 nuclear overview session industry viewpoint

International Nuclear Information System (INIS)

Carson, A.B.

1976-01-01

Lack of firm policy decisions and implementing regulations and program plans related to nuclear fuel cycle by-product wastes has become a major deterrent to progress in the constructive utilization of fission energy. In any event, the mismatch between waste management program accomplishments and perceived requirements has increased rather than decreased over recent years. Multi-agency programs and industry participation as well, at higher levels of effort than in the past, are required and are being initiated, but useful and lasting decisions still are some time off. From industry's viewpoint, all of the agency and industry programs related to waste management must be based on (a) a common view that no constructive activity is going to have zero personnel or environmental impact and that there generally will be a finite level of impact or risk to public health and safety that can be considered acceptable, and (b) consistent and rational consideration of what the levels of impact or risk are that can be considered acceptable in various circumstances. Regulatory requirements finally imposed must be related in some rational way to actual effects and their acceptable levels. Sound bases for timely decisions also require recognition of the fact that ''full and complete demonstration'' is not often really practical or necessary. Demonstration requirements for particular circumstances must be clearly defined and related to functional importance, extent of supporting technology and experience and other such rational factors. Finally, it is recognized that there are nontechnical issues the resolution of which are just as necessary to progress as the technical ones. However, such issues should not be allowed to lead to decisions or actions which are phenomenologically unsound or technically unsupported. After all, you might as well fall flat on your face as lean too far over backward

TWRS vadose zone contamination issue expert panel status report

International Nuclear Information System (INIS)

Shafer, D.S.

1997-01-01

When members were first canvassed for participation in the Vadose Zone Expert Panel the stated purpose for convening the Panel was to review a controversial draft report, the SX Tank Farm Report. This report was produced by a DOE Grand Junction Project Office (GJPO) contractor, RUST Geotech, now MACTEC-ERS, for the DOE Richland Office (DOERL). Three meetings were planned for June, July and August, 1995 to review the draft report and to complete a Panel report by mid-September. The Expert Panel has found its efforts confounded by various non-technical issues. The Expert Panel has chosen to address some of the non-technical issues in this Preface rather than to dilute the technical discussion that follows in the body of this independent expert panel status report (Panel Report). Rather than performing a straightforward manuscript review, the Panel was asked to resolve conflicting interpretations of gamma-ray logging measurements performed in vadose zone boreholes (drywells) surrounding the high-level radioactive wastes of the SX tank farm. There are numerous and complex technical issues that must be evaluated before the vertical and radial extent of contaminant migration at the SX tank farm can be accurately assessed. When the Panel first met in early June, 1996, it quickly became apparent that the scientific and technical issues were obscured by policy and institutional affairs which have polarized discussion among various segments of the Hanford organization. This situation reflects the kinds of institutional problems described separately in reports by the National Research Council of the National Academy of Sciences (NAS/NRC), The Hanford Tanks Environmental Impacts and Policy Choices and BmTiers to Science: Technical Management of the Department of Energy Environmental Remediation Program. The Vadose Zone Characterization Program, appears to be caught between conflicting pressures and organizational mandates, some imposed from outside DOE-RL and some self

M.A. Streicher findings regarding high-level waste tank corrosion issues

International Nuclear Information System (INIS)

Husa, E.I.

1994-01-01

Dr. Michael A. Streicher is a nationally recognized metallurgist and corrosion scientist. He has served on the Department of Energy, Headquarters Tank Structural Integrity panel as the primary corrosion technical expert since the panel's inception in October 1991. Attachments 3 through 13 are Dr. Streicher's correspondence and presentations to the panel between November 1991 and May 1994. This compilation addresses Dr. Streicher's findings on High-Level Waste tank corrosion issues such as: corrosion mechanisms in carbon steels; hydrogen generation from waste tank corrosion; stress corrosion cracking in carbon steel tanks; water line attack in Hanford's single-shell tanks; stress corrosion cracking of austenitic stainless steels; and materials selection for new Hanford waste tanks. These papers discuss both generic and specific corrosion issues associated with waste tanks and transfer systems at Hanford, Savannah River, Idaho National Engineering Laboratory, and West Valley Demonstration Project

A multi-criteria decision analysis assessment of waste paper management options

Energy Technology Data Exchange (ETDEWEB)

Hanan, Deirdre [Department of Design, Development, Environment and Materials, The Open University, Walton Hall, Milton Keynes, MK7 6AA (United Kingdom); Burnley, Stephen, E-mail: s.j.burnley@open.ac.uk [Department of Design, Development, Environment and Materials, The Open University, Walton Hall, Milton Keynes, MK7 6AA (United Kingdom); Cooke, David [Department of Design, Development, Environment and Materials, The Open University, Walton Hall, Milton Keynes, MK7 6AA (United Kingdom)

2013-03-15

Highlights: ► Isolated communities have particular problems in terms of waste management. ► An MCDA tool allowed a group of non-experts to evaluate waste management options. ► The group preferred local waste management solutions to export to the mainland. ► Gasification of paper was the preferred option followed by recycling. ► The group concluded that they could be involved in the decision making process. - Abstract: The use of Multi-criteria Decision Analysis (MCDA) was investigated in an exercise using a panel of local residents and stakeholders to assess the options for managing waste paper on the Isle of Wight. Seven recycling, recovery and disposal options were considered by the panel who evaluated each option against seven environmental, financial and social criteria. The panel preferred options where the waste was managed on the island with gasification and recycling achieving the highest scores. Exporting the waste to the English mainland for incineration or landfill proved to be the least preferred options. This research has demonstrated that MCDA is an effective way of involving community groups in waste management decision making.

A multi-criteria decision analysis assessment of waste paper management options

International Nuclear Information System (INIS)

Hanan, Deirdre; Burnley, Stephen; Cooke, David

2013-01-01

Highlights: ► Isolated communities have particular problems in terms of waste management. ► An MCDA tool allowed a group of non-experts to evaluate waste management options. ► The group preferred local waste management solutions to export to the mainland. ► Gasification of paper was the preferred option followed by recycling. ► The group concluded that they could be involved in the decision making process. - Abstract: The use of Multi-criteria Decision Analysis (MCDA) was investigated in an exercise using a panel of local residents and stakeholders to assess the options for managing waste paper on the Isle of Wight. Seven recycling, recovery and disposal options were considered by the panel who evaluated each option against seven environmental, financial and social criteria. The panel preferred options where the waste was managed on the island with gasification and recycling achieving the highest scores. Exporting the waste to the English mainland for incineration or landfill proved to be the least preferred options. This research has demonstrated that MCDA is an effective way of involving community groups in waste management decision making

Estimates of the solubilities of waste element radionuclides in waste isolation pilot plant brines: A report by the expert panel on the source term

International Nuclear Information System (INIS)

Hobart, D.E.; Bruton, C.J.; Trauth, K.M.; Anderson, D.R.

1996-05-01

Evaluation of the long-term performance of the WIPP includes estimation of the cumulative releases of radionuclide elements to the accessible environment. Nonradioactive lead is added because of the large quantity expected in WIPP wastes. To estimate the solubilities of these elements in WIPP brines, the Panel used the following approach. Existing thermodynamic data were used to identify the most likely aqueous species in solution through the construction of aqueous speciation diagrams. Existing thermodynamic data and expert judgment were used to identify potential solubility-limiting solid phases. Thermodynamic data were used to calculate the activities of the radionuclide aqueous species in equilibrium with each solid. Activity coefficients of the radionuclide-bearing aqueous species were estimated using Pitzer's equations. These activity coefficients were then used to calculate the concentration of each radionuclide at the 0.1 and 0.9 fractiles. The 0.5 fractile was chosen to represent experimental data with activity coefficient corrections as described above. Expert judgment was used to develop the 0.0, 0.25, 0.75, and 1.0 fractiles by considering the sensitivity of solubility to the potential variability in the composition of brine and gas, and the extent of waste contaminants, and extending the probability distributions accordingly. The results were used in the 1991 and 1992 performance assessment calculations. 68 refs

Estimates of the solubilities of waste element radionuclides in waste isolation pilot plant brines: A report by the expert panel on the source term

Energy Technology Data Exchange (ETDEWEB)

Hobart, D.E. [Sandia National Labs., Albuquerque, NM (United States)]|[Glenn T. Seaborg Inst. for Transactinium Science, Livermore, CA (United States); Bruton, C.J. [Sandia National Labs., Albuquerque, NM (United States)]|[Lawrence Livermore National Lab., CA (United States). Earth Sciences Dept.; Millero, F.J. [Sandia National Labs., Albuquerque, NM (United States)]|[Univ. of Miami, FL (United States). Rosenstiel School of Marine and Atmospheric Science; Chou, I.M. [Sandia National Labs., Albuquerque, NM (United States)]|[Geological Survey, Reston, VA (United States); Trauth, K.M.; Anderson, D.R. [Sandia National Labs., Albuquerque, NM (United States)

1996-05-01

Evaluation of the long-term performance of the WIPP includes estimation of the cumulative releases of radionuclide elements to the accessible environment. Nonradioactive lead is added because of the large quantity expected in WIPP wastes. To estimate the solubilities of these elements in WIPP brines, the Panel used the following approach. Existing thermodynamic data were used to identify the most likely aqueous species in solution through the construction of aqueous speciation diagrams. Existing thermodynamic data and expert judgment were used to identify potential solubility-limiting solid phases. Thermodynamic data were used to calculate the activities of the radionuclide aqueous species in equilibrium with each solid. Activity coefficients of the radionuclide-bearing aqueous species were estimated using Pitzer`s equations. These activity coefficients were then used to calculate the concentration of each radionuclide at the 0.1 and 0.9 fractiles. The 0.5 fractile was chosen to represent experimental data with activity coefficient corrections as described above. Expert judgment was used to develop the 0.0, 0.25, 0.75, and 1.0 fractiles by considering the sensitivity of solubility to the potential variability in the composition of brine and gas, and the extent of waste contaminants, and extending the probability distributions accordingly. The results were used in the 1991 and 1992 performance assessment calculations. 68 refs.

Session 1984-85. Radioactive waste. Minutes of evidence, Monday 20 May 1985. Greenpeace

International Nuclear Information System (INIS)

1985-01-01

The Environment Select Committee of the House of Commons received a memorandum from Greenpeace on radioactive waste, including the following aspects: UK nuclear power programme; Government policies; origins and inventories of waste; fuel reprocessing plants; waste storage, processing and disposal; classification of active wastes; transport; functions of some organisations concerned with radioactive wastes in UK; relevant international law; ICRP safety standards; London Dumping Convention; dispersal of radioactive wastes from Windscale - radiological impacts; discussion of particular proposals for disposal sites; sea dumping; deep sub-seabed disposal. Representatives of Greenpeace were examined on the subject of the memorandum and the Minutes of Evidence are recorded. (U.K.)

Closing session

International Nuclear Information System (INIS)

2014-01-01

This part makes a summary of the different sessions and discussions of the workshop in a series of slide presentations: Summary of Opening Session; Summary of Session 1: Analysis of External Hazard Potential; Summary of session 2: Specific features of analysis and modeling of particular natural external hazards; Summary of session-3: Practices and research efforts on natural external events PSA; Summary of session 4: Modeling of NPP response to natural external events in PSA; Summary of session 5: Seismic Risk Analysis; Summary of session 6: Use of external events PSA with the focus on regulatory body role; Facilitated discussion 1 summary: Where do we stand in the analysis of external events?; Summary Facilitated Discussion 2: Findings and Good Practices for External Events Analysis

Minutes of the first, second, and third meeting of the Panel for Continuing Review and Assessment of the ORNL Hydrofracture Technique (WMPORMOD), August 6--7, 1985; November 5-6, 1985; October 6, 1986, Oak Ridge National Laboratory, Oak Ridge, Tennessee: [Quarterly progress report, October--December 22, 1986

International Nuclear Information System (INIS)

1986-01-01

The open session began at 0945 with a brief discussion by Dr. Steven H. Stow of desirable clarifications in several areas of the text appearing in chapter 9 of the Management of Radioactive Waste at the Oak Ridge National Laboratory: A Technical Review (National Academy Press, 1985). The ORNL staff points were well taken, and generally consistent with the understandings of the panel members who had drafted the report sections. Material was then presented by ORNL staff included Review of information collected since the October 1984 briefing, Plans for Deep Monitoring Well Groundwater Sampling and Monitoring, Plans for the Knox Reconnaissance Well, Waste Sampling and Analysis, Regulatory Interfaces and the Permitting Process, and Alternatives to Hydrofracture. Each of the presentations was summarized in a handout

Review panel comments on geomedia specific research

International Nuclear Information System (INIS)

Heath, C.A.

1984-01-01

This includes remarks made by three panel members concerning geomedia-specific repository relevant research. The scientific work in the materials area has progressed significantly. Investigators are showing a better understanding of the importance of groundwater compositions. Significant attention is being paid to the importance of colloids and complexing agents. Good planning seems to be in evidence in the Nevada program. Much cooperation and planning in the materials program is needed. Requirements concerning the performance of waste management systems were included. Other topics discussed at the symposium were interactive testing of waste forms, canister materials, and repository rock. Characterization of the chemical and physical environment in the near-field was considered by several speakers. These papers and discussions were part of the Seventh International Symposium on the Scientific Ban's for Nuclear Waste Management

10 CFR 1.18 - Advisory Committee on Nuclear Waste.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Advisory Committee on Nuclear Waste. 1.18 Section 1.18... Panels, Boards, and Committees § 1.18 Advisory Committee on Nuclear Waste. The Advisory Committee on Nuclear Waste (ACNW) provides advice to the Commission on all aspects of nuclear waste management, as...

76 FR 20720 - Advisory Panel for Integrative Activities; Notice of Meeting

Science.gov (United States)

2011-04-13

... Foundation announces the following meeting: Name: Committee of Visitors Panel for the Experimental Program to Stimulate Competitive Research Science and Technology Centers (STC) 1373. Dates: May 16, 2011; 6 p.m.-8 p.m... materials. Agenda May 16, 2011 6 p.m.-8 p.m. Open Session; Welcome, overview of STC program. May 17, 2011 8...

Technical considerations for evaluating substantially complete containment of high-level waste within the waste package

Energy Technology Data Exchange (ETDEWEB)

Manaktala, H.K. (Southwest Research Inst., San Antonio, TX (USA). Center for Nuclear Waste Regulatory Analyses); Interrante, C.G. (Nuclear Regulatory Commission, Washington, DC (USA). Div. of High-Level Waste Management)

1990-12-01

This report deals with technical information that is considered essential for demonstrating the ability of the high-level radioactive waste package to provide substantially complete containment'' of its contents (vitrified waste form or spent light-water reactor fuel) for a period of 300 to 1000 years in a geological repository environment. The discussion is centered around technical considerations of the repository environment, materials and fabrication processes for the waste package components, various degradation modes of the materials of construction of the waste packages, and inspection and monitoring of the waste package during the preclosure and retrievability period, which could begin up to 50 years after initiation of waste emplacement. The emphasis in this report is on metallic materials. However, brief references have been made to other materials such as ceramics, graphite, bonded ceramic-metal systems, and other types of composites. The content of this report was presented to an external peer review panel of nine members at a workshop held at the Center for Nuclear Waste Regulatory Analyses (CNWRA), Southwest Research Institute, San Antonio, Texas, April 2--4, 1990. The recommendations of the peer review panel have been incorporated in this report. There are two companion reports; the second report in the series provides state-of-the-art techniques for uncertainty evaluations. 97 refs., 1 fig.

Technical considerations for evaluating substantially complete containment of high-level waste within the waste package

International Nuclear Information System (INIS)

Manaktala, H.K.; Interrante, C.G.

1990-12-01

This report deals with technical information that is considered essential for demonstrating the ability of the high-level radioactive waste package to provide ''substantially complete containment'' of its contents (vitrified waste form or spent light-water reactor fuel) for a period of 300 to 1000 years in a geological repository environment. The discussion is centered around technical considerations of the repository environment, materials and fabrication processes for the waste package components, various degradation modes of the materials of construction of the waste packages, and inspection and monitoring of the waste package during the preclosure and retrievability period, which could begin up to 50 years after initiation of waste emplacement. The emphasis in this report is on metallic materials. However, brief references have been made to other materials such as ceramics, graphite, bonded ceramic-metal systems, and other types of composites. The content of this report was presented to an external peer review panel of nine members at a workshop held at the Center for Nuclear Waste Regulatory Analyses (CNWRA), Southwest Research Institute, San Antonio, Texas, April 2--4, 1990. The recommendations of the peer review panel have been incorporated in this report. There are two companion reports; the second report in the series provides state-of-the-art techniques for uncertainty evaluations. 97 refs., 1 fig

Tourism and solid waste generation in Europe: A panel data assessment of the Environmental Kuznets Curve.

Science.gov (United States)

Arbulú, Italo; Lozano, Javier; Rey-Maquieira, Javier

2015-12-01

The relationship between tourism growth and municipal solid waste (MSW) generation has been, until now, the subject of little research. This is puzzling since the tourism sector is an important MSW generator and, at the same time, is willing to avoid negative impacts from MSW mismanagement. This paper aims to provide tools for tourism and MSW management by assessing the effects of tourism volume, tourism quality and tourism specialization on MSW generation in the UE. This is done using the Environmental Kuznets Curve (EKC) framework. The study considers a panel data for 32 European economies in the 1997-2010 periods. Empirical results support the EKC hypothesis for MSW and shows that northern countries tend to have lower income elasticity than less developed countries; furthermore, results confirm a non-linear and significant effect of tourism arrivals, expenditure per tourist and tourism specialization on MSW generation. Copyright © 2015 Elsevier Ltd. All rights reserved.

Atomic safety and licensing board panel: Annual report, Fiscal Year 1988

International Nuclear Information System (INIS)

1989-03-01

This is the fiscal year 1988 annual report of the Atomic Safety and Licensing Board Panel. In response to further reduction in is authorized staffing level and with an eye toward the proposed full- text, electronic docket of the expected High-Level Waste Repository proceedings, the Panel stepped up efforts during fiscal year 1988 to extend the scope, depth and availability of its Computer Assistance Project (CAP) through INQUIRE. INQUIRE, and the Panel's ability to use the system to expeditiously manage and search the massive records that characterize our most complex cases, has generated great interest among legal practitioners and adjudicatory bodies throughout the United States and Canada

Radioactive Waste Disposal into the Sea

International Nuclear Information System (INIS)

1961-01-01

Preventing pollution of the seas from the discharge of radioactive wastes has been recognized as an international problem of considerable magnitude. In April 1958 the United Nations Conference on the Law of the Sea adopted a Convention on the High Seas, Article 25 of which provides that every State shall take measures to prevent pollution of the seas from the dumping of radioactive wastes, taking into account any standards and regulations which may be formulated by the competent international organizations. The Conference also adopted a resolution recommending that the IAEA pursue studies and take action to assist States in controlling the discharge of radioactive materials into the sea. Later the same year, a Panel of experts was invited by me to meet in Vienna to study the technical and scientific problems connected with radioactive waste disposal into the sea, and Mr. H. Brynielsson of Sweden was designated Chairman of the Panel. Representatives of the United Nations, the Food and Agriculture Organization of the United Nations, the World Health Organization and the United Nations Educational, Scientific and Cultural Organization participated in the work of the Panel. After a second series of meetings in 1959, the Panel completed its study, setting forth the result of its work in a report dated 6 April 1960, which has been submitted to the Agency's Scientific Advisory Committee and to Member States for their information. The Panel's report is now published in the present volume of the Agency's Safety Series in the form in which it was submitted by the Chairman of the Panel. I should like to add that the report represents the views of the experts participating in their individual capacity in the work of the Panel. It is offered as an information document and it should not be regarded as an official statement by the Agency of its views or policies in relation to the subject discussed.

Topical Session on the Decommissioning and Dismantling Safety Case

International Nuclear Information System (INIS)

2002-01-01

Set up by the Radioactive Waste Management Committee (RWMC), the WPDD brings together senior representatives of national organisations who have a broad overview of Decommissioning and Dismantling (D and D) issues through their work as regulators, implementers, R and D experts or policy makers. These include representatives from regulatory authorities, industrial decommissioners from the NEA Cooperative Programme on Exchange of Scientific and Technical Information on Nuclear Installation Decommissioning Projects (CPD), and cross-representation from the NEA Committee on Nuclear Regulatory Activities, the Committee on Radiation Protection and Public Health, and the RWMC. The EC is a member of the WPDD and the IAEA also participates. This ensures co-ordination amongst activities in these international programmes. Participation from civil society organisations is considered on a case by case basis, and has already taken place through the active involvement of the Group of Municipalities with Nuclear Installations at the first meeting of the WPDD At its second meeting, in Paris, 5-7 December 2001, the WPDD held two topical sessions on the D and D Safety Case and on the Management of Materials from D and D, respectively. This report documents the topical session on the safety case. The topical session was meant to provide an exchange of information and experience on the following issues: What topics should be included in a safety case? Of what should it consist? Is there sufficient and complete guidance nationally and internationally? How do practices differ internationally? Main boundary condition to this session was that it would deal with plants where spent fuel has been removed. Also the topical sessions was kept at a level that makes the most of the varied constituency of the WPDD. Namely, interface issues are important, and issue-identification and discussion was the immediate goal. There was less interest in examining areas where variability amongst national

Managing nuclear waste: a better idea (Excerpt of conclusions and recommendations)

International Nuclear Information System (INIS)

1984-12-01

The panel concludes that an immediate effort must be made to improve the credibility, internal flexibility and cost-effectiveness of the Office of Civilian Radioactive Waste Management (OCRWM). However, in recognition that no modification to DOE/OCRWM organization would necessarily provide adequate stability and continuity, it is our principal recommendation that investigation of the specific steps necessary to implement, for example, a dedicated federally chartered corporation (the first choice of the Panel voting on organizational tests), should be undertaken immediately so that Congress can have a precise understanding of the legislative changes required to bring about such an organization. The main thrust of the Panel study has dealt with the structure and capabilities of various organizational alternatives for managing the high-level radioactive waste management program. The Panel also gave consideration to the financing processes of the Nuclear Waste Policy Act (NWPA), and to certain financing alternatives which might be substituted for the existing mechanisms. In doing so, the Panel encountered an array of financial uncertainties which confront the radioactive waste management program as it moves forward over the next two decades. At this juncture, it is extremely difficult to predict how future events, programmatic developments, and economic influences will affect the financing structure and cost level over the term of the program. It is the Panel's conclusion that the financing mechanism provided by Congress under the Nuclear Waste Policy Act appears to be fair, amenable to administrative implementation and cost controls, and sufficiently flexible to accommodate the full-recovery requirement of the legislation. Under NWPA, utilities are assessed a fee of 1 mill per kilowatthour of nuclear-generated electricity, plus a one-time fee for spent fuel accumulated prior to April 7, 1983

Utilization of waste tire rubber in manufacture of oriented strandboard.

Science.gov (United States)

Ayrilmis, Nadir; Buyuksari, Umit; Avci, Erkan

2009-09-01

Some physical and mechanical properties of oriented strandboards (OSBs) containing waste tire rubber at various addition levels based on the oven-dry strand weight, using the same method as that used in the manufacture of OSB. Two resin types, phenol-formaldehyde (PF) and polyisocyanate, were used in the experiments. The manufacturing parameters were: a specific gravity of 0.65 and waste tire rubber content (10/90, 20/80 and 30/70 by wt.% of waste tire rubber/wood strand). Average internal bond values of PF-bonded OSB panels with rubber chips were between 17.6% and 48.5% lower than the average of the control samples while polyisocyanate bonded OSBs were 16.5-50.6%. However, water resistance and mechanical properties of OSBs made using polyisocyanate resin were found to comply with general-purpose OSB minimum property requirements of EN 300 Type 1 (1997) values for use in dry conditions at the lowest tire rubber loading level (10%) based on the oven-dry panel weight. The tire rubber improved water resistance of the OSB panel due to its almost hydrophobic property. Based on the findings obtained from this study, we concluded that waste tire rubber could be used for general-purpose OSB manufacturing up to 10% ratio based on the oven-dry panel weight.

ECED 2013: Eastern and Central Europe Decommissioning. International Conference on Decommissioning of Nuclear Facilities. Conference Guide and Book of Abstracts

International Nuclear Information System (INIS)

2013-01-01

The Conference included the following sessions: (I) Opening session (2 contributions); (II) Managerial and Funding Aspects of Decommissioning (5 contributions); (III) Technical Aspects of Decommissioning I (6 contributions); (IV) Experience with Present Decommissioning Projects (4 contributions); (V) Poster Session (14 contributions); (VI) Eastern and Central Europe Decommissioning - Panel Discussion; (VII) Release of Materials, Waste Management and Spent Fuel Management (6 contributions); (VIII) Technical Aspects of Decommissioning II (5 contributions).

Geochemistry Review Panel report on the SRP geochemistry program and draft geochemistry summary program plan (May, 1986) and discussion of panel recommendations

International Nuclear Information System (INIS)

1986-12-01

The Geochemistry Review Panel (GRP) was established by the Salt Repository Project Office (SRPO) to help evaluate geochemistry-related issues in the US Department of Energy's nuclear waste repository program. The May 1986 meeting of the GRP reviewed the Salt Repository Program (SRP) geochemistry program developed by the Office of Nuclear Waste Isolation (ONWI). This program is described in the Draft Geochemistry Plan of April 9, 1986. This report documents the GRP's comments and recommendations on this subject and the ONWI responses to the specific points raised by the GRP

Low-level waste forum meeting reports

Energy Technology Data Exchange (ETDEWEB)

NONE

1990-12-31

This paper provides highlights from the October 1990 meeting of the Low Level Radioactive Waste Forum. Topics of discussion included: a special session on liability and financial assurance needs; proposal to dispose of mixed waste at federal facilities; state plans for interim storage; and hazardous materials legislation.

GLOBAL 2009: Closing speech - the bulk of technical sessions

International Nuclear Information System (INIS)

Greneche, D.

2009-01-01

The author proposes an overview of the content of the hundred technical sessions of the GLOBAL 2009 conference. Thus, he addresses the twelve main issues: the upstream part of the fuel cycle, the present status of used fuel recycling, the waste management strategies and technologies, the transportation and storage of used fuels and radioactive materials, the definitive storage of nuclear wastes, the new technologies for fuel recycling, advanced designs of reactor cores and fuel management, long life radionuclide transmutation systems, the non proliferation issue, material management and options for sustainable fuel cycles, dismantling, decommissioning and resulting material management, transverse topics (technical-economic studies, nuclear energy applications other than electricity production, challenges of sustainable development of nuclear energy, advanced researches)

Proceedings of the Topical Sessions on Media Relations held in June 2004 and 2005

International Nuclear Information System (INIS)

2006-01-01

An effective media strategy, including timely interaction with them is an indispensable tool for organisations or institutions involved in radioactive waste management. With this in mind, the Forum on Stakeholder Confidence (FSC) set up a Group on Communication and Outreach with a twofold objective: to assist FSC members in communicating with the radioactive waste management community, to assist FSC members in reaching a broader public. As part of this assignment, the Group organised two Topical Sessions on media strategy, in conjunction with the 2004 and 2005 FSC meetings. The main objective was to learn about the functioning of the media organisations, their structures and needs, with speakers chosen to represent the range of such media, as well as different countries and varying radioactive waste situations that may serve as illustrative examples, given the vast differences that may prevail between local, national, and international radioactive waste management situations and their treatment by the media. The sessions were attended by representatives of policy makers, regulators and implementers from the FSC organisations. The presentations and discussions illustrated current media strategies, best practices, successes and failures and lessons learn. These proceedings consist of a summary of the main points made by each speaker as well a collation of their papers

Nuclear innovation through collaboration. 35th Annual CNS conference and 39th CNS/CNA student conference

International Nuclear Information System (INIS)

2015-01-01

The Canadian Nuclear Society (CNS) held its 35th Annual Conference in Saint John, New Brunswick, Canada on May 31 to June 3, 2015, combined with the 39th Annual CNS/CNA Student Conference. With the theme of the conference, 'Nuclear Innovation through Collaboration', more than 425 delegates, exhibitors and students were in attendance. The conference commenced with two strong plenary sessions on Utility Collaborations to Improve Lifetime Performance; and, Performance Improvement Programs: Goals and Experience. The second day consisted of the panel discussions on International Developments in Used Nuclear Fuel Repository Programs, and two plenary sessions on: Enterprise Risk Management; and, Vendor Role in a Continuously Improving Industry. The third day contained a number of interesting features, including plenary sessions on Waste Management and Decommissioning; Developing Technologies and Resources, and a panel discussion on the Transportation of Used Nuclear Fuel. All three days of the conference also contained parallel sessions with over 100 technical papers presented at the main and student sessions. The technical session titles were: Refurbishment and Life Extension; Thermalhydraulics; Nuclear Materials; WMD - Radiation Monitoring; Safety and Licensing; Communication; Safety and Licensing; Instrumentation and Control; Advanced Reactor Designs; WMD - Deep Geological Repository Packaging; Reactor Physics; Chemistry and Materials; Advanced Fuel Cycles; Waste Management and Decommissioning; and, Medical Physics and Radiation Biology.

Radiation effects in glass waste forms for high-level waste and plutonium disposal

International Nuclear Information System (INIS)

Weber, W.J.; Ewing, R.C.

1997-01-01

A key challenge in the permanent disposal of high-level waste (HLW), plutonium residues/scraps, and excess weapons plutonium in glass waste forms is the development of predictive models of long-term performance that are based on a sound scientific understanding of relevant phenomena. Radiation effects from β-decay and α-decay can impact the performance of glasses for HLW and Pu disposition through the interactions of the α-particles, β-particles, recoil nuclei, and γ-rays with the atoms in the glass. Recently, a scientific panel convened under the auspices of the DOE Council on Materials Science to assess the current state of understanding, identify important scientific issues, and recommend directions for research in the area of radiation effects in glasses for HLW and Pu disposition. The overall finding of the panel was that there is a critical lack of systematic understanding on radiation effects in glasses at the atomic, microscopic, and macroscopic levels. The current state of understanding on radiation effects in glass waste forms and critical scientific issues are presented

The volume reduction of low-activity solid wastes. Report of a panel

International Nuclear Information System (INIS)

Pradel, J.; Parsons, P.J.; Malasek, E.

1970-01-01

The accumulation of large volumes of low-level solid radioactive wastes is a matter of concern to waste management authorities, particularly when the wastes are produced close to urban areas. Some of the older and larger nuclear establishments are situated in relatively sparsely populated regions where the problem of dealing with such wastes can even be solved on-site, usually by burial, with little or no pre-treatment. This is the most economical solution. Now, however, increasing amounts of wastes are being produced in more populated areas, and local storage can constitute a hindrance to urban development. It is therefore often necessary to transport the wastes elsewhere; to effect this economically the volume and, if possible, the weight must be reduced, so that the wastes can be transported in regulation packages. The present report is concerned with the methods by which this can be achieved for a large variety of solid materials that accrue as radioactive wastes. It has been compiled largely from information and experience gained at major establishments dealing with large quantities of waste, but articular attention has been paid to the interests of the waste management specialists working at smaller nuclear centres. The manual supplements the guides which have already appeared in IAEA publications series and have dealt with some specific aspect of waste management and, like them, it is oriented in the operational rather than the research direction

Proceedings of the tenth annual DOE low-level waste management conference: Session 5: Waste characterization and quality assurance

International Nuclear Information System (INIS)

1988-12-01

This document contains six papers on various aspects of low-level radioactive waste management. Topics include quality assurance programs; source terms; waste characterization programs; and DOE's information network modifications. Individual papers were processed separately for the data base

Coupling effect of waste automotive engine oil in the preparation of wood reinforced LDPE plastic composites for panels

Directory of Open Access Journals (Sweden)

Maame Adwoa Bentumah Animpong

2017-12-01

Full Text Available We demonstrated the formulation of wood plastic composite (WPC materials with flexural strength of 13.69 ± 0.09 MPa for applications in outdoor fencing using municipal waste precursors like low density polyethylene (LDPE plastics (54.0 wt. %, sawn wood dust with particle size between 64 and 500 μm derived from variable hardwood species (36.0 wt. % and used automotive engine oil (10 wt. %. The WPC panels were prepared by pre-compounding, extruding at a screw auger torque of 79.8 Nm and pressing through a rectangular mould of dimension 132 mm × 37 mm × 5 mm at temperature 150 °C. The efficacy of black waste oil, as a coupling agent, was demonstrated by the absence of voids and pull-outs on microscopic examination using scanning electron microscopy. No hazardous substances were exhaled during thermo-gravimetric mass spectrometry analysis. The percentage crystallinity of the LDPE in the as-prepared material determined by differential scanning calorimetry was 11.3%. Keywords: Wood plastic composites, Low density polyethylene, Wood dust, Physical, Thermal and mechanical properties

Managing nuclear waste: a better idea

International Nuclear Information System (INIS)

1984-12-01

This report presents the findings and recommendations of the Advisory Panel with regard to alternative approaches to financing and managing the construction and operation of civilian radioactive waste management facilities. Ten organizational alternatives are considered and four of them are focussed on. These four are: present DOE waste management structure; alternative governmental approach; public/private entity; and private corporation. Advantages and disadvantages of each alternative are covered. The preferred alternative is the Federal Corporation for Waste Management (FEDCORP)

Proceedings of the 6th Korea-China Joint workshop on nuclear waste management

International Nuclear Information System (INIS)

2005-11-01

This proceedings contains articles of 6th Korea-China Joint workshop on nuclear waste management. It was held on November 16-17, 2005 in Kyeongju, Korea. This proceedings is comprised of 3 sessions. The main subject titles of session are as follows: Nuclear fuel cycle, Radioactive waste treatment, Radwaste disposal and decontamination and decommissioning. (Yi, J. H.)

Radioactive waste isolation in salt: peer review of Westinghouse Electric Corporation's report on reference conceptual designs for a repository waste package

International Nuclear Information System (INIS)

Rote, D.M.; Hull, A.B.; Was, G.S.; Macdonald, D.D.; Wilde, B.E.; Russell, J.E.; Kruger, J.; Harrison, W.; Hambley, D.F.

1985-10-01

This report documents the findings of the peer panel constituted by Argonne National Laboratory to review Region A of Westinghouse Electric Corporation's report entitled Waste Package Reference Conceptual Designs for a Repository in Salt. The panel determined that the reviewed report does not provide reasonable assurance that US Nuclear Regulatory Commission (NRC) requirements for waste packages will be met by the proposed design. It also found that it is premature to call the design a ''reference design,'' or even a ''reference conceptual design.'' This review report provides guidance for the preparation of a more acceptable design document

Integrated Thermal Treatment Systems study: US Department of Energy Internal Review Panel report

International Nuclear Information System (INIS)

Cudahy, J.; Escarda, T.; Gimpel, R.

1995-04-01

The U.S. Department of Energy's (DOE) Office of Technology Development (OTD) commissioned two studies to uniformly evaluate nineteen thermal treatment technologies. These studies were called the Integrated Thermal Treatment System (ITTS) Phase I and Phase II. With the advice and guidance of the DOE Office of Environmental Management's (EM's) Mixed Waste Focus Group, OTD formed an ITTS Internal Review Panel, composed of scientists and engineers from throughout the DOE complex, the U.S. Environmental Protection Agency (EPA), the California EPA, and private experts. The Panel met from November 15-18, 1994, to review and comment on the ITTS studies, to make recommendations on the most promising thermal treatment systems for DOE mixed low level wastes (MLLW), and to make recommendations on research and development necessary to prove the performance of the technologies on MLLW

NEDO Forum 2001. Session on advanced power generation and storage technology development; NEDO Forum 2001. Shindenryoku gijutsu kaihatsu session

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-09-20

The presentations made at the above-named session and remarks made at the panel discussion of the NEDO (New Energy and Industrial Technology Development Organization) forum held in Tokyo on September 20, 2001, are collected in this report. Predicted by Deputy Chairman Tanaka of International Superconductivity Technology Center in his lecture entitled 'Energy problem in IT (information technology) oriented society' were that possibilities were high that power consumption would rapidly increase in line with the progress of broad band and wireless, that energy conservation and environmental technologies should be developed urgently, and that superconductivity technology would assume an important role. Discussed at the panel on 'Prospect of distributed power sources in power systems' were 'Power utilization by information communication in IT-oriented days and needs for development,' 'Energy utilization involving buildings and needs for development,' 'Tasks to discharge in cogeneration technology development and coordination with power systems,' 'Technical problems involving interconnection of distributed power sources and needs for development,' 'Present state of distributed power sources and needs for development,' and 'From Fuel and Storage Technology Development Department to Advanced Power Generation and Storage Technology Development Department.' (NEDO)

Geotechnical assessment and instrumentation needs for nuclear waste isolation in crystalline and argillaceous rocks

International Nuclear Information System (INIS)

1979-01-01

To evaluate the state-of-the-art, research needs, and research priorities related to waste disposal in largely impermeable rocks, scientists and engineers working on geologic aspects of nuclear waste disposal were brought together. This report and recommendations are the proceedings from that symposium. Three panels were organized on rock properties, fracture hydrology, and geochemistry. Panel discussions and recommendations are presented

Implementation of a panel of service users for the evaluation of mental health outpatient services.

Science.gov (United States)

Perreault, Michel; Renaud, Jeff; Bourassa, Francine; Beauchesne, Louise; Mpiana, André; Bernier, Sylvain; Milton, Diana

2010-12-01

The purpose of this study is to describe the experience of a standing panel of psychiatric outpatients over a period of five years. The procedure is used as a complementary method to assess client satisfaction regarding services provided by a Montreal psychiatric institute. During this period, 13 meetings were held, involving a total of 22 patients as active members of the panel. These sessions allowed 11 decision makers of the institute to consult the panel regarding various topics such as service organization, quality of services, and client information. In a context of internal evaluation, by giving direct and rapid access to service users' perspectives on key issues regarding service provision, the panel appeared to be a practical procedure for use in complement with other satisfaction assessment methods. Unplanned effects included the recruitment of participants as patient representatives on different hospital committees and associations, and as presenters in conferences and congresses.

National Waste Terminal Storage Program information meeting, December 7-8, 1976

International Nuclear Information System (INIS)

1976-01-01

Volume II of the report comprises copies of the slides from the talks presented at the second session of the National Waste Terminal Storage Program information meeting. This session was devoted to geologic studies

AREVA Technical Days (ATD) session 2: operations of the back-end of the nuclear fuel cycle; AREVA Technical Days (ATD) session 2: les activites du pole Aval du cycle du combustible nucleaire

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This second session deals with the reprocessing business, back-end financing mechanisms, technology transfer, environmental management, risk management programs, research and development contribution to waste volume reductions, issues and outlook of nuclear wastes, comparison of the open and closed cycles. (A.L.B.)

Round table discussion during session 2

International Nuclear Information System (INIS)

Mays, C.

2004-01-01

The round table discussions of the second session of the FSC Belgium Workshop addressed the following questions: - Do local stakeholders have, internally or externally, all the expertise they need in order to address the issues raised by radioactive waste management projects? - Do institutional stakeholders have all the expertise they need to take local impacts into account? - What kinds of expert input are sought and attained by the different stakeholders? - Were any formal methods used to aid local partnerships perform technology assessments? Or other types of assessment? - How to maintain the knowledge and expertise achieved by the stakeholders? Discussion took place after the plenary presentations, at tables grouping Belgian stakeholders and FSC delegates. As in Session I, most of the round table discussion focussed specifically on the experience of the local partnerships. Many insights were shared about the nature and role of expertise in complex decision making. They are summarised below, on the basis of the feedback provided to the plenary by each round table. Some of these insights can be generalised to other contexts. All in all, a profile emerged of the local partnerships as a unique and effective tool to deal with knowledge issues in managing risk. (author)

Nuclear fuel waste management and disposal concept: Report. Federal environmental assessment review process

International Nuclear Information System (INIS)

1998-01-01

The Canadian concept for disposing CANDU reactor waste or high-level nuclear wastes from reprocessing involves underground disposal in sealed containers emplaced in buffer-filled and sealed vaults 500--1,000 meters below ground, in plutonic rock of the Canadian Shield. This document presents the report of a panel whose mandate was to review this concept (rather than a specific disposal project at a specific site) along with a broad range of related policy issues, and to conduct that review in five provinces (including reviews with First Nations groups). It first outlines the review process and then describes the nature of the problem of nuclear waste management. It then presents an overview of the concept being reviewed, its implementation stages, performance assessment analyses performed on the concept, and implications of a facility based on that concept (health, environmental, social, transportation, economic). The fourth section examines the criteria by which the safety and acceptability of the concept should be evaluated. This is followed by a safety and acceptability evaluation from both technical and social perspectives. Section six proposes future steps for building and determining acceptability of the concept, including an Aboriginal participation process, creation of a Nuclear Fuel Waste Management Agency, and a public participation process. The final section discusses some issues outside the panel's mandate, such as energy policy and renewable energy sources. Appendices include a chronology of panel activities, a review of radiation hazards, comparison between nuclear waste management and the management of other wastes, a review of other countries' approaches to long-term management of nuclear fuel wastes, and details of a siting process proposed by the panel

Performance Study of an aSi Flat Panel Detector for Fast Neutron Imaging of Nuclear Waste

Energy Technology Data Exchange (ETDEWEB)

Schumann, M.; Mauerhofer, E. [Institute of Energy and Climate Research - Nuclear Waste Management and Reactor Safety, Forschungszentrum Juelich GmbH, 52425 Juelich (Germany); Engels, R.; Kemmerling, G. [Central Institute for Engineering, Electronics and Analytics - Electronic Systems, Forschungszentrum Juelich GmbH, 52425 Juelich (Germany); Frank, M. [MATHCCES - Department of Mathematics, RWTH Aachen University, 52062 Aachen (Germany); Havenith, A.; Kettler, J.; Klapdor-Kleingrothaus, T. [Institute of Nuclear Engineering and Technology Transfer, RWTH Aachen University, 52062 Aachen (Germany); Schitthelm, O. [Corporate Technology, Siemens AG, 91058 Erlangen (Germany)

2015-07-01

Radioactive waste must be characterized to check its conformance for intermediate storage and final disposal according to national regulations. For the determination of radio-toxic and chemo-toxic contents of radioactive waste packages non-destructive analytical techniques are preferentially used. Fast neutron imaging is a promising technique to assay large and dense items providing, in complementarity to photon imaging, additional information on the presence of structures in radioactive waste packages. Therefore the feasibility of a compact Neutron Imaging System for Radioactive waste Analysis (NISRA) using 14 MeV neutrons is studied in a cooperation framework of Forschungszentrum Juelich GmbH, RWTH Aachen University and Siemens AG. However due to the low neutron emission of neutron generators in comparison to research reactors the challenging task resides in the development of an imaging detector with a high efficiency, a low sensitivity to gamma radiation and a resolution sufficient for the purpose. The setup is composed of a commercial D-T neutron generator (Genie16GT, Sodern) with a surrounding shielding made of polyethylene, which acts as a collimator and an amorphous silicon flat panel detector (aSi, 40 x 40 cm{sup 2}, XRD-1642, Perkin Elmer). Neutron detection is achieved using a general propose plastic scintillator (EJ-260, Eljen Technology) linked to the detector. The thermal noise of the photodiodes is reduced by employing an entrance window made of aluminium. Optimal gain and integration time for data acquisition are set by measuring the response of the detector to the radiation of a 500 MBq {sup 241}Am-source. Detector performance was studied by recording neutron radiography images of materials with various, but well known, chemical compositions, densities and dimensions (Al, C, Fe, Pb, W, concrete, polyethylene, 5 x 8 x 10 cm{sup 3}). To simulate gamma-ray emitting waste radiographs in presence of a gamma-ray sources ({sup 60}Co, {sup 137}Cs, {sup 241

Session-RPE for quantifying the load of different youth basketball training sessions.

Science.gov (United States)

Lupo, C; Tessitore, A; Gasperi, L; Gomez, Mar

2017-03-01

The aim of the study was to evaluate youth basketball training, verifying the reliability of the session-RPE method in relation to session duration (session) categories. Six male youth basketball players (age, 16.5±0.5 years; height, 195.5±6.75 cm; body mass, 93.9±10.9 kg; and body mass index, 23.6±2.8 kg.m -2 ) were monitored (HR, type and duration of workouts) during 15 (66 individual) training sessions (80±26 minutes). Edwards' HR method was used as a reference measure of internal training load (ITL); the CR-10 RPE scale was administered 30 minutes after the end of each session. The results obtained showed that all comparisons between different session durations and workout portions revealed effects in term of Edwards' ITLs except for warm-up portions. Moderate to strong relationships between Edwards' and session- RPE methods emerged for all sessions (r = .85, P sessions (r range = .79 - .95, P session durations (session-RPE to monitor the ITL, regardless of session durations and workout portions.

Alternative Shear Panel Configurations for Light Wood Construction. Development, Seismic Performance, and Design Guidance

Science.gov (United States)

Wilcoski, James; Fischer, Chad; Allison, Tim; Malach, Kelly Jo

2002-04-01

Shear panels are used in light wood construction to resist lateral loads resulting from earthquakes or strong winds. These panels are typically made of wooden sheathing nailed to building frame members, but this standard panel design interferes with the installation of sheet insulation. A non-insulated shear panel conducts heat between the building interior and exterior wasting considerable amounts of energy. Several alternative shear panel designs were developed to avoid this insulation-mounting problem and sample panels were tested according to standard cyclic test protocols. One of the alternative designs consisted of diagonal steel straps nailed directly to the structural framing. Several others consisted of sheathing nailed to 2 x 4 framing then set into a larger 2 x 6 structural frame in such a way that no sheathing protruded beyond the edge of the 2 x 6 members. Also samples of industry-standard shear panels were constructed and tested in order to establish a performance baseline. Analytical models were developed to size test panels and predict panel behavior. A procedure was developed for establishing design capacities based on both test data and established baseline panel design capacity. The behavior of each panel configuration is documented and recommended design capacities are presented.

Performance assessment review guide for DOE low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Dodge, R.L.; Hansen, W.R.; Kennedy, W.E. Jr.; Layton, D.W.; Lee, D.W.; Maheras, S.T.; Neuder, S.M.; Wilhite, E.L.; Curl, R.U.; Grahn, K.F.; Heath, B.A.; Turner, K.H.

1991-10-01

This report was prepared under the direction of the Performance Assessment Peer Review Panel. The intent is to help Department of Energy sites prepare performance assessments that meet the Panel's expectations in terms of detail, quality, content, and consistency. Information on the Panel review process and philosophy are provided, as well as important technical issues that will be focused on during a review. This guidance is not intended to provide a detailed review plan as in NUREG-1200, Standard Review Plan for Review of a License Application for a Low-Level Radioactive Waste Disposal Facility (January 1988). The focus and intent of the Panel's reviews differ significantly from a regulatory review. The review of a performance assessment by the Panel uses the collective professional judgment of the members to ascertain that the approach taken the methodology used, the assumptions made, etc., are technically sound and adequately justified. The results of the Panel's review will be used by Department of Energy Headquarters in determining compliance with the requirements of DOE Order 5820.2A, ''Radioactive Waste Management.''

Clays in natural and engineered barriers for radioactive waste confinement

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

Andra organised an International Symposium on the use of Natural and Engineered Clay-based Barriers for the Containment of Radioactive Waste hold at the Congress Centre of Tours, France, in March 2005. The symposium provided an opportunity to take stock of the potential properties of the clay-based materials present in engineered or natural barriers in order to meet the containment specifications of a deep geological repository for radioactive waste. It was intended for specialists working in the various disciplines involved with clays and clay based minerals, as well as scientists from agencies and organisations dealing with investigations on the disposal of high-level and long-lived radioactive waste. The themes of the Symposium included geology, geochemistry, transfers of materials, alteration processes, geomechanics, as well as the recent developments regarding the characterisation of clays, as well as experiments in surface and underground laboratories. The symposium consisted of plenary sessions, parallel specialized sessions and poster sessions. (author)

Nuclear innovation through collaboration. 35th Annual CNS conference and 39th CNS/CNA student conference

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-07-01

The Canadian Nuclear Society (CNS) held its 35th Annual Conference in Saint John, New Brunswick, Canada on May 31 to June 3, 2015, combined with the 39th Annual CNS/CNA Student Conference. With the theme of the conference, 'Nuclear Innovation through Collaboration', more than 425 delegates, exhibitors and students were in attendance. The conference commenced with two strong plenary sessions on Utility Collaborations to Improve Lifetime Performance; and, Performance Improvement Programs: Goals and Experience. The second day consisted of the panel discussions on International Developments in Used Nuclear Fuel Repository Programs, and two plenary sessions on: Enterprise Risk Management; and, Vendor Role in a Continuously Improving Industry. The third day contained a number of interesting features, including plenary sessions on Waste Management and Decommissioning; Developing Technologies and Resources, and a panel discussion on the Transportation of Used Nuclear Fuel. All three days of the conference also contained parallel sessions with over 100 technical papers presented at the main and student sessions. The technical session titles were: Refurbishment and Life Extension; Thermalhydraulics; Nuclear Materials; WMD - Radiation Monitoring; Safety and Licensing; Communication; Safety and Licensing; Instrumentation and Control; Advanced Reactor Designs; WMD - Deep Geological Repository Packaging; Reactor Physics; Chemistry and Materials; Advanced Fuel Cycles; Waste Management and Decommissioning; and, Medical Physics and Radiation Biology.

MO-E-BRB-00: PANEL DISCUSSION: SBRT/SRS Case Studies - Lung

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-06-15

In this interactive session, lung SBRT patient cases will be presented to highlight real-world considerations for ensuring safe and accurate treatment delivery. An expert panel of speakers will discuss challenges specific to lung SBRT including patient selection, patient immobilization techniques, 4D CT simulation and respiratory motion management, target delineation for treatment planning, online treatment alignment, and established prescription regimens and OAR dose limits. Practical examples of cases, including the patient flow thought the clinical process are presented and audience participation will be encouraged. This panel session is designed to provide case demonstration and review for lung SBRT in terms of (1) clinical appropriateness in patient selection, (2) strategies for simulation, including 4D and respiratory motion management, and (3) applying multi imaging modality (4D CT imaging, MRI, PET) for tumor volume delineation and motion extent, and (4) image guidance in treatment delivery. Learning Objectives: Understand the established requirements for patient selection in lung SBRT Become familiar with the various immobilization strategies for lung SBRT, including technology for respiratory motion management Understand the benefits and pitfalls of applying multi imaging modality (4D CT imaging, MRI, PET) for tumor volume delineation and motion extent determination for lung SBRT Understand established prescription regimes and OAR dose limits.

Mathematics Intensive Summer Session (MISS). Final technical report

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-11-01

This final technical report appears in two parts: the report for the 1995 summer MISS program and the report for the 1996 summer MISS program. Copies of the US Department of Energy Pre-Freshman Enrichment Program 1995 Entry Form and 1996 Entry Form completed by all participants were sent to the Oak Ridge Institute for Science and Education in the fall of 1995 and 1996 respectively. Those forms are on file should they be needed. Attached also is a copy of the Summary of ideas for panel discussions, problem-solving sessions, or small group discussions presented at the Department of Energy Oak Ridge Institute for Science and Education Pre-Freshman Enrichment Program Project Directors Meeting held in San Antonio, TX, November 12--14, 1995.

Promoting business and entrepreneurial awareness in health care professionals: lessons from venture capital panels at medicine 2.0 conferences.

Science.gov (United States)

Miron-Shatz, Talya; Shatz, Itamar; Becker, Stefan; Patel, Jigar; Eysenbach, Gunther

2014-08-06

There are few mechanisms that bring the academic and business worlds together in a way that would maximize the success of health technology (health tech) start-ups by increasing researchers' knowledge about how to operate in the business world. Existing solutions (eg, technology transfer offices and dual degree MD/MBA programs) are often unavailable to researchers from outside the institution or to those who have already completed their primary education, such as practicing physicians. This paper explores current solutions and offers a partial solution: include venture capital (VC) panels in medical conferences. These VC panels educate academics on 2 important and interconnected issues: how to "pitch" their ideas in the business world and what to consider when creating a company. In these sessions, academia-based start-up companies present their ideas before a VC panel composed of professional investors and receive feedback on their idea, business plan, and presentation techniques. Recent panel recommendations from Medicine 2.0 conferences fell into 7 categories: (1) the product, service, or idea you are developing into a company, (2) determine market forces and identify the target audience, (3) describe your competitive advantage, (4) the business plan, (5) current and future resources and capabilities, (6) legal aspects, and (7) general advice on the art of pitching. The academic and business literature validates many of these recommendations suggesting that VC panels may be a viable and cost-effective introduction to business and entrepreneurial education for physicians and other health care professionals. Panels benefit not only the presenting companies, but also the physicians, psychologists, and other health care professionals attending the session. Incorporating VC panels into academic conferences might also illuminate the need for incorporating relevant business training within academia.

Promoting Business and Entrepreneurial Awareness in Health Care Professionals: Lessons From Venture Capital Panels at Medicine 2.0 Conferences

Science.gov (United States)

Patel, Jigar; Eysenbach, Gunther

2014-01-01

There are few mechanisms that bring the academic and business worlds together in a way that would maximize the success of health technology (health tech) start-ups by increasing researchers’ knowledge about how to operate in the business world. Existing solutions (eg, technology transfer offices and dual degree MD/MBA programs) are often unavailable to researchers from outside the institution or to those who have already completed their primary education, such as practicing physicians. This paper explores current solutions and offers a partial solution: include venture capital (VC) panels in medical conferences. These VC panels educate academics on 2 important and interconnected issues: how to “pitch” their ideas in the business world and what to consider when creating a company. In these sessions, academia-based start-up companies present their ideas before a VC panel composed of professional investors and receive feedback on their idea, business plan, and presentation techniques. Recent panel recommendations from Medicine 2.0 conferences fell into 7 categories: (1) the product, service, or idea you are developing into a company, (2) determine market forces and identify the target audience, (3) describe your competitive advantage, (4) the business plan, (5) current and future resources and capabilities, (6) legal aspects, and (7) general advice on the art of pitching. The academic and business literature validates many of these recommendations suggesting that VC panels may be a viable and cost-effective introduction to business and entrepreneurial education for physicians and other health care professionals. Panels benefit not only the presenting companies, but also the physicians, psychologists, and other health care professionals attending the session. Incorporating VC panels into academic conferences might also illuminate the need for incorporating relevant business training within academia. PMID:25100579

Expert panel on hydrogeology; report to AECL Research (1992)

International Nuclear Information System (INIS)

Domenico, P.A.; Grisak, G.E.; Schwartz, F.W.

1995-02-01

In 1992 AECL Research convened a panel of external hydrogeological experts consisting of P.A. Domenico, G.E. Grisak, and F.W. Schwartz, to review AECL's proposed approach to siting a geological repository in the rocks of the Canadian Shield for the safe disposal of Canada's nuclear fuel wastes. In particular the panel was asked to provide its opinion on 1) the soundness of the technical approach developed to characterize the groundwater flow systems for the purpose of selecting a location for a disposal vault, 2) the validity and effectiveness of the geological case study used to demonstrate the performance assessment methodology based on the hydrogeological conditions observed at the Whiteshell Research Area, and 3) the adequacy of the hydrogeological information that AECL proposes to use in its Environmental Impact Statement (EIS) of the disposal concept. This report presents the findings, conclusions and recommendations of the hydrogeology review panel. The report was submitted to AECL Research in 1992 December. (author). 24 refs., 2 tabs., 4 figs

Post-Session Authentication

DEFF Research Database (Denmark)

Ahmed, Naveed; Jensen, Christian D.

2012-01-01

Entity authentication provides confidence in the claimed identity of a peer entity, but the manner in which this goal is achieved results in different types of authentication. An important factor in this regard is the order between authentication and the execution of the associated session....... In this paper, we consider the case of post-session authentication, where parties authenticate each other at the end of their interactive session. This use of authentication is different from session-less authentication (e.g., in RFID) and pre-session authentication (e.g., for access control.) Post......-session authentication, although a new term, is not a new concept; it is the basis of at least a few practical schemes. We, for the first time, systematically study it and present the underlying authentication model. Further, we show that an important class of problems is solvable using post-session authentication...

Building the institutional capacity for managing commercial high-level radioactive waste

International Nuclear Information System (INIS)

1982-05-01

This report presents the findings and recommendations of an Academy panel formed to look into the major institutional issues associated with the commercial radioactive waste management program. The two major areas examined by the Panel were: (1) intergovernmental relationships, how federal, state, local and Indian tribal council governments relate to each other in the planning and implementation of a waste management program; and (2) interagency relationships, how the federal agencies with major responsibilities in this public policy arena interact with each other. The objective of the study was to apply the perspectives of public administration to a difficult and controversial question - how to devise and execute an effective waste management program workable within the constraints of the federal system

Topical session proceedings of the 4. IGSC meeting on: the potential impacts on repository safety from potential partitioning and transmutation programme

International Nuclear Information System (INIS)

Wollrath, Juergen; Voinis, Sylvie; Hadermann, Joerg; Van Luik, Abraham E.

2003-01-01

/or vitrified high-level waste. Thus, a Topical Session that focused on 'The potential impacts on repository safety from a potential P and T programme' was organised in the framework of the 4. plenary meeting of the IGSC (Integration Group for the Safety Case). This Topical Session sought to create IGSC awareness regarding potential issues involving P and T, other potential fuel cycle changes, and a repository safety case. The Topical Session focused on the recent scientific developments in potential national P and T strategies, and on international research on P and T and the potential impacts of P and T deployment on repository long-term performance and safety. 53 participants represented several national waste management organisations, regulatory authorities, and research institutions from 16 OECD member countries, IAEA and EC. The Topical Session was split in three parts: - Part A was related to national P and T strategies (e.g. which radionuclide are affected by P and T; implication on step-wise decision-making, what are the changes in potential doses...) - Part B consisted of EC and NEA/NDC presentations on the technical bases of P and T; (e.g. what is the resulting inventory of P and T, what is the schedule regarding developing and deploying P and T processes?) and, based on background provided by the previous presentations, - Part C was aimed at discussing the impact of P and T strategies on IGSC-related issues, and agreeing to key messages to be delivered to the RWMC. The current synthesis presented in part A of this document is aimed at briefly reflecting the material presented at the Topical Session and providing a short overview of the main outcomes of its discussions. The written contributions are compiled as-received without further elaboration, either as presentations or papers, in part B of the document. Part C gives the list of participants at this Topical Session

Proceedings of the topical session on stakeholder involvement in decommissioning projects

International Nuclear Information System (INIS)

Santiago, Juan Luis; Chandler, Steve; Metcalfe, Doug; Le Bars, Yves

2006-01-01

Set up by the Radioactive Waste Management Committee (RWMC), the WPDD brings together senior representatives of national organisations who have a broad overview of Decommissioning and Dismantling (D and D) issues through their work as regulators, implementers, R and D experts or policy makers. These include representatives from regulatory authorities, industrial decommissioners from the NEA Co-operative Programme on Exchange of Scientific and Technical Information on Nuclear Installation Decommissioning Projects (CPD), and cross-representation from the other NEA Committees. The EC is a member of the WPDD and the IAEA is participating as an observer. This broad participation provides good possibilities for the co-ordination efforts amongst activities in the international programmes. At its sixth meeting, in Paris, 14-16 November 2005, the WPDD held a topical session on the 'Stakeholder Involvement in Decommissioning Projects'. The topical session was jointly planned and run with members of the NEA Forum on Stakeholder Confidence (FSC). This report documents the topical session. The main text summarises the lessons learnt and includes the rapporteurs reports. Appendix 1 and 2 provide the agenda of the topical session and all contributed papers respectively. The Topical session also provided a stimuli to review all the contributions in the area of stakeholder involvement that the WPDD has received since its inception. A list of references is provided in Appendix 3. The topical session was meant to provide an exchange of information and experience on the following issues: - Views from Stakeholders Regarding Stakeholder Involvement and Their Own Role. - Case Studies on Stakeholders Confidence. At the end of each session time was allotted for a plenary discussion. The Rapporteur reviewed the main points and the lessons learnt at the end of the whole Topical Session. (authors)

Empleo de paneles compuestos por subproductos de centrales térmicas en fachadas trasdosadas

Directory of Open Access Journals (Sweden)

Alba, M. D.

2012-06-01

Full Text Available Two new recycled gypsum boards are proposed which have a better environmental performance due to the fact that they are made of traditional materials and new recycled ones derived from biomass (waste generated during the extraction of olive pomace and the coal combustion produced in power plants. Before using these wastes as raw materials, they have been submitted to chemical analysis and the panels made of them have been tested to prove their mechanical, thermal and fire performance. Subsequently, the new recycled panels have been implemented in a traditional facade solution to verify their functional and thermal feasibility. Finally, the results obtained show that the panels made of biomass ashes have a better mechanical and thermal performance than those made of coal ashes and that they can provide a sustainable alternative to the traditional facade materials due to its lower environmental impact based on the reduction of raw materials consumption and industrial waste. The new materials comply with the specifications of Spanish Technical Building Code in the region evaluated

Se presentan dos nuevas tipologías de paneles para trasdosado de fachadas, que proporcionan como mejora ambiental la combinación de materiales tradicionales con nuevos materiales reciclados obtenidos de residuos procedentes de la combustión de orujillo y de carbón en centrales térmicas. Con anterioridad a su uso, dichos residuos han sido sometidos a exhaustivos ensayos químicos y los paneles fabricados a partir de los mismos, a ensayos mecánicos, térmicos y de resistencia al fuego que justifican su empleo. Posteriormente, los nuevos paneles hechos a base de materiales reciclados se han implementado como trasdosado de una solución de fachada convencional para verificar su viabilidad funcional y el buen comportamiento aislante del conjunto. Finalmente, de los resultados obtenidos se extrae que los paneles fabricados con cenizas de orujillo tienen un mejor

DWPF recycle minimization: Brainstorming session

International Nuclear Information System (INIS)

Jacobs, R.A.; Poirier, M.R.

1993-01-01

The recycle stream from the DWPF constitutes a major source of water addition to the High Level Waste evaporator system. As now designed, the entire flow of 3.5 to 6.5 gal/min (at sign 25% and 75% attainment, respectively), or 2 gal/min during idling, flow to the 2H evaporator system (Tank 43). Substantial improvement in the HLW water balance and tank volume management is expected if the DWPF recycle to the HLW evaporator system can be significantly reduced. A task team has been appointed to study alternatives for reducing the flow to the HLW evaporator system and make recommendations for implementation and/or further study and evaluation. The brainstorming session detailed in this report was designed to produce the first cut options for the task team to further evaluate

Proceedings of the self-healing topical session of the IGSC Working Group on Measurement and Physical Understanding of Groundwater Flow through Argillaceous Media (Clay Club)

International Nuclear Information System (INIS)

2001-01-01

A Topical Session focused on the 'Evidence of, and Approaches to Self-Healing in Argillaceous Media' was organised in the framework to the 11. meeting of the Clay Club. It was held at Nancy in France on 16 May 2001 at the invitation of the French Organisation for Radioactive Waste Management (ANDRA). Twenty-six participants representing several national waste management organisations, regulatory authorities, geological surveys as well as academic community took part in the session. The Topical session was mainly aimed at exchanging information on: - The general point of view on self-healing from geomechanical and geochemical experts; - The approaches that are or will be followed by the various organisations in order to deal with self-healing. The geological settings covered in the presentations concerned the whole range of argillaceous media, from soft, plastic clays to indurated clay-stones, currently studied with respect to deep disposal of radioactive waste. The Topical Session showed the importance of a multidisciplinary approach to this topic. The presentations emphasised the interest of a state-of-the-art report on self-healing to provide a sound and disposal-dedicated scientific framework for subsequent studies related to this area

Proceedings of the Fifth Annual Participants' Information Meeting: DOE Low-Level Waste Management Program

International Nuclear Information System (INIS)

1983-12-01

The meeting consisted of the following six sessions: (1) plenary session I; (2) disposal technology; (3) characteristics and treatment of low-level waste; (4) environmental aspects and performance prediction; (5) overall summary sessions; and (6) plenary session II. Fifty two papers of the papers presented were processed for inclusion in the Energy Data Base

Panel discussion on rock mechanics issues in repository design

International Nuclear Information System (INIS)

Bieniawski, Z.T.; Kim, K.S.; Nataraja, M.

1996-01-01

The panel discussion was introduced by Mr. Z.T.(Richard) Bieniawski and then continued with five additional speakers. The topics covered in the discussion included rock mechanics pertaining to the design of underground facilities for the disposal of radioactive wastes and the safety of such facilities. The speakers included: Mr. Kun-Soo Kim who is a specialist in the area of rock mechanics testing during the Basalt Waste Isolation Project; Dr. Mysore Nataraja who is the senior project manager with the NRC; Dr. Michael Voegele who is the project manager for Science Applications International Corporation (SAIC) on the Yucca Mountain Project; Dr. Edward Cording who is a member of the Nuclear Waste Technical Review Board; and Dr. Hemendra Kalia who is employed by Los Alamos National Laboratory and coordinates various activities of testing programs at the Yucca Mountain Site

98th LHCC meeting Agenda OPEN Session and CLOSED Session

CERN Document Server

CERN. Geneva

2009-01-01

OPEN Session on Wednesday, 8 July at 9h00-11h00 in Main Auditorium, Live webcast, followed by CLOSED Session, Conference room 160-1-009 11h20-17h00. CLOSED Session continued on Thursday, 9 July at 9h00-12h30

Brine and Gas Flow Patterns Between Excavated Areas and Disturbed Rock Zone in the 1996 Performance Assessment for the Waste Isolation Pilot Plant for a Single Drilling Intrusion that Penetrates Repository and Castile Brine Reservoir

Energy Technology Data Exchange (ETDEWEB)

ECONOMY,KATHLEEN M.; HELTON,JON CRAIG; VAUGHN,PALMER

1999-10-01

The Waste Isolation Pilot Plant (WIPP), which is located in southeastern New Mexico, is being developed for the geologic disposal of transuranic (TRU) waste by the U.S. Department of Energy (DOE). Waste disposal will take place in panels excavated in a bedded salt formation approximately 2000 ft (610 m) below the land surface. The BRAGFLO computer program which solves a system of nonlinear partial differential equations for two-phase flow, was used to investigate brine and gas flow patterns in the vicinity of the repository for the 1996 WIPP performance assessment (PA). The present study examines the implications of modeling assumptions used in conjunction with BRAGFLO in the 1996 WIPP PA that affect brine and gas flow patterns involving two waste regions in the repository (i.e., a single waste panel and the remaining nine waste panels), a disturbed rock zone (DRZ) that lies just above and below these two regions, and a borehole that penetrates the single waste panel and a brine pocket below this panel. The two waste regions are separated by a panel closure. The following insights were obtained from this study. First, the impediment to flow between the two waste regions provided by the panel closure model is reduced due to the permeable and areally extensive nature of the DRZ adopted in the 1996 WIPP PA, which results in the DRZ becoming an effective pathway for gas and brine movement around the panel closures and thus between the two waste regions. Brine and gas flow between the two waste regions via the DRZ causes pressures between the two to equilibrate rapidly, with the result that processes in the intruded waste panel are not isolated from the rest of the repository. Second, the connection between intruded and unintruded waste panels provided by the DRZ increases the time required for repository pressures to equilibrate with the overlying and/or underlying units subsequent to a drilling intrusion. Third, the large and areally extensive DRZ void volumes is a

Brine and Gas Flow Patterns Between Excavated Areas and Disturbed Rock Zone in the 1996 Performance Assessment for the Waste Isolation Pilot Plant for a Single Drilling Intrusion that Penetrates Repository and Castile Brine Reservoir

International Nuclear Information System (INIS)

Economy, Kathleen M.; Helton, Jon Craig; Vaughn, Palmer

1999-01-01

The Waste Isolation Pilot Plant (WIPP), which is located in southeastern New Mexico, is being developed for the geologic disposal of transuranic (TRU) waste by the U.S. Department of Energy (DOE). Waste disposal will take place in panels excavated in a bedded salt formation approximately 2000 ft (610 m) below the land surface. The BRAGFLO computer program which solves a system of nonlinear partial differential equations for two-phase flow, was used to investigate brine and gas flow patterns in the vicinity of the repository for the 1996 WIPP performance assessment (PA). The present study examines the implications of modeling assumptions used in conjunction with BRAGFLO in the 1996 WIPP PA that affect brine and gas flow patterns involving two waste regions in the repository (i.e., a single waste panel and the remaining nine waste panels), a disturbed rock zone (DRZ) that lies just above and below these two regions, and a borehole that penetrates the single waste panel and a brine pocket below this panel. The two waste regions are separated by a panel closure. The following insights were obtained from this study. First, the impediment to flow between the two waste regions provided by the panel closure model is reduced due to the permeable and areally extensive nature of the DRZ adopted in the 1996 WIPP PA, which results in the DRZ becoming an effective pathway for gas and brine movement around the panel closures and thus between the two waste regions. Brine and gas flow between the two waste regions via the DRZ causes pressures between the two to equilibrate rapidly, with the result that processes in the intruded waste panel are not isolated from the rest of the repository. Second, the connection between intruded and unintruded waste panels provided by the DRZ increases the time required for repository pressures to equilibrate with the overlying and/or underlying units subsequent to a drilling intrusion. Third, the large and areally extensive DRZ void volumes is a

The Management of Information & Knowledge; Meeting of the Panel on Science and Technology with the Committee on Science and Astronautics, U.S. House of Representatives.

Science.gov (United States)

Congress of the U.S., Washington, DC. House Committee on Science and Technology.

The emphasis of the eleventh meeting of the Panel on Science and Technology was on the management of information and knowledge. It was organized essentially as a seminar with two papers given at each session. The topic of the first two papers presented was: "Computers, Communications, and the Economy." The papers given at the second session were…

EXPERIMENTAL INVESTIGATION ON PREFABRICATED ROAD PANEL BY USING WASTE MATERIALS

OpenAIRE

M. Aravinth; P. Arun Kumar; R. Aravind Kumar; S. Arun Kumar

2018-01-01

Plastics are user friendly but not eco-friendly as they are non-biodegradable. Generally it is disposed by way of land filling or incineration of materials which are hazardous. The better binding property of plastics in its molten state has helped in finding out a method of safe disposal of waste plastics, by using them in road laying. Use of plastic waste (HDPE) and Crumb Rubber. This not only allows us to collect modifier raw material at low cost, but also provides a solution towards ecolog...

Proceedings of the symposium on the on-site management of power reactor wastes

International Nuclear Information System (INIS)

Anon.

1979-01-01

This symposium represents a synthesis of some current practices and research and development work in the field of radioactive waste management at nuclear power plants. It includes the following sessions: radioactive waste management practices at nuclear power plants; waste production and operating experiences; coolant and liquid waste processing; solidification methods; volume reduction methods; solid waste containment

Session-RPE for quantifying the load of different youth basketball training sessions

Directory of Open Access Journals (Sweden)

C Lupo

2016-12-01

Full Text Available The aim of the study was to evaluate youth basketball training, verifying the reliability of the session-RPE method in relation to session duration (< and ≥ 80 minutes and workout typology (reduced and high warm-up, conditioning, technical, tactical, game portions within a single session categories. Six male youth basketball players (age, 16.5±0.5 years; height, 195.5±6.75 cm; body mass, 93.9±10.9 kg; and body mass index, 23.6±2.8 kg.m-2 were monitored (HR, type and duration of workouts during 15 (66 individual training sessions (80±26 minutes. Edwards’ HR method was used as a reference measure of internal training load (ITL; the CR-10 RPE scale was administered 30 minutes after the end of each session. The results obtained showed that all comparisons between different session durations and workout portions revealed effects in term of Edwards’ ITLs except for warm-up portions. Moderate to strong relationships between Edwards’ and session- RPE methods emerged for all sessions (r = .85, P < .001, player’s sessions (r range = .79 - .95, P < .001, session durations (< 80 minutes: r = .67, P < .001; ≥ 80 minutes: r = .75, P < .001, and workout portions (r range = .78 - .89, P range = .002 - < .001. The findings indicated that coaches of youth basketball players can successfully use session-RPE to monitor the ITL, regardless of session durations and workout portions.

WIPP panel simulations with gas generation

International Nuclear Information System (INIS)

DeVries, K.L.; Callahan, G.D.; Munson, D.E.

1996-01-01

An important issue in nuclear waste repository performance is the potential for fracture development resulting in pathways for release of radionuclides beyond the confines of the repository. A series of demonstration calculations using structural finite element analyses are presented here to examine the effect of internal gas generation on the response of a sealed repository. From the calculated stress fields, the most probable location for a fracture to develop was determined to be within the pillars interior to the repository for the range of parameter values considered. If a fracture interconnects the rooms and panels of the repository, fracture opening produces significant additional void volume to limit the excess gas pressure to less than 1.0 MPa above the overburden pressure. Consequently, the potential for additional fracture development into the barrier pillar is greatly reduced, which provides further confidence that the waste will be contained within the repository

Nuclear fuel waste disposal

International Nuclear Information System (INIS)

Allan, C.J.

1993-01-01

The Canadian concept for nuclear fuel waste disposal is based on disposing of the waste in a vault excavated 500-1000 m deep in intrusive igneous rock of the Canadian Shield. The author believes that, if the concept is accepted following review by a federal environmental assessment panel (probably in 1995), then it is important that implementation should begin without delay. His reasons are listed under the following headings: Environmental leadership and reducing the burden on future generations; Fostering public confidence in nuclear energy; Forestalling inaction by default; Preserving the knowledge base. Although disposal of reprocessing waste is a possible future alternative option, it will still almost certainly include a requirement for geologic disposal

Radioactive waste isolation in salt: peer review of Westinghouse Electric Corporation's report on reference conceptual designs for a repository waste package

Energy Technology Data Exchange (ETDEWEB)

Rote, D.M.; Hull, A.B.; Was, G.S.; Macdonald, D.D.; Wilde, B.E.; Russell, J.E.; Kruger, J.; Harrison, W.; Hambley, D.F.

1985-10-01

This report documents the findings of the peer panel constituted by Argonne National Laboratory to review Region A of Westinghouse Electric Corporation's report entitled Waste Package Reference Conceptual Designs for a Repository in Salt. The panel determined that the reviewed report does not provide reasonable assurance that US Nuclear Regulatory Commission (NRC) requirements for waste packages will be met by the proposed design. It also found that it is premature to call the design a ''reference design,'' or even a ''reference conceptual design.'' This review report provides guidance for the preparation of a more acceptable design document.

Session 1984-85. Radioactive waste. Minutes of evidence, Wednesday 19 June 1985. Natural Environment Council

International Nuclear Information System (INIS)

1985-01-01

The Environment Select Committee of the House of Commons received a memorandum from the Natural Environment Research Council, on the management and disposal of radioactive waste, under the headings: introduction; role of NERC in research relating to radioactive waste disposal; current NERC research; disposal of wastes in geological strata on land; disposal of wastes in the deep oceans; general comments on high level wastes; effluents discharged to the Irish Sea (dispersion in the Irish Sea; dispersion from the Irish Sea into other environments); concluding observations. Representatives of NERC were examined on the subject of the memorandum and the Minutes of Evidence are recorded. (U.K.)

Seventh annual DOE LLWMP participants' information meeting. DOE Low-Level Waste Management Program. Abstracts

International Nuclear Information System (INIS)

1985-08-01

The following sessions were held: International Low-Level Waste Management Activities; Low-Level Waste Disposal; Characteristics and Treatment of Low-Level Waste; Environmental Monitoring and Performance; Greater Confinement and Alternative Disposal Methods; Low-Level Waste Management; Corrective Measures; Performance Prediction and Assessment; and Siting New Defense and Commercial Low-Level Waste Disposal Facilities

78 FR 72612 - Criteria for the Certification and Recertification of the Waste Isolation Pilot Plant's...

Science.gov (United States)

2013-12-03

... of the shaft seals. The parameters used to represent the changes in performance assessment were... panel are filled with waste, the DOE intends to seal the drifts with engineered structures called panel... seal these drifts with engineered structures called panel closures. 40 CFR part 194, Criteria for the...

Session 21.8 - Challenges and Solutions to Light Pollution, RFI and Implementing IAU Resolution 2009 B5

Science.gov (United States)

Green, Richard

2016-10-01

The closing session included a panel on the challenge of raising cultural awareness of the negative effects of light pollution and RFI, and a discussion about the means to implement the IAU Resolution on the Right to Starlight. The strongest arguments to the public are that light pollution wastes precious energy and adds greenhouse gases, and that artificial light at night can be damaging to human health and to the natural environment. As astronomers, our community is concerned that the world is blinding itself to the electromagnetic radiation connecting us to the Universe. An outcome of successful advocacy would be to create demand for commercial products that minimize blue light and upward radiation. Implementation of the resolution on the Right to Starlight has multiple aspects. The IAU, through its site protection commission, should provide a clear technical description of "astronomy friendly" lighting and specifications for protection of the near zones around optical observatories. In addition, the commission should provide reference materials for astronomers giving public presentations, provide a forum for those seeking stronger local or national regulation, seek IAU approval for endorsement of protected status of sites and regions, and support the process of gaining UNESCO World Heritage Status for observatories and their regions.

Disposal Activities and the Unique Waste Streams at the Nevada National Security Site (NNSS)

International Nuclear Information System (INIS)

Arnold, P.

2012-01-01

This slide show documents waste disposal at the Nevada National Security Site. Topics covered include: radionuclide requirements for waste disposal; approved performance assessment (PA) for depleted uranium disposal; requirements; program approval; the Waste Acceptance Review Panel (WARP); description of the Radioactive Waste Acceptance Program (RWAP); facility evaluation; recent program accomplishments, nuclear facility safety changes; higher-activity waste stream disposal; and, large volume bulk waste streams

Review of the scientific and technical criteria for the Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

1984-01-01

The panel has evaluated the scientific and technical adequacy of work being done on the Waste Isolation Pilot Plant (WIPP) project to satisfy the charge to the panel set out in Chapter 1. The panel concluded that the scientific work has been carried out with a high degree of professional competence. The panel notes that the geology revealed by shaft sinking and excavation of drifts and the preliminary measurements generally confirm the geologic expectations derived from surface explorations and boreholes. The purity and volume of the salt, the absence of brine pockets at the repository horizon in the areas excavated, the absence of breccia pipes and of toxic gases, and the nearly horizontal bedding of the salt indicate that a repository can be constructed that will meet the geologic criteria for site selection. Thus, the important issues about the geology at the site have been resolved, but there remain some issues about the hydrology and design of the facility that should be resolved before large-scale transuranic (TRU) waste emplacement begins. The panel's conclusions and recommendations regarding the following studies are presented: site selection and characterization; in-situ tests and experiments; waste acceptance criteria; design and construction of underground facilities; and performance assessment. 65 references, 17 figures, 3 tables

Information management for the Department of Energy's Office of Civilian Radioactive Waste Management

International Nuclear Information System (INIS)

Cerny, B.A.

1992-01-01

This paper is an introduction to the session on the management of information within the Department of Energy's Office of Civilian Radioactive Waste Management (OCRWM). OCRWM'S mission will take decades to fulfill, and its success will leave a legacy of implications for millennia to come. The effective management of information during the life span of such a large and long term endeavor is critical. The programmatic information takes other forms: reports are written; policy documents are produced; correspondence is generated; and the daily flow of information through the program presses on staff as they sort, create, and respond to its demands. The major problem with electronic information generation within the public sector was aptly expressed at the beginning of the 1985 blue panel report of the Committee on the Records of Government: the United States is losing its institutional memory. This thought has been a major driver in our technical strategic planning and implementation

Proceedings of the Fifth Annual Participants' Information Meeting: DOE Low-Level Waste Management Program

Energy Technology Data Exchange (ETDEWEB)

1983-12-01

The meeting consisted of the following six sessions: (1) plenary session I; (2) disposal technology; (3) characteristics and treatment of low-level waste; (4) environmental aspects and performance prediction; (5) overall summary sessions; and (6) plenary session II. Fifty two papers of the papers presented were processed for inclusion in the Energy Data Base. (ATT)

Session-RPE for quantifying load of different youth taekwondo training sessions.

Science.gov (United States)

Lupo, Corrado; Capranica, Laura; Cortis, Cristina; Guidotti, Flavia; Bianco, Antonino; Tessitore, Antonio

2017-03-01

The session rating of perceived exertion (session-RPE) proved to be a valuable method to quantify the internal training load (ITL) in taekwondo. However, no study validated this method in youth taekwondo athletes performing different training sessions. Thus this study aimed at evaluating the reliability of the session-RPE to monitor the ITL of prepubescent taekwondo athletes during pre-competitive (PC) and competitive (C) training sessions. Five female (age: 12.0±0.7 y; height: 1.54±0.08 m; body mass: 48.8±7.3 kg) and four male (age: 12.0±0.8 yrs; height: 1.55±0.07 m; body mass: 47.3±5.3 kg) taekwondo athletes were monitored during 100 individual sessions (PC: N.=33; C: N.=67). The Edwards' HR method was used as reference measure of ITL; the CR-10 RPE scale was administered at 1- and 30-minutes from the end of each session. No difference for gender emerged. The ITLs of C (Edwards: 228±40 arbitrary units, AU) resulted higher than that of PC (192±26 AU; P=0.04). Although all training typologies and data collections achieved significant correlations between Edwards' and session-RPE methods, a large relationship (r =0.71, Psessions evaluated at 30 minutes of the recovery phases. Findings support coaches of prepubescent taekwondo athletes to successfully use session-RPE to monitor the ITL of different training typologies. However, PC training evaluated at 30 minutes of the recovery phase represents the best condition for a highly reliable ITL perception.

Technology of radioactive waste management avoiding environmental disposal

International Nuclear Information System (INIS)

1964-01-01

This report considers present radioactive waste management methods and practices. In addition, present research and development activity designed to minimize discharges to the environment are noted. During its deliberations the Panel was able to define certain avenues of research and development which should be explored to enable the almost complete containment of wastes. The experience and practices at establishments, where, for geographical, geological or other reasons, discharges of radioactive material to the environment are extremely small, served as the starting point for the Panel's deliberations. Details of the experience and practice, together with the results obtained at these establishments, are summarized in Part I and described in more detail in Part II of this report. 48 refs, 89 figs, 11 tabs

WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

J. D. Bigbee

2000-06-21

The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status.

WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT

International Nuclear Information System (INIS)

J. D. Bigbee

2000-01-01

The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status

Assessing treatment integrity in cognitive-behavioral therapy: comparing session segments with entire sessions.

Science.gov (United States)

Weck, Florian; Grikscheit, Florian; Höfling, Volkmar; Stangier, Ulrich

2014-07-01

The evaluation of treatment integrity (therapist adherence and competence) is a necessary condition to ensure the internal and external validity of psychotherapy research. However, the evaluation process is associated with high costs, because therapy sessions must be rated by experienced clinicians. It is debatable whether rating session segments is an adequate alternative to rating entire sessions. Four judges evaluated treatment integrity (i.e., therapist adherence and competence) in 84 randomly selected videotapes of cognitive-behavioral therapy for major depressive disorder, social anxiety disorder, and hypochondriasis (from three different treatment outcome studies). In each case, two judges provided ratings based on entire therapy sessions and two on session segments only (i.e., the middle third of the entire sessions). Interrater reliability of adherence and competence evaluations proved satisfactory for ratings based on segments and the level of reliability did not differ from ratings based on entire sessions. Ratings of treatment integrity that were based on entire sessions and session segments were strongly correlated (r=.62 for adherence and r=.73 for competence). The relationship between treatment integrity and outcome was comparable for ratings based on session segments and those based on entire sessions. However, significant relationships between therapist competence and therapy outcome were only found in the treatment of social anxiety disorder. Ratings based on segments proved to be adequate for the evaluation of treatment integrity. The findings demonstrate that session segments are an adequate and cost-effective alternative to entire sessions for the evaluation of therapist adherence and competence. Copyright © 2014. Published by Elsevier Ltd.

Roughness study on homogeneous layer panels manufactured from treated wood waste

Directory of Open Access Journals (Sweden)

Maria Fátima do Nascimento

2017-02-01

Full Text Available Natural resource exploration is growing, highlighting woods and joinery waste, wood industries and the like. This study presents homogeneous particleboard (PPH roughness characterization manufactured from treated wood waste. Normative document with values of Brazilian Technical Standard Association ABNT NBR 8404 (1984, was adopted as a reference. The results show that the manufactured PPH showed roughness class N 10, with roughness values (Ra of less than 12.5 microns.

Focused science shop - Potential environmental impact of radioactive waste disposal in comparison with other hazardous wastes. Deliverable 7

International Nuclear Information System (INIS)

Vojtechova, Hana

2008-07-01

An important part of the ARGONA project is the testing and application of novel participation and dialogue approaches. The Czech Republic is one of the countries where these approaches will be applied and tested. The ways in this is being done include a series of events involving different stakeholders such as a focused science shop, a consensus panel and an interaction panel. In the framework of these activities in the Czech Republic the focused science shop was held on March 12, 2008 in the Nuclear Research Institute (NRI) in Rez, and addressed the theme: 'Radioactive waste management and radiation risk in comparison with other hazardous waste and risks'. The main goal of this focused science shop was to increase awareness amongst the public of actual and potential effects of radioactive and toxic wastes and to prioritise questions/uncertainties that people might have in this field. The following topics were discussed: - Differences in the general perception of nuclear waste in comparison with other toxic wastes; - General public awareness of the issue of nuclear waste management and other toxic wastes management; - Management and ultimate disposal of radioactive waste and other toxic waste in terms of the technology employed; - NIMBY effect. A broader audience was selected with a suitable mixture of specialists and interested technical and non-technical peers including representatives from NRI, universities, Ministry of Industry and Trade, Ministry of the Environment, State Office for Nuclear Safety and Radioactive Waste Repository Authority, representatives of municipalities and NGOs, and waste producers such as CEZ plc etc. In the Czech Republic there is a general unwillingness by the public to actively participate in the NWM decision-making process. Therefore, despite all the efforts made by the project team, not all invited stakeholders attended the meeting. Despite this, the meeting was very positively received by those who did attend and indicates the

The performance assessment impacts of disposal of high-moisture, low-level radioactive waste at the Nevada Test Site

International Nuclear Information System (INIS)

Crowe, B.M.; Hansen, W.; Hechnova, A.; Voss, C.; Waters, R.; Sully, M.; Levitt, D.

1999-01-01

A panel of independent scientists was convened by the Department of Energy to assess the performance impacts of disposal of low-level radioactive waste from the Fernald Environmental Management Project. This waste stream was involved in a transportation incident in December 1997. A resulting outgrowth of investigations of the transportation incident was the recognition that the waste was transported and disposed in stress-fractured metal boxes and some of the waste contained excess moisture (high volumetric water contents). The panel was charged with determining whether disposal of this waste in the Area 5 radioactive waste management site on the Nevada Test Site has impacted the conclusions of the completed performance assessment. Three questions were developed by the panel to assess performance impacts: (1) the performance impacts of reduced container integrity, (2) the impact of reduced container integrity on subsidence of waste in the disposal pits and (3) the performance impacts of excess moisture. No performance or subsidence impacts were noted from disposal of the Fernald waste. The impacts of excess moisture were assessed through simulation modeling of the movement of moisture in the vadose zone assuming high water contents (wet waste) for different percentages of the waste inventory. No performance impacts were noted for either the base-case scenario (ambient conditions) or a scenario involving subsidence and flooding of the waste cells. The absence of performance impacts results form the extreme conservatism used in the Area 5-performance assessment and the robust nature of the disposal site

High insulation foam glass material from waste cathode ray tube panel glass

DEFF Research Database (Denmark)

König, Jakob; Petersen, Rasmus Rosenlund; Yue, Yuanzheng

. In general CRT consists of two types of glasses: barium/strontium containing glass (panel glass) and lead containing glass (funnel and panel glass). In this work we present the possibility to produce high performance insulation material from the recycled lead-free glass. We studied the influence of foaming...... between 750 and 850°C. We investigated the influence of milling time, particle size, foaming and oxidizing agent concentrations, temperature and time on the foaming process, foam density, foam porosity and homogeneity. Only moderate foaming was observed in carbon containing samples, while the addition...... of the oxidizing agent greatly improved the foaming quality. The results showed that the amount of oxygen available from the glass is not sufficient to combust all of the added carbon, therefore, additional oxygen was supplied via manganese reduction. In general, a minimum in the foam glass density was observed...

AREVA Technical Days (ATD) session 2: operations of the back-end of the nuclear fuel cycle

International Nuclear Information System (INIS)

2002-01-01

These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This second session deals with the reprocessing business, back-end financing mechanisms, technology transfer, environmental management, risk management programs, research and development contribution to waste volume reductions, issues and outlook of nuclear wastes, comparison of the open and closed cycles. (A.L.B.)

Cross-Site Transfer System at Hanford: long-term strategy for waste acceptance

International Nuclear Information System (INIS)

Shekarriz, A.; Onishi, Y.; Smith, P.A.; Sterner, M.; Rector, D.R.; Virden, J.

1997-02-01

This report summarizes results of a technical panel review of the current methodology for accepting waste for transport through the Hanford Replacement Cross-Site Transfer System (RCSTS), which was constructed to replace the existing pipelines that hydraulically connect the 200 West and 200 East areas. This report is a complement to an existing document (Hudson 1996); the methodology proposed in that document was refined based on panel recommendations. The refinements were focused around predicting and preventing the 3 main modes suspected of plugging the existing CSTS: precipitation, gelation, particle dropout/settling. The proposed analysis will require integration of computer modeling and laboratory experiments to build a defensible case for transportability of a proposed slurry composition for a given tank. This will be validated by recirculating actual tank waste, in-tank and in-farm, prior to transport. The panel's recommendation was that the probability of success of waste transfer would be greatly improved by integrating the predictive analysis with real-time control during RCSTS operation. The methodology will be optimized

Session 1984-1985. Radioactive waste. Minutes of evidence, Monday 13 May 1985. British Nuclear Fuels plc

Energy Technology Data Exchange (ETDEWEB)

1985-01-01

The Environment Select Committee of the House of Commons received a memorandum from British Nuclear Fuels plc on the treatment and preparation for disposal of radioactive wastes, under the headings: introduction; waste categories; waste management policy; waste arisings; waste treatment plans; appendix I - British Nuclear Fuels plc; appendix II - the nuclear fuel cycle for Magnox, AGR and LWR reactors; appendix III - control of liquid radioactive discharges from Sellafield and their environmental impact. Representatives of BNF plc were examined on the subject of the memorandum and the minutes of evidence are recorded.

Session 1984-85. Radioactive waste. Minutes of evidence, Monday 13 May 1985. British Nuclear Fuels plc

International Nuclear Information System (INIS)

1985-01-01

The Environment Select Committee of the House of Commons received a memorandum from British Nuclear Fuels plc on the treatment and preparation for disposal of radioactive wastes, under the headings: introduction; waste categories; waste management policy; waste arisings; waste treatment plans; appendix I - British Nuclear Fuels plc; appendix II - the nuclear fuel cycle for Magnox, AGR and LWR reactors; appendix III - control of liquid radioactive discharges from Sellafield and their environmental impact. Representatives of BNF plc were examined on the subject of the memorandum and the minutes of evidence are recorded. (U.K.)

Workshop on rock mechanics issues in repository design and performance assessment

International Nuclear Information System (INIS)

1996-04-01

The Center for Nuclear Waste Regulatory Analyses organized and hosted a workshop on ''Rock Mechanics Issues in Repository Design and Performance Assessment'' on behalf its sponsor the U.S. Nuclear Regulatory Commission (NRC). This workshop was held on September 19- 20, 1994 at the Holiday Inn Crowne Plaza, Rockville, Maryland. The objectives of the workshop were to stimulate exchange of technical information among parties actively investigating rock mechanics issues relevant to the proposed high-level waste repository at Yucca Mountain and identify/confirm rock mechanics issues important to repository design and performance assessment The workshop contained three technical sessions and two panel discussions. The participants included technical and research staffs representing the NRC and the Department of Energy and their contractors, as well as researchers from the academic, commercial, and international technical communities. These proceedings include most of the technical papers presented in the technical sessions and the transcripts for the two panel discussions

Experience with disposal of low-level radioactive waste: building confidence for and against the regulations

International Nuclear Information System (INIS)

Kastenberg, W.E.; Lowenthal, M.D.

2001-01-01

Following the controversy regarding the potential use of the Ward Valley site in California as a low level radioactive waste facility, an Advisory Group and a Scientific Panel were formed to recommend alternatives to the Governor. During the course of the Group and Panel deliberations, the arguments for and against near surface burial and waste classification were crystallized. In this paper we discuss the bases upon which the arguments were formed and what we can learn from them. (author)

Experience with disposal of low-level radioactive waste: building confidence for and against the regulations

Energy Technology Data Exchange (ETDEWEB)

Kastenberg, W.E.; Lowenthal, M.D. [University of California, Dept. of Nuclear Engineering, CA (United States)

2001-07-01

Following the controversy regarding the potential use of the Ward Valley site in California as a low level radioactive waste facility, an Advisory Group and a Scientific Panel were formed to recommend alternatives to the Governor. During the course of the Group and Panel deliberations, the arguments for and against near surface burial and waste classification were crystallized. In this paper we discuss the bases upon which the arguments were formed and what we can learn from them. (author)

TU-A-BRB-02: Panel Member

International Nuclear Information System (INIS)

Ma, L.

2016-01-01

Brain stereotactic radiosurgery (SRS) and spine stereotactic body radiation therapy (SBRT) are commonly treated by a multidisciplinary team of neurosurgeons, radiation oncologists, and medical physicists. However the treatment objectives, constraints, and technical considerations involved can be quite different between the two techniques. In this interactive session an expert panel of speakers will present clinical brain SRS and spine SBRT cases in order to demonstrate real-world considerations for ensuring safe and accurate treatment delivery and to highlight the significant differences in approach for each treatment site. The session will include discussion of topic such as clinical indications, immobilization, target definition, normal tissue tolerance limits, and beam arrangements. Learning Objectives: Understand the differences in indications and dose/fractionation strategies for intracranial SRS and spine SBRT. Describe the different treatment modalities which can be used to deliver intracranial SRS and spine SBRT. Cite the major differences in treatment setup and delivery principles between intracranial and spine treatments. Identify key critical structures and clinical dosimetric tolerance levels for spine SBRT and intracranial SRS. Understand areas of ongoing work to standardize intracranial SRS and spine SBRT procedures. Schlesinger: Research support: Elekta Instruments, AB; D. Schlesinger, Elekta Instruments, AB - research support; B. Winey, No relevant external funding for this subject.

TU-A-BRB-03: Panel Member

International Nuclear Information System (INIS)

Winey, B.

2016-01-01

Brain stereotactic radiosurgery (SRS) and spine stereotactic body radiation therapy (SBRT) are commonly treated by a multidisciplinary team of neurosurgeons, radiation oncologists, and medical physicists. However the treatment objectives, constraints, and technical considerations involved can be quite different between the two techniques. In this interactive session an expert panel of speakers will present clinical brain SRS and spine SBRT cases in order to demonstrate real-world considerations for ensuring safe and accurate treatment delivery and to highlight the significant differences in approach for each treatment site. The session will include discussion of topic such as clinical indications, immobilization, target definition, normal tissue tolerance limits, and beam arrangements. Learning Objectives: Understand the differences in indications and dose/fractionation strategies for intracranial SRS and spine SBRT. Describe the different treatment modalities which can be used to deliver intracranial SRS and spine SBRT. Cite the major differences in treatment setup and delivery principles between intracranial and spine treatments. Identify key critical structures and clinical dosimetric tolerance levels for spine SBRT and intracranial SRS. Understand areas of ongoing work to standardize intracranial SRS and spine SBRT procedures. Schlesinger: Research support: Elekta Instruments, AB; D. Schlesinger, Elekta Instruments, AB - research support; B. Winey, No relevant external funding for this subject.

TU-A-BRB-02: Panel Member

Energy Technology Data Exchange (ETDEWEB)

Ma, L. [UCSF Comprehensive Cancer Center (United States)

2016-06-15

Brain stereotactic radiosurgery (SRS) and spine stereotactic body radiation therapy (SBRT) are commonly treated by a multidisciplinary team of neurosurgeons, radiation oncologists, and medical physicists. However the treatment objectives, constraints, and technical considerations involved can be quite different between the two techniques. In this interactive session an expert panel of speakers will present clinical brain SRS and spine SBRT cases in order to demonstrate real-world considerations for ensuring safe and accurate treatment delivery and to highlight the significant differences in approach for each treatment site. The session will include discussion of topic such as clinical indications, immobilization, target definition, normal tissue tolerance limits, and beam arrangements. Learning Objectives: Understand the differences in indications and dose/fractionation strategies for intracranial SRS and spine SBRT. Describe the different treatment modalities which can be used to deliver intracranial SRS and spine SBRT. Cite the major differences in treatment setup and delivery principles between intracranial and spine treatments. Identify key critical structures and clinical dosimetric tolerance levels for spine SBRT and intracranial SRS. Understand areas of ongoing work to standardize intracranial SRS and spine SBRT procedures. Schlesinger: Research support: Elekta Instruments, AB; D. Schlesinger, Elekta Instruments, AB - research support; B. Winey, No relevant external funding for this subject.

TU-A-BRB-03: Panel Member

Energy Technology Data Exchange (ETDEWEB)

Winey, B. [Massachusetts General Hospital (United States)

2016-06-15

Brain stereotactic radiosurgery (SRS) and spine stereotactic body radiation therapy (SBRT) are commonly treated by a multidisciplinary team of neurosurgeons, radiation oncologists, and medical physicists. However the treatment objectives, constraints, and technical considerations involved can be quite different between the two techniques. In this interactive session an expert panel of speakers will present clinical brain SRS and spine SBRT cases in order to demonstrate real-world considerations for ensuring safe and accurate treatment delivery and to highlight the significant differences in approach for each treatment site. The session will include discussion of topic such as clinical indications, immobilization, target definition, normal tissue tolerance limits, and beam arrangements. Learning Objectives: Understand the differences in indications and dose/fractionation strategies for intracranial SRS and spine SBRT. Describe the different treatment modalities which can be used to deliver intracranial SRS and spine SBRT. Cite the major differences in treatment setup and delivery principles between intracranial and spine treatments. Identify key critical structures and clinical dosimetric tolerance levels for spine SBRT and intracranial SRS. Understand areas of ongoing work to standardize intracranial SRS and spine SBRT procedures. Schlesinger: Research support: Elekta Instruments, AB; D. Schlesinger, Elekta Instruments, AB - research support; B. Winey, No relevant external funding for this subject.

TU-A-BRB-01: Panel Member

Energy Technology Data Exchange (ETDEWEB)

Schlesinger, D. [University of Virginia Health Systems (United States)

2016-06-15

Brain stereotactic radiosurgery (SRS) and spine stereotactic body radiation therapy (SBRT) are commonly treated by a multidisciplinary team of neurosurgeons, radiation oncologists, and medical physicists. However the treatment objectives, constraints, and technical considerations involved can be quite different between the two techniques. In this interactive session an expert panel of speakers will present clinical brain SRS and spine SBRT cases in order to demonstrate real-world considerations for ensuring safe and accurate treatment delivery and to highlight the significant differences in approach for each treatment site. The session will include discussion of topic such as clinical indications, immobilization, target definition, normal tissue tolerance limits, and beam arrangements. Learning Objectives: Understand the differences in indications and dose/fractionation strategies for intracranial SRS and spine SBRT. Describe the different treatment modalities which can be used to deliver intracranial SRS and spine SBRT. Cite the major differences in treatment setup and delivery principles between intracranial and spine treatments. Identify key critical structures and clinical dosimetric tolerance levels for spine SBRT and intracranial SRS. Understand areas of ongoing work to standardize intracranial SRS and spine SBRT procedures. Schlesinger: Research support: Elekta Instruments, AB; D. Schlesinger, Elekta Instruments, AB - research support; B. Winey, No relevant external funding for this subject.

TU-A-BRB-01: Panel Member

International Nuclear Information System (INIS)

Schlesinger, D.

2016-01-01

Brain stereotactic radiosurgery (SRS) and spine stereotactic body radiation therapy (SBRT) are commonly treated by a multidisciplinary team of neurosurgeons, radiation oncologists, and medical physicists. However the treatment objectives, constraints, and technical considerations involved can be quite different between the two techniques. In this interactive session an expert panel of speakers will present clinical brain SRS and spine SBRT cases in order to demonstrate real-world considerations for ensuring safe and accurate treatment delivery and to highlight the significant differences in approach for each treatment site. The session will include discussion of topic such as clinical indications, immobilization, target definition, normal tissue tolerance limits, and beam arrangements. Learning Objectives: Understand the differences in indications and dose/fractionation strategies for intracranial SRS and spine SBRT. Describe the different treatment modalities which can be used to deliver intracranial SRS and spine SBRT. Cite the major differences in treatment setup and delivery principles between intracranial and spine treatments. Identify key critical structures and clinical dosimetric tolerance levels for spine SBRT and intracranial SRS. Understand areas of ongoing work to standardize intracranial SRS and spine SBRT procedures. Schlesinger: Research support: Elekta Instruments, AB; D. Schlesinger, Elekta Instruments, AB - research support; B. Winey, No relevant external funding for this subject.

Formal description of the OSI session layer: session service

NARCIS (Netherlands)

van Sinderen, Marten J.; van Eijk, P.H.J.; Vissers, C.A.; Diaz, M.

1989-01-01

The LOTOS formal description of the OSI session service is presented on basis of specification samples from the full description, giving account of how specification styles and session service architectural elements are reflected in the description. Both information (data types) and process

Mobile fission and activation products in nuclear waste disposal

Energy Technology Data Exchange (ETDEWEB)

Umeki, H; Evans, N; Czervinski, K; Bruggeman, Ch; Poineau, F; Breynaert, A; Reiler, P; Pablo, J de; Pipon, Y; Molnar, M; Nishimura, T; Kienzler, B; Van Iseghem, P; Crovisier, J L; Wieland, E; Mace, N; Pablo, J de; Spahiu, K; Cui, D; Lida, Y; Charlet, L; Liu, X; Sato, H; Goutelard, F; Savoye, S; Glaus, M; Poinssot, C; Seby, F; Sato, H; Tournassat, Ch; Montavon, G; Rotenberg, B; Spahiu, K; Smith, G; Marivoet, J; Landais, P; Bruno, J; Johnson, H; Umeki, L; Geckeis, H; Giffaut, E; Grambow, B; Dierckx, A

2007-07-01

This document gathers 33 oral presentations that were made at this workshop dedicated to the mobility of some radionuclides in nuclear waste disposal. The workshop was organized into 6 sessions: 1) performance assessment, 2) speciation/interaction in aqueous media, 3) radioactive wastes, 4) redox processes at interfaces, 5) diffusion processes, and 6) retention processes.

Mobile fission and activation products in nuclear waste disposal

International Nuclear Information System (INIS)

Umeki, H.; Evans, N.; Czervinski, K.; Bruggeman, Ch.; Poineau, F.; Breynaert, A.; Reiler, P.; Pablo, J. de; Pipon, Y.; Molnar, M.; Nishimura, T.; Kienzler, B.; Van Iseghem, P.; Crovisier, J.L.; Wieland, E.; Mace, N.; Pablo, J. de; Spahiu, K.; Cui, D.; Lida, Y.; Charlet, L.; Liu, X.; Sato, H.; Goutelard, F.; Savoye, S.; Glaus, M.; Poinssot, C.; Seby, F.; Sato, H.; Tournassat, Ch.; Montavon, G.; Rotenberg, B.; Spahiu, K.; Smith, G.; Marivoet, J.; Landais, P.; Bruno, J.; Johnson, H.; Umeki, L.; Geckeis, H.; Giffaut, E.; Grambow, B.; Dierckx, A.

2007-01-01

This document gathers 33 oral presentations that were made at this workshop dedicated to the mobility of some radionuclides in nuclear waste disposal. The workshop was organized into 6 sessions: 1) performance assessment, 2) speciation/interaction in aqueous media, 3) radioactive wastes, 4) redox processes at interfaces, 5) diffusion processes, and 6) retention processes

Panel Analysis

DEFF Research Database (Denmark)

Brænder, Morten; Andersen, Lotte Bøgh

2014-01-01

Based on our 2013-article, ”Does Deployment to War Affect Soldiers' Public Service Motivation – A Panel Study of Soldiers Before and After their Service in Afghanistan”, we present Panel Analysis as a methodological discipline. Panels consist of multiple units of analysis, observed at two or more...... in research settings where it is not possible to distribute units of analysis randomly or where the independent variables cannot be manipulated. The greatest disadvantage in regard to using panel studies is that data may be difficult to obtain. This is most clearly vivid in regard to the use of panel surveys...... points in time. In comparison with traditional cross-sectional studies, the advantage of using panel studies is that the time dimension enables us to study effects. Whereas experimental designs may have a clear advantage in regard to causal inference, the strength of panel studies is difficult to match...

Proceedings of the eighth annual DOE low-level waste management forum: Technical Session 8, Future DOE low-level waste management

International Nuclear Information System (INIS)

1987-02-01

This volume contains the following papers: (1) DOE Systems Approach and Integration; (2) Impacts of Hazardous Waste Regulation on Low-Level Waste Management; (3) Site Operator Needs and Resolution Status; and (4) Establishment of New Disposal Capacity for the Savannah River Plant. All papers have been processed for inclusion in the Energy Data Base. (AT)

Potential environmental hazards of photovoltaic panel disposal: Discussion of Tammaro et al. (2015).

Science.gov (United States)

Sinha, Parikhit

2017-02-05

In their recent publication in Journal of Hazardous Materials (http://dx.doi.org/10.1016/j.jhazmat.2015.12.018), Tammaro et al. evaluate the potential environmental impacts of an illegal disposal scenario of photovoltaic panels in the European Union. Critical assumptions that underlie the study's conclusions would benefit from clarification. A scenario of photovoltaic panels finely crushed and abandoned in nature is not supported with field breakage data, in which photovoltaic panels remain largely intact with a number of glass fractures or cracks, as opposed to breakage into cm-scale pieces. Fate and transport analysis is necessary to evaluate how leachate transforms and disperses in moving from the point of emissions to the point of exposure, prior to making comparisons with drinking water limits. Some hazardous metal content has declined in both crystalline silicon and thin film panels, including a 50% decline in semiconductor material intensity in CdTe thin film panels (g CdTe/W) from 2009 to 2015. Waste laws, recycling requirements and minimum treatment standards under the EU WEEE Directive, and illegal disposal rates affect the accuracy of forecasts of releasable metal amounts from PV panels in Europe through 2050. Copyright © 2016 Elsevier B.V. All rights reserved.

A new way to ask the experts: Rating radioactive waste risks

International Nuclear Information System (INIS)

Kerr, R.A.

1996-01-01

The possible risks of a proposed nuclear waste repository at Yucca Mountain include the dozen or more young volcanos near by. Now some earth scientists have a new approach to evaluating hazards accounting for uncertainty at every step - 'expert elicitation.' This pulls together a panel of experts, carefully assesses the uncertainties of each of their views then mathematically combines their risk estimates along with the accompanying uncertainties. The article goes on to describe just such a panel which considered seismic hazards to Yucca Mountain, how they came to their conclusions, the arguments about the conclusions, and the future of expert elicitation in evaluating the risks of nuclear waste disposal

Radioactive waste management turning options into solution

International Nuclear Information System (INIS)

Neubauer, J.

2000-10-01

Most of the statements from representatives of different countries and institutions focused on the status of high level radioactive waste management, including spent fuel repositories. Speakers dealing with such topics were representatives from countries applying nuclear power for electricity production. They all reported about there national programs on technical and safety aspects of radioactive waste management. The panel discussion extended to questions on political sensitivities and public acceptance; in this respect, interesting developments are taking place in Finland and Sweden. It is expected that Finland will operate a final repository for spent fuel in 10 - 15 years from now, followed close by Sweden. Other countries, however, face decisions by policy makers and elected officials to postpone dealing with waste disposal concerns. In this connection there is relevant experience in our country, too - even in the absence of spent fuel or other high level waste to be dealt with. During personal discussions with representatives of other countries not using nuclear power it was confirmed that there are similar or shared experiences. Development of publicly -accepted solutions to radioactive waste management remains an important issue. Independent of the amount or the activity of radioactive waste, the public at large remains skeptical despite the agreement among experts that disposal can be safe, technically feasible and environmentally sound. In countries not using nuclear power there are only small quantities of low and intermediate level radioactive waste. Therefore, international co-operation among such countries should be an option. There was common understanding by representatives from Norway, Italy and Austria that international co-operation should be developed for treatment and disposal of such waste. For the moment however it has to be accepted that, for political reasons, it is not possible. Forced to deal with the lack of near-term solutions, the

Glass science tutorial: Lecture No. 7, Waste glass technology for Hanford

International Nuclear Information System (INIS)

Kruger, A.A.

1995-07-01

This paper presents the details of the waste glass tutorial session that was held to promote knowledge of waste glass technology and how this can be used at the Hanford Reservation. Topics discussed include: glass properties; statistical approach to glass development; processing properties of nuclear waste glass; glass composition and the effects of composition on durability; model comparisons of free energy of hydration; LLW glass structure; glass crystallization; amorphous phase separation; corrosion of refractories and electrodes in waste glass melters; and glass formulation for maximum waste loading

The chemistry of nuclear fuel waste disposal

International Nuclear Information System (INIS)

Wiles, D.R.

2002-01-01

About one-fifth of the world's supply of energy is derived from nuclear fission. While this important source of power avoids the environmental and resource problems of most other fuels, and although nuclear accident statistics are much less alarming, no other peacetime technology has evoked such public disquiet and impassioned feeling. Central to dealing with these fears is the management and disposal of radioactive waste. An expert Canadian panel in 1977 recommended permanent disposal of wastes in deep geological formations, providing a basis for subsequent policies and research. In 1988, the Federal Environmental Assessment Review Office (FEARO) appointed a panel to assess the proposed disposal concepts and to recommend government policy. The panel in turn appointed a Scientific Review Group to examine the underlying science. Behind all these issues lay one central question: How well is the chemistry understood? This became the principal concern of Professor Donald Wiles, the senior nuclear chemist of the Scientific Review Group. In this book, Dr. Wiles carefully describes the nature of radioactivity and of nuclear power and discusses in detail the management of radioactive waste by the multi-barrier system, but also takes an unusual approach to assessing the risks. Using knowledge of the chemical properties of the various radionuclides in spent fuel, this book follows each of the important radionuclides as it travels through the many barriers placed in its path. It turns out that only two radionuclides are able to reach the biosphere, and they arrive at the earth's surface only after many thousands of years. A careful analysis of the critical points of the disposal plan emphasizes site rejection criteria and other stages at which particular care must be taken, demonstrating how dangers can be anticipated and putting to rest the fear of nuclear fuel waste and its geological burial

National Waste Terminal Storage Program information meeting, December 7-8, 1976. [Slides only, no text

Energy Technology Data Exchange (ETDEWEB)

1976-12-06

Volume II of the report comprises copies of the slides from the talks presented at the second session of the National Waste Terminal Storage Program information meeting. This session was devoted to geologic studies. (LK)

Radioactive waste management: a summary of state laws and administration

International Nuclear Information System (INIS)

1983-09-01

This is the second update of Radioactive Waste Management: A Summary of State Laws and Administration. It completely replaces the first update (15 April 1983). The updated report covers the administration, the legislature and the laws in the 50 states related to radioactive waste. The report for each state is divided into four sections: Cover Page; Administrative; Legislative; and Applicable Legislation. The cover page indicates whether or not it is an Agreement State, the low-level waste compacts in which the state is listed as an eligible state, and the high-level waste repository site screening regions in which the state or a portion of it is located. Included under the compacts is a description of what the state has done or currently plans to do, as well as the compact status of other eligible states in the region. The Administrative section provides information on the governor, lead agencies, other involved administrative agencies, relevant commissions, boards and councils and various contacts. In a number of states, Boards of Health or similar boards are lead agencies, so they have been listed in that section. Each board's administrative agency is listed under it. The Legislative section provides general information on the legislature and lists legislative leaders, the relevant committees and their chairs, and a legislative contact. Many legislatures do not set a date for session adjournment, so the date listed represents a combination of information provided by the states and by the history of past sessions. In the section covering Applicable Legislation, laws related to radiation protection, low-level waste and high-level waste have been summarized. Hazardous waste siting laws are included for states that do not have a siting law covering radioactive waste. The section also contains summaries of relevant bills introduced in 1982 and 1983 legislative sessions and this disposition. In general, the information in this report is accurate as of July 15, 1983

Proceedings of the tenth annual DOE low-level waste management conference: Session 4: Waste treatment minimization

International Nuclear Information System (INIS)

1988-12-01

This document contains eleven papers on various aspects of low-level radioactive waste management. Topics in this volume include: volume reduction plans; incentitives; and cost proposals; acid detoxification and reclamation; decontamination of lead; leach tests; West Valley demonstration project status report; and DOE's regional management strategies. Individual papers were processed separately for the data base

Energy Frontier Research Centers: A View from Senior EFRC Representatives (2011 EFRC Summit, panel session)

International Nuclear Information System (INIS)

Drell, Persis; Armstrong, Neal; Carter, Emily; DePaolo, Don; Gunnoe, Brent

2011-01-01

A distinguished panel of scientists from the EFRC community provide their perspective on the importance of EFRCs for addressing critical energy needs at the 2011 EFRC Summit. Persis Drell, Director at SLAC, served as moderator. Panel members are Neal Armstrong (Director of the Center for Interface Science: Solar Electric Materials, led by the University of Arizona), Emily Carter (Co-Director of the Combustion EFRC, led by Princeton University. She is also Team Leader of the Heterogeneous Functional Materials Center, led by the University of South Carolina), Don DePaolo (Director of the Center for Nanoscale Control of Geologic CO2, led by LBNL), and Brent Gunnoe (Director of the Center for Catalytic Hydrocarbon Functionalization, led by the University of Virginia). The 2011 EFRC Summit and Forum brought together the EFRC community and science and policy leaders from universities, national laboratories, industry and government to discuss 'Science for our Nation's Energy Future.' In August 2009, the Office of Science established 46 Energy Frontier Research Centers. The EFRCs are collaborative research efforts intended to accelerate high-risk, high-reward fundamental research, the scientific basis for transformative energy technologies of the future. These Centers involve universities, national laboratories, nonprofit organizations, and for-profit firms, singly or in partnerships, selected by scientific peer review. They are funded at $2 to $5 million per year for a total planned DOE commitment of $777 million over the initial five-year award period, pending Congressional appropriations. These integrated, multi-investigator Centers are conducting fundamental research focusing on one or more of several 'grand challenges' and use-inspired 'basic research needs' recently identified in major strategic planning efforts by the scientific community. The purpose of the EFRCs is to integrate the talents and expertise of leading scientists in a setting designed to accelerate

Proceedings of the tenth annual DOE low-level waste management conference: Session 6: Closure and decommissioning

International Nuclear Information System (INIS)

1988-12-01

This document contains eight papers on various aspects of low-level radioactive waste management. Topics include: site closure; ground cover; alternate cap designs; performance monitoring of waste trenches; closure options for a mixed waste site; and guidance for environmental monitoring. Individual papers were processed separately for the data base

Radioactive waste: first report from the Environment Committee

International Nuclear Information System (INIS)

1986-01-01

In the first report of the Environment Committee of the House of Commons, session 1985/86, on radioactive waste the types and classification of wastes are described and the general management and disposal of contained wastes discussed. Health hazards from waste sources and dose limits are discussed. The role of reprocessing and its justification are discussed and recommendations made. The need to bridge the gap between the nuclear industry and the public by the publication of more information and a more open approach are stressed. The report closed with an account of government policy and regulations regarding radioactive wastes and the enforcement of such regulations. The proceedings of the committee end the report. (U.K.)

Social and economic aspects of radioactive waste disposal: considerations for institutional management

National Research Council Canada - National Science Library

National Research Council Staff; Board on Radioactive Waste Management; Commission on Physical Sciences, Mathematics, and Applications; Division on Engineering and Physical Sciences; National Research Council; National Academy of Sciences

1984-01-01

... for Institutional Management Panel on Social and Economic Aspects of Radioactive Waste Management Board on Radioactive Waste Management Commission on Physical Sciences, Mathematics, and Resources National Research Council NATIONAL ACADEMY PRESS Washington, D.C. 1984 Copyrightthe cannot be not from book, paper however, version for formatting, original authoritative ...

Waste Management in Universities and Colleges. Workshop Proceedings (Madison, Wisconsin, July 9-11, 1980).

Science.gov (United States)

Association of Physical Plant Administrators of Universities and Colleges, Washington, DC.

In response to a request from the Wisconsin Department of Natural Resources, Region V of the United States Environmental Protection Agency (EPA) sponsored a workshop on waste management in universities and colleges. It consisted of four sessions: (1) managing general university waste and regulatory concerns; (2) chemical waste management; (3)…

Greenhouse gas accounting and waste management

DEFF Research Database (Denmark)

Gentil, Emmanuel; Christensen, Thomas Højlund; Aoustin, E.

2009-01-01

Accounting of emissions of greenhouse gas (GHG) is a major focus within waste management. This paper analyses and compares the four main types of GHG accounting in waste management including their special features and approaches: the national accounting, with reference to the Intergovernmental...... specifically, the clean development mechanism (CDM) methodology, introduced to support cost-effective reduction in GHG emissions. These types of GHG accounting, in principle, have a common starting point in technical data on GHG emissions from specific waste technologies and plants, but the limited...... Panel on Climate Change (IPCC), the corporate level, as part of the annual reporting on environmental issues and social responsibility, life-cycle assessment (LCA), as an environmental basis for assessing waste management systems and technologies, and finally, the carbon trading methodology, and more...

A summary of available information on ferrocyanide tank wastes

International Nuclear Information System (INIS)

Burger, L.L.; Strachan, D.M.; Reynolds, D.A.; Schulz, W.W.

1991-10-01

Ferrocyanide wastes were generated at the Hanford site during the mid to late 1950s to make more tank space available for the storage of high level nuclear waste. The ferrocyanide process was developed as a method of removing 137 Cs from existing waste solutions and from process solutions that resulted from the recovery of valuable uranium in waste tanks. During the coarse of the research associated with the ferrocyanide process, it was discovered that ferrocyanide materials when mixed with NaNO 3 and/or NaNO 2 exploded. This chemical reactivity became an issue in the 1980s when the safety associated with the storage of ferrocyanide wastes in Hanford tanks became prominent. These safety issues heightened in the late 1980s and led to the current scrutiny of the safety associated with these wastes and the current research and waste management programs. Over the past three years, numerous explosive test have been carried out using milligram quantities of cyanide compounds. These tests provide information on the nature of possible tank reactions. On heating a mixture of ferrocyanide and nitrate or nitrite, an explosive reaction normally begins at about 240 degrees C, but may occur well below 200 degrees C in the presence of catalysts or organic compounds that may act as initiators. The energy released is highly dependent on the course of the reaction. Three attempts to model hot spots in local areas of the tanks indicate a very low probability of having a hot spot large enough and hot enough to be of concern. The main purpose of this document is to inform the members of the Tank Waste Science Panel of the background and issues associated with the ferrocyanide wastes. Hopefully, this document fulfills similar needs outside of the framework of the Tank Waste Science Panel. 50 refs., 9 figs., 7 tabs

First days of R and D in radioactive waste management

International Nuclear Information System (INIS)

1993-01-01

The first meeting of R and D in radioactive waste management was organized by ENRESA on 21,22,23 April 1993. The main objective was to disseminate the most relevant works within the 2nd R and D plan, and to establish and adequate form involved for discussion R and D radioactive waste management. (Author) The meeting was articulated in 50 sessions: I.- Low and medium radioactive wastes II.- High level radioactive wastes: activities of ENRESA III.- High level radioactive wastes: near field. IV.- Biosphere, radiological protection, behaviour evaluation V.- Dismantling and decommissioning nuclear facilities VI.- Geosphere

Role of scientific experts and communication experts at the inhabitants briefing session for the risk communication

International Nuclear Information System (INIS)

Sano, Kazumi

2012-01-01

After the accident of the Fukushima Daiichi Nuclear Power Plant, enormous amount of waste contaminated by radioactive cesium has been produced. Burned ash that contained radiocesium ( 137 Cs) more than 8,000 Bq/kg will be stored at the not-yet-located final deposit. Until the final deposit is finally constructed, however, the radioactive ash should be stored safely at temporal deposits. Inhabitants briefing sessions for locating the temporal deposits are held at many places in the east Japan. But, they met difficulty in establishing smooth communication between citizens and the administrations. In this paper, I classify the questions arose from citizens at the inhabitants briefing session at Tokatsu area, Chiba prefecture, and discuss what role could scientists and science communicators play at this session. In addition, I classified the voices of inhabitants reported in the newspapers and discuss the media bias. (author)

Post-Session Authentication

OpenAIRE

Ahmed , Naveed; Jensen , Christian ,

2012-01-01

Part 1: Full Papers; International audience; Entity authentication provides confidence in the claimed identity of a peer entity, but the manner in which this goal is achieved results in different types of authentication. An important factor in this regard is the order between authentication and the execution of the associated session. In this paper, we consider the case of post-session authentication, where parties authenticate each other at the end of their interactive session. This use of a...

Session 1984-85. Radioactive waste. Minutes of evidence, Wednesday 23 October 1985. Department of the Environment

International Nuclear Information System (INIS)

1985-01-01

The Environment Select Committee of the House of Commons received a memorandum from the Department of the Environment on radioactive waste and reprocessing, under the headings: long-term management of spent fuel; comparison of wastes arising from reprocessing and storage/disposal of spent fuel; the spent fuel assemblies; waste arising from spent-fuel management at reactor sites; reprocessing wastes; long-term storage and direct disposal of spent fuel; liquid and gaseous discharges; CEGB note on the drying-off and subsequent long term storage of spent magnox fuel. The Minister of the Environment and representatives of the Department of the Environment were examined on the subject of the memorandum. The problems of finding sites suitable for radioactive waste storage/disposal and acceptable to public opinion were discussed. (U.K.)

WIPP [Waste Isolation Pilot Plant] panel entryway seal: Numerical simulation of seal composite interaction for preliminary design evaluation

International Nuclear Information System (INIS)

Argueello, J.G.

1988-04-01

This report presents the results of a series of structural analyses performed to evaluate the structural interaction of the components of a potential two-component panel entryway seal configuration with each other and with the rock salt formation at the repository horizon of the Waste Isolation Pilot Plant. A two-dimensional axisymmetric geomechanical model is used to numerically simulate the interaction of the components of a 30.48 m (100 ft) long seal, consisting of concrete end caps and a crushed salt core, with each other and with the surrounding formation. Issues addressed in this report pertain to the consolidation of the crushed salt in terms of how much of the seal core reaches effective consolidation in the presence of the stiff concrete end caps since these could conceivably cause bridging (retardation of closure around the core) to occur. In addition, the stress field in the end caps is evaluated to determine if the concrete component maintains its integrity. The stresses induced in the surrounding formation are also evaluated to determine if the presence of the concrete component in the seal system results in a ''tightening'' of the formation around the seal. 20 refs., 43 figs., 2 tabs

Standardization of radioactive waste categories

International Nuclear Information System (INIS)

1970-01-01

A large amount of information about most aspects of radioactive waste management has been accumulated and made available to interested nations in recent years. The efficiency of this service has been somewhat hampered because the terminology used to describe the different types of radioactive waste has varied from country to country and indeed from installation to installation within a given country. This publication is the outcome of a panel meeting on Standardization of Radioactive Waste Categories. It presents a simple standard to be used as a common language between people working in the field of waste management at nuclear installations. The purpose of the standard is only to act as a practical tool for increasing efficiency in communicating, collecting and assessing technical and economical information in the common interest of all nations and the developing countries in particular. 20 refs, 1 fig., 3 tabs

Perceived risks of nuclear fuel waste disposal: trust, compensation, and public acceptance in Canada

International Nuclear Information System (INIS)

Hine, D.W.; Summers, C.

1996-01-01

AECL's recommendation to place the high-level radioactive waste in corrosion resistant containers and bury it in underground vaults several hundred metres deep in the rock of the Canadian shield is presently under federal review. If and when the disposal concept is approved by the federal review panel, a search will begin for a suitable host community. Given that siting guidelines prevent the government from unilaterally imposing the waste on a reluctant community, identifying a suitable site may represent the single greatest obstacle to successfully implementing the disposal concept. Even if the concept is approved by the review panel, it may be very difficult to find a community that is willing to accept the waste. In the US, efforts to site an underground disposal facility for high-level nuclear waste at Yucca Mountain has run into strong opposition from local residents and politicians, resulting in long delays and major cost overruns

Experimental investigation of sound absorption properties of perforated date palm fibers panel

International Nuclear Information System (INIS)

Elwaleed, A K; Nikabdullah, N; Nor, M J M; Tahir, M F M; Zulkifli, R

2013-01-01

This paper presents the sound absorption properties of a natural waste of date palm fiber perforated panel. A single layer of the date palm fibers was tested in this study for its sound absorption properties. The experimental measurements were carried out using impedance tube at the acoustic lab, Faculty of Engineering, Universiti Kebangsaan Malaysia. The experiment was conducted for the panel without air gap, with air gap and with perforated plate facing. Three air gap thicknesses of 10 mm, 20 mm and 30 mm were used between the date palm fiber sample and the rigid backing of the impedance tube. The results showed that when facing the palm date fiber sample with perforated plate the sound absorption coefficient improved at the higher and lower frequency ranges. This increase in sound absorption coincided with reduction in medium frequency absorption. However, this could be improved by using different densities or perforated plate with the date palm fiber panel.

Minimising waste in the food and drink sector: using the business club approach to facilitate training and organisational development.

Science.gov (United States)

Hyde, Katherine; Miller, Linda; Smith, Ann; Tolliday, Jo

2003-04-01

The aim of the East Anglian Waste Minimisation in the Food And Drink Industry Project was to develop waste minimisation capability in food and drink sector companies by providing a structured training programme and consultancy support to participating members of a business club. The business club forum provided the structure within which interactive training and development sessions were delivered. Expertise and assistance in implementing waste minimisation and waste management programmes was given to member companies at their sites. The project resulted in pound 1,800,000 per annum of identified savings with pound 1,100,000 of verified savings already achieved. Training and development contributed fundamentally to these project outcomes and achievements. The structured training package used three different approaches or methods. Teaching and workshop sessions were used to present interactive training on waste minimisation practice. These were supplemented by interactive 'report-back' sessions where the 'project champions' presented progress reports to the club on waste minimisation at their sites. An overview of the business club approach is described, together with an account of the successes and challenges of applying a structured training and development programme and the barriers to waste minimisation that were overcome. Training effectiveness was measured according to reaction, learning, application and impact.

Regular Formal Evaluation Sessions are Effective as Frame-of-Reference Training for Faculty Evaluators of Clerkship Medical Students.

Science.gov (United States)

Hemmer, Paul A; Dadekian, Gregory A; Terndrup, Christopher; Pangaro, Louis N; Weisbrod, Allison B; Corriere, Mark D; Rodriguez, Rechell; Short, Patricia; Kelly, William F

2015-09-01

Face-to-face formal evaluation sessions between clerkship directors and faculty can facilitate the collection of trainee performance data and provide frame-of-reference training for faculty. We hypothesized that ambulatory faculty who attended evaluation sessions at least once in an academic year (attendees) would use the Reporter-Interpreter-Manager/Educator (RIME) terminology more appropriately than faculty who did not attend evaluation sessions (non-attendees). Investigators conducted a retrospective cohort study using the narrative assessments of ambulatory internal medicine clerkship students during the 2008-2009 academic year. The study included assessments of 49 clerkship medical students, which comprised 293 individual teacher narratives. Single-teacher written and transcribed verbal comments about student performance were masked and reviewed by a panel of experts who, by consensus, (1) determined whether RIME was used, (2) counted the number of RIME utterances, and (3) assigned a grade based on the comments. Analysis included descriptive statistics and Pearson correlation coefficients. The authors reviewed 293 individual teacher narratives regarding the performance of 49 students. Attendees explicitly used RIME more frequently than non-attendees (69.8 vs. 40.4 %; p sessions used RIME terminology more frequently and provided more accurate grade recommendations than teachers who did not attend. Formal evaluation sessions may provide frame-of-reference training for the RIME framework, a method that improves the validity and reliability of workplace assessment.

Evaluation of Odor-Reducing Commercial Products for Animal Waste

OpenAIRE

Shukla, Shuchi S.

1997-01-01

Six odor-reducing commercial products were tested for their efficacy in reducing odors from dairy and swine wastes. A sensory panel method was utilized for odor evaluations, in which the panel played an important part. Comparisons between products were made for agitated and unagitated conditions and effect of storage time (three weeks in which experiments were performed). Cotton pieces tied to the mouth of the sample jars were useful in absorbing the odors. Odor-treated jars were observed and...

Efficiency Effects of Unit-based Pricing Systems and Institutional Choices of Waste Collection

NARCIS (Netherlands)

Dijkgraaf, E.; Gradus, R.H.J.M.

2015-01-01

Municipal residential waste costs are rising. Therefore, it is important to introduce measures that lower waste collection and disposal costs. Based on a large panel data set for the Netherlands we show that unit-based pricing systems are more important from a cost-minimizing point of view than the

Panel and planar experimental shear behavior of wood panels ...

African Journals Online (AJOL)

Panel shear strength along the thickness and planar shear along the length of wood panels laminated softwood oriented OSB 10 mm thick, conditioned at different moisture contents (anhydrous medium, ambient temperature and humid medium) was measured on standardized test specimens, cut in half lengthwise panel ...

Cost savings of unit-based pricing of household waste; the case of the Netherlands

NARCIS (Netherlands)

E. Dijkgraaf (Elbert); R.H.J.M. Gradus (Raymond)

2003-01-01

textabstractUsing a panel data set for Dutch municipalities we estimate effects for weight-based, bag-based, frequency-based and volume-based pricing of household waste collection. Unit-based pricing shows to be effective in reducing solid and compostable and increasing recyclable waste. Pricing has

Radioactive waste isolation in salt: peer review of the Office of Nuclear Waste Isolation's reports on preferred repository sites within the Palo Duro Basin, Texas

International Nuclear Information System (INIS)

Fenster, D.; Edgar, D.; Gonzales, S.; Domenico, P.; Harrison, W.; Engelder, T.; Tisue, M.

1984-04-01

Documents are being submitted to the Salt Repository Project Office (SRPO) of the US Department of Energy (DOE) by Battelle Memorial Institute's Office of Nuclear Waste Isolation (ONWI) to satisfy milestones of the Salt Repository Project of the Civilian Radioactive Waste Management Program. Some of these documents are being reviewed by multidisciplinary groups of peers to ensure DOE of their adequacy and credibility. Adequacy of documents refers to their ability to meet the standards of the US Nuclear Regulatory Commission, as enunciated in 10 CFR 60, and the requirements of the National Environmental Policy Act and the Nuclear Waste Policy Act of 1982. Credibility of documents refers to the validity of the assumptions, methods, and conclusions, as well as to the completeness of coverage. This report summarizes Argonne's review of ONWI's two-volume draft report entitled Identification of Preferred Sites within the Palo Duro Basin: Vol. 1 - Palo Duro Location A, and Vol. 2 - Palo Duro Location B, dated January 1984. Argonne was requested by DOE to review these documents on January 17 and 24, 1984 (see App. A). The review procedure involved obtaining written comments on the reports from three members of Argonne's core peer review staff and three extramural experts in related research areas. The peer review panel met at Argonne on February 6, 1984, and reviewer comments were integrated into this report by the review session chairman, with the assistance of Argonne's core peer review staff. All of the peer review panelists concurred in the way in which their comments were represented in this report (see App. B). A letter report and a draft of this report were sent to SRPO on February 10, 1984, and April 17, 1984, respectively. 5 references

Waste package emplacement borehole option study

International Nuclear Information System (INIS)

Streeter, W.S.

1992-03-01

This study evaluates the cost and thermal effects of various waste package emplacement configurations that differ in emplacement orientation, number of containers per borehole, and standoff distance at the potential Yucca Mountain nuclear waste repository. In this study, eight additional alternatives to the vertical and horizontal orientation options presented in the Site Characterization Plan Conceptual Design Report are considered. Typical panel layout configurations based on thermal analysis of the waste and cost estimates for design and construction, operations, and closure and decommissioning were made for each emplacement option. For the thermal analysis average waste 10 years out of reactor and the SIM code were used to determine whether the various configurations temperatures would exceed the design criteria for temperature. This study does not make a recommendation for emplacement configuration, but does provide information for comparison of alternatives

Sessions and Separability in Security Protocols

DEFF Research Database (Denmark)

Carbone, Marco; Guttman, Joshua

2013-01-01

Despite much work on sessions and session types in non- adversarial contexts, session-like behavior given an active adversary has not received an adequate definition and proof methods. We provide a syntactic property that guarantees that a protocol has session-respecting executions. Any uncomprom......Despite much work on sessions and session types in non- adversarial contexts, session-like behavior given an active adversary has not received an adequate definition and proof methods. We provide a syntactic property that guarantees that a protocol has session-respecting executions. Any...

Evaluating the technical aspects of mixed waste treatment technologies

International Nuclear Information System (INIS)

Bagaasen, L.M.; Scott, P.A.

1992-10-01

This report discusses treatment of mixed wastes which is thought to be more complicated than treatment of either hazardous or radioactive wastes. In fact, the treatment itself is no more complicated: however, the regulations that define acceptability of the final waste disposal system are significantly more entangled, and sometimes in apparent conflict. This session explores the factors that influence the choice of waste treatment technologies, and expands on some of the limitations to their application. The objective of the presentation is to describe the technical factors that influence potential treatment processes and the ramifications associated with particular selections (for example, the generation of secondary waste streams). These collectively provide a framework for making informed treatment process selections

Multiparty Asynchronous Session Types

DEFF Research Database (Denmark)

Honda, Kohei; Yoshida, Nobuko; Carbone, Marco

2016-01-01

. This work extends the foregoing theories of binary session types to multiparty, asynchronous sessions, which often arise in practical communication-centered applications. Presented as a typed calculus for mobile processes, the theory introduces a new notion of types in which interactions involving multiple......Communication is a central elements in software development. As a potential typed foundation for structured communication-centered programming, session types have been studied over the past decade for a wide range of process calculi and programming languages, focusing on binary (two-party) sessions...... peers are directly abstracted as a global scenario. Global types retain the friendly type syntax of binary session types while specifying dependencies and capturing complex causal chains of multiparty asynchronous interactions. A global type plays the role of a shared agreement among communication peers...

Optimum design of composite panel with photovoltaic-thermo module. Absorbing effect of cooling panel; Hikari netsu fukugo panel no saiteki sekkei. Reikyaku panel no kyunetsu koka

Energy Technology Data Exchange (ETDEWEB)

Sato, M; Kikuchi, S; Tani, T [Science University of Tokyo, Tokyo (Japan); Kadotani, K; Imaizumi, H [Komatsu Ltd., Tokyo (Japan)

1996-10-27

The composite panel with photovoltaic-thermo module becomes higher in energy-saving than the conventional air-conditioning system by the independent radiational heating and cooling effect obtained when the generating panel using a solar cell module is combined with the heating and cooling panel using a thermo-element module. The output of a solar cell module can be directly used because the solar cell module operates in AC. This paper reports the relation between the absorbed value and power consumption of the cooling panel, while paying attention to the cooling panel. The performance coefficient of the maximum absorbed value from an non-absorbing substance to a cooling panel is 2 to 3. Assume that the cooling panel during non-adiabatic operation is operated using a solar cell module of 800 W/m{sup 2} in solar intensity and 15% in conversion efficiency. The cooling-surface temperature difference is 12.12 K, and the maximum absorbed value of a non-absorbing substance to a cooling panel is 39.12 W/m{sup 2}. The absorbed value of the outer temperature to the cooling panel is 74.4 W/m{sup 2}, and each performance coefficient is 3.26 and 0.62. The absorbed value must be calculated for evaluation from the cooling-surface temperature difference measured directly from the cooling panel. 4 refs., 8 figs., 1 tab.

Exergy metrication of radiant panel heating and cooling with heat pumps

International Nuclear Information System (INIS)

Kilkis, Birol

2012-01-01

Highlights: ► Rational Exergy Management Model analytically relates heat pumps and radiant panels. ► Heat pumps driven by wind energy perform better with radiantpanels. ► Better CO 2 mitigation is possible with wind turbine, heat pump, radiant panel combination. ► Energy savings and thermo-mechanical performance are directly linked to CO 2 emissions. - Abstract: Radiant panels are known to be energy efficient sensible heating and cooling systems and a suitable fit for low-exergy buildings. This paper points out the little known fact that this may not necessarily be true unless their low-exergy demand is matched with low-exergy waste and alternative energy resources. In order to further investigate and metricate this condition and shed more light on this issue for different types of energy resources and energy conversion systems coupled to radiant panels, a new engineering metric was developed. Using this metric, which is based on the Rational Exergy Management Model, true potential and benefits of radiant panels coupled to ground-source heat pumps were analyzed. Results provide a new perspective in identifying the actual benefits of heat pump technology in curbing CO 2 emissions and also refer to IEA Annex 49 findings for low-exergy buildings. Case studies regarding different scenarios are compared with a base case, which comprises a radiant panel system connected to a natural gas-fired condensing boiler in heating and a grid power-driven chiller in cooling. Results show that there is a substantial CO 2 emission reduction potential if radiant panels are optimally operated with ground-source heat pumps driven by renewable energy sources, or optimally matched with combined heat and power systems, preferably running on alternative fuels.

Pollution prevention and waste minimization opportunity assessment in environmental restoration

International Nuclear Information System (INIS)

Roybal, J.A.; Willison, C.P.

1997-01-01

The Environmental Restoration (ER) Project at Sandia National Laboratories implicitly subscribed to the philosophy of pollution prevention and waste minimization. As a result of a Department of Energy (DOE) offer, Pollution Prevention Opportunity Assessments (PPOA) were conducted at two ER sites and a decontamination and Demolition (D and D) site. The purpose of one of the PPOAs was to identify pollution prevention (P2) opportunities during environmental remediation at the Classified Waste Landfill located at Sandia National Laboratories, New Mexico (SNL/NM). The remediation activities at this site are scheduled to begin in the fall of 1997. The PPOA included presentations by the team members, a tour of the site, and a brainstorming session to list the waste streams, identify P2 opportunities and rank them in order of priority. Twenty-five P2 opportunities were identified during the brainstorming session of which twenty-two opportunities were selected for further investigation. Those twenty-two opportunities are discussed in this paper. A cost benefit analysis was performed for each P2 opportunity based on the estimated waste volume, feasibility, and cost. Pollution Prevention by Design (P2D) was incorporated into the PPOA to introduce waste minimization techniques that can be used during the planning phase of restoration projects

Building the institutional capacity for managing commercial high-level radioactive waste

Energy Technology Data Exchange (ETDEWEB)

None

1982-05-01

In July 1981, the Office of Nuclear Waste Management of the Department of Energy contracted with the National Academy of Public Administration for a study of institutional issues associated with the commercial radioactive waste management program. The two major sets of issues which the Academy was asked to investigate were (1) intergovernmental relationships, how federal, state, local and Indian tribal council governments relate to each other in the planning and implementation of a waste management program, and (2) interagency relationships, how the federal agencies with major responsibilities in this public policy arena interact with each other. The objective of the study was to apply the perspectives of public administration to a difficult and controversial question - how to devise and execute an effective waste management program workable within the constraints of the federal system. To carry out this task, the Academy appointed a panel composed of individuals whose background and experience would provide the several types of knowledge essential to the effort. The findings of this panel are presented along with the executive summary. The report consists of a discussion of the search for a radioactive waste management strategy, and an analysis of the two major groups of institutional issues: (1) intergovernmental, the relationship between the three major levels of government; and (2) interagency, the relationships between the major federal agencies having responsibility for the waste management program.

Building the institutional capacity for managing commercial high-level radioactive waste

International Nuclear Information System (INIS)

1982-05-01

In July 1981, the Office of Nuclear Waste Management of the Department of Energy contracted with the National Academy of Public Administration for a study of institutional issues associated with the commercial radioactive waste management program. The two major sets of issues which the Academy was asked to investigate were (1) intergovernmental relationships, how federal, state, local and Indian tribal council governments relate to each other in the planning and implementation of a waste management program, and (2) interagency relationships, how the federal agencies with major responsibilities in this public policy arena interact with each other. The objective of the study was to apply the perspectives of public administration to a difficult and controversial question - how to devise and execute an effective waste management program workable within the constraints of the federal system. To carry out this task, the Academy appointed a panel composed of individuals whose background and experience would provide the several types of knowledge essential to the effort. The findings of this panel are presented along with the executive summary. The report consists of a discussion of the search for a radioactive waste management strategy, and an analysis of the two major groups of institutional issues: (1) intergovernmental, the relationship between the three major levels of government; and (2) interagency, the relationships between the major federal agencies having responsibility for the waste management program

Statement to the 36th session of the General Conference of the International Atomic Energy Agency 21 September 1992; Statement to the 47th session of the United Nations General Assembly 21 October 1992

International Nuclear Information System (INIS)

Blix, H.

1993-01-01

IAEA Director General, Hans Blix, in his statements to the 47th session of the United Nations General Assembly and to the 36th session of the General Conference of the IAEA, reminded that 1992 marks the fiftieth anniversary of controlled nuclear fission and the thirty-fifth anniversary of the IAEA. He specially commented on the various measures taken during the past year to strengthen the IAEA's safeguards system as a part of the challenge to reduce the risk of a further spread of nuclear weapons. He also discussed the role of the IAEA in the fields of nuclear safety, nuclear waste, transfer of technology and assistance to developing countries and the financing and management of the Agency within the UN system

KONTEC 2009. Report about the 9th International Symposium on ''Conditioning of radioactive operational and decommissioning wastes''

International Nuclear Information System (INIS)

Anon.

2009-01-01

''Kontec 2009'' was organized in Dresden on April 15-17, 2009. For the 8 th time, this established international meeting covered the subjects of ''Conditioning of Radioactive Operational and Decommissioning Wastes'' and ''Decommissioning and Dismantling of Nuclear Facilities'' and the R and D Status Report delivered by the German Federal Ministry for Education and Research on this key topic. Some 790 participants from 13 countries heard and discussed the contributions to the three-day meeting. The program of the symposium comprised plenary sessions dealing with these 4 key subjects: Disposal of Radioactive Residues from Nuclear Facilities' Operation and Decommissioning, Decommissioning and Dismantling of Nuclear Facilities, Facilities and Systems for the Conditioning of Operational and Decommissioning Wastes, Transport, Interim and Final Storage of Non-heat Generating Wastes (i.e. Konrad). The sessions were supplemented by poster sessions and selected short presentations under the heading of ''Kontec Direct.'' (orig.)

LLW Forum meeting report, May 7--9, 1997

International Nuclear Information System (INIS)

Norris, C.; Brown, H.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-05-01

The Low-Level Radioactive Waste Forum met in Chicago, Illinois, on may 7--9, 1997. Twenty-three Forum Participants, Alternate Forum Participants, and meeting designees representing 20 compacts and states participated. A report on the meeting is given under the following subtitles: New developments in states and compacts; Upgrading an existing disposal facility; Revisions to DOE Order 5820 re DOE waste management; Conference of radiation control program directors: Recent and upcoming activities; National Conference of State Legislatures' (NCSL) low-level radioactive waste working group: Recent and upcoming activities; Executive session; LLW forum business session; Public involvement and risk communication: Success at West Valley, New York; DOE low-level waste management program; impact of the International Atomic Energy Agency's convention on waste; Panel discussion: The environmental justice concept--Past, present and future; New technologies for processing and disposal of LLRW; High-level and low-level radioactive waste: A dialogue on parallels and intersections; Draft agreement re uniform application of manifesting procedures; Regulatory issues focus; LLW forum October 1997 agenda planning; Resolutions; LLW forum regulatory issues discussion group meets; and Attendance

Effects of Post-Session Wheel Running on Within-Session Changes in Operant Responding

Science.gov (United States)

Aoyama, Kenjiro

2007-01-01

This study tested the effects of post-session wheel running on within-session changes in operant responding. Lever-pressing by six rats was reinforced by a food pellet under a continuous reinforcement (CRF) schedule in 30-min sessions. Two different flavored food pellets were used as reinforcers. In the wheel conditions, 30-min operant-sessions…

CIGEO public debate. Presentation of the Citizens' Conference - Press file. Presentation of the citizens panel opinion

International Nuclear Information System (INIS)

Hermitte, Marie-Angele; Bedu, Clemence; Besnus, Francois; Brom, Jean-Marie; Grambow, Bernd; Ruedinger, Andreas; Fourniau, Jean-Michel; Bobbio, Luigi; Blatrix, Cecile

2013-01-01

After a presentation of the organisation and implementation of the Citizens' Conference, a presentation of the members of the steering committee and of the assessment committee of this conference, this document presents the opinion of the citizen panel in the framework of the public debate on the Cigeo project of deep underground disposal of radioactive wastes. This opinion notably outlines the waste issue as an inter-generational issue, comments the calendar and condition of the Cigeo project, states the panel opinion on risks which are specific to the Cigeo project, discusses the issue of recoverability and reversibility, discusses the issue of site memory, evokes the possibility of exploitation of geothermal energy, outlines the importance of health and environmental monitoring, comments opportunities for local development, and discusses cost and financing assessments. An appendix presents the different training programmes proposed during the citizens' conference

Workshop on rock mechanics issues in repository design and performance assessment

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-04-01

The Center for Nuclear Waste Regulatory Analyses organized and hosted a workshop on ``Rock Mechanics Issues in Repository Design and Performance Assessment`` on behalf its sponsor the U.S. Nuclear Regulatory Commission (NRC). This workshop was held on September 19- 20, 1994 at the Holiday Inn Crowne Plaza, Rockville, Maryland. The objectives of the workshop were to stimulate exchange of technical information among parties actively investigating rock mechanics issues relevant to the proposed high-level waste repository at Yucca Mountain and identify/confirm rock mechanics issues important to repository design and performance assessment The workshop contained three technical sessions and two panel discussions. The participants included technical and research staffs representing the NRC and the Department of Energy and their contractors, as well as researchers from the academic, commercial, and international technical communities. These proceedings include most of the technical papers presented in the technical sessions and the transcripts for the two panel discussions. Selected papers have been indexed separately for inclusion the Energy Science and Technology Database.

Meet Your Future: An Interactive Panel on Industry Careers

Science.gov (United States)

Lambert, Steven

There will be a brief presentation showing some statistics about careers in physics followed by a panel discussion. The panelists are: Pavel Kornilovich, HP Inc., Senior Technologist Erik Lucero, Google Santa Barbara, Hardware Engineer Raja Rajasekaran, Toptica-USA, Western Regional Sales & Application Manager Tiffany Santos, Western Digital, Principal Research Engineer Krysta Svore, Microsoft, Principal Researcher & Research Manager Each panelist will introduce themselves and give a brief overview of their career path. We'll then open it up to audience participation. Bring your questions about working in the private sector: daily responsibilities, work environment, how to prepare for this path, making contacts, and anything else you'd like to hear about. We look forward to an interactive and lively session.

Weight-based pricing in the collection of household waste. The Oostzaan case

International Nuclear Information System (INIS)

Linderhof, Vincent; Kooreman, Peter; Allers, Maarten; Wiersma, Doede

2001-01-01

This paper provides an empirical analysis of the effects of weight-based pricing in the collection of household waste. Using a comprehensive panel data set on all households in a Dutch municipality we estimate short-run as well as long-run price effects for the amounts of both compostable and non-recyclable household waste. We find significant and sizeable price effects, with the elasticity for compostable waste being four times as large as the elasticity for non-recyclable waste. Long-run elasticities are about 30% larger than short-run elasticities

Training Sessions and Materials Present Ways to Improve System Efficiency: OIT Technical Assistance Fact Sheet: Training

International Nuclear Information System (INIS)

Ericksen, E.

1999-01-01

Interested in learning about innovative ways to improve the efficiency of your plant's steam, electric motor, and compressed air systems? This US Department of Energy Office of Industrial Technologies fact sheet offers information regarding training sessions, teleconferences, and various training materials to teach you and your company ways to reduce energy use, save money, and reduce waste and pollution through system optimization

Photovoltaic solar panels of crystalline silicon: characterization and separation

International Nuclear Information System (INIS)

Diasa, P.R.; Benevita, M.G.; Veita, H.M.

2014-01-01

The search for alternative power generation sources has been intensified in recent years. One of these alternatives is solar energy, since it is a virtually inexhaustible source and generates relatively small environmental impact compared to other traditional generation sources. The collection of solar energy and its conversion into thermal or electrical energy is only possible through the use of photovoltaic panels. These panels have a limited lifespan and will eventually be replaced by new ones. Thus, in the near future, large amounts of solar modules can be discarded as waste electronics. In order to retrieve important raw materials, reducing production costs and environmental impacts, recycling such materials is important. In this paper, photovoltaic module components were characterized through visual inspection, FRX, EDS and AAS. The glass was identified as ordinary glass (soda-lime glass), which allows reuse without any previous treatment and the metallic filaments were identified as tin- lead coated copper. (author)

Effective medical treatment of opiate addiction. National Consensus Development Panel on Effective Medical Treatment of Opiate Addiction.

Science.gov (United States)

1998-12-09

To provide clinicians, patients, and the general public with a responsible assessment of the effective approaches to treat opiate dependence. A nonfederal, nonadvocate, 12-member panel representing the fields of psychology, psychiatry, behavioral medicine, family medicine, drug abuse, epidemiology, and the public. In addition, 25 experts from these same fields presented data to the panel and a conference audience of 600. Presentations and discussions were divided into 3 phases over 2 1/2 days: (1) presentations by investigators working in the areas relevant to the consensus questions during a 2-day public session; (2) questions and statements from conference attendees during open discussion periods that are part of the public session; and (3) closed deliberations by the panel during the remainder of the second day and morning of a third day. The conference was organized and supported by the Office of Medical Applications of Research, National Institutes of Health. The literature was searched through MEDLINE and other National Library of Medicine and online databases from January 1994 through September 1997 and an extensive bibliography of 941 references was provided to the panel and the conference audience. Experts prepared abstracts for their presentations as speakers at the conference with relevant citations from the literature. Scientific evidence was given precedence over clinical anecdotal experience. The panel, answering predefined questions, developed its conclusions based on the scientific evidence presented in open forum and the scientific literature. The panel composed a draft statement that was read in its entirety and circulated to the experts and the audience for comment. Thereafter, the panel resolved conflicting recommendations and released a revised statement at the end of the conference. The panel finalized the revisions within a few weeks after the conference. The draft statement was made available on the World Wide Web immediately following its

First Doctoral student assembly and poster session at CERN

CERN Multimedia

2010-01-01

Presently, 130 doctoral students at CERN do their research on “technical” subjects such as magnets and cryogenics, beam and detector physics, computing and vacuum, among others.   Student present  their scientific achievements at the first doctoral student assembly. To present their scientific achievements and to bring together the students with CERN supervisors and CERN’s management was the main objective of the first doctoral student assembly and poster session, held June 30. The photograph shows about half of those who presented posters, all in their second year of assignment, and ready to attach their work to the panels. Another aim of the assembly was to discuss the outcome of the anonymous questionnaire and to gain feedback for the improvement of the doctoral student program. While there is vast overall satisfaction, improvements should aim at strengthening the links between students, CERN supervisors, and university professors. With 24 posters prese...

Uncertainty and sensitivity analyses for gas and brine migration at the Waste Isolation Pilot Plant, May 1992

International Nuclear Information System (INIS)

Helton, J.C.; Bean, J.E.; Butcher, B.M.; Garner, J.W.; Vaughn, P.; Schreiber, J.D.; Swift, P.N.

1993-08-01

Uncertainty and sensitivity analysis techniques based on Latin hypercube sampling, partial correlation analysis, stepwise regression analysis and examination of scatterplots are used in conjunction with the BRAGFLO model to examine two phase flow (i.e., gas and brine) at the Waste Isolation Pilot Plant (WIPP), which is being developed by the US Department of Energy as a disposal facility for transuranic waste. The analyses consider either a single waste panel or the entire repository in conjunction with the following cases: (1) fully consolidated shaft, (2) system of shaft seals with panel seals, and (3) single shaft seal without panel seals. The purpose of this analysis is to develop insights on factors that are potentially important in showing compliance with applicable regulations of the US Environmental Protection Agency (i.e., 40 CFR 191, Subpart B; 40 CFR 268). The primary topics investigated are (1) gas production due to corrosion of steel, (2) gas production due to microbial degradation of cellulosics, (3) gas migration into anhydrite marker beds in the Salado Formation, (4) gas migration through a system of shaft seals to overlying strata, and (5) gas migration through a single shaft seal to overlying strata. Important variables identified in the analyses include initial brine saturation of the waste, stoichiometric terms for corrosion of steel and microbial degradation of cellulosics, gas barrier pressure in the anhydrite marker beds, shaft seal permeability, and panel seal permeability

Physical and mechanical properties of degraded waste surrogate material

International Nuclear Information System (INIS)

Hansen, F.D.; Mellegard, K.D.

1998-03-01

This paper discusses rock mechanics testing of surrogate materials to provide failure criteria for compacted, degraded nuclear waste. This daunting proposition was approached by first assembling all known parameters such as the initial waste inventory and rock mechanics response of the underground setting after the waste is stored. Conservative assumptions allowing for extensive degradation processes helped quantify the lowest possible strength conditions of the future state of the waste. In the larger conceptual setting, computations involve degraded waste behavior in transient pressure gradients as gas exits the waste horizon into a wellbore. Therefore, a defensible evaluation of tensile strength is paramount for successful analyses and intentionally provided maximal failed volumes. The very conservative approach assumes rampant degradation to define waste surrogate composition. Specimens prepared from derivative degradation product were consolidated into simple geometries for rock mechanics testing. Tensile strength thus derived helped convince a skeptical peer review panel that drilling into the Waste Isolation Pilot Plant (WIPP) would not likely expel appreciable solids via the drill string

The third session of the United Nations Commission on Sustainable Development

International Nuclear Information System (INIS)

Guerrero, Juan Carlos

1996-01-01

Between the 11 and April of 1995, 28 almost three years later of the summit of the earth, representatives of countless countries and non government organizations (ONG) to carry out the third session of the Commission of Sustainable Development (CSD); in her were shared and they evaluated the different national experiences once again in the implementation of the program 21. The third session of the CSD began its work with two discussions in panel. The first; about the resources and financial mechanisms.; and the second; on regional matters. Then were carried out general debates on the advances in the execution of the program 21 and the drafts of the different recommendations were discussed adopted in three discussion groups: the group to that treated the chapters 2, 3, 4, 5 and 33 of the program 21; the group b that discussed the chapters 8, 34, 35 and 40; and the group c (regional matters) that embraced the chapters 10, 11, 12, 13, 14, 15 and 21 of the program 21. Two days they were devoted to the presentation of national strategies for the sustainable development and of national experiences in the administration of the earth and the sustainable agriculture that showed local advances in the implementation of the program 21

Nuclear Waste Issues. Hearings before the Subcommittee on Energy and Power of the Committee on Energy and Commerce, US House of Representatives, One Hundredth Congress, First Session, on H.R. 2888 and H.R. 2967, June 11, 1987

International Nuclear Information System (INIS)

Anon.

1987-01-01

Proceedings of the hearings before the Subcommittee on Energy and Power of the Committee on Energy and Commerce held on two separate dates as the first sessions on bills H.R. 2888 and H.R. 2967 are recorded here. These bills would suspend certain activities of the Department of Energy (DOE) under the Nuclear Waste Policy Act of 1982 and would establish a nuclear waste policy review commission and an office of the nuclear waste negotiator. The hearings on 11 June 1987 examined the DOE's proposal to build a monitored retrievable storage facility (MRS) in Tennessee on the site of the Clinch Breeder Reactor. The General Accounting Office has questioned the adequacy of the DOE's study that recommended building the MRS. Testimony was presented by representatives of the American Nuclear Council; Community and Economic Development Division, General Accounting Office; Wisconsin Radioactive Waste Review Board; Washington Nuclear Waste Board; Sierra Club; Department of Health and Environment, State of Tennessee; Texas Nuclear Waste Programs Office; the Nuclear Regulatory Commission and the DOE. The Governor of Washington, Hon. Marilyn Lloyd, and Hon. Bart Gordon presented testimony. The concerns of the testimony were that the DOE was not ready to build the MRS - not enough study had been done to merit spending hugh amounts of money. Testimony on the two bills was not very supportive of the bills as they had been sponsored

International Seminar on Nuclear War and Planetary Emergencies : 46th Session : The Role of Science in the Third Millennium

CERN Document Server

2014-01-01

Proceedings of the 46th Session of the International Seminars on Nuclear War and Planetary Emergencies held in "E. Majorana" Centre for Scientific Culture, Erice, Sicily. This Seminar has again gathered, in 2013, over 100 scientists from 43 countries in an interdisciplinary effort that has been going on for the last 32 years, to examine and analyze planetary problems which had been followed up, all year long, by the World Federation of Scientists' Permanent Monitoring Panels.

Inventory of contaminants in waste wood; Inventering av foeroreningar i returtrae

Energy Technology Data Exchange (ETDEWEB)

Jermer, Joeran; Ekvall, Annika; Tullin, Claes [Swedish National Testing and Research Inst., Boraas (Sweden)

2001-03-01

Waste wood is increasingly used as fuel in Sweden. It is of Swedish origin as well as imported, mainly from Germany and the Netherlands. The waste wood is contaminated by e.g. paint and wood preservatives and objects of metal, glass, plastics etc. The contaminants may cause technical problems such as deposits and corrosion as well as plugging of air openings. The present study has focussed on potential contaminants in waste wood that could cause problems of technical as well as environmental nature. The major chemical contaminants are surface treatments (paints etc) and wood preservatives. The surface treatments contribute in particular to contaminants of zinc and lead. In some cases zinc has been found to cause severe deposits in the furnaces. Surface treatments also contribute to increased levels of sodium, chlorine, sulphur and nitrogen. Preservative-treated wood is the most important source of increased levels of copper, chromium and arsenic in the waste wood. Waste wood imported from Germany contains less arsenic but the same amount of copper and chromium as Swedish waste wood. The contents of mercury in German waste wood can be expected to be higher than in waste wood of Swedish origin. The fraction consisting of wood-based panels is comparably free from contaminants but as a result of the high contents of adhesives wood-based panels contribute to a higher proportion of nitrogen in waste wood than in forest residues. A great number of non-wood compounds (such as plastics and metals) do also contaminate waste wood. By careful and selective demolition and various sorting procedures most non-wood compounds will be separated from the waste wood. Waste sorting analyses carried out indicate that the waste wood contains approximately 1% non-wood compounds, mainly plastic and metal compounds, glass, dirt, concrete, bricks and gypsum. This may seem to be a small proportion, but if large amounts of waste wood are incinerated the non-wood compounds will inevitably cause

Proceedings of the sixth annual Participants' Information Meeting DOE Low-Level Waste Management Program

International Nuclear Information System (INIS)

1984-12-01

Sessions were held on disposal technology, characteristics and treatment of low-level waste, environmental aspects and performance prediction, predicting source terms for low-level wastes (LLW), performance assessment for LLW disposal facilities, and approaches to LLW facility siting and characteristics. Fifty-six papers were indexed separately

Session Types at the Mirror

Directory of Open Access Journals (Sweden)

Luca Padovani

2009-12-01

Full Text Available We (redefine session types as projections of process behaviors with respect to the communication channels they use. In this setting, we give session types a semantics based on fair testing. The outcome is a unified theory of behavioral types that shares common aspects with conversation types and that encompass features of both dyadic and multi-party session types. The point of view we provide sheds light on the nature of session types and gives us a chance to reason about them in a framework where every notion, from well-typedness to the subtyping relation between session types, is semantically -rather than syntactically- grounded.

Comprehensive metabolic panel

Science.gov (United States)

Metabolic panel - comprehensive; Chem-20; SMA20; Sequential multi-channel analysis with computer-20; SMAC20; Metabolic panel 20 ... Chernecky CC, Berger BJ. Comprehensive metabolic panel (CMP) - blood. In: ... Tests and Diagnostic Procedures . 6th ed. St Louis, MO: ...

Noise Reduction in Double‿Panel Structures by Cavity and Panel Resonance Control

NARCIS (Netherlands)

Ho, J.; Berkhoff, Arthur P.

2011-01-01

This paper presents an investigation of the cavity and the panel resonance control in a double‿panel structure. The double‿panel structure, which consists of two panels with air in the gap, is widely adopted in many applications such as aerospace due to its light weight and effective

Noise reduction in double-panel structures by cavity and panel resonance control

NARCIS (Netherlands)

Ho, J.-H.; Berkhoff, A.P

2011-01-01

This paper presents an investigation of the cavity and the panel resonance control in a double‐panel structure. The double‐panel structure, which consists of two panels with air in the gap, is widely adopted in many applications such as aerospace due to its light weight and effective

Modeling and low-level waste management: an interagency workshop

Energy Technology Data Exchange (ETDEWEB)

Little, C.A.; Stratton, L.E. (comps.)

1980-01-01

The interagency workshop on Modeling and Low-Level Waste Management was held on December 1-4, 1980 in Denver, Colorado. Twenty papers were presented at this meeting which consisted of three sessions. First, each agency presented its point of view concerning modeling and the need for models in low-level radioactive waste applications. Second, a larger group of more technical papers was presented by persons actively involved in model development or applications. Last of all, four workshops were held to attempt to reach a consensus among participants regarding numerous waste modeling topics. Abstracts are provided for the papers presented at this workshop.

Modeling and low-level waste management: an interagency workshop

International Nuclear Information System (INIS)

Little, C.A.; Stratton, L.E.

1980-01-01

The interagency workshop on Modeling and Low-Level Waste Management was held on December 1-4, 1980 in Denver, Colorado. Twenty papers were presented at this meeting which consisted of three sessions. First, each agency presented its point of view concerning modeling and the need for models in low-level radioactive waste applications. Second, a larger group of more technical papers was presented by persons actively involved in model development or applications. Last of all, four workshops were held to attempt to reach a consensus among participants regarding numerous waste modeling topics. Abstracts are provided for the papers presented at this workshop

PERBANDINGAN UNJUK KERJA ANTARA PANEL SEL SURYA BERPENJEJAK DENGAN PANEL SEL SURYA DIAM

Directory of Open Access Journals (Sweden)

Syafaruddin Ch

2010-07-01

Full Text Available The ability to produce electrical energy at Solar Power Plant  is highly dependent on the magnitude and duration of sun exposure on the solar cell panels. The movement of the sun from east to west that periodicity in every day is a problem at  the  optimization generation of electricity at  Solar Power Plant   if using solar panel that motionless. This is because the solar cell panel can not catch the maximum sun exposure. To solve the above problem then designed a solar cell panel  tracker  capable of follo-wing the movements of the sun. Then conducted a test to see the performance of solar cell pa-nel  tracker  and compare it with the performance of solar cell panel was motionless. The testing doing along 6 days, with way to irradiate the panel of solar cells  tracker  and panels of solar cell motionless with sun exposure  along a  full day. Then the electric current generated each panel were recorded. The comparison of current then generating comparison of electric power delivery. The result show that the solar cell panel  tracker  produce the average current is 2.19 A whereas solar-cell panel still 1.97 A.  This result   indicate that average power for solar cell panel  tracker  39.41 W while for solar cell panel that motionless is  35.46 W. These results indicate that the performance of solar cell panel  tracker  better than  solar cell panel motionless.

Noise Reduction in Double‿Panel Structures by Cavity and Panel Resonance Control

OpenAIRE

Ho, J.; Berkhoff, Arthur P.

2011-01-01

This paper presents an investigation of the cavity and the panel resonance control in a double‿panel structure. The double‿panel structure, which consists of two panels with air in the gap, is widely adopted in many applications such as aerospace due to its light weight and effective transmission‿loss at high frequency. However, the resonance of the cavity and the poor transmission‿loss at low frequency limit its noise control performance. Applying active control forces on the panels or utili...

Summary: Hadron dynamics sessions

International Nuclear Information System (INIS)

Carroll, A.S.; Londergan, J.T.

1993-01-01

Four sessions on Hadron Dynamics were organized at this Workshop. The first topic, QCD Exclusive Reactions and Color Transparency, featured talks by Ralston, Heppelman and Strikman; the second, QCD and Inclusive Reactions had talks by Garvey, Speth and Kisslinger. The third dynamics session, Medium Modification of Elementary Interactions had contributions from Kopeliovich, Alves and Gyulassy; the fourth session Pre-QCD Dynamics and Scattering, had talks by Harris, Myhrer and Brown. An additional joint Spectroscopy/Dynamics session featured talks by Zumbro, Johnson and McClelland. These contributions are reviewed briefly in this summary. Two additional joint sessions between Dynamics and η physics are reviewed by the organizers of the Eta sessions. In such a brief review there is no way the authors can adequately summarize the details of the physics presented here. As a result, they concentrate only on brief impressionistic sketches of the physics topics discussed and their interrelations. They include no bibliography in this summary, but simply refer to the talks given in more detail in the Workshop proceedings. They focus on topics which were common to several presentations in these sessions. First, nuclear and particle descriptions of phenomena are now clearly converging, in both a qualitative and quantitative sense; they show several examples of this convergence. Second, an important issue in hadron dynamics is the extent to which elementary interactions are modified in nuclei at high energies and/or densities, and they illustrate some of these medium effects. Finally, they focus on those dynamical issues where hadron facilities can make an important, or even a unique, contribution to the knowledge of particle and nuclear physics

Proceedings of conference on public policy issues in nuclear waste management

Energy Technology Data Exchange (ETDEWEB)

1976-01-01

This conference was designed to provide a public forum in which to identify and discuss the legal, institutional, social, environmental, and other public policy issues relating to nuclear waste management. This volume is a comprehensive synthesis of the speeches, papers, and discussions during the plenary and luncheon sessions. Preliminary goals are proposed for nuclear waste management. Separate abstracts were prepared for the ten papers. (DLC)

Radioactive Waste Management - Community Policy and Research Initiatives. The sixth international conference on the management and disposal of radioactive waste - Euradwaste '04

Energy Technology Data Exchange (ETDEWEB)

Forsstroem, Hans [Research Directorate Energy, Nuclear Fission and Radiation Protection, European Commission, MO-75 5/37, 200 avenue de la Loi, B-1049 Brussels (Belgium); Ruiz, P Fernandez [DG Research, Energy, Consejo de Seguridad Nuclear, CSN, C/ Justo Dorado, 11, E-28040 Madrid (Spain)

2004-07-01

The sixth international conference on the management and disposal of radioactive waste organized be European Commission, held on 29-31 March 2004 in Luxembourg aimed to cover the following objectives: - To present EC policy in waste management, in particular the proposed 'Directive on the Management of Spent Nuclear Fuel and Radioactive Waste' and to discuss relating issues such as the effect on national programmes, site selection, EU added value, the case for EU safety standards, and various socio-political aspects; - To highlight the main results of the Fifth Framework Programme (FP5) of EURATOM for 'Nuclear Energy, Fission Research and Training Activities' in the field of waste in spent fuel management and disposal, and partitioning and transmutation; - To present examples of activities under FP5 and to discuss further research European integration through FP6. The program was divided into two main groups: 1. 'Community Policy and Socio-Political Aspects' which included sessions on community policy initiatives, disposal option, common safety standards and public involvement and acceptance; 2. 'Community Research Activities - FP5' which included sessions on partitioning and transmutation, geological disposal and research networking. There were 29 oral presentations and 36 poster presentations which, for the latter, allowed detailed presentations of the results of the EU-funded research projects. The conference was attended by some 240 participants from 27 countries.

Paneling architectural freeform surfaces

KAUST Repository

Eigensatz, Michael

2010-07-25

The emergence of large-scale freeform shapes in architecture poses big challenges to the fabrication of such structures. A key problem is the approximation of the design surface by a union of patches, so-called panels, that can be manufactured with a selected technology at reasonable cost, while meeting the design intent and achieving the desired aesthetic quality of panel layout and surface smoothness. The production of curved panels is mostly based on molds. Since the cost of mold fabrication often dominates the panel cost, there is strong incentive to use the same mold for multiple panels. We cast the major practical requirements for architectural surface paneling, including mold reuse, into a global optimization framework that interleaves discrete and continuous optimization steps to minimize production cost while meeting user-specified quality constraints. The search space for optimization is mainly generated through controlled deviation from the design surface and tolerances on positional and normal continuity between neighboring panels. A novel 6-dimensional metric space allows us to quickly compute approximate inter-panel distances, which dramatically improves the performance of the optimization and enables the handling of complex arrangements with thousands of panels. The practical relevance of our system is demonstrated by paneling solutions for real, cutting-edge architectural freeform design projects.

Paneling architectural freeform surfaces

KAUST Repository

Eigensatz, Michael

2010-07-26

The emergence of large-scale freeform shapes in architecture poses big challenges to the fabrication of such structures. A key problem is the approximation of the design surface by a union of patches, socalled panels, that can be manufactured with a selected technology at reasonable cost, while meeting the design intent and achieving the desired aesthetic quality of panel layout and surface smoothness. The production of curved panels is mostly based on molds. Since the cost of mold fabrication often dominates the panel cost, there is strong incentive to use the same mold for multiple panels. We cast the major practical requirements for architectural surface paneling, including mold reuse, into a global optimization framework that interleaves discrete and continuous optimization steps to minimize production cost while meeting user-specified quality constraints. The search space for optimization is mainly generated through controlled deviation from the design surface and tolerances on positional and normal continuity between neighboring panels. A novel 6-dimensional metric space allows us to quickly compute approximate inter-panel distances, which dramatically improves the performance of the optimization and enables the handling of complex arrangements with thousands of panels. The practical relevance of our system is demonstrated by paneling solutions for real, cutting-edge architectural freeform design projects. © 2010 ACM.

Fluorescent lamp and ballast disposal-efficiency and the environment: Panel discussion

Energy Technology Data Exchange (ETDEWEB)

Bleasby, P.

1996-01-01

This panel discussion looked at the present state of problems related to the disposal of fluorescent lamps and ballasts. EPA has not issued a ruling defining what is to be done, and as a result different areas of the country, and different users are treating the products differently. The authors review the history of the problem, where the environmental concerns are, possible alternatives for disposal, be it landfill, recycling, incineration, or treatment as hazardous wastes, and policy concerns with regard to this issue.

ERM 593 Applied Project_Guidance for Reviewing and Approving a Waste Stream Profile in the Waste Compliance and Tracking System_Final_05-05-15

Energy Technology Data Exchange (ETDEWEB)

Elicio, Andy U. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-05-05

My ERM 593 applied project will provide guidance for the Los Alamos National Laboratory Waste Stream Profile reviewer (i.e. RCRA reviewer) in regards to Reviewing and Approving a Waste Stream Profile in the Waste Compliance and Tracking System. The Waste Compliance and Tracking system is called WCATS. WCATS is a web-based application that “supports the generation, characterization, processing and shipment of LANL radioactive, hazardous, and industrial waste.” The LANL generator must characterize their waste via electronically by filling out a waste stream profile (WSP) in WCATS. Once this process is completed, the designated waste management coordinator (WMC) will perform a review of the waste stream profile to ensure the generator has completed their waste stream characterization in accordance with applicable state, federal and LANL directives particularly P930-1, “LANL Waste Acceptance Criteria,” and the “Waste Compliance and Tracking System User's Manual, MAN-5004, R2,” as applicable. My guidance/applied project will describe the purpose, scope, acronyms, definitions, responsibilities, assumptions and guidance for the WSP reviewer as it pertains to each panel and subpanel of a waste stream profile.

WIPP supplementary roof support system, Room 1, Panel 1: Geotechnical field data analysis bi-annual report

International Nuclear Information System (INIS)

1992-01-01

In June 1991, Waste Isolation Division (WID) initiated the design effort to develop a supplementary roof support system to extend the life of Room 1, Panel 1, to allow successful completion of the bin-scale test program. A number of potential options for ground control were considered leading to the finalization of the currently installed roof support system. This highly instrumented system is ''state of the art'' for mine ground control and will provide extensive geotechnical data. The system is an innovative blend of several standard techniques and incorporates five of the suggestions made by the Geotechnical Panel in its report of June 1991, on the effective life of Rooms in Panel 1. The design was subjected to an exhaustive scrutiny by two formal Design Review Panels and was approved based on reviewed design documents, on-site observations at the WIPP underground facility, and detailed discussions with members of the design team. The original requirement was to have only a section of the room completed in October in preparation for first waste receipt. This goal was met and the relatively complex installation in the entire room was completed in December 1991. The Support System, with all its instrumentation, is now fully operational and generating geotechnical data. Examination of extensometer, closure and load cell data indicate that Room support is performing within the design parameters. All the anchors were initially loaded to approximately 445 kN (1000 lbs). The results of load cell monitoring indicates a steady increase of load on the rock bolts. The anchors installed near the room centerline have shown the greatest increase with the outermost anchors showing little or no load

Implementation of a novel population panel management curriculum among interprofessional health care trainees.

Science.gov (United States)

Kaminetzky, Catherine P; Beste, Lauren A; Poppe, Anne P; Doan, Daniel B; Mun, Howard K; Woods, Nancy Fugate; Wipf, Joyce E

2017-12-22

Gaps in chronic disease management have led to calls for novel methods of interprofessional, team-based care. Population panel management (PPM), the process of continuous quality improvement across groups of patients, is rarely included in health professions training for physicians, nurses, or pharmacists. The feasibility and acceptance of such training across different healthcare professions is unknown. We developed and implemented a novel, interprofessional PPM curriculum targeted to diverse health professions trainees. The curriculum was implemented annually among internal medicine residents, nurse practitioner students and residents, and pharmacy residents co-located in a large, academic primary care site. Small groups of interprofessional trainees participated in supervised quarterly seminars focusing on chronic disease management (e.g., diabetes mellitus, hypertension, or chronic obstructive pulmonary disease) or processes of care (e.g., emergency department utilization for nonacute conditions or chronic opioid management). Following brief didactic presentations, trainees self-assessed their clinic performance using patient-level chart review, presented individual cases to interprofessional staff and faculty, and implemented subsequent feedback with their clinic team. We report data from 2011 to 2015. Program evaluation included post-session participant surveys regarding attitudes, knowledge and confidence towards PPM, ability to identify patients for referral to interprofessional team members, and major learning points from the session. Directed content analysis was performed on an open-ended survey question. Trainees (n = 168) completed 122 evaluation assessments. Trainees overwhelmingly reported increased confidence in using PPM and increased knowledge about managing their patient panel. Trainees reported improved ability to identify patients who would benefit from multidisciplinary care or referral to another team member. Directed content analysis

Expert Panel Elicitation of Seismicity Following Glaciation in Sweden

International Nuclear Information System (INIS)

Hora, Stephen; Jensen, Mikael

2005-12-01

The Swedish Radiation Protection Authority, the Swedish Nuclear Power Inspectorate and the Swedish Nuclear Fuel and Waste Management Company have jointly carried out a project on expert panel elicitation on the issue of glacial induced Swedish earthquakes. Following a broad nomination procedure, 5 experts were chosen by a selection committee of 4 professors within Earth sciences disciplines. The 5 experts presented judgments about the frequency of earthquakes greater the magnitude 6 within 10 km for two Swedish sites, Oskarshamn and Forsmark, in connection with a glaciation cycle. The experts' median value vas 0,1 earthquakes for one glaciation cycle

Expert Panel Elicitation of Seismicity Following Glaciation in Sweden

Energy Technology Data Exchange (ETDEWEB)

Hora, Stephen; Jensen, Mikael (eds.)

2005-12-15

The Swedish Radiation Protection Authority, the Swedish Nuclear Power Inspectorate and the Swedish Nuclear Fuel and Waste Management Company have jointly carried out a project on expert panel elicitation on the issue of glacial induced Swedish earthquakes. Following a broad nomination procedure, 5 experts were chosen by a selection committee of 4 professors within Earth sciences disciplines. The 5 experts presented judgments about the frequency of earthquakes greater the magnitude 6 within 10 km for two Swedish sites, Oskarshamn and Forsmark, in connection with a glaciation cycle. The experts' median value vas 0,1 earthquakes for one glaciation cycle.

Panel 5: Microbiology and Immunology Panel

Science.gov (United States)

Murphy, Timothy F.; Chonmaitree, Tasnee; Barenkamp, Stephen; Kyd, Jennelle; Nokso-Koivisto, Johanna; Patel, Janak A.; Heikkinen, Terho; Yamanaka, Noboru; Ogra, Pearay; Swords, W. Edward; Sih, Tania; Pettigrew, Melinda M.

2014-01-01

Objective The objective is to perform a comprehensive review of the literature from January 2007 through June 2011 on the virology, bacteriology, and immunology related to otitis media. Data Sources PubMed database of the National Library of Medicine. Review Methods Three subpanels with co-chairs comprising experts in the virology, bacteriology, and immunology of otitis media were formed. Each of the panels reviewed the literature in their respective fields and wrote draft reviews. The reviews were shared with all panel members, and a second draft was created. The entire panel met at the 10th International Symposium on Recent Advances in Otitis Media in June 2011 and discussed the review and refined the content further. A final draft was created, circulated, and approved by the panel. Conclusion Excellent progress has been made in the past 4 years in advancing an understanding of the microbiology and immunology of otitis media. Advances include laboratory-based basic studies, cell-based assays, work in animal models, and clinical studies. Implications for Practice The advances of the past 4 years formed the basis of a series of short-term and long-term research goals in an effort to guide the field. Accomplishing these goals will provide opportunities for the development of novel interventions, including new ways to better treat and prevent otitis media. PMID:23536533

Proceedings of the fourth annual participants' information meeting, DOE Low-Level Waste Management Program

International Nuclear Information System (INIS)

Large, D.E.; Mezga, L.J.; Stratton, L.E.; Rose, R.R.

1982-10-01

The Fourth Annual Participants' Information Meeting of the Department of Energy Low-Level Waste Management Program was held in Denver, Colorado, August 31 to September 2, 1982. The purpose of the meeting was to report and evaluate technology development funded by the program and to examine mechanisms for technology transfer. The meeting consisted of an introductory plenary session, followed by two concurrent overview sessions and then six concurrent technical sessions. There were two group meetings to review the findings of the technical sessions. The meeting concluded with a plenary summary session in which the major findings of the meeting were addressed. All papers have been abstracted and indexed for the Energy Data Base

Proceedings of the tenth annual DOE low-level waste management conference: Session 2: Site performance assessment

International Nuclear Information System (INIS)

1988-12-01

This document contains twelve papers on various aspects of low-level radioactive waste management. Topics of this volume include: performance assessment methodology; remedial action alternatives; site selection and site characterization procedures; intruder scenarios; sensitivity analysis procedures; mathematical models for mixed waste environmental transport; and risk assessment methodology. Individual papers were processed separately for the database

Public reactions to nuclear waste: Citizens' views of repository siting

International Nuclear Information System (INIS)

Rosa, E.A.

1993-01-01

This book presents revised and updated papers from a panel of social scientists, at the 1989 AAAS meetings, that examined the public's reactions to nuclear waste disposal and the repository siting process. The papers report the results of original empirical research on citizens' views of nuclear waste repository siting. Topics covered include the following: content analysis of public testimony; sources of public concern about nuclear waste disposal in Texas agricultural communities; local attitudes toward high-level waste repository at Hanford; perceived risk and attitudes toward nuclear wastes; attitudes of Nevada urban residents toward a nuclear waste repository; attitudes of rural community residents toward a nuclear waste respository. An introductory chapter provides background and context, and a concluding chapter summarizes the implications of the reports. Two additional chapters cover important features of high-level waste disposal: long term trends in public attitudes toward nuclear energy and nuclear waste policy and assessment of the effects on the Los Vegas convention business if a high-level nuclear waste depository were sited in Nevada

Radioactive waste legislation. Hearings before the Subcommittee on Energy and the Environment of the Committee on Interior and Insular Affairs, House of Representatives, Ninety-Seventh Congress, First Session on H.R. 1993; H.R. 2800; H.R. 2840; H.R. 2881; H.R. 3809, June 23 and 25; July 9, 1981

International Nuclear Information System (INIS)

Anon.

1981-01-01

This three-day hearing was held to consider five bills on radioactive waste, set priorities for a repository construction program, consider an administration proposal to develop a small-scale test facility for deep permanent storage of high-level wastes, and determine what role the public and private sectors should assume. The hearing record includes the text of H.R. 1993, H.R. 2800, H.R. 2840, H.R. 2881, and H.R. 3809; the statements of 10 witnesses and two panels; and three appendices with additional material submitted for the record

Comparisons between various cavity and panel noise reduction control in double-panel structures

NARCIS (Netherlands)

Ho, J.H.; Kalverboer, J.; Berkhoff, A.P.

2012-01-01

This paper presents comparisons between various panel and cavity resonance control methods to reduce the transmitted sound in a double-panel structure. The double-panel, which consists of two panels with air in the gap, has the advantages of low weight and effective transmission-loss at high

Report of the nineteenth session, Athens, 8-12 May 1989

International Nuclear Information System (INIS)

1989-01-01

The Joint Group of Experts on the Scientific Aspects of Marine Pollution (GESAMP) held its nineteenth session at UNEP's Co-ordinating Unit of the Mediterranean Action Plan in Athens, from 8 to 12 May 1989. The following subjects were discussed at the meeting: Review of the potentially harmful substances (carcinogenic, mutagenic and teratogenic substances; chlorinated hydrocarbons; oil and oil spill dispersants and chemicals), interchange of pollutants between the atmosphere and the oceans, coastal modelling, state of the marine environment and long-term ecological consequences of low-level contamination of the marine environment. The future works in marine environmental protection and management as well as assessment and regulation of waste disposal in the marine environment were also planned

Proceedings of the tenth annual DOE low-level waste management conference: Session 2: Site performance assessment

Energy Technology Data Exchange (ETDEWEB)

1988-12-01

This document contains twelve papers on various aspects of low-level radioactive waste management. Topics of this volume include: performance assessment methodology; remedial action alternatives; site selection and site characterization procedures; intruder scenarios; sensitivity analysis procedures; mathematical models for mixed waste environmental transport; and risk assessment methodology. Individual papers were processed separately for the database. (TEM)

Proceedings of the 1996 international conference on deep geological disposal of radioactive waste

International Nuclear Information System (INIS)

1996-01-01

The 1996 September International Conference on Deep Geological Disposal of Radioactive Waste was held in Winnipeg, Canada. Speakers from many countries that have or are developing geological disposal technologies presented the current research and implementation strategies for the deep geological disposal of radioactive wastes. Special sessions focused on International Trends in Geological Disposal and Views on Confidence Building in Radioactive Waste Management; Excavation Disturbed Zone (EDZ) Workshop; Educator's Program and Workshop and a Roundtable on Social Issues in Siting

Topical Session on Funding Issues in Connection with Decommissioning of Nuclear Power Plants - 9 November 2004

International Nuclear Information System (INIS)

2006-01-01

Set up by the Radioactive Waste Management Committee (RWMC), the WPDD brings together senior representatives of national organisations who have a broad overview of Decommissioning and Dismantling (D and D) issues through their work as regulators, implementers, R and D experts or policy makers. These include representatives from regulatory authorities, industrial decommissioners from the NEA Co-operative Programme on Exchange of Scientific and Technical Information on Nuclear Installation Decommissioning Projects (CPD), and cross-representation from the other NEA Committees. The EC is a member of the WPDD and the IAEA is participating as an observer. This broad participation provides good possibilities for the co-ordination efforts amongst activities in the international programmes. At its fifth meeting, in Paris, 8-10 November 2004, the WPDD held a topical session on the 'Funding Issues in Connection with Decommissioning of Nuclear Power Plants'. This report documents the topical session on Funding. An agenda of the Topical session can be found in Appendix 1. The topical session was meant to provide an exchange of information and experience on the following issues: Ethical Values; Actual Experiences of Fund Setting and Management; Uncertainties in Funding. At the end of each session time was allotted for a plenary discussion. The Rapporteur reviewed the main points and the lessons learnt at the end of the whole Topical Session. The Topical Session is documented as follows. A summary of the presentations, the country reports, the discussions and the key issues and lessons learnt is given in the main part of this report. The agenda of the Topical session can be found in Appendix 1 and the full papers supporting each presentation are given in Appendix 2. The national presentations on 'Actual experiences of Fund Setting and Management' in session 2 can be found in Appendix 3 and the national presentations on 'Uncertainties in Funding' in session 3 can be found in

II Meeting of R and D in radioactive waste management, Madrid 14-16 June, 1995

International Nuclear Information System (INIS)

1995-01-01

The second meeting of R and D in radioactive waste management was organized by ENRESA on 14-16 June 1995 The main objective was to disseminate the most relevant works within the 2nd R and d plan, and to establish and adequate form involved for discussion R and D radioactive waste management. The meeting was articulated in 50 sessions: I.- Low and medium radioactive wastes. II.- High level radioactive wastes: activities of ENRESA III.- High level radioactive wastes: near field. IV.- Biosphere, radiological protection, behaviour evaluation. V.- Dismantling and decommissioning nuclear facilities VI.- Geosphere

Rapporteur's report - Topical session on stakeholder involvement in decommissioning projects, November 14, 2005

International Nuclear Information System (INIS)

Le Bars, Yves

2006-01-01

Having heard all participants along this day, the Rapporteur recalls, first, the shift we have to adopt in decision making process, and then gives three types of conclusions: the specificities of the decommissioning and dismantling (DD) compared with radioactive waste management; a first assessment of the decision making processes presented during this session, regarding the FSC criteria; and some others conclusions with some ideas for improvement: the need for stronger national policies, the 3 pillars of the local confidence, and the importance of mobilizing staff for a successful DD

Radioactive Waste Management - Community Policy and Research Initiatives. The sixth international conference on the management and disposal of radioactive waste - Euradwaste '04

Energy Technology Data Exchange (ETDEWEB)

Forsstroem, Hans [Research Directorate Energy, Nuclear Fission and Radiation Protection, European Commission, MO-75 5/37, 200 avenue de la Loi, B-1049 Brussels (Belgium); Ruiz, P. Fernandez (ed.) [DG Research, Energy, Consejo de Seguridad Nuclear, CSN, C/ Justo Dorado, 11, E-28040 Madrid (Spain)

2004-07-01

The sixth international conference on the management and disposal of radioactive waste organized be European Commission, held on 29-31 March 2004 in Luxembourg aimed to cover the following objectives: - To present EC policy in waste management, in particular the proposed 'Directive on the Management of Spent Nuclear Fuel and Radioactive Waste' and to discuss relating issues such as the effect on national programmes, site selection, EU added value, the case for EU safety standards, and various socio-political aspects; - To highlight the main results of the Fifth Framework Programme (FP5) of EURATOM for 'Nuclear Energy, Fission Research and Training Activities' in the field of waste in spent fuel management and disposal, and partitioning and transmutation; - To present examples of activities under FP5 and to discuss further research European integration through FP6. The program was divided into two main groups: 1. 'Community Policy and Socio-Political Aspects' which included sessions on community policy initiatives, disposal option, common safety standards and public involvement and acceptance; 2. 'Community Research Activities - FP5' which included sessions on partitioning and transmutation, geological disposal and research networking. There were 29 oral presentations and 36 poster presentations which, for the latter, allowed detailed presentations of the results of the EU-funded research projects. The conference was attended by some 240 participants from 27 countries.

Proceedings of the US Department of Energy, Office of Environmental Restoration and Waste Management: Waste Reduction Workshop 6

International Nuclear Information System (INIS)

1991-04-01

The sixth of a series of waste reduction workshops was held at the Airport Hilton Hotel in Atlanta, Georgia, on February 6--7, 1991. These workshops are held under the auspices of the Department of Energy's (DOE's) Office of Environmental Restoration and Waste Management (EM). The focus of this workshop was the review of guidance and the status of conducting process waste assessments (PWAs). Other highlights of the workshop were the status of the Environmental Protection Agency's (EPA's) Pollution Prevention Program, and presentations on budgeting for waste reduction and the impact of the toxic release inventory (TRI) reporting requirements on pollution prevention activities. Concurrent sessions on the second day included case studies of the experiences at various sites on the subjects of recycling, incentives, source reduction, volume and toxicity reduction, and material procurement. The impact of new state laws on waste reduction efforts at Oak Ridge, Lawrence Livermore National Laboratory, and Hanford were also reviewed by representatives from those sites. These workshops assist DOE waste-generating sites in implementing waste minimization (WMIN) plans and programs, thus providing for optimal waste reduction within the DOE complex. All wastes are considered liquid, solid, and airborne, within the categories of high-level waste, transuranic waste (TRU), low-level waste (LLW), hazardous waste, mixed waste, office waste, and sanitary wastes. Topics of discussion within workshops encompass a wide range of subjects, including any method or technical activity from waste generation to disposal, such as process design or improvement, substitution of materials, waste segregation and recycling/reuse, waste treatment and processing, and administrative controls (procurement and waste awareness training). Consideration is also given to activities for remedial action and for decontamination and disposal

Proceedings of the 3rd Workshop of R and D and technologies on Radioactive Waste management. Vol. 1,2

International Nuclear Information System (INIS)

1998-01-01

The sessions present at the 3rd workshops on radioactive waste management are: 1. Bases for the radioactive waste management 2. Capsule fuel barrier 3. Barriers for engineering 4. Geologic barriers 5. The biosphere as barrier

Solar reflection panels

Science.gov (United States)

Diver, Jr., Richard B.; Grossman, James W [Albuquerque, NM; Reshetnik, Michael [Boulder, CO

2006-07-18

A solar collector comprising a glass mirror, and a composite panel, wherein the back of the mirror is affixed to a front surface of the composite panel. The composite panel comprises a front sheet affixed to a surface of a core material, preferably a core material comprising a honeycomb structure, and a back sheet affixed to an opposite surface of the core material. The invention may further comprise a sealing strip, preferably comprising EPDM, positioned between the glass mirror and the front surface of the composite panel. The invention also is of methods of making such solar collectors.

State-of-the-Art Solid Waste Management Life-Cycle Modeling Workshop

DEFF Research Database (Denmark)

Damgaard, Anders; Levis, James W.

There are many alternatives for the management of solid waste including recycling, biological treatment, thermal treatment and landfill disposal. In many cases, solid waste management systems include the use of several of these processes. Solid waste life-cycle assessment models are often used...... to evaluate the environmental consequences of various waste management strategies. The foundation of every life-cycle model is the development and use of process models to estimate the emissions from solid waste unit processes. The objective of this workshop is to describe life-cycle modeling of the solid...... waste processes and systems. The workshop will begin with an introduction to solid waste life-cycle modeling and available models, which will be followed by sessions on life-cycle process modeling for individual processes (e.g., landfills, biological treatment, and thermal treatment). The first part...

AECL's concept for the disposal of nuclear fuel waste and the importance of its implementation

International Nuclear Information System (INIS)

Allan, C.J.

1993-07-01

Since 1978, Canada has been investigating a concept for permanently dealing with the nuclear fuel waste from Canadian CANDU (Canada Deuterium Uranium) nuclear generating stations. The concept is based on disposing of the waste in a vault excavated 500 to 1000 m deep in intrusive igneous rock of the Canadian Shield. AECL Research will soon be submitting an environmental impact statement (EIS) on the concept for review by a Panel through the federal environmental assessment and review process (EARP). In accordance with AECL Research's mandate and in keeping with the detailed requirements of the review Panel, AECL Research has conducted extensive studies on a wide variety of technical and socio-economic issues associated with the concept. If the concept is accepted, we can and should continue our responsible approach and take the next steps towards constructing a disposal facility for Canada's used nuclear fuel waste

What are the social concerns? round table discussions during session 1 of the Fsc workshop in Canada

International Nuclear Information System (INIS)

Mays, C.

2003-01-01

The first session of the Ottawa Workshop addressed the identification of social concerns regarding the management of low-level radioactive waste and nuclear fuel waste. The Forum on Stakeholder Confidence recognizes that concerns about e.g., equity, lifestyle, culture and economy are intrinsically important. These concerns also form the context of radioactive waste management, and so institutional frameworks must address them. Canadian legislation sets up assurance that due consideration will be given to social concerns. The Canadian Environmental Assessment Act requires that proposed large infrastructure projects be assessed for adverse effects on the environment, including social and economic impacts (Ferch, this volume). The requirements on social impact assessment have recently been reinforced. The new Canadian Nuclear Fuel Waste Act (NFWA) was voted in Summer 2002 and brought into force in November 2002. It directs the nuclear energy corporations to establish a waste management organisation. This organisation must propose at least three approaches for the management of fuel waste, and then implement the approach that is selected or approved by the Governor in Council. The NWFA explicitly requires the study of ethical, social and economic considerations, as well as relative benefits, risks and costs associated with each proposed management approach. (author)

Waste Isolation Pilot Plant 2003 Site Environmental Report

Energy Technology Data Exchange (ETDEWEB)

Washington Regulatory and Environmental Services

2005-09-03

-products management, defense nuclear materials security and safeguards and security investigations, and defense research and development. The waste must also meet the WIPP Waste Acceptance Criteria. When TRU waste arrives at WIPP, it is transported into the Waste Handling Building. The waste containers are removed from the shipping containers, placed on the waste hoist, and lowered to the repository level of 655 m (2,150 ft; approximately 0.5 mi) below the surface. Next, the containers of waste are removed from the hoist and placed in excavated storage rooms in the Salado Formation, a thick sequence of evaporite beds deposited approximately 250 million years ago (Figure 1.1). After each panel has been filled with waste, specially designed closures are emplaced. When all of WIPP's panels have been filled, at the conclusion of WIPP operations, seals will be placed in the shafts. Salt under pressure is relatively plastic, and mine openings will be allowed to creep closed for final disposal, encapsulating and isolating the waste.

Waste Isolation Pilot Plant 2003 Site Environmental Report

International Nuclear Information System (INIS)

2005-01-01

-products management, defense nuclear materials security and safeguards and security investigations, and defense research and development. The waste must also meet the WIPP Waste Acceptance Criteria. When TRU waste arrives at WIPP, it is transported into the Waste Handling Building. The waste containers are removed from the shipping containers, placed on the waste hoist, and lowered to the repository level of 655 m (2,150 ft; approximately 0.5 mi) below the surface. Next, the containers of waste are removed from the hoist and placed in excavated storage rooms in the Salado Formation, a thick sequence of evaporite beds deposited approximately 250 million years ago (Figure 1.1). After each panel has been filled with waste, specially designed closures are emplaced. When all of WIPP's panels have been filled, at the conclusion of WIPP operations, seals will be placed in the shafts. Salt under pressure is relatively plastic, and mine openings will be allowed to creep closed for final disposal, encapsulating and isolating the waste.

Secure Execution of Distributed Session Programs

Directory of Open Access Journals (Sweden)

Nuno Alves

2011-10-01

Full Text Available The development of the SJ Framework for session-based distributed programming is part of recent and ongoing research into integrating session types and practical, real-world programming languages. SJ programs featuring session types (protocols are statically checked by the SJ compiler to verify the key property of communication safety, meaning that parties engaged in a session only communicate messages, including higher-order communications via session delegation, that are compatible with the message types expected by the recipient. This paper presents current work on security aspects of the SJ Framework. Firstly, we discuss our implementation experience from improving the SJ Runtime platform with security measures to protect and augment communication safety at runtime. We implement a transport component for secure session execution that uses a modified TLS connection with authentication based on the Secure Remote Password (SRP protocol. The key technical point is the delicate treatment of secure session delegation to counter a previous vulnerability. We find that the modular design of the SJ Runtime, based on the notion of an Abstract Transport for session communication, supports rapid extension to utilise additional transports whilst separating this concern from the application-level session programming task. In the second part of this abstract, we formally prove the target security properties by modelling the extended SJ delegation protocols in the pi-calculus.

Neutron data compilation. Report of a Panel sponsored by the International Atomic Energy Agency and held in Brookhaven, 10-14 February 1969

Energy Technology Data Exchange (ETDEWEB)

NONE

1969-02-15

The IAEA organized and convened a Panel on Neutron Data Compilation. This Panel was organized by the Agency following the recommendations made by the International Nuclear Data Committee (INDC) which agreed that a general review of world neutron data compilation activities was desirable. In this context neutron data compilation encompasses the collection, storage and dissemination of bibliographic information and of qualitative and numerical data on the interaction of neutrons with nuclei and atoms for all incident energies. Such information and data have important applications in low energy neutron physics and many important. areas of nuclear technology. The principal objective of the Panel on Neutron Data Compilation, Which was held at Brookhaven National Laboratory during 10-14 February 1969, was to review how the world's principal data centers located at Brookhaven, Saclay, Obninsk and Vienna could ideally meet the demands and needs of experimental and theoretical neutron physicists, evaluators, reactor physicists as well as other existing and potential users. Fourteen papers were considered during formal sessions of the Panel and are reported on the following pages. The members of the Panel separated into five working groups to consider specific terms of references and make recommendations. Their reports were discussed.

Proficiency testing for sensory profile panels : measuring panel performance

NARCIS (Netherlands)

Mcewan, J.A.; Hunter, E.A.; Gemert, L.J. van; Lea, P.

2002-01-01

Proficiency testing in sensory analysis is an important step towards demonstrating that results from one sensory panel are consistent with the results of other sensory panels. The uniqueness of sensory analysis poses some specific problems for measuring the proficiency of the human instrument

Proceedings of the fourth annual participants' information meeting, DOE Low-Level Waste Management Program

Energy Technology Data Exchange (ETDEWEB)

Large, D.E.: Mezga, L.J.; Stratton, L.E.; Rose, R.R. (comps.)

1982-10-01

The Fourth Annual Participants' Information Meeting of the Department of Energy Low-Level Waste Management Program was held in Denver, Colorado, August 31 to September 2, 1982. The purpose of the meeting was to report and evaluate technology development funded by the program and to examine mechanisms for technology transfer. The meeting consisted of an introductory plenary session, followed by two concurrent overview sessions and then six concurrent technical sessions. There were two group meetings to review the findings of the technical sessions. The meeting concluded with a plenary summary session in which the major findings of the meeting were addressed. All papers have been abstracted and indexed for the Energy Data Base.

Large thermal protection system panel

Science.gov (United States)

Weinberg, David J. (Inventor); Myers, Franklin K. (Inventor); Tran, Tu T. (Inventor)

2003-01-01

A protective panel for a reusable launch vehicle provides enhanced moisture protection, simplified maintenance, and increased temperature resistance. The protective panel includes an outer ceramic matrix composite (CMC) panel, and an insulative bag assembly coupled to the outer CMC panel for isolating the launch vehicle from elevated temperatures and moisture. A standoff attachment system attaches the outer CMC panel and the bag assembly to the primary structure of the launch vehicle. The insulative bag assembly includes a foil bag having a first opening shrink fitted to the outer CMC panel such that the first opening and the outer CMC panel form a water tight seal at temperatures below a desired temperature threshold. Fibrous insulation is contained within the foil bag for protecting the launch vehicle from elevated temperatures. The insulative bag assembly further includes a back panel coupled to a second opening of the foil bag such that the fibrous insulation is encapsulated by the back panel, the foil bag, and the outer CMC panel. The use of a CMC material for the outer panel in conjunction with the insulative bag assembly eliminates the need for waterproofing processes, and ultimately allows for more efficient reentry profiles.

Reflecting variable opening insulating panel

International Nuclear Information System (INIS)

Nungesser, W.T.

1976-01-01

A description is given of a reflecting variable opening insulating panel assembly, comprising a static panel assembly of reflecting insulation sheets forming a cavity along one side of the panel and a movable panel opening out by sliding from the cavity of the static panel, and a locking device for holding the movable panel in a position extending from the cavity of the static panel. This can apply to a nuclear reactor of which the base might require maintenance and periodical checking and for which it is desirable to have available certain processes for the partial dismantling of the insulation [fr

Proceedings of the tenth annual DOE low-level waste management conference: Session 3: Disposal technology and facility development

International Nuclear Information System (INIS)

1988-12-01

This document contains ten papers on various aspects of low-level radioactive waste management. Topics include: design and construction of a facility; alternatives to shallow land burial; the fate of tritium and carbon 14 released to the environment; defense waste management; engineered sorbent barriers; remedial action status report; and the disposal of mixed waste in Texas. Individual papers were processed separately for the data base

IV meeting of R and D in research and technological development of radioactive waste management

International Nuclear Information System (INIS)

2001-01-01

These Technical Publications include the main papers presented during the IV R and D Symposium on Radioactive Wastes Management Technology, promoted by ENRESA and held in the Barcelona University during November 2000. The papers correspond both to the Technical Sessions and the Seminars and they are a document of inestimable value that indicates the high technological value reached in the radioactive waste management as a result of a clear and continuous R and D politics together with an intense and productive international collaboration. Throughout the papers of this document the technological status and the capacities developed in all different fields of the radioactive waste management are shown. The main subjects discussed include: low and medium activity wastes management, dismantling of nuclear plants, partitioning and transmutation of long life radionuclide and mainly deep geological disposal. Through the papers corresponding to the scientific sessions the state of the art in the mentioned areas is reviewed with special emphasis, as the achievements and developments reached in Spain. Through the seminars, many outstanding aspects of the R and D in radioactive wastes such as the biosphere role, the numerical modelling and the underground laboratories, can be studied in depth. (Author)

Deconstructing the Nature of Safety and Acceptability in Nuclear Fuel Waste Management, Canada

International Nuclear Information System (INIS)

Murphy, Brenda L.

2003-01-01

Since the Hare report was released in 1977, Canada's nuclear fuel waste management policies have been focused on one option, deep geologic disposal. However, since new legislation, called the Nuclear Fuel Waste Management Act came into force on November 15, 2002, the newly established Nuclear Waste Management Organisation has been mandated to review, over the next three years, not only deep geologic disposal but also to consider a suite of other options including reactor-site and centralised storage, and both above and below ground options. At this point in time, the process for the study and the criteria by which it will be evaluated are still quite unclear. The need for this new approach to NFW management in Canada was highlighted by an Environmental Assessment Panel (EA Panel) report in 1998. This EA Panel reviewed the 1994 environmental impact statement submitted by Atomic Energy Canada Limited (AECL) regarding the concept of deep geologic disposal in the Canadian Shield (Disposal Concept EA). The EA Panel's key conclusion was: From a technical perspective, safety of the AECL concept has been on balance adequately demonstrated for a conceptual stage of development, but from a social perspective, it has not. As it stands, the AECL concept for deep geological disposal has not been demonstrated to have broad public support. The concept in its current form does not have the required level of acceptability to be adopted as Canada's approach for managing nuclear fuel wastes. AECL's study consisted of a review of the deep geologic disposal concept, since no site has yet been selected. It is generally understood that this type of disposal facility, if eventually sited, will be located on the Ontario portion of the Canadian Shield because Ontario power generators own and manage about 90% of Canada's NFW. This key EA Panel conclusion is predicated on the use of two key decision-making criteria - safety and acceptability. This paper reviews and assesses the specific ways

The Role of the Biosphere in a Safety Case. IGSC topical session at the third IGSC Meeting

International Nuclear Information System (INIS)

Russell, Sean; Voinis, Sylvie; Alonso, Jesus; Van Luik, Abraham E.

2002-01-01

The safety case is a collection of arguments at a given stage of repository development in support of the long-term safety of the repository. The safety case comprises the findings of a safety assessment and a statement of confidence in these findings. The biosphere is one of the features of a geologic repository system for the long-term management of radioactive waste. The biosphere is important in a safety assessment since it is the place where humans and most organisms live and where regulations are made. Generally speaking, the biosphere is more dynamic than the geosphere and its evolution with time can significantly affect dose estimations and potential impacts of a geologic repository (e.g., climate change, glaciation, civilisation movement, etc.). That is, other parts of the repository system (vault, geosphere) are more robust or constant in time than the ever changing biosphere. Most of the variability associated with future events in the biosphere is driven by climate change. Climatic change and the characteristics of future societies are important sources of uncertainties Biosphere. Uncertainty can be addressed using reference or example biospheres, or alternative safety indicators such as radionuclide concentration or radionuclide flux from the geosphere to the surface biosphere (as indicated by the recent regulatory guidance in Finland), or by comparing predicted radionuclide concentrations from a repository with background levels in the environment. Thus, a Topical Session that focused on the 'Role of the Biosphere in a Safety Case' was organised in the framework of the 3. plenary meeting of the IGSC. This Topical Session reviewed the role of the biosphere in a safety case for geologic disposal of radioactive waste and discusses recent developments in international programs (IAEA Biomass, EC Bioclim), the views of regulators and the strategies being adopted by several implementers for incorporating the biosphere in their safety assessments

2. plan of R and D: methodological technological, instrumental and numerical developments for radioactive wastes management

International Nuclear Information System (INIS)

1995-10-01

The second meeting of R and D in radioactive waste management was organized by ENRESA on June 1995 in Madrid. The main objective was to disseminate the most relevant works within the R and D plan, and to establish an adequate form involved for discussion R and D radioactive waste management. The meeting was articulated in the followings sessions: I.- Low and medium radioactive wastes II.- High level radioactive wastes: activities of ENRESA III.- High level radioactive wastes: near field IV.- Biosphere, radiological protection, behaviour evaluation V.-Dismantling and decommissioning nuclear facilities VI.- Geosphere (Author)

The United States Department of Energy process for performance assessment for disposal of low-level radioactive waste

International Nuclear Information System (INIS)

Wood, D.E.; Owens, K.W.; Wilhite, E.L.; Duggan, G.J.

1993-02-01

The US Department of Energy (DOE) manages disposal of low-level radioactive waste through the requirements of DOE Order 5820.2A on Radioactive Waste Management. The order specifies long-term performance objectives for permanent disposal, requires a performance assessment to determine compliance with those objectives, and establishes a Peer Review Panel to review those assessments for technical quality and completeness. A Performance Assessment Task Team has been established to provide guidance and recommend policy for implementation and interpretation of the requirements to those preparing the assessments. This paper describes the requirements, the Peer Review Panel, the Performance Assessment Task Team, and their activities to date

Cavity Control and Panel Control Strategies in Double-Panel Structures for Transmitted Noise Reduction

NARCIS (Netherlands)

Ho, J.; Kalverboer, J.; Berkhoff, Arthur P.

2012-01-01

Investigation and comparisons of the cavity control and the panel control in a double-panel structure are presented in this paper. The double-panel structure, which comprises two panels with air in the gap, provides the advantages of low sound-transmission at high frequency, low heat-transmission

MO-F-201-00: PANEL DISCUSSION: Preparing for Parts 2 and 3 of the ABR Therapy Medical Physics Exam

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-06-15

The goal of this session is to provide guidance to medical physicists undergoing the American Board of Radiology certification process in therapeutic medical physics. This panel discussion will focus on parts 2 (computer-based) and 3 (oral) of the examination. Unlike the latter portions of the exam which are specialty-driven, part 1 is universal for all medical physics fields and will not be addressed. This session is structured into different topics that aim to guide the participants on how to successfully prepare for the board exams. The subjects of discussion will include timing and strategies for exam preparation, crucial differences in preparing for the clinical computer-based exam versus the oral exam, what study tools are currently available for each, etc. The panel discussion format will allow the speakers to collectively present their experience and advice relating to each topic and foment audience participation. Learning Objectives: Know the main differences between what is expected for parts 2 and 3 Know different resources for test preparation Know how to formulate a plan to best study for each part based on the specific skill set the two parts require Know how to best present his/her answers during the oral examination – demeanor, answer structure, etc.

MO-F-201-00: PANEL DISCUSSION: Preparing for Parts 2 and 3 of the ABR Therapy Medical Physics Exam

International Nuclear Information System (INIS)

2016-01-01

The goal of this session is to provide guidance to medical physicists undergoing the American Board of Radiology certification process in therapeutic medical physics. This panel discussion will focus on parts 2 (computer-based) and 3 (oral) of the examination. Unlike the latter portions of the exam which are specialty-driven, part 1 is universal for all medical physics fields and will not be addressed. This session is structured into different topics that aim to guide the participants on how to successfully prepare for the board exams. The subjects of discussion will include timing and strategies for exam preparation, crucial differences in preparing for the clinical computer-based exam versus the oral exam, what study tools are currently available for each, etc. The panel discussion format will allow the speakers to collectively present their experience and advice relating to each topic and foment audience participation. Learning Objectives: Know the main differences between what is expected for parts 2 and 3 Know different resources for test preparation Know how to formulate a plan to best study for each part based on the specific skill set the two parts require Know how to best present his/her answers during the oral examination – demeanor, answer structure, etc.

Hepatic (Liver) Function Panel

Science.gov (United States)

... Educators Search English Español Blood Test: Hepatic (Liver) Function Panel KidsHealth / For Parents / Blood Test: Hepatic (Liver) ... kidneys ) is working. What Is a Hepatic (Liver) Function Panel? A liver function panel is a blood ...

Workshop: poster session

International Nuclear Information System (INIS)

Schell, W.R.; Colgan, P.A.

1990-01-01

The poster session consisted of a microcosm of projects encompassing the wide range of problems in the radioecology of natural and semi-natural ecosystems. The authors presented a brief resume of the poster at a plenary session during which highlights were pointed out. The range of studies covered microbial transfer, fungi, insects herbicides, lichens, solid speciation of cesium, soil properties, plant cover, transfer factors from soil to plants, uptake by sludge fertilizers, fertilizer remediation and compartmental models for soil-plant uptake. (author)

CONSUMER ATTITUDE AND BEHAVIOUR TOWARDS FOOD WASTE

Directory of Open Access Journals (Sweden)

Monika Radzymińska

2016-03-01

Full Text Available This paper presents the attitudes and behaviour of young consumers towards food waste based on a pilot qualitative research and data published in the literature. Qualitative research was conducted with the use of focus grou p method, with approximately 8–10 selected students per group. Four focus group sessions were held, with open discussion led by a moderator and the scenario containing problematic issues. The study included a total of thirty-seven students, aged 22– 25 years. Studies have shown that negative attitude of household towards food waste is not frequently refl ected in consumers’ behaviour, despite their fundamental knowledge on how to reduce food waste. Respondents emphasized the need for educational campaigns. Properly selected and presented information will stimulate both consumer’s attitude and behaviour.

Panel Resonance Control and Cavity Control in Double-Panel Structures for Active Noise Reduction

NARCIS (Netherlands)

Ho, J.; Berkhoff, Arthur P.

2011-01-01

An analytical and experimental investigation of panel resonance control and cavity control in a double-panel structure is presented in this paper. The double-panel structure, which consists of two panels with air in the gap, is widely adopted in many applications such as aerospace due to its low

Intra-session and inter-session variability of nitric oxide pulmonary diffusing capacity in adults with cystic fibrosis.

Science.gov (United States)

Radtke, Thomas; Benden, Christian; Maggi-Beba, Marion; Kriemler, Susi; van der Lee, Ivo; Dressel, Holger

2017-12-01

We evaluated the intra-session and inter-session variability of the diffusing capacity of nitric oxide (DLNO), carbon monoxide (DLCO), alveolar-capillary membrane diffusing capacity for carbon monoxide (DMCO) and pulmonary capillary blood volume (Vc) in patients with cystic fibrosis (CF). Patients performed single-breath diffusing capacity measurements during all of 3 consecutive study visits. Precision of gas diffusing parameters was quantified by within-subject standard deviation (SD ws ) and coefficient of variation (CV). Intra-session and inter-session reproducibility was determined by SD ws *2.77. 15 clinically stable patients were included. The intra-session precision of gas diffusing parameters improved over the study visits. The inter-session SD ws for DLNO, DLCO, DMCO, and Vc was 4.8, 1.3, 2.4, and 4.3, respectively. Reproducibility was 13.3, 3.8, 6.7 and 12.0mLmin -1 mmHg -1 ; CV was 4.4, 4.7, 4.4 and 5.8%, respectively. The intra-session variability of DLNO, DLCO, DMCO and Vc improves with breath-hold maneuver training in test-naïve patients with CF, indicating a learning effect. Inter-session reproducibility data are lower than those previously reported in healthy subjects. Copyright © 2017 Elsevier B.V. All rights reserved.

Underground disposal of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

NONE

1979-08-15

Disposal of low- and intermediate-level radioactive wastes by shallow land burial, emplacement in suitable abandoned mines, or by deep well injection and hydraulic fracturing has been practised in various countries for many years. In recent years considerable efforts have been devoted in most countries that have nuclear power programmes to developing and evaluating appropriate disposal systems for high-level and transuranium-bearing waste, and to studying the potential for establishing repositories in geological formations underlaying their territories. The symposium, organized jointly by the IAEA and OECD's Nuclear Energy Agency in cooperation with the Geological Survey of Finland, provided an authoritative account of the status of underground disposal programmes throughout the world in 1979. It was evidence of the experience that has been gained and the comprehensive investigations that have been performed to study various options for the underground disposal of radioactive waste since the last IAEA/NEA symposium on this topic (Disposal of Radioactive Waste into the Ground) was held in 1967 in Vienna. The 10 sessions covered the following topics: National programme and general studies, Disposal of solid waste at shallow depth and in rock caverns, underground disposal of liquid waste by deep well injection and hydraulic fracturing, Disposal in salt formations, Disposal in crystalline rocks and argillaceous sediments, Thermal aspects of disposal in deep geological formations, Radionuclide migration studies, Safety assessment and regulatory aspects.

Radioactive waste management: a summary of state laws and administration. National Low-Level Radioactive Waste Mangement Program

International Nuclear Information System (INIS)

1983-05-01

This is the first quarterly update of Radioactive Waste Management: A Summary of State Laws and Administration. Because states have been very active on waste management issues, the whole report is being reissued in this update. It covers the administration, the legislature and the laws in the 50 states related to radioactive waste. The report for each state is divided into four sections: Cover Page; Administrative; Legislative; and Applicable Legislation. The cover page indicates whether or not it is an Agreement State, the low-level waste compacts in which the state is listed as an eligible state, and the high-level waste repository site screening regions in which the state or a portion of it is located. The administrative section provides information on the governor, lead agencies, other involved administrative agencies, relevant commissions, boards and councils and various contacts. The Legislative section provides general information on the legislature and lists legislative leaders, the relevant committees and their chairs and a legislative contact. In the section covering Applicable Legislation, laws related to radiation protection, low-level waste and high-level waste have been summarized. Hazardous waste siting laws are included for states that do not have a siting law covering radioactive waste. The section also contains summaries of relevant bills introduced in 1982 and 1983 legislative sessions and their disposition. In general, the information in this report is accurate as of 15 April 1983

The Public Poster Session

Science.gov (United States)

Levine-Rasky, Cynthia

2009-01-01

This note describes the use of a student poster session as an innovative approach to student learning. The local context for the assignment is provided, followed by a description of the course for which the poster was prepared, details about the assignment including its evaluation, and practical considerations for planning a poster session. The…

Waste Isolation Pilot Plant 2005 Site Environmental Report

Energy Technology Data Exchange (ETDEWEB)

Washington Regulatory and Environmental Services

2006-10-13

investigations, and defense research and development. The waste must also meet the WIPP Waste Acceptance Criteria. When TRU waste arrives at WIPP, it is transported into the Waste Handling Building. The waste containers are removed from the shipping containers, placed on the waste hoist, and lowered to the repository level of 655 m (2,150 ft; approximately 0.5 mi) below the surface. Next, the containers of waste are removed from the hoist and placed in excavated disposal rooms in the Salado Formation, a thick sequence of evaporite beds deposited approximately 250 million years ago (Figure 1.1). After each panel of seven rooms has been filled with waste, specially designed closures are emplaced. When all of WIPP's panels have been filled, at the conclusion of WIPP operations, seals will be placed in the shafts. One of the main attributes of salt, as a rock formation in which to isolate radioactive waste, is the ability of the salt to creep, that is, to deform continuously over time. Excavations into which the waste-filled drums are placed will close eventually, flowing around the drums and sealing them within the formation.

Performance comparison between silicon solar panel and dye-sensitized solar panel in Malaysia

Science.gov (United States)

Hamed, N. K. A.; Ahmad, M. K.; Urus, N. S. T.; Mohamad, F.; Nafarizal, N.; Ahmad, N.; Soon, C. F.; Ameruddin, A. S.; Faridah, A. B.; Shimomura, M.; Murakami, K.

2017-09-01

In carrying out experimental research in performance between silicon solar panel and dye-sensitive solar panel, we have been developing a device and a system. This system has been developed consisting of controllers, hardware and software. This system is capable to get most of the input sources. If only need to change the main circuit and coding for a different source input value. This device is able to get the ambient temperature, surface temperature, surrounding humidity, voltage with load, current with load, voltage without load and current without load and save the data into external memory. This device is able to withstand the heat and rain as it was fabricated in a waterproof box. This experiment was conducted to examine the performance of both the solar panels which are capable to maintain their stability and performance. A conclusion based on data populated, the distribution of data for dye-sensitized solar panel is much better than silicon solar panel as dye-sensitized solar panel is very sensitive to heat and not depend only on midday where is that is the maximum ambient temperature for both solar panel as silicon solar panel only can give maximum and high output only when midday.

Analysis of 3-panel and 4-panel microscale ionization sources

International Nuclear Information System (INIS)

Natarajan, Srividya; Parker, Charles B.; Glass, Jeffrey T.; Piascik, Jeffrey R.; Gilchrist, Kristin H.; Stoner, Brian R.

2010-01-01

Two designs of a microscale electron ionization (EI) source are analyzed herein: a 3-panel design and a 4-panel design. Devices were fabricated using microelectromechanical systems technology. Field emission from carbon nanotube provided the electrons for the EI source. Ion currents were measured for helium, nitrogen, and xenon at pressures ranging from 10 -4 to 0.1 Torr. A comparison of the performance of both designs is presented. The 4-panel microion source showed a 10x improvement in performance compared to the 3-panel device. An analysis of the various factors affecting the performance of the microion sources is also presented. SIMION, an electron and ion optics software, was coupled with experimental measurements to analyze the ion current results. The electron current contributing to ionization and the ion collection efficiency are believed to be the primary factors responsible for the higher efficiency of the 4-panel microion source. Other improvements in device design that could lead to higher ion source efficiency in the future are also discussed. These microscale ion sources are expected to find application as stand alone ion sources as well as in miniature mass spectrometers.

Report on the international symposium on radiological issues for Fukushima's revitalized future

International Nuclear Information System (INIS)

Sato, Nobuhiro

2015-12-01

On May 30 - 31, 2015, the fourth and last convention entitled 'International Symposium on Radiological Issues for Fukushima's Revitalized Future' was held in Iizaka Onsen, Fukushima city, under auspices of Institute of Environmental Radioactivity at Fukushima University and other organizations. The following four subjects were the main topics of this symposium: Decontamination/radioactive waste; Environmental radiation/external exposure; Marine/agricultural products, food, internal exposure; and Issues at the Fukushima Daiichi NPP site. The program included 2 invited lectures by overseas guest speakers, 12 oral presentations, 80 poster presentations, and 2 panel discussion sessions, in which over 600 participants consisting of researchers, experts, community dwellers, and young students had lively discussion in a warm and friendly atmosphere. It is noteworthy that several poster presentations were given by high school and junior college students in Fukushima in this international symposium. This report is a collection of the presentation slides and the transcriptions of Q and A sessions for oral lectures as well as the transcriptions of the panel discussion sessions. (J.P.N.)

Proceedings of the tenth annual DOE low-level waste management conference: Session 1: Institutional and regulatory issues

International Nuclear Information System (INIS)

1988-12-01

This document contains eleven papers on various aspects of low-level radioactive waste regulation. Topics include: EPA environmental standards; international exemption principles; the concept of below regulatory concern; envirocare activities in Utah; mixed waste; FUSRAP and the Superfund; and a review of various incentive programs. Individual papers are processed separately for the data base

Viewers' perceptions of a YouTube music therapy session video.

Science.gov (United States)

Gregory, Dianne; Gooding, Lori G

2013-01-01

Recent research revealed diverse content and varying levels of quality in YouTube music therapy videos and prompted questions about viewers' discrimination abilities. This study compares ratings of a YouTube music therapy session video by viewers with different levels of music therapy expertise to determine video elements related to perceptions of representational quality. Eighty-one participants included 25 novices (freshmen and sophomores in an introductory music therapy course), 25 pre-interns (seniors and equivalency students who had completed all core Music Therapy courses), 26 professionals (MT-BC or MT-BC eligibility) with a mean of 1.75 years of experience, and an expert panel of 5 MT-BC professionals with a mean of 11 years of experience in special education. After viewing a music therapy special education video that in previous research met basic competency criteria and professional standards of the American Music Therapy Association, participants completed a 16-item questionnaire. Novices' ratings were more positive (less discriminating) compared to experienced viewers' neutral or negative ratings. Statistical analysis (ANOVA) of novice, pre-intern, and professional ratings of all items revealed significant differences p, .05) for specific therapy content and for a global rating of representational quality. Experienced viewers' ratings were similar to the expert panel's ratings. Content analysis of viewers' reasons for their representational quality ratings corroborated ratings of therapy-specific content. A video that combines and clearly depicts therapy objectives, client improvement, and the effectiveness of music within a therapeutic intervention best represent the music therapy profession in a public social platform like YouTube.

Healthcare waste management: an interpretive structural modeling approach.

Science.gov (United States)

Thakur, Vikas; Anbanandam, Ramesh

2016-06-13

Purpose - The World Health Organization identified infectious healthcare waste as a threat to the environment and human health. India's current medical waste management system has limitations, which lead to ineffective and inefficient waste handling practices. Hence, the purpose of this paper is to: first, identify the important barriers that hinder India's healthcare waste management (HCWM) systems; second, classify operational, tactical and strategical issues to discuss the managerial implications at different management levels; and third, define all barriers into four quadrants depending upon their driving and dependence power. Design/methodology/approach - India's HCWM system barriers were identified through the literature, field surveys and brainstorming sessions. Interrelationships among all the barriers were analyzed using interpretive structural modeling (ISM). Fuzzy-Matrice d'Impacts Croisés Multiplication Appliquée á un Classement (MICMAC) analysis was used to classify HCWM barriers into four groups. Findings - In total, 25 HCWM system barriers were identified and placed in 12 different ISM model hierarchy levels. Fuzzy-MICMAC analysis placed eight barriers in the second quadrant, five in third and 12 in fourth quadrant to define their relative ISM model importance. Research limitations/implications - The study's main limitation is that all the barriers were identified through a field survey and barnstorming sessions conducted only in Uttarakhand, Northern State, India. The problems in implementing HCWM practices may differ with the region, hence, the current study needs to be replicated in different Indian states to define the waste disposal strategies for hospitals. Practical implications - The model will help hospital managers and Pollution Control Boards, to plan their resources accordingly and make policies, targeting key performance areas. Originality/value - The study is the first attempt to identify India's HCWM system barriers and prioritize

Medical Waste Management Training for Healthcare Managers - a Necessity?

Directory of Open Access Journals (Sweden)

Aclan Ozder

2013-07-01

Full Text Available Background:This is an interventional study, since a training has been given, performed in order to investigate whether training has significant impact on knowledge levels of healthcare managers (head-nurses, assistant head nurses, hospital managers and deputy managers regarding bio-medical waste management.Methods:The study was conducted on 240 volunteers during June – August 2010 in 12 hospitals serving in Istanbul (private, public, university, training-research hospitals and other healthcare institutions. A survey form prepared by the project guidance team was applied to the participants through the internet before and after the training courses. The training program was composed of 40 hours of theory and 16 hours of practice sessions taught by persons known to have expertise in their fields. Methods used in the analysis of the data chi-square and t-tests in dependent groups.Results:67.5% (162 of participants were female. 42.5% (102 are working in private, and 21.7% in state-owned hospitals. 50.4% are head-nurses, and 18.3% are hospital managers.A statistically significant difference was found among those who had received medical waste management training (preliminary test and final test and others who had not (p<0.01. It was observed that information levels of all healthcare managers who had received training on waste management had risen at the completion of that training session.Conclusion:On the subject of waste management, to have trained healthcare employees who are responsible for the safe disposal of wastes in hospitals is both a necessity for the safety of patients and important for its contribution to the economy of the country.

Topical session proceedings of the 6. IGSC Meeting. The role of monitoring in a safety case

International Nuclear Information System (INIS)

2005-01-01

This report summarises the outcomes of a topical session focused on the role of monitoring in a safety case. It was held as part of the 6. plenary meeting of the IGSC. It was attended by 39 participants, representing waste management organisations and regulatory authorities from 15 NEA member countries, the IAEA and the European Commission. The main purpose of this topical session was to create a platform for exchanging views on the key monitoring issues of interest to build confidence in a safety case e.g. relationship with the post-closure phase, functions, requirements, and to determine to what extent the main actions are to be addressed by the IGSC on its ongoing activities on defining the elements of a safety case. The topical session was indeed mainly aimed at exchanging information on: - National strategies or programmes in NEA members' countries. Member countries have organisations planning their own strategy, but some are already, to some extend engaged in implementing monitoring activities, e.g. Posiva Oy, US-DOE-YM, Andra. - Feedback from international projects, e.g. the EC Thematic Network on 'The role of Monitoring in a Phased Approach to Geological Disposal of Radioactive Waste', and the IAEA programme of work. - The expectations of regulators, e.g. SKI. Part A of this document summarises the material orally presented and provides the main lessons drawn from the presentations and the discussions that followed them. The overheads presented are compiled without any further elaboration by the NEA Secretariat as Part B of the document. Part C gives the list of participants. The document as a whole provides a synthesis of current issues in monitoring of a deep geological disposal facility

Antinuclear antibody panel

Science.gov (United States)

... page: //medlineplus.gov/ency/article/003535.htm Antinuclear antibody panel To use the sharing features on this page, please enable JavaScript. The antinuclear antibody panel is a blood test that looks at ...

Hepatitis virus panel

Science.gov (United States)

... page: //medlineplus.gov/ency/article/003558.htm Hepatitis virus panel To use the sharing features on this page, please enable JavaScript. The hepatitis virus panel is a series of blood tests used ...

Waste disposal experts meet

Energy Technology Data Exchange (ETDEWEB)

NONE

1959-01-15

Problems connected with the disposal into the sea of radioactive wastes from peaceful uses of atomic energy are being examined by a panel of experts, convened by the International Atomic Energy Agency. These experts from eight different countries held a first meeting at IAEA headquarters in Vienna from 4-9 December 1958, under the chairmanship of Dr. Harry Brynielsson, Director General of the Swedish Atomic Energy Company. The countries represented are: Canada, Czechoslovakia, France, Japan, Netherlands, United Kingdom and United States. The group will meet again in 1959. (author)

REINFORCED COMPOSITE PANEL

DEFF Research Database (Denmark)

2003-01-01

A composite panel having front and back faces, the panel comprising facing reinforcement, backing reinforcement and matrix material binding to the facing and backing reinforcements, the facing and backing reinforcements each independently comprising one or more reinforcing sheets, the facing rein...... by matrix material, the facing and backing reinforcements being interconnected to resist out-of-plane relative movement. The reinforced composite panel is useful as a barrier element for shielding structures, equipment and personnel from blast and/or ballistic impact damage....

Photovoltaic solar panels of crystalline silicon: Characterization and separation.

Science.gov (United States)

Dias, Pablo Ribeiro; Benevit, Mariana Gonçalves; Veit, Hugo Marcelo

2016-03-01

Photovoltaic panels have a limited lifespan and estimates show large amounts of solar modules will be discarded as electronic waste in a near future. In order to retrieve important raw materials, reduce production costs and environmental impacts, recycling such devices is important. Initially, this article investigates which silicon photovoltaic module's components are recyclable through their characterization using X-ray fluorescence, X-ray diffraction, energy dispersion spectroscopy and atomic absorption spectroscopy. Next, different separation methods are tested to favour further recycling processes. The glass was identified as soda-lime glass, the metallic filaments were identified as tin-lead coated copper, the panel cells were made of silicon and had silver filaments attached to it and the modules' frames were identified as aluminium, all of which are recyclable. Moreover, three different components segregation methods have been studied. Mechanical milling followed by sieving was able to separate silver from copper while chemical separation using sulphuric acid was able to detach the semiconductor material. A thermo gravimetric analysis was performed to evaluate the use of a pyrolysis step prior to the component's removal. The analysis showed all polymeric fractions present degrade at 500 °C. © The Author(s) 2016.

Linearly Refined Session Types

Directory of Open Access Journals (Sweden)

Pedro Baltazar

2012-11-01

Full Text Available Session types capture precise protocol structure in concurrent programming, but do not specify properties of the exchanged values beyond their basic type. Refinement types are a form of dependent types that can address this limitation, combining types with logical formulae that may refer to program values and can constrain types using arbitrary predicates. We present a pi calculus with assume and assert operations, typed using a session discipline that incorporates refinement formulae written in a fragment of Multiplicative Linear Logic. Our original combination of session and refinement types, together with the well established benefits of linearity, allows very fine-grained specifications of communication protocols in which refinement formulae are treated as logical resources rather than persistent truths.

INEL studies concerning solidification of low-level waste in cement

International Nuclear Information System (INIS)

Mandler, J.W.

1989-01-01

The Idaho National Engineering Laboratory (INEL) has performed numerous studies addressing issues concerning the solidification of low-level radioactive waste in cement. These studies have been performed for both the Nuclear Regulatory Commission (NRC) and the Department of Energy (DOE). This short presentation will only outline the major topics addressed in some of these studies, present a few conclusions, and identify some of the technical concerns we have. More details of the work and pertinent results will be given in the Working Group sessions. The topics that have been addressed at the INEL which are relevant to this Workshop include (1) solidification of ion-exchange resins and evaporator waste in cement at commercial nuclear power plants, (2) leachability and compressive strength of power plant waste solidified in cement, (3) suggested guidelines for preparation of a solid waste process control program (PCP), (4) cement solidification of EPICOR-II resin wastes, and (5) performance testing of cement-solidified EPICOR-II resin wastes

Rational Design of Composite Panels

DEFF Research Database (Denmark)

Riber, Hans Jørgen

1996-01-01

A non-linear structural model for composite panels is presented. The non-linear terms in the lateral displacements are modelled as an additional set of lateral loads acting on the panel. Hence the solution is reduced to that of an equivalent panel with small displacements In order to treat sandwich...... Norske Veritas', DNV, building rules concerning high-speed light craft, in which the panel scantlings are often restricted by a maximum lateral deflection connected with the panel span....

Composite panel development at JPL

Science.gov (United States)

Mcelroy, Paul; Helms, Rich

1988-01-01

Parametric computer studies can be use in a cost effective manner to determine optimized composite mirror panel designs. An InterDisciplinary computer Model (IDM) was created to aid in the development of high precision reflector panels for LDR. The materials properties, thermal responses, structural geometries, and radio/optical precision are synergistically analyzed for specific panel designs. Promising panels designs are fabricated and tested so that comparison with panel test results can be used to verify performance prediction models and accommodate design refinement. The iterative approach of computer design and model refinement with performance testing and materials optimization has shown good results for LDR panels.

17. Meeting municipal waste Magdeburg. Residual waste - recycling - resource; 17. Tagung Siedlungsabfallwirtschaft Magdeburg. Restabfall - Recycling - Ressource

Energy Technology Data Exchange (ETDEWEB)

Haase, Hartwig (ed.)

2012-11-01

Within the 17th meeting Waste Management at Residential Areas from 12th o 13th September, 2012 in Magdeburg (Federal Republic of Germany), the following lectures were held: (1) Opening Session - Waste management in Saxony-Anhalt (O. Aeikens); (2) World with future - the eco-social perspective (F.J. Radermacher); (3) Global commodity markets - rare earths and their recycling (I. Fahimi); (4) The further development of nearhousehold capture of recyclable materials (J. Seitel); (5) On the future of the disposal management (J. Balg); (6) Options for action for the future of the municipal waste management (A. Gosten); (7) Current models of the capture of recyclable materials in Germany (M. Kerkhoff); (8) The recycling bin as a pilot test in Hanover (R. Middendorf); (9) Position of BellandVision on the implementation of a unified recycling bin (J. Soelling); (10) What will change with the new Recycle Economy Law according to the material flows and waste treatment capacities? (H. Alwast); (11) Waste management plan Saxony-Anhalt - Current developments (S. Hagel); (12) Wastes from the thermal waste treatment - Risk potential and disposal (G.-R. Behr); (13) Landfill Mining - Contribution of the waste management to the securing of resources (K. Fricke); (14) Logistic process design and system design in the transport of wastes in developing countries using Serbia as an example (Z. Jovanovic); (15) Example of good practices in the subsequent use of landfills - Solar park Cracauer Anger (M. Harnack); (16) Ecoloop - energy efficient gasification in the limestone moving-bed (R. Moeller); (17) Utilization of waste and biomass as a resource? Only by means of an intelligent logistics. (S. Trojahn); (18) Renewable energy resources - Experiences of a network provider (J. Kempmann).

Minutes of the Tank Waste Science Panel Meeting March 25--27, 1992

International Nuclear Information System (INIS)

Schutz, W.W.; Strachan, D.M.

1992-08-01

Discussions from the seventh meeting of the Tank Waste Science are presented in Colorado. The subject areas included the generation of gases in Tank 241-SY-101, the possible use of sonication as a mitigation method, and analysis for organic constituents in core samples. Results presented and discussed include: Ferrocyanides appear to be rapidly dissolved in 1M NaOH; upon standing in the laboratory at ambient conditions oxalate precipitates from simulated wastes containing HEDTA. This suggests that one of the main components in the solids in Tank 241-SY-101 is oxalate; hydrogen evolved from waste samples from Tank 241-SY-101 is five times that observed in the off gas from the tank; data suggest that mitigation of Tank 241-SY-101 will not cause a high release of dissolved N 2 O; when using a slurry for radiation studies, a portion of the generated gases is very difficult to remove. To totally recover the generated gases, the solids must first be dissolved. This result may have an impact on mitigation by mixing if the gases are not released. Using 13 C-labeled organics in thermal degradation studies has allowed researchers to illucidate much of the kinetic mechanism for the degradation of HEDTA and glycolate. In addition to some of the intermediate, more complex organic species, oxalate, formate, and CO 2 were identified; and analytic methods for organics in radioactive complex solutions such as that found in Tank 241-SY-101 have been developed and others continue to be developed

Forecasting waste compositions: A case study on plastic waste of electronic display housings.

Science.gov (United States)

Peeters, Jef R; Vanegas, Paul; Kellens, Karel; Wang, Feng; Huisman, Jaco; Dewulf, Wim; Duflou, Joost R

2015-12-01

Because of the rapid succession of technological developments, the architecture and material composition of many products used in daily life have drastically changed over the last decades. As a result, well-adjusted recycling technologies need to be developed and installed to cope with these evolutions. This is essential to guarantee continued access to materials and to reduce the ecological impact of our material consumption. However, limited information is currently available on the material composition of arising waste streams and even less on how these waste streams will evolve. Therefore, this paper presents a methodology to forecast trends in the material composition of waste streams. To demonstrate the applicability and value of the proposed methodology, it is applied to forecast the evolution of plastic housing waste from flat panel display (FPD) TVs, FPD monitors, cathode ray tube (CRT) TVs and CRT monitors. The results of the presented forecasts indicate that a wide variety of plastic types and additives, such as flame retardants, are found in housings of similar products. The presented case study demonstrates that the proposed methodology allows the identification of trends in the evolution of the material composition of waste streams. In addition, it is demonstrated that the recycling sector will need to adapt its processes to deal with the increasing complexity of plastics of end-of-life electronic displays while respecting relevant directives. Copyright © 2015 Elsevier Ltd. All rights reserved.

Supersonic Panel Flutter Test Results for Flat Fiber-Glass Sandwich Panels with Foamed Cores

Science.gov (United States)

Tuovila, W. J.; Presnell, John G., Jr.

1961-01-01

Flutter tests have been made on flat panels having a 1/4 inch-thick plastic-foam core covered with thin fiber-glass laminates. The testing was done in the Langley Unitary Plan wind tunnel at Mach numbers from 1.76 t o 2.87. The flutter boundary for these panels was found to be near the flutter boundary of thin metal panels when compared on the basis of an equivalent panel stiffness. The results also demonstrated that the depth of the cavity behind the panel has a pronounced influence on flutter. Changing the cavity depth from 1 1/2 inches to 1/2 inch reduced the dynamic pressure at start of flutter by 40 percent. No flutter was obtained when the spacers on the back of the panel were against the bottom of the cavity.

Panel Resource Management (PRM) Implementation and Effects within Safety Review Panel Settings and Dynamics

Science.gov (United States)

Taylor, Robert W.; Nash, Sally K.

2007-01-01

While technical training and advanced degree's assure proficiency at specific tasks within engineering disciplines, they fail to address the potential for communication breakdown and decision making errors familiar to multicultural environments where language barriers, intimidating personalities and interdisciplinary misconceptions exist. In an effort to minimize these pitfalls to effective panel review, NASA's lead safety engineers to the ISS Safety Review Panel (SRP), and Payload Safety Review Panel (PSRP) initiated training with their engineers, in conjunction with the panel chairs, and began a Panel Resource Management (PRM) program. The intent of this program focuses on the ability to reduce the barriers inhibiting effective participation from all panel attendees by bolstering participants confidence levels through increased communication skills, situational awareness, debriefing, and a better technical understanding of requirements and systems.

Solar panel cleaning robot

Science.gov (United States)

Nalladhimmu, Pavan Kumar Reddy; Priyadarshini, S.

2018-04-01

As the demand of electricity is increasing, there is need to using the renewable sources to produce the energy at present of power shortage, the use of solar energy could be beneficial to great extent and easy to get the maximum efficiency. There is an urgent in improving the efficiency of solar power generation. Current solar panels setups take a major power loss when unwanted obstructions cover the surface of the panels. To make solar energy more efficiency of solar array systems must be maximized efficiency evaluation of PV panels, that has been discussed with particular attention to the presence of dust on the efficiency of the PV panels have been highlighted. This paper gives the how the solar panel cleaning system works and designing of the cleaning system.

Topical session proceedings of the 5. IGSC meeting on: observations regarding the safety case in recent safety assessment studies

International Nuclear Information System (INIS)

Hooper, Alan J.; Voinis, Sylvie; Van Luik, Abraham E.

2004-01-01

Within the NEA, the IGSC (Integration Group for the Safety Case) has, as an essential role, to develop common views on such key aspects of the safety case. Therefore, since the inauguration of the IGSC in 2000, four meetings were organised with topical sessions to explore various of these key aspects. This is a report on the fifth such topical session, held as part of the 5. plenary meeting of the IGSC. The session was attended by 36 participants, representing waste management organisations and regulatory authorities from 16 NEA member countries, the IAEA and the European Commission. The purpose of this topical session was to provide support to the finalising of the IGSC safety case brochure by getting a description of the safety case content of the IAEA Draft Safety Requirements document and by getting an overview of progress that could be observed from national organisations on developing their cases for system safety and/or developing the required methodologies. The objective was that the IGSC safety case brochure should be supportive of the IAEA/NEA document, and be reflective of the experience of the IGSC member programmes and organisations. The topical session was mainly aimed at exchanging information on: - The safety case related content of the proposed IAEA/NEA document (currently titled: 'IAEA Safety Standards Series, Geological Disposal of Radioactive Waste, Draft Safety Requirements (DS-154)'). - National programmes where safety assessments have recently been completed, e.g. ONDRAF/NIRAS, Nagra and Andra. - Feedback from international peer reviews, e.g. the Andra Dossier 2001 Argile, the Belgian SAFIR 2 report, the SR 97 report and the US-DOE Yucca Mountain TSPA. - The evolution of some national assessment methods and approaches e.g. SKB and Nagra. - The content of the draft IGSC safety case brochure entitled: 'The Nature and Purpose of the Post-closure Safety Case in Geological Disposal'. This document presents the various

Evaluation and review of alternative waste forms for immobilization of high level radioactive wastes. Report number 3

International Nuclear Information System (INIS)

1981-01-01

A discussion of the relative strengths and weaknesses of the alternative forms and recommendations for future program directions are presented in the body of this report. In addition to the relative ranking, the Peer Review Panel makes the following observations and recommendations: (1) Differences in overall performance of most of the uncoated waste forms are relatively small when compared under approximately equivalent conditions. (2) The increased scientific basis for this class of waste forms has not yet been sufficient to achieve reliably large improvements in waste form performance over the best borosilicate glasses. (3) The increased leach rates at elevated temperatures and the uncertainty regarding mechanisms of leaching under repository conditions continue to indicate that surface temperatures of waste canisters and especially any waste form-water interfaces should be restricted to less than 100 0 C, until more data is available to indicate otherwise. (4) Improvements are noteworthy, but there is still a need for adopting additional standardized tests, standard reference materials, common units and standardized methods of data presentation in the nuclear waste program. (5) Comparative data on leach rates in waters equilibrated with candidate rocks and potential geologic environments are almost non-existent and are essential to establish relevant long term extrapolation of waste form performance.(6) Understanding radiation damage effects on the microstructure and leaching mechanisms of polycrystalline ceramics is still insufficient to judge long term reliability of this class of waste forms. (7) More extensive data on rates and mechanisms of leaching of all waste forms under radiation and repository conditions are needed. (8) Additional studies of fundamental mechanisms controlling long term reliability of glass and alternative waste forms are strongly encouraged

47 CFR 97.513 - VE session manager requirements.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 5 2010-10-01 2010-10-01 false VE session manager requirements. 97.513 Section... SERVICES AMATEUR RADIO SERVICE Qualifying Examination Systems § 97.513 VE session manager requirements. (a) A VE session manager may be selected by the VE team for each examination session. The VE session...

Lightweight, Thermally Insulating Structural Panels

Science.gov (United States)

Eisen, Howard J.; Hickey, Gregory; Wen, Liang-Chi; Layman, William E.; Rainen, Richard A.; Birur, Gajanana C.

1996-01-01

Lightweight, thermally insulating panels that also serve as structural members developed. Honeycomb-core panel filled with low-thermal-conductivity, opacified silica aerogel preventing convection and minimizes internal radiation. Copper coating on face sheets reduces radiation. Overall thermal conductivities of panels smaller than state-of-art commercial non-structurally-supporting foam and fibrous insulations. On Earth, panels suitable for use in low-air-pressure environments in which lightweight, compact, structurally supporting insulation needed; for example, aboard high-altitude aircraft or in partially evacuated panels in refrigerators.

IV meeting of R and d in research and technological development of radioactive waste management. Vol. 3

International Nuclear Information System (INIS)

2001-01-01

These Technical Publications include the main papers presented during the IV R and D symposium on Radioactive Wastes Management Technology, promoted by ENRESA and held in the Barcelona University during November 2001. The papers correspond both to the Technical Sessions and the Seminars and they are a document of inestimable value that indicates the high technological value reached in the radioactive waste management as a result of a clear and continuous R and D politics together with an intense and productive international collaboration. Throughout the papers of this document the technological status and the capacities developed in all different fields of the radioactive waste management are shown. The main subjects discussed include: low and medium activity wastes management, dismantling of nuclear plants, partitioning and transmutation of long life radionuclide and mainly deep geological disposal. Through the papers corresponding to the scientific sessions the state of the art in the mentioned areas is reviewed with special emphasis, as the achievements and developments reached in Spain. Through the seminars, many outstanding aspects of the R and D in radioactive wastes such as the biosphere role, the numerical modelling and the underground laboratories, can be studied in depth. (Author)

IV meeting of R and D in research and technological development of radioactive waste management. Vol. 4

International Nuclear Information System (INIS)

2001-01-01

These Technical Publications include the main papers presented during the IV R and d Symposium on Radioactive Wastes Management Technology, promoted by ENRESA and held in the Barcelona University during November 2001. The papers correspond both to the technical Sessions and the Seminars and they are a document of inestimable value that indicates the high technological value reached in the radioactive waste management as a result of a clear and continuous R and D politics together with an intense and productive international collaboration. Throughout the papers of this document the technological status and the capacities developed in all different fields of the radioactive waste management are shown. the main subjects discussed include: low and medium activity wastes management, dismantling of nuclear plants, partitioning and transmutation of long life radionuclide and mainly deep geological disposal. Through the papers corresponding to the scientific sessions the state of the art in the mentioned areas is reviewed with special emphasis as the achievements and developments reached in Spain. Through the seminars, many outstanding aspects of the R and D in radioactive wastes such as the biosphere role, the numerical modelling and the underground laboratories, can be studied in depth. (Author)

IV meeting of R and D in research and technological development of radioactive waste management. Vol. 1

International Nuclear Information System (INIS)

2001-01-01

These Technical Publications include the main papers presented during the IV R and D Symposium on Radioactive Wastes management Technology, promoted by ENRESA and held in the Barcelona University during November 2001. The papers correspond both to the Technical Sessions and the Seminars and they are a document of inestimable value that indicates the high technological value reached in the radioactive waste management as a result of a clear and continuous R and D politics together with in intense and productive international collaboration. Throughout the papers of this document the technological status and the capacities developed in all different fields of the radioactive waste management are shown. The main subjects discussed include: low and medium activity wastes management, dismantling of nuclear plants, partitioning and transmutation of long life radionuclide and mainly deep geological disposal. Through the papers corresponding to the scientific sessions the state of the art in the mentioned areas is reviewed with special emphasis, as the achievements and developments reached in Spain. Through the seminars, many outstanding aspects of the R and D in radioactive wastes such as the biosphere role, the numerical modelling and the underground laboratories, can be studies in depth. (Author)

Proceedings of the Third Annual Information Meeting DOE Low-Level Waste-Management Program

Energy Technology Data Exchange (ETDEWEB)

Large, D.E.; Lowrie, R.S.; Stratton, L.E.; Jacobs, D.G. (comps.)

1981-12-01

The Third Annual Participants Information Meeting of the Low-Level Waste Management Program was held in New Orleans, Louisiana, November 4-6, 1981 The specific purpose was to bring together appropriate representatives of industry, USNRC, program management, participating field offices, and contractors to: (1) exchange information and analyze program needs, and (2) involve participants in planning, developing and implementing technology for low-level waste management. One hundred seven registrants participated in the meeting. Presentation and workshop findings are included in these proceedings under the following headings: low-level waste activities; waste treatment; shallow land burial; remedial action; greater confinement; ORNL reports; panel workshops; and summary. Forty-six papers have been abstracted and indexed for the data base.

Proceedings of the Third Annual Information Meeting DOE Low-Level Waste-Management Program

International Nuclear Information System (INIS)

Large, D.E.; Lowrie, R.S.; Stratton, L.E.; Jacobs, D.G.

1981-12-01

The Third Annual Participants Information Meeting of the Low-Level Waste Management Program was held in New Orleans, Louisiana, November 4-6, 1981 The specific purpose was to bring together appropriate representatives of industry, USNRC, program management, participating field offices, and contractors to: (1) exchange information and analyze program needs, and (2) involve participants in planning, developing and implementing technology for low-level waste management. One hundred seven registrants participated in the meeting. Presentation and workshop findings are included in these proceedings under the following headings: low-level waste activities; waste treatment; shallow land burial; remedial action; greater confinement; ORNL reports; panel workshops; and summary. Forty-six papers have been abstracted and indexed for the data base

PERBANDINGAN UNJUK KERJA ANTARA PANEL SEL SURYA BERPENJEJAK DENGAN PANEL SEL SURYA DIAM

OpenAIRE

Syafaruddin Ch

2010-01-01

The ability to produce electrical energy at Solar Power Plant  is highly dependent on the magnitude and duration of sun exposure on the solar cell panels. The movement of the sun from east to west that periodicity in every day is a problem at  the  optimization generation of electricity at  Solar Power Plant   if using solar panel that motionless. This is because the solar cell panel can not catch the maximum sun exposure. To solve the above problem then designed a solar cell panel  tracker...

Clays in natural and engineered barriers for radioactive waste confinement

International Nuclear Information System (INIS)

2007-01-01

The meeting covers all topics concerning natural argillaceous geological barriers and the clay material based engineered barrier systems, investigated by means of: laboratory experiments on clay samples (new analytical developments), in situ experiments in underground research laboratories, mock-up demonstrations, natural analogues, as well as numerical modelling and global integration approaches (including up-scaling processes and treatment of uncertainties). The works presented deal with: examples of broad research programs (national or international) on the role of natural and artificial clay barriers for radionuclide confinement; clay-based repository concepts: repository designs, including technological and safety issues related to the use of clay for nuclear waste confinement; geology and clay characterisation: mineralogy, sedimentology, paleo-environment, diagenesis, dating techniques, discontinuities in rock clay, fracturing, self sealing processes, role of organic matter and microbiological processes; geochemistry: pore water geochemistry, clay thermodynamics, chemical retention, geochemical modelling, advanced isotopic geochemistry; mass transfer: water status and hydraulic properties in low permeability media, pore space geometry, water, solute and gas transfer processes, colloid mediated transport, large scale movements, long-term diffusion; alteration processes: oxidation effects, hydration-dehydration processes, response to thermal stress, iron-clay interactions, alkaline perturbation; geomechanics: thermo-hydro-mechanical behaviour of clay, rheological models, EDZ characterisation and evolution, coupled behaviour and models (HM, THM, THMC). A particular interest is given to potential contributions coming from fields of activities other than radioactive waste management, which take advantage of the confinement properties of the clay barrier (oil and gas industries, gas geological storage, CO 2 geological sequestration, chemical waste isolation

Clays in natural and engineered barriers for radioactive waste confinement

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

The meeting covers all topics concerning natural argillaceous geological barriers and the clay material based engineered barrier systems, investigated by means of: laboratory experiments on clay samples (new analytical developments), in situ experiments in underground research laboratories, mock-up demonstrations, natural analogues, as well as numerical modelling and global integration approaches (including up-scaling processes and treatment of uncertainties). The works presented deal with: examples of broad research programs (national or international) on the role of natural and artificial clay barriers for radionuclide confinement; clay-based repository concepts: repository designs, including technological and safety issues related to the use of clay for nuclear waste confinement; geology and clay characterisation: mineralogy, sedimentology, paleo-environment, diagenesis, dating techniques, discontinuities in rock clay, fracturing, self sealing processes, role of organic matter and microbiological processes; geochemistry: pore water geochemistry, clay thermodynamics, chemical retention, geochemical modelling, advanced isotopic geochemistry; mass transfer: water status and hydraulic properties in low permeability media, pore space geometry, water, solute and gas transfer processes, colloid mediated transport, large scale movements, long-term diffusion; alteration processes: oxidation effects, hydration-dehydration processes, response to thermal stress, iron-clay interactions, alkaline perturbation; geomechanics: thermo-hydro-mechanical behaviour of clay, rheological models, EDZ characterisation and evolution, coupled behaviour and models (HM, THM, THMC). A particular interest is given to potential contributions coming from fields of activities other than radioactive waste management, which take advantage of the confinement properties of the clay barrier (oil and gas industries, gas geological storage, CO{sub 2} geological sequestration, chemical waste isolation

Panel data analysis using EViews

CERN Document Server

Agung, I Gusti Ngurah

2013-01-01

A comprehensive and accessible guide to panel data analysis using EViews software This book explores the use of EViews software in creating panel data analysis using appropriate empirical models and real datasets. Guidance is given on developing alternative descriptive statistical summaries for evaluation and providing policy analysis based on pool panel data. Various alternative models based on panel data are explored, including univariate general linear models, fixed effect models and causal models, and guidance on the advantages and disadvantages of each one is given. Panel Data Analysis

Waste Isolation Pilot Plant Annual Site Environmental Report for 2005

International Nuclear Information System (INIS)

2006-01-01

research and development. The waste must also meet the WIPP Waste Acceptance Criteria. When TRU waste arrives at WIPP, it is transported into the Waste Handling Building. The waste containers are removed from the shipping containers, placed on the waste hoist, and lowered to the repository level of 655 m (2,150 ft; approximately 0.5 mi) below the surface. Next, the containers of waste are removed from the hoist and placed in excavated disposal rooms in the Salado Formation, a thick sequence of evaporite beds deposited approximately 250 million years ago (Figure 1.1). After each panel of seven rooms has been filled with waste, specially designed closures are emplaced. When all of WIPP's panels have been filled, at the conclusion of WIPP operations, seals will be placed in the shafts. One of the main attributes of salt, as a rock formation in which to isolate radioactive waste, is the ability of the salt to creep, that is, to deform continuously over time. Excavations into which the waste-filled drums are placed will close eventually, flowing around the drums and sealing them within the formation.

Decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Schneider, K.J.

1979-01-01

The Symposium was jointly sponsored by OECD/NEA and IAEA and was attended by more than 225 participants from 26 countries. Forty one papers were presented in eight sessions which covered the following topics: national and international policies and planning; engineering considerations relevant to decommissioning; radiological release considerations and waste classifications; decommissioning experience; and decontamination and remote operations. In addition, a panel of decommissioning experts discussed questions from the participants

RECIPANEL: RECYCLED PAPER PANELS

Directory of Open Access Journals (Sweden)

HERNÁN CAÑOLA

2012-01-01

Full Text Available En este artículo se estudia la fabricación y el comportamiento mecánico de paneles a base de papel reciclado. El objetivo principal del proyecto es producir un prototipo de panel que emplee elementos provenientes de residuos sólidos (papel periódico y de un material conglomerante (cemento Portland blanco. El panel debe ser económico, debe tener buenas propiedades mecánicas y debe tener dimensiones comerciales para su uso en muros tabiques y en cielos falsos en la industria de la construcción. El Recipanel es un panel no estructural a base de papel reciclado. El Recipanel cumple las normas colombianas en lo relativo a los paneles de uso no estructural y presenta además unas excelentes características mecánicas.

Technology Evaluation Workshop Report for Tank Waste Chemical Characterization

International Nuclear Information System (INIS)

Eberlein, S.J.

1994-04-01

A Tank Waste Chemical Characterization Technology Evaluation Workshop was held August 24--26, 1993. The workshop was intended to identify and evaluate technologies appropriate for the in situ and hot cell characterization of the chemical composition of Hanford waste tank materials. The participants were asked to identify technologies that show applicability to the needs and good prospects for deployment in the hot cell or tanks. They were also asked to identify the tasks required to pursue the development of specific technologies to deployment readiness. This report describes the findings of the workshop. Three focus areas were identified for detailed discussion: (1) elemental analysis, (2) molecular analysis, and (3) gas analysis. The technologies were restricted to those which do not require sample preparation. Attachment 1 contains the final workshop agenda and a complete list of attendees. An information package (Attachment 2) was provided to all participants in advance to provide information about the Hanford tank environment, needs, current characterization practices, potential deployment approaches, and the evaluation procedure. The participants also received a summary of potential technologies (Attachment 3). The workshop opened with a plenary session, describing the background and issues in more detail. Copies of these presentations are contained in Attachments 4, 5 and 6. This session was followed by breakout sessions in each of the three focus areas. The workshop closed with a plenary session where each focus group presented its findings. This report summarizes the findings of each of the focus groups. The evaluation criteria and information about specific technologies are tabulated at the end of each section in the report. The detailed notes from each focus group are contained in Attachments 7, 8 and 9

WIPP's Hazardous Waste Facility Permit Renewal Application

International Nuclear Information System (INIS)

Most, W.A.; Kehrman, R.F.

2009-01-01

Hazardous waste permits issued by the New Mexico Environment Department (NMED) have a maximum term of 10-years from the permit's effective date. The permit condition in the Waste Isolation Pilot Plant's (WIPP) Hazardous Waste Facility Permit (HWFP) governing renewal applications, directs the Permittees to submit a permit application 180 days prior to expiration of the Permit. On October 27, 1999, the Secretary of the NMED issued to the United States Department of Energy (DOE), the owner and operator of WIPP, and to Washington TRU Solutions LLC (WTS), the Management and Operating Contractor and the cooperator of WIPP, a HWFP to manage, store, and dispose hazardous waste at WIPP. The DOE and WTS are collectively known as the Permittees. The HWFP is effective for a fixed term not to exceed ten years from the effective date of the Permit. The Permittees may renew the HWFP by submitting a new permit application at least 180 calendar days before the expiration date, of the HWFP. The Permittees are not proposing any substantial changes in the Renewal Application. First, the Permittees are seeking the authority to dispose of Contact-Handled and Remote-Handled TRU mixed waste in Panel 8. Panels 4 through 7 have been approved in the WIPP Hazardous Waste Facility Permit as it currently exists. No other change to the facility or to the manner in which hazardous waste is characterized, managed, stored, or disposed is being requested. Second, the Permittees also seek to include the Mine Ventilation Rate Monitoring Plan, as Attachment Q in the HWFP. This Plan has existed as a separate document since May 2000. The NMED has requested that the Plan be submitted as part of the Renewal Application. The Permittees have been operating to the Mine Ventilation Rate Monitoring Plan since the Plan was submitted. Third, some information submitted in the original WIPP RCRA Part B Application has been updated, such as demographic information. The Permittees will submit this information in the

Summary of Technical Sessions - Summary and Recommendations

International Nuclear Information System (INIS)

2013-01-01

Technical Session 1 - Development achievements of BEPU methods and State of the Art: The objective of this session was to present the different approaches dealing with Best Estimate codes and uncertainties evaluations. Existing methods were summarized and different papers were focused on specific methods stressing their bases, peculiarities, advantages and limitations. As a result of the session a picture of the current State of the Art was obtained. The session comprised six papers. Technical Session 2 - International comparative activities: This session had as a main objective to review the activities launched in the past and present from the NEA in connection with BEPU methods, with focus on the applicability of conclusions derived from former benchmarks like UMS, the main outcomes of the recently finished BEMUSE project, and the objectives and relevance of UAM and PREMIUM projects. The session comprised four papers. Technical Session 3 - Applications: Licensing, safety analysis support, regulatory body views and industry activities: This session focused on the application of current methods in safety analyses. Contributions from industry, technical safety organizations and regulatory bodies were provided. As a result, a view of the penetration of BEPU methods in current safety analyses was obtained, as well as an indication of the evolution in the near future. Elements such as licensing practices, assessment process, etc. were considered. The session comprised nine papers. Technical Session 4. BEPU methods extension to new fields The session addressed the extension of BEPU methods beyond their current use. By now such methods are mainly applied to classic deterministic environment but it is believed that their benefits could be extended to other fields. Seven papers were presented in the session dealing with subjects that fit in the objectives established in the workshop programme. The papers cover areas like: extension to CFD, quantification of global safety

Peer review of the Nevada Nuclear Waste Storage Investigations, August 24-28, 1981

Energy Technology Data Exchange (ETDEWEB)

NONE

1984-02-01

On August 24-28, 1981, a peer review of three major areas of the Nevada Nuclear Waste Storage Investigations was conducted at the Riviera Hotel in Las Vegas, Nevada. The three investigative areas were: (1) geology/hydrology, (2) geotechnical/geoengineering, and (3) environmental studies. A separate review panel was established for each of the investigative areas which was composed of experts representing appropriate fields of expertise. A total of twenty nationally known or prominent state and local experts served on the three review panels.

Peer review of the Nevada Nuclear Waste Storage Investigations, August 24-28, 1981

International Nuclear Information System (INIS)

1984-02-01

On August 24-28, 1981, a peer review of three major areas of the Nevada Nuclear Waste Storage Investigations was conducted at the Riviera Hotel in Las Vegas, Nevada. The three investigative areas were: (1) geology/hydrology, (2) geotechnical/geoengineering, and (3) environmental studies. A separate review panel was established for each of the investigative areas which was composed of experts representing appropriate fields of expertise. A total of twenty nationally known or prominent state and local experts served on the three review panels

Landfill waste and recycling: Use of a screening-level risk assessment tool for end-of-life cadmium telluride (CdTe) thin-film photovoltaic (PV) panels

International Nuclear Information System (INIS)

Cyrs, William D.; Avens, Heather J.; Capshaw, Zachary A.; Kingsbury, Robert A.; Sahmel, Jennifer; Tvermoes, Brooke E.

2014-01-01

Grid-connected solar photovoltaic (PV) power is currently one of the fastest growing power-generation technologies in the world. While PV technologies provide the environmental benefit of zero emissions during use, the use of heavy metals in thin-film PV cells raises important health and environmental concerns regarding the end-of-life disposal of PV panels. To date, there is no published quantitative assessment of the potential human health risk due to cadmium leaching from cadmium telluride (CdTe) PV panels disposed in a landfill. Thus, we used a screening-level risk assessment tool to estimate possible human health risk associated with disposal of CdTe panels into landfills. In addition, we conducted a literature review of potential cadmium release from the recycling process in order to contrast the potential health risks from PV panel disposal in landfills to those from PV panel recycling. Based on the results of our literature review, a meaningful risk comparison cannot be performed at this time. Based on the human health risk estimates generated for PV panel disposal, our assessment indicated that landfill disposal of CdTe panels does not pose a human health hazard at current production volumes, although our results pointed to the importance of CdTe PV panel end-of-life management. - Highlights: • Analysis of possible human health risk posed by disposal of CdTe panels into landfills. • Qualitative comparison of risks associated with landfill disposal and recycling of CdTe panels. • Landfill disposal of CdTe panels does not pose a human health hazard at current production volumes. • There could be potential risks associated with recycling if not properly managed. • Factors other than concerns over toxic substances will likely drive the decisions of how to manage end-of-life PV panels

Characteristics of potential repository wastes

International Nuclear Information System (INIS)

Cowart, C.G.; Notz, K.J.

1992-10-01

This report presents the results of a fully documented peer review of DOE/RW-0184, Rev. 1, ''Characteristics of Potential Repository Wastes''. The peer review was chaired and administered by oak Ridge National Laboratory (ORNL) for the Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) and was conducted in accordance with OCRWM QA procedure QAAP 3.3 ''Peer Review'' for the purpose of quailing the document for use in OCRWM quality-affecting work. The peer reviewers selected represent a wide range of experience and knowledge particularly suitable for evaluating the subject matter. A total of 596 formal comments were documented by the seven peer review panels, and all were successfully resolved. The peers reached the conclusion that DOE/RW-0184, Rev. 1, is quality determined and suitable for use in quality-affecting work

High-level nuclear waste disposal

International Nuclear Information System (INIS)

Burkholder, H.C.

1985-01-01

The meeting was timely because many countries had begun their site selection processes and their engineering designs were becoming well-defined. The technology of nuclear waste disposal was maturing, and the institutional issues arising from the implementation of that technology were being confronted. Accordingly, the program was structured to consider both the technical and institutional aspects of the subject. The meeting started with a review of the status of the disposal programs in eight countries and three international nuclear waste management organizations. These invited presentations allowed listeners to understand the similarities and differences among the various national approaches to solving this very international problem. Then seven invited presentations describing nuclear waste disposal from different perspectives were made. These included: legal and judicial, electric utility, state governor, ethical, and technical perspectives. These invited presentations uncovered several issues that may need to be resolved before high-level nuclear wastes can be emplaced in a geologic repository in the United States. Finally, there were sixty-six contributed technical presentations organized in ten sessions around six general topics: site characterization and selection, repository design and in-situ testing, package design and testing, disposal system performance, disposal and storage system cost, and disposal in the overall waste management system context. These contributed presentations provided listeners with the results of recent applied RandD in each of the subject areas

Make Your Own Solar Panel.

Science.gov (United States)

Suzuki, David

1992-01-01

Presents an activity in which students make a simulated solar panel to learn about the principles behind energy production using solar panels. Provides information about how solar panels function to produce energy. (MCO)

Intermediate, low, and very low level waste management at ANDRA (agence nationale pour la gestion des dechets radioactifs) in France

International Nuclear Information System (INIS)

Senoo, Muneaki

2005-01-01

On 28th September in 2004, RANDEC invited Mr. Jean-Louis Tison from ANDRA as a lecturer of the special session of the 16th RANDEC Annual Symposium. An ANDRA-RANDEC technical meeting was held on the next day, where Mr. Vincent Carlier invited from ANDRA, too participated. Here, present status of intermediate, low, and very low level waste management in France is reviewed based on the information which were obtained from the special session of the 16th RANDEC Annual Symposium and the ANDRA-RANDEC technical meeting. In France, ANDRA is implementing radioactive waste management under the following policy; 'Intermediate, low, and very-low-level (ILVLL) waste is managed in order to establish as soon as possible a final disposal system, the temporary or long term storage option being considered only for the high-level waste (HLW) such as the vitrified fission products or particular materials such as some sealed sources for which no final disposal solution still exists.' The Agency is financed on the basis of the 'polluter-pays' principle and contracts its services directly with waste owners. (author)

DRSPALL :spallings model for the Waste Isolation Pilot Plant 2004 recertification.

Energy Technology Data Exchange (ETDEWEB)

Gilkey, Amy P. (GRAM Inc., Albuquerque, NM); Hansen, Clifford W.; Schatz, John F. (John F. Schatz Research & Consulting, Inc., Del Mar, CA); Rudeen, David Keith (GRAM Inc., Albuquerque, NM); Lord, David L.

2006-02-01

This report presents a model to estimate the spallings releases for the Waste Isolation Pilot Plant Performance Assessment (WIPP PA). A spallings release in the context of WIPP PA refers to a portion of the solid waste transported from the subsurface repository to the ground surface due to inadvertent oil or gas drilling into the WIPP repository at some time after site closure. Some solid waste will be removed by the action of the drillbit and drilling fluid; this waste is referred to as cuttings and cavings. If the repository is pressurized above hydrostatic at the time of intrusion, solid waste material local to the borehole may be subject to mechanical failure and entrainment in high-velocity gases as the repository pressure is released to the borehole. Solid material that fails and is transported into the wellbore and thus to the surface comprise the spallings releases. The spallings mechanism is analogous to a well blowout in the modern oil and gas drilling industry. The current spallings conceptual model and associated computer code, DRSPALL, were developed for the 2004 recertification because the prior spallings model used in the 1996 WIPP Compliance Certification Application (CCA) was judged by an independent peer review panel as inadequate (DOE 1996, 9.3.1). The current conceptual model for spallings addresses processes that take place several minutes before and after a borehole intrusion of a WIPP waste room. The model couples a pipe-flow wellbore model with a porous flow repository model, allowing high-pressure gas to flow from the repository to the wellbore through a growing cavity region at the well bottom. An elastic stress model is applied to the porous solid domain that allows for mechanical failure of repository solids if local tensile stress exceeds the tensile strength of the waste. Tensile-failed solids may be entrained into the wellbore flow stream by a fluidized bed model, in which case they are ultimately transported to the land surface

Proceedings of the Canadian Nuclear Society 2. international conference on radioactive waste management

International Nuclear Information System (INIS)

1986-01-01

These proceedings contain 136 papers on waste management from 19 countries. An index of the delegates and their affiliations is included. Emphasis was laid on the Canadian program for geologic disposal in hard rock. Sessions dealt with the following: storage and disposal, hydrogeology and geochemistry, transportation, buffers and backfill, public attitudes, tailings, site investigations and geomechanics, concrete, economics, licensing, matrix materials and container design, durability of fuel, biosphere modelling, radioactive waste processing, and future options

Non-Thermal Plasma (NTP) session overview: Second International Symposium on Environmental Applications of Advanced Oxidation Technologies (AOTs)

International Nuclear Information System (INIS)

Rosocha, L.A.

1996-01-01

Advanced Oxidation Technologies (used in pollution control and treating hazardous wastes) has expanded from using hydroxyl radicals to treat organic compounds in water, to using reductive free radicals as well, and to application to pollutants in both gases and aqueous media. Non-Thermal Plasma (NTP) is created in a gas by an electrical discharge or energetic electron injection. Highly reactive species (O atoms, OH, N radicals, plasma electrons) react with entrained hazardous organic chemicals in the gas, converting them to CO2, H2O, etc. NTP can be used to simultaneously remove different kinds of pollutants (eg, VOCs, SOx, NOx in flue gases). This paper presents an overview of NTP technology for pollution control and hazardous waste treatment; it is intended as an introduction to the NTP session of the symposium

Statement to the 47th session of the United Nations General Assembly

International Nuclear Information System (INIS)

Blix, H.

1993-01-01

IAEA Director General, Hans Blix, in his statement to the 47th session of the United Nations General Assembly on 21 October 1992, reminded that 1992 marks the fiftieth anniversary of controlled nuclear fission and the thirty-fifth anniversary of the IAEA. He specially commented on the various measures taken during the past year to strengthen the IAEA's safeguards system as a part of the challenge to reduce the risk of a further spread of nuclear weapons. He also discussed the role of the IAEA in the fields of nuclear safety, nuclear waste, transfer of technology and assistance to developing countries and the financing and management of the Agency within the UN system

Solar panel parallel mounting configuration

Science.gov (United States)

Mutschler, Jr., Edward Charles (Inventor)

1998-01-01

A spacecraft includes a plurality of solar panels interconnected with a power coupler and an electrically operated device to provide power to the device when the solar cells are insolated. The solar panels are subject to bending distortion when entering or leaving eclipse. Spacecraft attitude disturbances are reduced by mounting each of the solar panels to an elongated boom made from a material with a low coefficient of thermal expansion, so that the bending of one panel is not communicated to the next. The boom may be insulated to reduce its bending during changes in insolation. A particularly advantageous embodiment mounts each panel to the boom with a single mounting, which may be a hinge. The single mounting prevents transfer of bending moments from the panel to the boom.

Seismic hazard analysis. Review panel, ground motion panel, and feedback results

International Nuclear Information System (INIS)

Bernreuter, D.L.

1981-10-01

The Site Specific Spectra Project (SSSP) was a multi-year study funded by the U.S. Nuclear Regulatory Commission to provide estimates of the seismic hazards at a number of nuclear power plant sites in the Eastern U.S. A key element of our approach was the Peer Review Panel, which we formed in order to ensure that our use of expert opinion was reasonable. We discuss the Peer Review Panel results and provide the complete text of each member's report. In order to improve the ground motion model, an Eastern U.S. Ground Motion Model Panel was formed. In Section 4 we tabulate the responses from the panel members to our feedback questionnaire and discuss the implications of changes introduced by them. We conclude that the net difference in seismic hazard values from those presented in Volume 4 is small and does not warrant a reanalysis. (author)

Mounting clips for panel installation

Science.gov (United States)

Cavieres, Andres; Al-Haddad, Tristan; Goodman, Joseph

2017-07-11

A photovoltaic panel mounting clip comprising a base, central indexing tabs, flanges, lateral indexing tabs, and vertical indexing tabs. The mounting clip removably attaches one or more panels to a beam or the like structure, both mechanically and electrically. It provides secure locking of the panels in all directions, while providing guidance in all directions for accurate installation of the panels to the beam or the like structure.

Current and potential uses of bioactive molecules from marine processing waste.

Science.gov (United States)

Suleria, Hafiz Ansar Rasul; Masci, Paul; Gobe, Glenda; Osborne, Simone

2016-03-15

Food industries produce huge amounts of processing waste that are often disposed of incurring expenses and impacting upon the environment. For these and other reasons, food processing waste streams, in particular marine processing waste streams, are gaining popularity amongst pharmaceutical, cosmetic and nutraceutical industries as sources of bioactive molecules. In the last 30 years, there has been a gradual increase in processed marine products with a concomitant increase in waste streams that include viscera, heads, skins, fins, bones, trimmings and shellfish waste. In 2010, these waste streams equated to approximately 24 million tonnes of mostly unused resources. Marine processing waste streams not only represent an abundant resource, they are also enriched with structurally diverse molecules that possess a broad panel of bioactivities including anti-oxidant, anti-coagulant, anti-thrombotic, anti-cancer and immune-stimulatory activities. Retrieval and characterisation of bioactive molecules from marine processing waste also contributes valuable information to the vast field of marine natural product discovery. This review summarises the current use of bioactive molecules from marine processing waste in different products and industries. Moreover, this review summarises new research into processing waste streams and the potential for adoption by industries in the creation of new products containing marine processing waste bioactives. © 2015 Society of Chemical Industry.

The Neuromuscular, Biochemical, and Endocrine Responses to a Single-Session Vs. Double-Session Training Day in Elite Athletes.

Science.gov (United States)

Johnston, Michael J; Cook, Christian J; Drake, David; Costley, Lisa; Johnston, Julie P; Kilduff, Liam P

2016-11-01

Johnston, MJ, Cook, CJ, Drake, D, Costley, L, Johnston, JP, and Kilduff, LP. The neuromuscular, biochemical, and endocrine responses to a single-session vs. double-session training day in elite athletes. J Strength Cond Res 30(11): 3098-3106, 2016-The aim of this study was to compare the acute neuromuscular, biochemical, and endocrine responses of a training day consisting of a speed session only with performing a speed-and-weights training session on the same day. Fifteen men who were academy-level rugby players completed 2 protocols in a randomized order. The speed-only protocol involved performing 6 maximal effort repetitions of 50-m running sprints with 5 minutes of recovery between each sprint, whereas the speed-and-weights protocol involved the same sprinting session but was followed 2 hours later by a lower-body weights session consisting of 4 sets of 5 backsquats and Romanian deadlift at 85% one repetition maximum. Testosterone, cortisol, creatine kinase, lactate, and perceived muscle soreness were determined immediately before, immediately after, 2 hours after, and 24 hours after both the protocols. Peak power, relative peak power, jump height, and average rate of force development were determined from a countermovement jump (CMJ) at the same time points. After 24-hours, muscle soreness was significantly higher after the speed-and-weights protocol compared with the speed-only protocol (effect size η = 0.253, F = 4.750, p ≤ 0.05). There was no significant difference between any of the CMJ variables at any of the posttraining time points. Likewise, creatine kinase, testosterone, and cortisol were unaffected by the addition of a weight-training session. These data indicate that the addition of a weight-training session 2 hours after a speed session, whereas increasing the perception of fatigue the next day does not result in a difference in endocrine response or in neuromuscular capability.

Greenhouse gas accounting and waste management.

Science.gov (United States)

Gentil, Emmanuel; Christensen, Thomas H; Aoustin, Emmanuelle

2009-11-01

Accounting of emissions of greenhouse gas (GHG) is a major focus within waste management. This paper analyses and compares the four main types of GHG accounting in waste management including their special features and approaches: the national accounting, with reference to the Intergovernmental Panel on Climate Change (IPCC), the corporate level, as part of the annual reporting on environmental issues and social responsibility, life-cycle assessment (LCA), as an environmental basis for assessing waste management systems and technologies, and finally, the carbon trading methodology, and more specifically, the clean development mechanism (CDM) methodology, introduced to support cost-effective reduction in GHG emissions. These types of GHG accounting, in principle, have a common starting point in technical data on GHG emissions from specific waste technologies and plants, but the limited availability of data and, moreover, the different scopes of the accounting lead to many ways of quantifying emissions and producing the accounts. The importance of transparency in GHG accounting is emphasised regarding waste type, waste composition, time period considered, GHGs included, global warming potential (GWP) assigned to the GHGs, counting of biogenic carbon dioxide, choice of system boundaries, interactions with the energy system, and generic emissions factors. In order to enhance transparency and consistency, a format called the upstream-operating-downstream framework (UOD) is proposed for reporting basic technology-related data regarding GHG issues including a clear distinction between direct emissions from waste management technologies, indirect upstream (use of energy and materials) and indirect downstream (production of energy, delivery of secondary materials) activities.

Performance objectives of the tank waste remediation system low-level waste disposal program

International Nuclear Information System (INIS)

1994-01-01

Before low-level waste may be disposed of, a performance assessment must be written and then approved by the U.S. Department of Energy. The performance assessment is to determine whether open-quotes reasonable assuranceclose quotes exists that the performance objectives of the disposal facility will be met. The DOE requirements for waste disposal require: the protection of public health and safety; and the protection of the environment. Although quantitative limits are sometimes stated (for example, the all exposure pathways exposure limit is 25 mrem/year), usually the requirements are stated in a general nature. Quantitative limits were established by: investigating all potentially applicable regulations as well as interpretations of the Peer Review Panel which DOE has established to review performance assessments, interacting with program management to establish their needs, and interacting with the public (i.e., the Hanford Advisory Board members; as well as affected Indian tribes) to understand the values of residents in the Pacific Northwest

Testing and Performance Validation of a Shielded Waste Segregation and Clearance Monitor Designed for the Measurement of Low Level Waste-13043

International Nuclear Information System (INIS)

Mason, John A.; Burke, Kevin J.; Towner, Antony C.N.; Beaven, Graham; Spence, Robert

2013-01-01

This paper describes the development, testing and validation of a shielded waste segregation and clearance monitor designed for the measurement of low-density low-level waste (LLW). The monitor is made of a measurement chamber surrounded by detectors and a shielded outer frame. The shielded chamber consists of a steel frame, which contains typically 1.5 inches (3.81 cm) of lead and 0.5 inches (1.27 cm) of steel shielding. Inside the shielding are plastic scintillator panels, which serve as gross gamma ray detectors. The detector panels, with embedded photomultipliers, completely surround the internal measurement chamber on all 6 sides. Care has been taken to distribute the plastic scintillator detectors in order to optimise both the efficiency for gamma ray detection and at the same time achieve a volumetric sensitivity, which is as uniform as possible. A common high voltage power supply provides the bias voltage for each of the six photomultipliers. The voltage signals arising from the detectors and photomultipliers are amplified by six sensitive amplifiers. Each amplifier incorporates a single channel analyser with both upper and lower thresholds and the digitised counts from each detector are recorded on six scalars. Operation of the device is by means of a microprocessor from which the scalars are controlled. An internal load cell linked to the microprocessor determines the weight of the waste object, and this information is used to calculate the specific activity of the waste. The monitor makes background measurements when the shielded door is closed and a sample, usually a bag of low-density waste, is not present in the measurement chamber. Measurements of the minimum detectable activity (MDA) of an earlier large volume prototype instrument are reported as part of the development of the Waste Segregation and Clearance Monitor (WSCM) described in the paper. For the optimised WSCM a detection efficiency of greater than 32% was measured using a small Cs-137

Poster Sessions in Marketing Education: An Empirical Examination

Science.gov (United States)

Stegemann, Nicole; Sutton-Brady, Catherine

2009-01-01

Poster sessions provide a creative and stimulating alternative to traditional assessment methods in marketing. Poster sessions, as a means of assessment, have long been used in science fields. This article presents the successful implementation of poster sessions as a means of assessment in a postgraduate unit of study. Poster sessions in…

Attendance at NHS mandatory training sessions.

Science.gov (United States)

Brand, Darren

2015-02-17

To identify factors that affect NHS healthcare professionals' attendance at mandatory training sessions. A quantitative approach was used, with a questionnaire sent to 400 randomly selected participants. A total of 122 responses were received, providing a mix of qualitative and quantitative data. Quantitative data were analysed using statistical methods. Open-ended responses were reviewed using thematic analysis. Clinical staff value mandatory training sessions highly. They are aware of the requirement to keep practice up-to-date and ensure patient safety remains a priority. However, changes to the delivery format of mandatory training sessions are required to enable staff to participate more easily, as staff are often unable to attend. The delivery of mandatory training should move from classroom-based sessions into the clinical area to maximise participation. Delivery should be assisted by local 'experts' who are able to customise course content to meet local requirements and the requirements of different staff groups. Improved arrangements to provide staff cover, for those attending training, would enable more staff to attend training sessions.

Using session types as an effect system

Directory of Open Access Journals (Sweden)

Dominic Orchard

2016-02-01

Full Text Available Side effects are a core part of practical programming. However, they are often hard to reason about, particularly in a concurrent setting. We propose a foundation for reasoning about concurrent side effects using sessions. Primarily, we show that session types are expressive enough to encode an effect system for stateful processes. This is formalised via an effect-preserving encoding of a simple imperative language with an effect system into the pi-calculus with session primitives and session types (into which we encode effect specifications. This result goes towards showing a connection between the expressivity of session types and effect systems. We briefly discuss how the encoding could be extended and applied to reason about and control concurrent side effects.

Session II-J. Sociopolitical initiatives

International Nuclear Information System (INIS)

Mountain, J.M.

1981-01-01

The following papers were presented in this session: (1) state interactions in the NWTS Program; (2) state legislation on nuclear waste disposal; (3) federal legislation - United States House of Representatives; (4) federal legislation - United States Senate; (5) policy aspects of federal-state relations; (6) inplementing a federal-state partnership on repository siting. In the first paper the project manager for the ONWI contractor for sociopolitical research activities discusses the status of state interactions in all of the states covered by the program, including those states where activities are being conducted on federal reservations of the Department of Energy. In the second paper, the legal staff of the Battelle Project Management Division reports on legislative developments affecting the NWTS Program in various states where activities are under way and in states where legislation of interest has been enacted even though there may not be a program presence at this time. Various bills now before Congress and trends in the congressional mood or developing concepts are discussed in papers 3 and 4 by two key members of the Congressional committee. The policy aspects of federal-state relationships as viewed from the general perspective of the National Governors Association are discussed in the fifth paper. The final paper is a discussion on the real-world implementation of federal-state interactions on repository siting, particularly from the state perspective

Enduring Nuclear Fuel Cycle, Proceedings of a panel discussion

Energy Technology Data Exchange (ETDEWEB)

Walter, C. E., LLNL

1997-11-18

The panel reviewed the complete nuclear fuel cycle in the context of alternate energy resources, energy need projections, effects on the environment, susceptibility of nuclear materials to theft, diversion, and weapon proliferation. We also looked at ethical considerations of energy use, as well as waste, and its effects. The scope of the review extended to the end of the next century with due regard for world populations beyond that period. The intent was to take a long- range view and to project, not forecast, the future based on ethical rationales, and to avoid, as often happens, long-range discussions that quickly zoom in on only the next few decades. A specific nuclear fuel cycle technology that could satisfy these considerations was described and can be applied globally.

78 FR 41937 - Joint Meeting of the Gastroenterology-Urology Panel and the Radiological Devices Panel of the...

Science.gov (United States)

2013-07-12

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2013-N-0816] Joint Meeting of the Gastroenterology-Urology Panel and the Radiological Devices Panel of the Medical...: Gastroenterology-Urology Panel and Radiological Devices Panel of the Medical Devices Advisory Committee. General...

Possibility of using waste tire composites reinforced with rice straw as construction materials.

Science.gov (United States)

Yang, Han-Seung; Kim, Dae-Jun; Lee, Young-Kyu; Kim, Hyun-Joong; Jeon, Jin-Yong; Kang, Chun-Won

2004-10-01

Agricultural lignocellulosic fiber (rice straw)-waste tire particle composite boards were manufactured for use as insulation boards in construction, using the same method as that used in the wood-based panel industry. The manufacturing parameters were: a specific gravity of 0.8 and a rice straw content (10/90, 20/80 and 30/70 by wt.% of rice straw/waste tire particle). A commercial polyurethane adhesive for rubber was used as the composite binder. The water proof, water absorption and thickness swelling properties of the composite boards were better than those of wood particleboard. Furthermore, the flexibility and flexural properties of the composite boards were superior to those of other wood-based panel products. The composite boards also demonstrated good acoustical insulation, electrical insulation, anti-caustic and anti-rot properties. These boards can be used to prevent impact damage, are easily modifiable and are inexpensive. They are able to be used as a substitute for insulation boards and other flexural materials in construction.

Graph Transformation for Consolidation of Creativity Sessions Results

DEFF Research Database (Denmark)