Sample results from the interim salt disposition program macrobatch 9 tank 21H qualification samples

Energy Technology Data Exchange (ETDEWEB)

Peters, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2015-11-01

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 9 for the Interim Salt Disposition Program (ISDP). This document reports characterization data on the samples of Tank 21H.

Results from the Interim Salt Disposition Program Macrobatch 11 Tank 21H Acceptance Samples

Energy Technology Data Exchange (ETDEWEB)

Peters, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Bannochie, C. J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-11-13

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of verification of Macrobatch (Salt Batch) 11 for the Interim Salt Disposition Program (ISDP) for processing. This document reports characterization data on the samples of Tank 21H and fulfills the requirements of Deliverable 3 of the Technical Task Request (TTR).

Analysis of removal of residual decay heat from interim storage facilities by means of the CFD program FLUENT

International Nuclear Information System (INIS)

Stratmann, W.; Hages, P.

2004-01-01

Within the scope of nuclear licensing procedures of on-site interim storage facilities for dual purpose casks it is necessary, among other things, to provide proof of sufficient removal of the residual decay heat emitted by the casks. The results of the analyses performed for this purpose define e.g. the boundary conditions for further thermal analyses regarding the permissible cask component temperatures or the maximum permissible temperatures of the fuel cladding tubes of the fuel elements stored in the casks. Up to now, for the centralized interim storage facilities in Germany such analyses were performed on the basis of experimental investigations using scaled-down storage geometries. In the engineering phase of the Lingen on-site interim storage facility, proof was furnished for the first time using the CFD (computational fluid dynamics) program FLUENT. The program FLUENT is an internationally recognized and comprehensively verified program for the calculation of flow and heat transport processes. Starting from a brief discussion of modeling and the different boundary conditions of the computation, this contribution presents various results regarding the temperatures of air, cask surfaces and storage facility components, the mass flows through the storage facility and the heat transfer at the cask surface. The interface point to the cask-specific analyses is defined to be the cask surface

Long Term Inactive Well Program requirements : interim directive ID 97-08

International Nuclear Information System (INIS)

1997-01-01

The Alberta Energy and Utilities Board and the petroleum industry have agreed that industry must take proactive measures to reduce the number of long term inactive wells in Alberta. This interim directive outlines the requirements of the Long Term Inactive Well Program, and provides a schedule for industry to reduce the number of inactive wells. EUB estimates that there are currently 35,000 inactive wells in Alberta, 10,000 of which have been inactive for more than 10 consecutive years. These wells pose a financial risk to the Abandonment Fund which was established to help fund the abandonment of orphan wells. The Long Term Inactive Well Program was created based on the recommendations of a joint government/industry committee, and will operate for five years. 5 tabs

76 FR 60937 - Draft License Renewal Interim Staff Guidance LR-ISG-2011-02; Aging Management Program for Steam...

Science.gov (United States)

2011-09-30

...-2011-02; Aging Management Program for Steam Generators AGENCY: Nuclear Regulatory Commission. ACTION... License Renewal Interim Staff Guidance (LR-ISG), LR-ISG-2011-02, ``Aging Management Program for Steam... using Revision 3 of NEI 97-06 to manage steam generator aging. The Draft LR-ISG revises the NRC staff's...

Savannah River interim waste management program plan: FY 1984. Revision 1

International Nuclear Information System (INIS)

1983-10-01

This document provides the program plan as requested by the Savannah River Operations Office of the Department of Energy. The plan was developed to provide a working knowledge of the nature and extent of the interim waste management programs being undertaken by Savannah River (SR) contractors for the Fiscal Year 1984. In addition, the document projects activities for several years beyond 1984 to adequately plan for safe handling and storage of radioactive wastes generated at Savannah River and for developing technology for improved management of low-level solid wastes. A revised plan will be issued prior to the beginning of the first quarter of each fiscal year. In this document, work descriptions and milestone schedules are current as of the date of publication. Budgets are based on available information as of June 1983

Tribal child welfare. Interim final rule.

Science.gov (United States)

2012-01-06

The Administration for Children and Families (ACF) is issuing this interim final rule to implement statutory provisions related to the Tribal title IV-E program. Effective October 1, 2009, section 479B(b) of the Social Security Act (the Act) authorizes direct Federal funding of Indian Tribes, Tribal organizations, and Tribal consortia that choose to operate a foster care, adoption assistance and, at Tribal option, a kinship guardianship assistance program under title IV-E of the Act. The Fostering Connections to Success and Increasing Adoptions Act of 2008 requires that ACF issue interim final regulations which address procedures to ensure that a transfer of responsibility for the placement and care of a child under a State title IV-E plan to a Tribal title IV-E plan occurs in a manner that does not affect the child's eligibility for title IV-E benefits or medical assistance under title XIX of the Act (Medicaid) and such services or payments; in-kind expenditures from third-party sources for the Tribal share of administration and training expenditures under title IV-E; and other provisions to carry out the Tribal-related amendments to title IV-E. This interim final rule includes these provisions and technical amendments necessary to implement a Tribal title IV-E program.

Physical protection of shipments of irradiated reactor fuel; Interim guidance. Regulatory report

International Nuclear Information System (INIS)

1980-06-01

During May, 1979, the U.S. Nuclear Regulatory Commission approved for issuance in effective form new interim regulations for strengthening the protection of spent fuel shipments against sabotage and diversion. The new regulations were issued without benefit of public comment, but comments from the public were solicited after the effective date. Based upon the public comments received, the interim regulations were amended and reissued in effective form as a final interim rule in May, 1980. The present document supersedes a previously issued interim guidance document, NUREG-0561 (June, 1979) which accompanied the original rule. This report has been revised to conform to the new interim regulations on the physical protection of shipments of irradiated reactor fuel which are likely to remain in effect until the completion of an ongoing research program concerning the response of spent fuel to certain forms of sabotage, at which time the regulations may be rescinded, modified or made permanent, as appropriate. This report discusses the amended regulations and provides a basis on which licensees can develop an acceptable interim program for the protection of spent fuel shipments

Interim restorations.

Science.gov (United States)

Gratton, David G; Aquilino, Steven A

2004-04-01

Interim restorations are a critical component of fixed prosthodontic treatment, biologically and biomechanically. Interim restoration serves an important diagnostic role as a functional and esthetic try-in and as a blueprint for the design of the definitive prosthesis. When selecting materials for any interim restoration, clinicians must consider physical properties, handling properties, patient acceptance, and material cost. Although no single material meets all the requirements and material classification alone of a given product is not a predictor of clinical performance, bis-acryl materials are typically best suited to single-unit restorations, and poly(methylmethacrylate) interim materials are generally ideal for multi-unit, complex, long-term, interim fixed prostheses. As with most dental procedures, the technique used for fabrication has a greater effect on the final result than the specific material chosen.

Information management architecture for an integrated computing environment for the Environmental Restoration Program. Environmental Restoration Program, Volume 3, Interim technical architecture

International Nuclear Information System (INIS)

1994-09-01

This third volume of the Information Management Architecture for an Integrated Computing Environment for the Environmental Restoration Program--the Interim Technical Architecture (TA) (referred to throughout the remainder of this document as the ER TA)--represents a key milestone in establishing a coordinated information management environment in which information initiatives can be pursued with the confidence that redundancy and inconsistencies will be held to a minimum. This architecture is intended to be used as a reference by anyone whose responsibilities include the acquisition or development of information technology for use by the ER Program. The interim ER TA provides technical guidance at three levels. At the highest level, the technical architecture provides an overall computing philosophy or direction. At this level, the guidance does not address specific technologies or products but addresses more general concepts, such as the use of open systems, modular architectures, graphical user interfaces, and architecture-based development. At the next level, the technical architecture provides specific information technology recommendations regarding a wide variety of specific technologies. These technologies include computing hardware, operating systems, communications software, database management software, application development software, and personal productivity software, among others. These recommendations range from the adoption of specific industry or Martin Marietta Energy Systems, Inc. (Energy Systems) standards to the specification of individual products. At the third level, the architecture provides guidance regarding implementation strategies for the recommended technologies that can be applied to individual projects and to the ER Program as a whole

ITER Conceptual design: Interim report

International Nuclear Information System (INIS)

1990-01-01

This interim report describes the results of the International Thermonuclear Experimental Reactor (ITER) Conceptual Design Activities after the first year of design following the selection of the ITER concept in the autumn of 1988. Using the concept definition as the basis for conceptual design, the Design Phase has been underway since October 1988, and will be completed at the end of 1990, at which time a final report will be issued. This interim report includes an executive summary of ITER activities, a description of the ITER device and facility, an operation and research program summary, and a description of the physics and engineering design bases. Included are preliminary cost estimates and schedule for completion of the project

Automotive Mechanics Occupational Performance Survey. Interim Report.

Science.gov (United States)

Borcher, Sidney D.; Leiter, Paul B.

The purpose of this federally-funded interim report is to present the results of a task inventory analysis survey of automotive mechanics completed by project staff within the Instructional Systems Design Program at the Center for Vocational and Technical Education. Intended for use in curriculum development for vocational education programs in…

Diesel Emission Control -- Sulfur Effects (DECSE) Program; Phase I Interim Data Report No. 1

Energy Technology Data Exchange (ETDEWEB)

DOE; ORNL; NREL; EMA; MECA

1999-08-15

The Diesel Emission Control-Sulfur Effects (DECSE) is a joint government/industry program to determine the impact of diesel fuel sulfur levels on emission control systems whose use could lower emissions of nitrogen oxides (NO{sub x}) and particulate matter (PM) from on-highway trucks in the 2002--2004 model years. Phase 1 of the program was developed with the following objectives in mind: (1) evaluate the effects of varying the level of sulfur content in the fuel on the emission reduction performance of four emission control technologies; and (2) measure and compare the effects of up to 250 hours of aging on selected devices for multiple levels of fuel sulfur content. This interim data report summarizes results as of August, 1999, on the status of the test programs being conducted on three technologies: lean-NO{sub x} catalysts, diesel particulate filters and diesel oxidation catalysts.

Immobilized high-level waste interim storage alternatives generation and analysis and decision report

International Nuclear Information System (INIS)

CALMUS, R.B.

1999-01-01

This report presents a study of alternative system architectures to provide onsite interim storage for the immobilized high-level waste produced by the Tank Waste Remediation System (TWRS) privatization vendor. It examines the contract and program changes that have occurred and evaluates their impacts on the baseline immobilized high-level waste (IHLW) interim storage strategy. In addition, this report documents the recommended initial interim storage architecture and implementation path forward

A randomized controlled trial of interim methadone maintenance.

Science.gov (United States)

Schwartz, Robert P; Highfield, David A; Jaffe, Jerome H; Brady, Joseph V; Butler, Carol B; Rouse, Charles O; Callaman, Jason M; O'Grady, Kevin E; Battjes, Robert J

2006-01-01

Effective alternatives to long waiting lists for entry into methadone hydrochloride maintenance treatment are needed to reduce the complications of continuing heroin dependence and to increase methadone treatment entry. To compare the effectiveness of interim methadone maintenance with that of the usual waiting list condition in facilitating methadone treatment entry and reducing heroin and cocaine use and criminal behavior. Randomized, controlled, clinical trial using 2 conditions, with treatment assignment on a 3:2 basis to interim maintenance-waiting list control. A methadone treatment program in Baltimore. A total of 319 individuals meeting the criteria for current heroin dependence and methadone maintenance treatment. Participants were randomly assigned to either interim methadone maintenance, consisting of an individually determined methadone dose and emergency counseling only for up to 120 days, or referral to community-based methadone treatment programs. Entry into comprehensive methadone maintenance therapy at 4 months from baseline; self-reported days of heroin use, cocaine use, and criminal behavior; and number of urine drug test results positive for heroin and cocaine at the follow-up interview conducted at time of entry into comprehensive methadone treatment (or at 4 months from baseline for participants who did not enter regular treatment). Significantly more participants assigned to the interim methadone maintenance condition entered comprehensive methadone maintenance treatment by the 120th day from baseline (75.9%) than those assigned to the waiting list control condition (20.8%) (Pmethadone maintenance results in a substantial increase in the likelihood of entry into comprehensive treatment, and is an effective means of reducing heroin use and criminal behavior among opioid-dependent individuals awaiting entry into a comprehensive methadone treatment program.

The NASA cosmic ray program for the 1990's and beyond Interim report of the NASA Cosmic Ray Program Working Group

International Nuclear Information System (INIS)

Ahlen, S.P.; Binns, W.R.; Cherry, M.L.; Gaisser, T.K.; Jones, W.V.; Ling, J.C.; Mewaldt, R.A.; Muller, D.; Ormes, J.O.; Ramaty, R.; Stone, E.C.; Waddington, C.J.; Webber, W.R.; Miedenbeck, M.E.

1990-01-01

The interim report of the 1989 NASA Cosmic Ray Program Working Group is presented. The report summarizes the cosmic ray program for the 1990's, including the recently approved ACE, Astromag, HNC, POEMS, and SAMPEX missions, as well as other key elements of the program. New science themes and candidate missions are identified for the first part of the 21st Century, including objectives that might be addressed as part of the Human Exploration Initiative. Among the suggested new thrusts for the 21st century are: an Interstellar Probe into the nearby interstellar medium; a Lunar-Based Calorimeter to measure the cosmic ray composition near ∼10 16 eV; high precision element and isotope spectroscopy of ultraheavy (Z≥30) elements; and new, more sensitive, studies of impulsive solar flare events

Interim format and content for a physical security plan for nuclear power plants

International Nuclear Information System (INIS)

1977-02-01

The document serves as interim guidance to assist the licensee or applicant in the preparation of a physical security plan. It is to be used in conjunction with interim acceptance criteria for physical security programs, which will be distributed at a later date

Industrial complementarities between interim storage and reversible geological repository - 59237

International Nuclear Information System (INIS)

Hoorelbeke, Jean-Michel

2012-01-01

2006 French Act provides for a research program on interim storage to be carried out along with the repository project development. This program has been guided by the complementarities between interim storage and the repository project. The main research issues address the longevity of storage facilities, up to 100 years, their versatility with regard to waste package types and their modularity to match future needs progressively. In parallel the dialogue between Andra and waste producers will continue to propose optimized waste management scenarios. (author)

DEVELOPMENT OF THERAPEUTIC STRATEGIES FOR OBESITY AND COMORBID DISORDERS BASED ON OBSERVATIONAL PROGRAMS: INTERIM RESULTS OF THE RUSSIAN OBSERVATIONAL PROGRAM PRIMAVERA

Directory of Open Access Journals (Sweden)

E. A. Troshina

2015-01-01

Full Text Available Aim: To assess interim results of the Russian observational program PrimaVera on efficacy and safety sibutramine (Reduxin® for treatment of obesity within routine medical practice. Materials and methods: This multicenter observational program included patients with obesity aged below 65  years, excluding those with uncontrolled arterial hypertension, coronary heart disease, heart failure and cerebrovascular disease. All patients were administered sibutramine for treatment of their obesity. During out-patient follow-up visits, physicians assessed changes in patients’ body mass, blood pressure and heart rate, as well as registered adverse events. Maximal treatment duration was 12 months. In this report, the results from 16  515  patients are analyzed, 82% of whom (n=13 192 were females.Results: After 3  months of treatment body mass index (BMI decreased by 2.81±1.0  kg/m², after 6 months, by 5.17±2.15 kg/m². At 12 months decrease in BMI was 1.3-fold higher compared to 6  months’ results and amounted to 6.76±2.93  kg/m². Reduction of body mass with longterm (above 6  months treatment with sibutramine under supervision of a physician was associated with a decrease in systolic and diastolic blood pressure levels (by 4.1 mm Hg, in both cases and did not lead to an increase in heart rate (Δ=-1.02  bpm. Based on data from 16  515  medical records processed up to now, 397  episodes of adverse events were registered, with none of them being serious.Conclusion: This interim results of the program PrimaVera confirmed favorable safety profile of Reduxin® and its high efficacy in the treatment of obesity.

Results from the interim salt disposition program macrobatch 10 tank ²¹H qualification samples

Energy Technology Data Exchange (ETDEWEB)

Peters, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Bannochie, C. J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-02-23

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 10 for the Interim Salt Disposition Program (ISDP). This document reports characterization data on the samples of Tank 21H and fulfills the requirements of Deliverable 3 of the Technical Task Request (TTR). Further work will report the results of the Extraction-Scrub-Strip (ESS) testing (Task 5 of the TTR) using the Tank 21H material. Task 4 of the TTR (MST Strike) will not be completed for Salt Batch 10.

Single-shell tank interim stabilization project plan

Energy Technology Data Exchange (ETDEWEB)

Ross, W.E.

1998-05-11

This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities, and interfaces; and operational methods. This plan serves as the project executional baseline.

Single-shell tank interim stabilization project plan

Energy Technology Data Exchange (ETDEWEB)

Ross, W.E.

1998-03-27

Solid and liquid radioactive waste continues to be stored in 149 single-shell tanks at the Hanford Site. To date, 119 tanks have had most of the pumpable liquid removed by interim stabilization. Thirty tanks remain to be stabilized. One of these tanks (C-106) will be stabilized by retrieval of the tank contents. The remaining 29 tanks will be interim stabilized by saltwell pumping. In the summer of 1997, the US Department of Energy (DOE) placed a moratorium on the startup of additional saltwell pumping systems because of funding constraints and proposed modifications to the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) milestones to the Washington State Department of Ecology (Ecology). In a letter dated February 10, 1998, Final Determination Pursuant to Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) in the Matter of the Disapproval of the DOE`s Change Control Form M-41-97-01 (Fitzsimmons 1998), Ecology disapproved the DOE Change Control Form M-41-97-01. In response, Fluor Daniel Hanford, Inc. (FDH) directed Lockheed Martin Hanford Corporation (LNMC) to initiate development of a project plan in a letter dated February 25, 1998, Direction for Development of an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan in Support of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). In a letter dated March 2, 1998, Request for an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan, the DOE reaffirmed the need for an aggressive SST interim stabilization completion project plan to support a finalized Tri-Party Agreement Milestone M-41 recovery plan. This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities

Single-shell tank interim stabilization project plan

International Nuclear Information System (INIS)

Ross, W.E.

1998-01-01

Solid and liquid radioactive waste continues to be stored in 149 single-shell tanks at the Hanford Site. To date, 119 tanks have had most of the pumpable liquid removed by interim stabilization. Thirty tanks remain to be stabilized. One of these tanks (C-106) will be stabilized by retrieval of the tank contents. The remaining 29 tanks will be interim stabilized by saltwell pumping. In the summer of 1997, the US Department of Energy (DOE) placed a moratorium on the startup of additional saltwell pumping systems because of funding constraints and proposed modifications to the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) milestones to the Washington State Department of Ecology (Ecology). In a letter dated February 10, 1998, Final Determination Pursuant to Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) in the Matter of the Disapproval of the DOE's Change Control Form M-41-97-01 (Fitzsimmons 1998), Ecology disapproved the DOE Change Control Form M-41-97-01. In response, Fluor Daniel Hanford, Inc. (FDH) directed Lockheed Martin Hanford Corporation (LNMC) to initiate development of a project plan in a letter dated February 25, 1998, Direction for Development of an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan in Support of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). In a letter dated March 2, 1998, Request for an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan, the DOE reaffirmed the need for an aggressive SST interim stabilization completion project plan to support a finalized Tri-Party Agreement Milestone M-41 recovery plan. This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities

Insights from the interim reliability evaluation program pertinent to reactor safety issues

International Nuclear Information System (INIS)

Carlson, D.D.

1983-01-01

The Interim Reliability Evaluation Program (IREP) consisted of concurrent probabilistic analyses of four operating nuclear power plants. This paper presents and integrated view of the results of the analyses drawing insights pertinent to reactor safety. The importance to risk of accident sequences initiated by transients and small loss-of-coolant accidents was confirmed. Support systems were found to contribute significantly to the sets of dominant accident sequences, either due to single failures which could disable one or more mitigating systems or due to their initiating plant transients. Human errors in response to accidents also were important risk contributors. Consideration of operator recovery actions influences accident sequence frequency estimates, the list of accident sequences dominating core melt, and the set of dominant risk contributors. Accidents involving station blackout, reactor coolant pump seal leaks and ruptures, and loss-of-coolant accidents requiring manual initiation of coolant injection were found to be risk significant

Indiana application for interim authorization, phase I, hazardous waste management program--Environmental Protection Agency. Notice of public hearing and public comment period.

Science.gov (United States)

1982-04-12

EPA regulations to protect human health and the environment from the improper management of hazardous waste were published in the Federal Register on May 19, 1980 (45 FR 33063). These regulations include provisions for authorization of State programs to operate in lieu of the Federal program. Today EPA is announcing the availability for public review of the Indiana application for Phase I Interim Authorization, inviting public comment, and giving notice of a public hearing to be held on the application.

Interim overdentures.

Science.gov (United States)

Fenton, A H

1976-07-01

The construction of an interim overdenture using existing removable partial dentures with natural tooth crowns and artificial teeth can be a simple and economical method of providing patients with dentures while tissues heal and teeth are prepared and restored. A more definite prognosis for both the patient and his remaining dentition can be established before the final overdenture is completed. The procedures necessary to provide three types of interim overdentures have been outlined. Patients tolerate this method of changing their dentitions extremely well.

Radioactive waste interim storage in Germany

International Nuclear Information System (INIS)

2015-12-01

The short summary on the radioactive waste interim storage in Germany covers the following issues: importance of interim storage in the frame of radioactive waste management, responsibilities and regulations, waste forms, storage containers, transport of vitrified high-level radioactive wastes from the reprocessing plants, central interim storage facilities (Gorleben, Ahaus, Nord/Lubmin), local interim storage facilities at nuclear power plant sites, federal state collecting facilities, safety, radiation exposure in Germany.

Single-Shell Tank (SST) Interim Stabilization Project Plan

International Nuclear Information System (INIS)

VLADIMIROFF, D.T.; BOYLES, V.C.

2000-01-01

This project plan establishes the management framework for the conduct of the CHG Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organization structure, roles, responsibilities, and interfaces; and operational methods. This plan serves as the project executional baseline

Commentary: Interim leadership of academic departments at U.S. medical schools.

Science.gov (United States)

Grigsby, R Kevin; Aber, Robert C; Quillen, David A

2009-10-01

Medical schools and teaching hospitals are experiencing more frequent turnover of department chairs. Loss of a department chair creates instability in the department and may have a negative effect on the organization at large. Interim leadership of academic departments is common, and interim chairs are expected to immediately demonstrate skills and leadership abilities. However, little is known about how persons are prepared to assume the interim chair role. Newer competencies for effective leadership include an understanding of the business of medicine, interpersonal and communication skills, the ability to deal with conflict and solve adaptive challenges, and the ability to build and work on teams. Medical schools and teaching hospitals need assistance to meet the unique training and support needs of persons serving as interim leaders. For example, the Association of American Medical Colleges and individual chair societies can develop programs to allow current chairs to reflect on their present positions and plan for the future. Formal leadership training, mentorship opportunities, and conscientious succession planning are good first steps in preparing to meet the needs of academic departments during transitions in leadership. Also, interim leadership experience may be useful as a means for "opening the door" to underrepresented persons, including women, and increasing the diversity of the leadership team.

76 FR 43571 - Small Business HUBZone Program; Government Contracting Programs

Science.gov (United States)

2011-07-21

... SMALL BUSINESS ADMINISTRATION 13 CFR Part 126 RIN 3245-AG45 Small Business HUBZone Program; Government Contracting Programs AGENCY: U.S. Small Business Administration. ACTION: Interim final rule with request for comments. SUMMARY: This interim final rule amends the U.S. Small Business Administration's...

The cost and impact of the interim federal health program cuts on child refugees in Canada.

Science.gov (United States)

Evans, Andrea; Caudarella, Alexander; Ratnapalan, Savithiri; Chan, Kevin

2014-01-01

On June 30, 2012, Interim Federal Health Program (IFHP) funding was cut for refugee claimant healthcare. The potential financial and healthcare impacts of these cuts on refugee claimants are unknown. We conducted a one-year retrospective chart review spanning 6 months before and after IFHP funding cuts at The Hospital for Sick Children, a tertiary care children's hospital in Toronto. We analyzed emergency room visits characteristics, admission rates, reasons for admission, and financial records including billing from Medavie Blue Cross. There were 173 refugee children visits to the emergency room in the six months before and 142 visits in the six months after funding cuts. The total amount billed to the IFHP program during the one-year of this study was $131,615. Prior to the IFHP cuts, 46% of the total emergency room bills were paid by IFHP compared to 7% after the cuts (pinstitution in the country increased.

7 CFR 1738.21 - Interim financing.

Science.gov (United States)

2010-01-01

... 7 Agriculture 11 2010-01-01 2010-01-01 false Interim financing. 1738.21 Section 1738.21... Interim financing. (a) Upon notification by RUS that an applicant's application is considered complete, the applicant may enter into an interim financing agreement with a lender other than RUS or use its...

7 CFR 1735.75 - Interim financing.

Science.gov (United States)

2010-01-01

... 7 Agriculture 11 2010-01-01 2010-01-01 false Interim financing. 1735.75 Section 1735.75... Involving Loan Funds § 1735.75 Interim financing. (a) A borrower may submit a written request for RUS approval of interim financing if it is necessary to close an acquisition before the loan to finance the...

Public School Finance Problems in Texas. An Interim Report.

Science.gov (United States)

Texas Research League, Austin.

The U.S. District Court ruling in Rodriguez vs San Antonio Independent School District, which struck down Texas' school finance system as inequitable and unconstitutional, provided the impetus for publishing this interim report. The report documents the growing cost of State-supported public school programs--the primary concern prior to the…

Reducing Health Services for Refugees Through Reforms to the Interim Federal Health Program

Directory of Open Access Journals (Sweden)

Andrew C. Stevenson

2018-04-01

Full Text Available Since 1957 the Interim Federal Health Program (IFHP has provided temporary health care coverage to refugees and refugee claimants, but in 2012 the Conservative government reformed the IFHP, reducing, or eliminating access to health services for these groups. The government framed the changes around fairness and safety, stating that it would save tax payers $100 million over five years, reduce incentive for migrants with unfounded refugee claims from coming to Canada, protect public health and safety, and defend the integrity of the immigration system. With a Conservative majority, the reform was easily implemented despite a lack of evidence supporting these claims. In 2014, the Federal Court rejected the government's notion of fairness and safety, ruling that the cuts were cruel and unusual treatment of an already vulnerable population. The government appealed this ruling but, in 2016, the Liberals took power and restored funding to the IFHP to pre-2012 levels. Ad hoc evaluations predicted inequitable and adverse impacts on refugees, negative impacts on health, and increased costs to refugees, provincial governments, and health providers. Overall the threats and weaknesses of this reform clearly outweighed the few and unconvincing opportunities and strengths of the program, leading to its demise.

Acceptable TRU packaging for interim storage and/or terminal isolation: FY-1977 final report

International Nuclear Information System (INIS)

Doty, J.W.; Peterson, J.B.

1978-01-01

A program was conducted for the definition and demonstration of acceptable waste packages for defense transuranic waste for interim storage and terminal isolation. During FY-1977, a Contractor Questionnaire was used to gather pertinent data and to assess contractor concerns. This information was integrated into basic application data in the form of a checklist. Conceptual Container Design Specifications were developed by analyzing and evaluating the application data against Federal Regulations and interim/terminal storage constraints

The Homestake Interim Laboratory and Homestake DUSEL

Science.gov (United States)

Lesko, Kevin T.

2011-12-01

The former Homestake gold mine in Lead South Dakota is proposed for the National Science Foundation's Deep Underground Science and Engineering Laboratory (DUSEL). The gold mine provides expedient access to depths in excess of 8000 feet below the surface (>7000 mwe). Homestake's long history of promoting scientific endeavours includes the Davis Solar Neutrino Experiment, a chlorine-based experiment that was hosted at the 4850 Level for more than 30 years. As DUSEL, Homestake would be uncompromised by competition with mining interests or other shared uses. The facility's 600-km of drifts would be available for conversion for scientific and educational uses. The State of South Dakota, under Governor Rounds' leadership, has demonstrated exceptionally strong support for Homestake and the creation of DUSEL. The State has provided funding totalling $46M for the preservation of the site for DUSEL and for the conversion and operation of the Homestake Interim Laboratory. Motivated by the strong educational and outreach potential of Homestake, the State contracted a Conversion Plan by world-recognized mine-engineering contractor to define the process of rehabilitating the facility, establishing the appropriate safety program, and regaining access to the facility. The State of South Dakota has established the South Dakota Science and Technology Authority to oversee the transfer of the Homestake property to the State and the rehabilitation and preservation of the facility. The Homestake Scientific Collaboration and the State of South Dakota's Science and Technology Authority has called for Letters of Interest from scientific, educational and engineering collaborations and institutions that are interested in hosting experiments and uses in the Homestake Interim Facility in advance of the NSF's DUSEL, to define experiments starting as early as 2007. The Homestake Program Advisory Committee has reviewed these Letters and their initial report has been released. Options for

The Homestake Interim Laboratory and Homestake DUSEL

International Nuclear Information System (INIS)

Lesko, Kevin T.

2011-01-01

The former Homestake gold mine in Lead South Dakota is proposed for the National Science Foundation's Deep Underground Science and Engineering Laboratory (DUSEL). The gold mine provides expedient access to depths in excess of 8000 feet below the surface (>7000 mwe). Homestake's long history of promoting scientific endeavours includes the Davis Solar Neutrino Experiment, a chlorine-based experiment that was hosted at the 4850 Level for more than 30 years. As DUSEL, Homestake would be uncompromised by competition with mining interests or other shared uses. The facility's 600-km of drifts would be available for conversion for scientific and educational uses. The State of South Dakota, under Governor Rounds' leadership, has demonstrated exceptionally strong support for Homestake and the creation of DUSEL. The State has provided funding totalling $46M for the preservation of the site for DUSEL and for the conversion and operation of the Homestake Interim Laboratory. Motivated by the strong educational and outreach potential of Homestake, the State contracted a Conversion Plan by world-recognized mine-engineering contractor to define the process of rehabilitating the facility, establishing the appropriate safety program, and regaining access to the facility. The State of South Dakota has established the South Dakota Science and Technology Authority to oversee the transfer of the Homestake property to the State and the rehabilitation and preservation of the facility. The Homestake Scientific Collaboration and the State of South Dakota's Science and Technology Authority has called for Letters of Interest from scientific, educational and engineering collaborations and institutions that are interested in hosting experiments and uses in the Homestake Interim Facility in advance of the NSF's DUSEL, to define experiments starting as early as 2007. The Homestake Program Advisory Committee has reviewed these Letters and their initial report has been released. Options for

Remedial design report and remedial action work plan for the 100-HR-3 and 100-KR-4 groundwater operable units' interim action

International Nuclear Information System (INIS)

1996-09-01

This document is a combination remedial design report and remedial action work plan for the 100-HR-3 and 100-KR-4 Operable Units (located on the Hanford Site in Richland, Washington) interim action. The interim actions described in this document represent the first of an ongoing program to address groundwater contamination in each operable unit. This document describes the design basis, provides a description of the interim action, and identifies how they will meet the requirements set forth in the interim action Record of Decision

1987 Federal interim storage fee study: A technical and economic analysis

International Nuclear Information System (INIS)

1987-09-01

This document is the latest in a series of reports that are published annually by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). This information in the report, which was prepared by E.R. Johnson Associates under subcontract to PNL, will be used by the DOE to establish a payment schedule for interim storage of spent nuclear fuel under the Federal Interim Storage (FIS) Program, which was mandated by the Nuclear Waste Policy Act of 1982. The information in this report will be used to establish the schedule of charges for FIS services for the year commencing January 1, 1988. 13 tabs

1987 Federal interim storage fee study: A technical and economic analysis

Energy Technology Data Exchange (ETDEWEB)

1987-09-01

This document is the latest in a series of reports that are published annually by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). This information in the report, which was prepared by E.R. Johnson Associates under subcontract to PNL, will be used by the DOE to establish a payment schedule for interim storage of spent nuclear fuel under the Federal Interim Storage (FIS) Program, which was mandated by the Nuclear Waste Policy Act of 1982. The information in this report will be used to establish the schedule of charges for FIS services for the year commencing January 1, 1988. 13 tabs.

Used Fuel Logistics: Decades of Experience with transportation and Interim storage solutions

Energy Technology Data Exchange (ETDEWEB)

Orban, G.; Shelton, C.

2015-07-01

Used fuel inventories are growing worldwide. While some countries have opted for a closed cycle with recycling, numerous countries must expand their interim storage solutions as implementation of permanent repositories is taking more time than foreseen. In both cases transportation capabilities will have to be developed. AREVA TN has an unparalleled expertise with transportation of used fuel. For more than 50 years AREVA TN has safely shipped more than 7,000 used fuel transport casks. The transportation model that was initially developed in the 1970s has been adapted and enhanced over the years to meet more restrictive regulatory requirements and evolving customer needs, and to address public concerns. The numerous “lessons learned” have offered data and guidance that have allowed for also efficient and consistent improvement over the decades. AREVA TN has also an extensive experience with interim dry storage solutions in many countries on-site but also is working with partners to developed consolidated interim storage facility. Both expertise with storage and transportation contribute to safe, secure and smooth continuity of the operations. This paper will describe decades of experience with a very successful transportation program as well as interim storage solutions. (Author)

Burn site groundwater interim measures work plan.

Energy Technology Data Exchange (ETDEWEB)

Witt, Jonathan L. (North Wind, Inc., Idaho Falls, ID); Hall, Kevin A. (North Wind, Inc., Idaho Falls, ID)

2005-05-01

This Work Plan identifies and outlines interim measures to address nitrate contamination in groundwater at the Burn Site, Sandia National Laboratories/New Mexico. The New Mexico Environment Department has required implementation of interim measures for nitrate-contaminated groundwater at the Burn Site. The purpose of interim measures is to prevent human or environmental exposure to nitrate-contaminated groundwater originating from the Burn Site. This Work Plan details a summary of current information about the Burn Site, interim measures activities for stabilization, and project management responsibilities to accomplish this purpose.

24 CFR 35.1330 - Interim controls.

Science.gov (United States)

2010-04-01

... Lead-Paint Hazard Evaluation and Hazard Reduction Activities § 35.1330 Interim controls. Interim..., cleanable covering or coating, such as metal coil stock, plastic, polyurethane, or linoleum. (3) Surfaces...

Interim reliability evaluation program: analysis of the Arkansas Nuclear One. Unit 1 Nuclear Power Plant

International Nuclear Information System (INIS)

Kolb, G.J.; Kunsman, D.M.; Bell, B.J.

1982-06-01

This report represents the results of the analysis of Arkansas Nuclear One (ANO) Unit 1 nuclear power plant which was performed as part of the Interim Reliability Evaluation Program (IREP). The IREP has several objectives, two of which are achieved by the analysis presented in this report. These objectives are: (1) the identification, in a preliminary way, of those accident sequences which are expected to dominate the public health and safety risks; and (2) the development of state-of-the-art plant system models which can be used as a foundation for subsequent, more intensive applications of probabilistic risk assessment. The primary methodological tools used in the analysis were event trees and fault trees. These tools were used to study core melt accidents initiated by loss of coolant accidents (LOCAs) of six different break size ranges and eight different types of transients

AGR-1 Data Qualification Interim Report

International Nuclear Information System (INIS)

Abbott, Machael

2009-01-01

Projects for the very-high-temperature reactor (VHTR) program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR Program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor (AGR-1) experiment, the processing of these data within NDMAS, and reports the interim FY09 qualification status of the AGR-1 data to date. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category, which is assigned by the data generator, and include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing, to confirm that the data are an accurate representation of the system or object being measured, and (3) documentation that the data were collected under an NQA-1 or equivalent QA program. The interim qualification status of the following four data streams is reported in this document: (1) fuel fabrication data, (2) fuel irradiation data, (3) fission product monitoring system (FPMS) data, and (4) Advanced Test Reactor (ATR) operating conditions data. A final report giving the NDMAS qualification status of all AGR-1 data (including cycle 145A) is planned for February 2010

Solid waste burial grounds interim safety analysis

International Nuclear Information System (INIS)

Saito, G.H.

1994-01-01

This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment

Solid waste burial grounds interim safety analysis

Energy Technology Data Exchange (ETDEWEB)

Saito, G.H.

1994-10-01

This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment.

Interim-status groundwater monitoring plan for the 216-B-63 trench

Energy Technology Data Exchange (ETDEWEB)

Sweeney, M.D.

1995-02-09

This document outlines the groundwater monitoring plan, under RCRA regulations in 40 CFR 265 Subpart F and WAC173-300-400, for the 216-B-63 Trench. This interim status facility is being sampled under detection monitoring criteria and this plan provides current program conditions and requirements.

Reliability Centered Maintenance for Savannah River Site's interim waste management facilities

International Nuclear Information System (INIS)

Hauer, K.A.; Wilson, J.F.

1992-01-01

The application of Reliability Centered Maintenance (RCM) has been shown to be an effective means to optimize maintenance programs or to establish new programs. The key to success of any RCM program is to customize the methodology to meet the specific needs of the implementing organization. This paper discusses how RCM is being used to establish the preventive maintenance program and how the resulting system data is being used to support the Technical Baseline reconstitution effort for the interim Waste Management Division of Westinghouse Savannah River Company (WSRC)

Progress and future direction for the interim safe storage and disposal of Hanford high level waste (HLW)

International Nuclear Information System (INIS)

Wodrich, D.D.

1996-01-01

This paper describes the progress made at the largest environmental cleanup program in the United States. Substantial advances in methods to start interim safe storage of Hanford Site high-level wastes, waste characterization to support both safety- and disposal-related information needs, and proceeding with cost-effective disposal by the US DOE and its Hanford Site contractors, have been realized. Challenges facing the Tank Waste Remediation System Program, which is charged with the dual and parallel missions of interim safe storage and disposal of the high-level tank waste stored at the Hanford Site, are described

Maywood Interim Storage Site environmental report for calendar year 1989, Maywood, New Jersey

International Nuclear Information System (INIS)

1990-05-01

The environmental monitoring program, which began in 1984, was continued in 1989 at the Maywood Interim Storage Site (MISS), a US Department of Energy (DOE) facility located in the Borough of Maywood and the Township of Rochelle Park, New Jersey. MISS is currently used for storage of soils contaminated with low-level radioactivity. MISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to identify and decontaminate or otherwise control sites where residual radioactive materials are present. The monitoring program at MISS measures thoron and radon concentrations in air; external gamma radiation levels; and thorium, uranium, and radium concentrations in surface water, groundwater, and sediment. Additionally, several nonradiological parameters are measured in groundwater. The radiation dose was calculated for a hypothetical maximally exposed individual to verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and to assess its potential effects on public health. This report presents the results of the environmental monitoring program conducted at the US Department of Energy's (DOE) Maywood Interim Storage Site (MISS) during calendar year 1989. Environmental monitoring began at MISS in 1984. 19 refs., 23 figs., 14 tabs

Maywood Interim Storage Site environmental report for calendar year 1989, Maywood, New Jersey

Energy Technology Data Exchange (ETDEWEB)

1990-05-01

The environmental monitoring program, which began in 1984, was continued in 1989 at the Maywood Interim Storage Site (MISS), a US Department of Energy (DOE) facility located in the Borough of Maywood and the Township of Rochelle Park, New Jersey. MISS is currently used for storage of soils contaminated with low-level radioactivity. MISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to identify and decontaminate or otherwise control sites where residual radioactive materials are present. The monitoring program at MISS measures thoron and radon concentrations in air; external gamma radiation levels; and thorium, uranium, and radium concentrations in surface water, groundwater, and sediment. Additionally, several nonradiological parameters are measured in groundwater. The radiation dose was calculated for a hypothetical maximally exposed individual to verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and to assess its potential effects on public health. This report presents the results of the environmental monitoring program conducted at the US Department of Energy's (DOE) Maywood Interim Storage Site (MISS) during calendar year 1989. Environmental monitoring began at MISS in 1984. 19 refs., 23 figs., 14 tabs.

Interim Evaluation of the Project P.A.T.H.S.: Findings Based on Different Datasets

Directory of Open Access Journals (Sweden)

Daniel T. L. Shek

2012-01-01

Full Text Available Interim evaluation studies were carried out in order to examine the implementation details of the Tier 1 Program of the Project P.A.T.H.S. (Positive Adolescent Training through Holistic Social Programmes in Hong Kong. Quantitative results of the interim evaluation findings based on eight datasets collected from 2006 to 2009 are reported in this paper. Three hundred and seventy-eight schools were randomly selected to provide information on the implementation details of the program via face-to-face interviews, telephone interviews, and self-completed questionnaires. Results showed that a majority of the workers perceived that the students had positive responses to the program and the program was helpful to the students. In conjunction with other process evaluation findings, the present study suggests that the implementation quality of the Tier 1 Program of the Project P.A.T.H.S. is high. The present study also provides support for the effectiveness of the Tier 1 Program of the Project P.A.T.H.S. in Hong Kong.

Interim Sanitary Landfill Groundwater Monitoring Report. 1997 Annual Report

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-01-01

Eight wells of the LFW series monitor groundwater quality in the Steed Pond Aquifer (Water Table) beneath the Interim Sanitary Landfill at the Savannah River Site (SRS). These wells are sampled semiannually to comply with the South Carolina Department of Health and Environmental Control Modified Municipal Solid Waste Permit 025500-1120 (formerly dWP-087A) and as part of the SRS Groundwater Monitoring Program.

Wayne Interim Storage Site annual environmental report for calendar year 1991, Wayne, New Jersey. [Wayne Interim Storage Site

Energy Technology Data Exchange (ETDEWEB)

None

1992-09-01

This document describes the envirormental monitoring program at the Wayne Interim Storage Site (WISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring of WISS and surrounding area began in 1984 when Congress added the site to the US Department of Energy's (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. WISS is a National Priorities List site. The environmental monitoring program at WISS includes sampling networks for radon and thoron concentrations in air; external gamma radiation exposure; and radium-226, radium-228, thorium-232, and total uranium concentrations in surface water, sediment, and groundwater. Several nonradiological parameters are also measured in groundwater. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides, dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment.

Maywood Interim Storage Site annual environmental report for calendar year 1991, Maywood, New Jersey. [Maywood Interim Storage Site

Energy Technology Data Exchange (ETDEWEB)

None

1992-09-01

This document describes the environmental monitoring program at the Maywood Interim Storage Site (MISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring of MISS began in 1984 when congress added the site to the US Department of Energy's (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a DOE program to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental monitoring program at MISS includes sampling networks for radon and thoron concentrations in air; external gamma radiation-exposure; and total uranium, radium-226, radium-228, thorium-232, and thorium-230 concentrations in surface water, sediment, and groundwater. Additionally, several nonradiological parameters are measured in surface water, sediment, and groundwater. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides (DCGs), dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment.

Interim analysis: A rational approach of decision making in clinical trial.

Science.gov (United States)

Kumar, Amal; Chakraborty, Bhaswat S

2016-01-01

Interim analysis of especially sizeable trials keeps the decision process free of conflict of interest while considering cost, resources, and meaningfulness of the project. Whenever necessary, such interim analysis can also call for potential termination or appropriate modification in sample size, study design, and even an early declaration of success. Given the extraordinary size and complexity today, this rational approach helps to analyze and predict the outcomes of a clinical trial that incorporate what is learned during the course of a study or a clinical development program. Such approach can also fill the gap by directing the resources toward relevant and optimized clinical trials between unmet medical needs and interventions being tested currently rather than fulfilling only business and profit goals.

Interim analysis: A rational approach of decision making in clinical trial

Directory of Open Access Journals (Sweden)

Amal Kumar

2016-01-01

Full Text Available Interim analysis of especially sizeable trials keeps the decision process free of conflict of interest while considering cost, resources, and meaningfulness of the project. Whenever necessary, such interim analysis can also call for potential termination or appropriate modification in sample size, study design, and even an early declaration of success. Given the extraordinary size and complexity today, this rational approach helps to analyze and predict the outcomes of a clinical trial that incorporate what is learned during the course of a study or a clinical development program. Such approach can also fill the gap by directing the resources toward relevant and optimized clinical trials between unmet medical needs and interventions being tested currently rather than fulfilling only business and profit goals.

24 CFR 982.516 - Family income and composition: Regular and interim examinations.

Science.gov (United States)

2010-04-01

... VOUCHER PROGRAM Rent and Housing Assistance Payment § 982.516 Family income and composition: Regular and... assistance payment. (For a voucher tenancy, the housing assistance payment shall be calculated in accordance... the housing assistance payment resulting from an interim redetermination. (2) At the effective date of...

Interim Administrators in Higher Education: A National Study

Science.gov (United States)

Huff, Marie Thielke; Neubrander, Judy

2015-01-01

The focus of this paper is on the roles and experiences of interim administrators in higher education. A survey was given to current and recent interim administrators in four-year public universities and colleges across the United States. The goals were to identify the advantages and disadvantages of using and serving as interims, and to solicit…

Engineering Task Plan for Hose-In-Hose Transfer Lines for the Interim Stabilization Program

International Nuclear Information System (INIS)

TORRES, T.D.

2000-01-01

The document is the Engineering Task Plan for the engineering, design services, planning, project integration and management support for the design, modification, installation and testing of an over ground transfer (OGT) system to support the interim stabilization of S/SX and U Tank Farms

Subsurface Interim Measures/Interim Remedial Action Plan/Environmental Assessment and Decision Document, Operable Unit No. 2

International Nuclear Information System (INIS)

1992-01-01

The subject Interim Measures/Interim Remedial Action plan/Environmental Assessment (IM/IRAP/EA) addresses residual free-phase volatile organic compound (VOC) contamination suspected in the subsurface within an area identified as Operable Unit No. 2 (OU2). This IM/IRAP/EA also addresses radionuclide contamination beneath the 903 Pad at OU2. Although subsurface VOC and radionuclide contamination on represent a source of OU2 ground-water contamination, they pose no immediate threat to public health or the environment. This IM/IRAP/EA identifies and evaluates interim remedial actions for removal of residual free-phase VOC contamination from three different subsurface environments at OU2. The term ''residual'' refers to the non-aqueous phase contamination remaining in the soil matrix (by capillary force) subsequent to the passage of non-aqueous or free-phase liquid through the subsurface. In addition to the proposed actions, this IM/IRAP/EA presents an assessment of the No Action Alternative. This document also considers an interim remedial action for the removal of radionuclides from beneath the 903 Pad

Engineering Task Plan for Hose-In-Hose Transfer Lines for the Interim Stabilization Program

International Nuclear Information System (INIS)

RUNG, M.P.

2000-01-01

This document is the Engineering Task Plan for the engineering, design services, planning, project integration and management support for the design, modification, installation and testing of an over ground transfer (OGT) system to support the interim stabilization of nine tanks in the 241-S/SX Tank Farms

Decision on performing interim analysis for comparative clinical trials.

Science.gov (United States)

Pak, Kyongsun; Jacobus, Susanna; Uno, Hajime

2017-09-01

In randomized-controlled trials, interim analyses are often planned for possible early trial termination to claim superiority or futility of a new therapy. While unblinding is necessary to conduct the formal interim analysis in blinded studies, blinded data also have information about the potential treatment difference between the groups. We developed a blinded data monitoring tool that enables investigators to predict whether they observe such an unblinded interim analysis results that supports early termination of the trial. Investigators may skip some of the planned interim analyses if an early termination is unlikely. We specifically focused on blinded, randomized-controlled studies to compare binary endpoints of a new treatment with a control. Assuming one interim analysis is planned for early termination for superiority or futility, we conducted extensive simulation studies to assess the impact of the implementation of our tool on the size, power, expected number of interim analyses, and bias in the treatment effect. The numerical study showed the proposed monitoring tool does not affect size or power, but dramatically reduces the expected number of interim analyses when the effect of the treatment difference is small. The tool serves as a useful reference when interpreting the summary of the blinded data throughout the course of the trial, without losing integrity of the study. This tool could potentially save the study resources and budget by avoiding unnecessary interim analyses.

Addendum to IFMIF-CDA interim report

Energy Technology Data Exchange (ETDEWEB)

Maekawa, Hiroshi; Ida, Mizuho [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; eds.

1996-08-01

During the second IFMIF-CDA Design Integration Workshop, the conceptual design and contents of `IFMIF-CDA Interim Report` were examined and discussed at both general and group meetings. Based on these discussion, the final IFMIF-CDA Report will be modified from the `Interim Report`. This report describes the outline of these modification. (author)

Addendum to IFMIF-CDA interim report

International Nuclear Information System (INIS)

Maekawa, Hiroshi; Ida, Mizuho

1996-08-01

During the second IFMIF-CDA Design Integration Workshop, the conceptual design and contents of 'IFMIF-CDA Interim Report' were examined and discussed at both general and group meetings. Based on these discussion, the final IFMIF-CDA Report will be modified from the 'Interim Report'. This report describes the outline of these modification. (author)

Interim reliability-evaluation program: analysis of the Browns Ferry, Unit 1, nuclear plant. Appendix B - system descriptions and fault trees

International Nuclear Information System (INIS)

Mays, S.E.; Poloski, J.P.; Sullivan, W.H.; Trainer, J.E.; Bertucio, R.C.; Leahy, T.J.

1982-07-01

This report describes a risk study of the Browns Ferry, Unit 1, nuclear plant. The study is one of four such studies sponsored by the NRC Office of Research, Division of Risk Assessment, as part of its Interim Reliability Evaluation Program (IREP), Phase II. This report is contained in four volumes: a main report and three appendixes. Appendix B provides a description of Browns Ferry, Unit 1, plant systems and the failure evaluation of those systems as they apply to accidents at Browns Ferry. Information is presented concerning front-line system fault analysis; support system fault analysis; human error models and probabilities; and generic control circuit analyses

Systems management support for ERCDC study of undergrounding and berm containment. Interim report. Preliminary program assessment and follow-on program development

Energy Technology Data Exchange (ETDEWEB)

1977-08-01

Interim results of a study being conducted with respect to the technological aspects of the costs and benefits of underground nuclear power plant construction in direct support of the California Energy Commission's legislative mandate in this area are presented. The program was directed towards problem scoping, methodology evaluation, program definition and planning for subsequent, more detailed investigations of underground facility designs and their potential advantages and disadvantages. The material presented describes the results of (a) systems analyses which were conducted to determine logical requirements for determination of those elements of a nuclear power plant which should be constructed underground; (b) bounding estimates of incremental plant costs for a variety of underground concepts; (c) applicable prior experience in underground facility design and construction which could be used to identify potential sources of strength and weaknessees of underground nuclear power plants; (d) estimates of seismic environments for underground construction in California; (e) preliminary descriptions of underground reactor accident scenarios; (f) bounding estimates of the consequences of such accidents, in terms of comparisons of relative emissions of radioactivity with respect to similar accidents for surface-sited nuclear power plants and (g) results of analyses of several other important technological aspects of the problem. A description is also provided of the program development work performed to provide planning and criteria for subsequent investigations to determine: (a) definitive underground nuclear power plant designs and costs, and (b) estimates of accident consequences in underground nuclear power plants.

Systems management support for ERCDC study of undergrounding and berm containment. Interim report. Preliminary program assessment and follow-on program development

International Nuclear Information System (INIS)

1977-08-01

Interim results of a study being conducted with respect to the technological aspects of the costs and benefits of underground nuclear power plant construction in direct support of the California Energy Commission's legislative mandate in this area are presented. The program was directed towards problem scoping, methodology evaluation, program definition and planning for subsequent, more detailed investigations of underground facility designs and their potential advantages and disadvantages. The material presented describes the results of (a) systems analyses which were conducted to determine logical requirements for determination of those elements of a nuclear power plant which should be constructed underground; (b) bounding estimates of incremental plant costs for a variety of underground concepts; (c) applicable prior experience in underground facility design and construction which could be used to identify potential sources of strength and weaknessees of underground nuclear power plants; (d) estimates of seismic environments for underground construction in California; (e) preliminary descriptions of underground reactor accident scenarios; (f) bounding estimates of the consequences of such accidents, in terms of comparisons of relative emissions of radioactivity with respect to similar accidents for surface-sited nuclear power plants and (g) results of analyses of several other important technological aspects of the problem. A description is also provided of the program development work performed to provide planning and criteria for subsequent investigations to determine: (a) definitive underground nuclear power plant designs and costs, and (b) estimates of accident consequences in underground nuclear power plants

Sustainable Solutions for Nuclear used Fuels Interim Storage

International Nuclear Information System (INIS)

Arslan, Marc; Favet, Dominique; Issard, Herve; Le Jemtel, Amaury; Drevon, Caroline

2014-01-01

AREVA has a unique experience in providing sustainable solutions for used fuel management, fitted with the needs of different customers in the world and with regulation in different countries. These solutions entail both recycling and interim storage technologies. In a first part, we will describe the various types of solutions for Interim Storage of UNF that have been implemented around the world for interim storage at reactor or centralized Pad solution in canisters dry storage, vault type storages for dry storage, dry storage of transportation casks (dual purpose) pools for wet storage, The experience for all these different families of interim storages in which AREVA is involved is extensive and will be discussed with respect to the new challenges: increase of the duration of the interim storage (long term interim storage) increase of burn up of the fuels In a second part of the presentation, special recycling features will be presented. In that case, interim storage of the used fuels is ensured in pools. This provides in the long term good conditions for the behaviour of the fuel and its retrievability. With recycling, the final waste (Universal Canister of vitrified fission products and compacted hulls and end pieces): is stable and licensed in many countries for the final disposal (France, UK, Belgium, NL, Switzerland, Germany, Japan, upcoming: Spain, Australia, Italy). Presents neither safety criticality risks nor proliferation risks (AREVA conditioned HLW and LL-ILW are free of IAEA safeguard constraints thanks to AREVA process high recovery and purification yields). It can therefore be safely stored in interim storage for more than 100 years before final disposal. Some economic considerations will also be discussed. In particular, in the case of long term interim storage of used fuels, there are growing uncertainties regarding the future needs of repackaging and transportation, which can result in future cost overruns. Meanwhile, in the recycling policy

Retention of long-term interim restorations with sodium fluoride enriched interim cement

Science.gov (United States)

Strash, Carolyn

Purpose: Interim fixed dental prostheses, or "provisional restorations", are fabricated to restore teeth when definitive prostheses are made indirectly. Patients undergoing extensive prosthodontic treatment frequently require provisionalization for several months or years. The ideal interim cement would retain the restoration for as long as needed and still allow for ease of removal. It would also avoid recurrent caries by preventing demineralization of tooth structure. This study aims to determine if adding sodium fluoride varnish to interim cement may assist in the retention of interim restorations. Materials and methods: stainless steel dies representing a crown preparation were fabricated. Provisional crowns were milled for the dies using CAD/CAM technology. Crowns were provisionally cemented onto the dies using TempBond NE and NexTemp provisional cements as well as a mixture of TempBond NE and Duraphat fluoride varnish. Samples were stored for 24h then tested or thermocycled for 2500 or 5000 cycles before being tested. Retentive strength of each cement was recorded using a universal testing machine. Results: TempBond NE and NexTemp cements performed similarly when tested after 24h. The addition of Duraphat significantly decreased the retention when added to TempBond NE. NexTemp cement had high variability in retention over all tested time periods. Thermocycling for 2500 and 5000 cycles significantly decreased the retention of all cements. Conclusions: The addition of Duraphat fluoride varnish significantly decreased the retention of TempBond NE and is therefore not recommended for clinical use. Thermocycling significantly reduced the retention of TempBond NE and NexTemp. This may suggest that use of these cements for three months, as simulated in this study, is not recommended.

The Nord interim store

International Nuclear Information System (INIS)

Leushacke, D.F.; Rittscher, D.

1996-01-01

In line with the decision taken in 1990 to shut down and decommission the Greifswald and Rheinsberg Nuclear Power Stations, the waste management concept of the Energiewerke Nord is based on direct and complete decommissioning of the six shut down reactor units within the next fifteen years. One key element of this concept is the construction and use of the Zwischenlager Nord (Nord Interim Store, ZLN) for holding the existing nuclear fuels and for interim and decay storage of the radioactive materials arising in decommissioning and demolition. The owner and operator of the store is Energiewerke Nord GmbH. The interim store has the functions of a processing and Energiewerke Nord GmbH. The interim store has the functions of a processing and treatment station and buffer store for the flows of residues arising. As a radioactive waste management station, it accommodates nuclear fuels, radioactive waste or residues which are not treated any further. It is used as a buffer store to allow the materials accumulating in disassembly to be stored temporarily before or after treatment in order to ensure continuous loading of the treatment plants. When operated as a processing station, the ZLN is able to handle nearly all types of radioactive waste and residues arising, except for nuclear fuels. These installations allow the treatment of radioactive residues to be separated from the demolition work both physically and in time. The possibilities of interium storage and buffer storage of untreated waste and waste packages make for high flexibility in logistics and waste management strategy. (orig.) [de

Interim storage of radioactive waste packages

International Nuclear Information System (INIS)

1998-01-01

This report covers all the principal aspects of production and interim storage of radioactive waste packages. The latest design solutions of waste storage facilities and the operational experiences of developed countries are described and evaluated in order to assist developing Member States in decision making and design and construction of their own storage facilities. This report is applicable to any category of radioactive waste package prepared for interim storage, including conditioned spent fuel, high level waste and sealed radiation sources. This report addresses the following issues: safety principles and requirements for storage of waste packages; treatment and conditioning methods for the main categories of radioactive waste; examples of existing interim storage facilities for LILW, spent fuel and high level waste; operational experience of Member States in waste storage operations including control of storage conditions, surveillance of waste packages and observation of the behaviour of waste packages during storage; retrieval of waste packages from storage facilities; technical and administrative measures that will ensure optimal performance of waste packages subject to various periods of interim storage

Terrestrial gravity data analysis for interim gravity model improvement

Science.gov (United States)

1987-01-01

This is the first status report for the Interim Gravity Model research effort that was started on June 30, 1986. The basic theme of this study is to develop appropriate models and adjustment procedures for estimating potential coefficients from terrestrial gravity data. The plan is to use the latest gravity data sets to produce coefficient estimates as well as to provide normal equations to NASA for use in the TOPEX/POSEIDON gravity field modeling program.

Reliability Centered Maintenance for Savannah River Site's interim waste management facilities

Energy Technology Data Exchange (ETDEWEB)

Hauer, K.A. (Westinghouse Savannah River Co., Aiken, SC (United States)); Wilson, J.F. (PRC, Inc. (US))

1992-01-01

The application of Reliability Centered Maintenance (RCM) has been shown to be an effective means to optimize maintenance programs or to establish new programs. The key to success of any RCM program is to customize the methodology to meet the specific needs of the implementing organization. This paper discusses how RCM is being used to establish the preventive maintenance program and how the resulting system data is being used to support the Technical Baseline reconstitution effort for the interim Waste Management Division of Westinghouse Savannah River Company (WSRC).

76 FR 19909 - International Terrorism Victim Expense Reimbursement Program

Science.gov (United States)

2011-04-11

... 1121-AA78 International Terrorism Victim Expense Reimbursement Program AGENCY: Office of Justice... promulgating this interim-final rule for its International Terrorism Victim Expense Reimbursement Program... international terrorism. DATES: Effective date: This interim-final rule is effective April 11, 2011. Comment...

76 FR 58790 - Notice of Interim Approval

Science.gov (United States)

2011-09-22

... to the customers. Rate Scenario 3--Original Cumberland Marketing Policy The third rate alternative... an interim basis to the customers. Rate Scenario 3--Original Cumberland Marketing Policy The third... allocated on an interim basis to the customers. Rate Scenario 3--Original Cumberland Marketing Policy The...

Interim site characterization report and ground-water monitoring program for the Hanford site solid waste landfill

International Nuclear Information System (INIS)

Fruland, R.M.; Hagan, R.A.; Cline, C.S.; Bates, D.J.; Evans, J.C.; Aaberg, R.L.

1989-07-01

Federal and state regulations governing the operation of landfills require utilization of ground-water monitoring systems to determine whether or not landfill operations impact ground water at the point of compliance (ground water beneath the perimeter of the facility). A detection-level ground-water monitoring system was designed, installed, and initiated at the Hanford Site Solid Waste Landfill (SWL). Chlorinated hydrocarbons were detected at the beginning of the ground-water monitoring program and continue to be detected more than 1 year later. The most probable source of the chlorinated hydrocarbons is washwater discharged to the SWL between 1985 and 1987. This is an interim report and includes data from the characterization work that was performed during well installation in 1987, such as field observations, sediment studies, and geophysical logging results, and data from analyses of ground-water samples collected in 1987 and 1988, such as field parameter measurements and chemical analyses. 38 refs., 27 figs., 8 tabs

Diesel Emission Control -- Sulfur Effects (DECSE) Program; Phase I Interim Date Report No. 3: Diesel Fuel Sulfur Effects on Particulate Matter Emissions

Energy Technology Data Exchange (ETDEWEB)

DOE; ORNL; NREL; EMA; MECA

1999-11-15

The Diesel Emission Control-Sulfur Effects (DECSE) is a joint government/industry program to determine the impact of diesel fuel sulfur levels on emission control systems whose use could lower emissions of nitrogen oxides (NO{sub x}) and particulate matter (PM) from on-highway trucks in the 2002--2004 model years. Phase 1 of the program was developed with the following objectives in mind: (1) evaluate the effects of varying the level of sulfur content in the fuel on the emission reduction performance of four emission control technologies; and (2) measure and compare the effects of up to 250 hours of aging on selected devices for multiple levels of fuel sulfur content. This interim report covers the effects of diesel fuel sulfur level on particulate matter emissions for four technologies.

The Interim Financial Statements: The Case of Greece

OpenAIRE

Rogdaki, E.I.; Kazantzis, Ch.

1999-01-01

The following paper refers to the accounting and auditing issues which emerge in the preparation of the interim financial statements of the companies: Firstly, the interim financial statements are defined as being the financial statements that provide useful information about the financial position and the financial results of a company which are realized and accrued during the fiscal year. The interim financial statements can be prepared on a monthly basis, on a quarterly basis or covering a...

The cost and impact of the interim federal health program cuts on child refugees in Canada.

Directory of Open Access Journals (Sweden)

Andrea Evans

Full Text Available INTRODUCTION: On June 30, 2012, Interim Federal Health Program (IFHP funding was cut for refugee claimant healthcare. The potential financial and healthcare impacts of these cuts on refugee claimants are unknown. METHODS: We conducted a one-year retrospective chart review spanning 6 months before and after IFHP funding cuts at The Hospital for Sick Children, a tertiary care children's hospital in Toronto. We analyzed emergency room visits characteristics, admission rates, reasons for admission, and financial records including billing from Medavie Blue Cross. RESULTS: There were 173 refugee children visits to the emergency room in the six months before and 142 visits in the six months after funding cuts. The total amount billed to the IFHP program during the one-year of this study was $131,615. Prior to the IFHP cuts, 46% of the total emergency room bills were paid by IFHP compared to 7% after the cuts (p<0.001. INTERPRETATION: After the cuts to the IFHP, The Hospital for Sick Children was unable to obtain federal health coverage for the vast majority of refugee claimant children registered under the IFHP. This preliminary analysis showed that post-IFHP cuts healthcare costs at the largest tertiary pediatric institution in the country increased.

Waste resources utilization program. Interim report, June 30, 1976

International Nuclear Information System (INIS)

1976-07-01

This is an interim report on the effects of the combined use of heat and ionizing radiation (thermoradiation) as a treatment for ridding sewage sludge of pathogenic organisms as well as its effect on the physical-chemical properties. This activity couples two major environmental problems, disposition of human and of nuclear waste, in an attempt to provide a framework in which both will become useful resources. This combined treatment might be chosen to inactivate both heat labile (but possibly radiation resistant) and radiation labile (but possibly heat resistant) organisms. The cost-effective analyses of such a treatment are being examined. Sludge treated with thermoradiation offers considerable potential for use as a fertilizer in agriculture or a soil conditioner for land reclamation free of the potential health hazards associated with conventional methods of land disposal. Treated sludge may also provide a low-cost substitute for high-nutritional components in ruminant diets

Effectiveness of interim remedial actions at a radioactive waste facility

International Nuclear Information System (INIS)

Devgun, J.S.; Beskid, N.J.; Peterson, J.M.; Seay, W.M.; McNamee, E.

1989-01-01

Over the past eight years, several interim remedial actions have been taken at the Niagara Falls Storage Site (NFSS), primarily to reduce radon and gamma radiation exposures and to consolidate radioactive waste into a waste containment facility. Interim remedial actions have included capping of vents, sealing of pipes, relocation of the perimeter fence (to limit radon risk), transfer and consolidation of waste, upgrading of storage buildings, construction of a clay cutoff wall (to limit the potential groundwater transport of contaminants), treatment and release of contaminated water, interim use of a synthetic liner, and emplacement of an interim clay cap. An interim waste containment facility was completed in 1986. 6 refs., 3 figs

Elder Abuse Demonstration Project. Third Interim Report to the Illinois General Assembly on Public Acts 83-1259 and 83-1432.

Science.gov (United States)

Illinois State Dept. on Aging, Springfield.

This document contains the third annual interim report of the Illinois Elder Abuse Demonstration Program. It discusses the overall intent of the demonstration program, trends and changes in the third year of the demonstration program compared with the results from the first two years of the program, and achievements and recommendations for a…

Reliability Centered Maintenance for Savannah River Site`s interim waste management facilities. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Hauer, K.A. [Westinghouse Savannah River Co., Aiken, SC (United States); Wilson, J.F. [PRC, Inc. (US)

1992-06-01

The application of Reliability Centered Maintenance (RCM) has been shown to be an effective means to optimize maintenance programs or to establish new programs. The key to success of any RCM program is to customize the methodology to meet the specific needs of the implementing organization. This paper discusses how RCM is being used to establish the preventive maintenance program and how the resulting system data is being used to support the Technical Baseline reconstitution effort for the interim Waste Management Division of Westinghouse Savannah River Company (WSRC).

An Approach for Evaluating the Technical Quality of Interim Assessments

Science.gov (United States)

Li, Ying; Marion, Scott; Perie, Marianne; Gong, Brian

2010-01-01

Increasing numbers of schools and districts have expressed interest in interim assessment systems to prepare for summative assessments and to improve teaching and learning. However, with so many commercial interim assessments available, schools and districts are struggling to determine which interim assessment is most appropriate to their needs.…

National Ignition Facility Cryogenic Target Systems Interim Management Plan

International Nuclear Information System (INIS)

Warner, B

2002-01-01

Restricted availability of funding has had an adverse impact, unforeseen at the time of the original decision to projectize the National Ignition Facility (NIF) Cryogenic Target Handling Systems (NCTS) Program, on the planning and initiation of these efforts. The purpose of this document is to provide an interim project management plan describing the organizational structure and management processes currently in place for NCTS. Preparation of a Program Execution Plan (PEP) for NCTS has been initiated, and a current draft is provided as Attachment 1 to this document. The National Ignition Facility is a multi-megajoule laser facility being constructed at Lawrence Livermore National Laboratory (LLNL) by the National Nuclear Security Administration (NNSA) in the Department of Energy (DOE). Its primary mission is to support the Stockpile Stewardship Program (SSP) by performing experiments studying weapons physics, including fusion ignition. NIF also supports the missions of weapons effects, inertial fusion energy, and basic science in high-energy-density physics. NIF will be operated by LLNL under contract to the University of California (UC) as a national user facility. NIF is a low-hazard, radiological facility, and its operation will meet all applicable federal, state, and local Environmental Safety and Health (ES and H) requirements. The NCTS Interim Management Plan provides a summary of primary design criteria and functional requirements, current organizational structure, tracking and reporting procedures, and current planning estimates of project scope, cost, and schedule. The NIF Director controls the NIF Cryogenic Target Systems Interim Management Plan. Overall scope content and execution schedules for the High Energy Density Physics Campaign (SSP Campaign 10) are currently undergoing rebaselining and will be brought into alignment with resources expected to be available throughout the NNSA Future Years National Security Plan (FYNSP). The revised schedule for

75 FR 70083 - Emergency Forest Restoration Program and Emergency Conservation Program

Science.gov (United States)

2010-11-17

... Restoration Program and Emergency Conservation Program AGENCY: Farm Service Agency, USDA. ACTION: Interim rule. SUMMARY: The Farm Service Agency (FSA) is amending regulations as required by the Food, Conservation, and... as follows: PART 701--EMERGENCY CONSERVATION PROGRAM, EMERGENCY FOREST RESTORATION PROGRAM, AND...

Disposal facility data for the interim performance

International Nuclear Information System (INIS)

Eiholzer, C.R.

1995-01-01

The purpose of this report is to identify and provide information on the waste package and disposal facility concepts to be used for the low-level waste tank interim performance assessment. Current concepts for the low-level waste form, canister, and the disposal facility will be used for the interim performance assessment. The concept for the waste form consists of vitrified glass cullet in a sulfur polymer cement matrix material. The waste form will be contained in a 2 x 2 x 8 meter carbon steel container. Two disposal facility concepts will be used for the interim performance assessment. These facility concepts are based on a preliminary disposal facility concept developed for estimating costs for a disposal options configuration study. These disposal concepts are based on vault type structures. None of the concepts given in this report have been approved by a Tank Waste Remediation Systems (TWRS) decision board. These concepts will only be used in th interim performance assessment. Future performance assessments will be based on approved designs

The challenges facing the long term interim storage

Energy Technology Data Exchange (ETDEWEB)

Iracane, D. [CEA Sacaly, Dir. de la Simulation et des Outils Experimentaux-DSOE, 91 - Gif sur Yvette (France); Marvy, A. [CEA Saclay, Dir. du Developpement et de l' Innovation Nucleares-DDIN, 91 - Gif Sur Yvette (France)

2001-07-01

In France electricity generation by means of commercial nuclear power plants has come to a point where it contributes to the national demand at a level of 80%. The safety performance of the production system has also reached a high level of both maturity and reliability taking advantage of the cumulative effect of a 30 years long learning experience and ever more stringent safety requirements. The policy to reprocess spent fuel has been overriding but no final decision has yet been made regarding the ultimate disposition of the waste streams. Although studies on deep geological disposal are ongoing, France is also looking at whether and under which conditions a long-term interim storage may provide an effective flexibility to the fuel cycle back-end. We discuss thereafter the needs and the paramount objectives of this latter R and D program. Results are being framed as potential guiding criteria for decision makers and various stakeholders. In first part, we propose a general analysis which emphasises that a long term interim storage is more than a classical nuclear facility because it explicitly requires long-lasting control and creates a burden for Society during many generations. Then, in second part, we offer an overview of the technical results from the R and D program as they stand at the time of writing. As an answer to the Government request, a strong emphasis has been put on this research for three years. Conclusion is an attempt to outline the societal context in which future decisions will have to be made. (author)

The challenges facing the long term interim storage

International Nuclear Information System (INIS)

Iracane, D.; Marvy, A.

2001-01-01

In France electricity generation by means of commercial nuclear power plants has come to a point where it contributes to the national demand at a level of 80%. The safety performance of the production system has also reached a high level of both maturity and reliability taking advantage of the cumulative effect of a 30 years long learning experience and ever more stringent safety requirements. The policy to reprocess spent fuel has been overriding but no final decision has yet been made regarding the ultimate disposition of the waste streams. Although studies on deep geological disposal are ongoing, France is also looking at whether and under which conditions a long-term interim storage may provide an effective flexibility to the fuel cycle back-end. We discuss thereafter the needs and the paramount objectives of this latter R and D program. Results are being framed as potential guiding criteria for decision makers and various stakeholders. In first part, we propose a general analysis which emphasises that a long term interim storage is more than a classical nuclear facility because it explicitly requires long-lasting control and creates a burden for Society during many generations. Then, in second part, we offer an overview of the technical results from the R and D program as they stand at the time of writing. As an answer to the Government request, a strong emphasis has been put on this research for three years. Conclusion is an attempt to outline the societal context in which future decisions will have to be made. (author)

Subsurface Interim Measures/Interim Remedial Action Plan/ Environmental Assessment and Decision Document, Operable Unit No. 2

International Nuclear Information System (INIS)

1992-01-01

The subject Interim Measures/Interim Remedial Action plan/Environmental Assessment (IM/IRAP/EA) addresses residual free-phase volatile organic compound (VOC) contamination suspected in the subsurface within an area identified as Operable Unit No. 2 (OU2). This IM/IRAP/EA also addresses radionuclide contamination beneath the 903 Pad at OU2. Although subsurface VOC and radionuclide contamination on represent a source of OU2 ground-water contamination, they pose no immediate threat to public health or the environment. This volume contains five appendices

CMM Interim Check Design of Experiments (U)

Energy Technology Data Exchange (ETDEWEB)

Montano, Joshua Daniel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-07-29

Coordinate Measuring Machines (CMM) are widely used in industry, throughout the Nuclear Weapons Complex and at Los Alamos National Laboratory (LANL) to verify part conformance to design definition. Calibration cycles for CMMs at LANL are predominantly one year in length and include a weekly interim check to reduce risk. The CMM interim check makes use of Renishaw’s Machine Checking Gauge which is an off-the-shelf product simulates a large sphere within a CMM’s measurement volume and allows for error estimation. As verification on the interim check process a design of experiments investigation was proposed to test a couple of key factors (location and inspector). The results from the two-factor factorial experiment proved that location influenced results more than the inspector or interaction.

Permitting plan for the high-level waste interim storage

International Nuclear Information System (INIS)

Deffenbaugh, M.L.

1997-01-01

This document addresses the environmental permitting requirements for the transportation and interim storage of solidified high-level waste (HLW) produced during Phase 1 of the Hanford Site privatization effort. Solidified HLW consists of canisters containing vitrified HLW (glass) and containers that hold cesium separated during low-level waste pretreatment. The glass canisters and cesium containers will be transported to the Canister Storage Building (CSB) in a U.S. Department of Energy (DOE)-provided transportation cask via diesel-powered tractor trailer. Tri-Party Agreement (TPA) Milestone M-90 establishes a new major milestone, and associated interim milestones and target dates, governing acquisition and/or modification of facilities necessary for: (1) interim storage of Tank Waste Remediation Systems (TWRS) immobilized HLW (IHLW) and other canistered high-level waste forms; and (2) interim storage and disposal of TWRS immobilized low-activity tank waste (ILAW). An environmental requirements checklist and narrative was developed to identify the permitting path forward for the HLW interim storage (HLWIS) project (See Appendix B). This permitting plan will follow the permitting logic developed in that checklist

Evaluation of ERA-Interim precipitation data in complex terrain

Science.gov (United States)

Gao, Lu; Bernhardt, Matthias; Schulz, Karsten

2013-04-01

Precipitation controls a large variety of environmental processes, which is an essential input parameter for land surface models e.g. in hydrology, ecology and climatology. However, rain gauge networks provides the necessary information, are commonly sparse in complex terrains, especially in high mountainous regions. Reanalysis products (e.g. ERA-40 and NCEP-NCAR) as surrogate data are increasing applied in the past years. Although they are improving forward, previous studies showed that these products should be objectively evaluated due to their various uncertainties. In this study, we evaluated the precipitation data from ERA-Interim, which is a latest reanalysis product developed by ECMWF. ERA-Interim daily total precipitation are compared with high resolution gridded observation dataset (E-OBS) at 0.25°×0.25° grids for the period 1979-2010 over central Alps (45.5-48°N, 6.25-11.5°E). Wet or dry day is defined using different threshold values (0.5mm, 1mm, 5mm, 10mm and 20mm). The correspondence ratio (CR) is applied for frequency comparison, which is the ratio of days when precipitation occurs in both ERA-Interim and E-OBS dataset. The result shows that ERA-Interim captures precipitation occurrence very well with a range of CR from 0.80 to 0.97 for 0.5mm to 20mm thresholds. However, the bias of intensity increases with rising thresholds. Mean absolute error (MAE) varies between 4.5 mm day-1 and 9.5 mm day-1 in wet days for whole area. In term of mean annual cycle, ERA-Interim almost has the same standard deviation of the interannual variability of daily precipitation with E-OBS, 1.0 mm day-1. Significant wet biases happened in ERA-Interim throughout warm season (May to August) and dry biases in cold season (November to February). The spatial distribution of mean annual daily precipitation shows that ERA-Interim significant underestimates precipitation intensity in high mountains and northern flank of Alpine chain from November to March while pronounced

12 CFR 541.18 - Interim Federal savings association.

Science.gov (United States)

2010-01-01

... an existing savings and loan holding company or to facilitate any other transaction the Office may... 12 Banks and Banking 5 2010-01-01 2010-01-01 false Interim Federal savings association. 541.18... REGULATIONS AFFECTING FEDERAL SAVINGS ASSOCIATIONS § 541.18 Interim Federal savings association. The term...

Interim Service ISDN Satellite (ISIS) network model for advanced satellite designs and experiments

Science.gov (United States)

Pepin, Gerard R.; Hager, E. Paul

1991-01-01

The Interim Service Integrated Services Digital Network (ISDN) Satellite (ISIS) Network Model for Advanced Satellite Designs and Experiments describes a model suitable for discrete event simulations. A top-down model design uses the Advanced Communications Technology Satellite (ACTS) as its basis. The ISDN modeling abstractions are added to permit the determination and performance for the NASA Satellite Communications Research (SCAR) Program.

Interim sanitary landfill groundwater monitoring report. 1996 Annual report

International Nuclear Information System (INIS)

Bagwell, L.A.

1997-01-01

Eight wells of the LFW series monitor groundwater quality in the Steed Pond Aquifer (Water Table) beneath the Interim Sanitary Landfill at the Savannah River Site. These wells are sampled semiannually to comply with the South Carolina Department of Health and Environmental Control Modified Municipal Solid Waste Permit 025500-1120 and as part of the SRS Groundwater Monitoring Program. Trichlorofluoromethane and 1,1,1-trichloroethane were elevated in one sidegradient well and one downgradient well during 1996. Zinc was elevated in three downgradient wells and also was detected in the associated laboratory blanks for two of those wells. Specific conductance was elevated in one background well and one sidegradient well. Barium and copper exceeded standards in one sidegradient well, and dichloromethane (a common laboratory contaminant) was elevated in another sidegradient well. Barium, copper, and dichloromethane were detected in the associated blanks for these wells, also. The groundwater flow direction in the Steed Pond Acquifer (Water Table) beneath the Interim Sanitary Landfill was to the southeast (universal transverse Mercator coordinates). The flow rate in this unit was approximately 210 ft/year during first quarter 1996 and 180 ft/yr during third quarter 1996

76 FR 52996 - Public Company Accounting Oversight Board; Order Approving Proposed Temporary Rule for an Interim...

Science.gov (United States)

2011-08-24

... Accounting Oversight Board; Order Approving Proposed Temporary Rule for an Interim Program of Inspection Related to Audits of Brokers and Dealers August 18, 2011. I. Introduction On June 21, 2011, the Public... that would be imposed on different categories of registered public accounting firms and classes of...

Design review report FFTF interim storage cask

International Nuclear Information System (INIS)

Scott, P.L.

1995-01-01

Final Design Review Report for the FFTF Interim Storage Cask. The Interim Storage Cask (ISC) will be used for long term above ground dry storage of FFTF irradiated fuel in Core Component Containers (CCC)s. The CCC has been designed and will house assemblies that have been sodium washed in the IEM Cell. The Solid Waste Cask (SWC) will transfer a full CCC from the IEM Cell to the RSB Cask Loading Station where the ISC will be located to receive it. Once the loaded ISC has been sealed at the RSB Cask Loading Station, it will be transferred by facility crane to the DSWC Transporter. After the ISC has been transferred to the Interim Storage Area (ISA), which is yet to be designed, a mobile crane will be used to place the ISC in its final storage location

Choosing a spent fuel interim storage system

International Nuclear Information System (INIS)

Roland, V.; Hunter, I.

2001-01-01

The Transnucleaire Group has developed different modular solutions to address spent fuel interim storage needs of NPP. These solutions, that are present in Europe, USA and Asia are metal casks (dual purpose or storage only) of the TN 24 family and the NUHOMS canister based system. It is not always simple for an operator to sort out relevant choice criteria. After explaining the basic designs involved on the examples of the TN 120 WWER dual purpose cask and the NUHOMS 56 WWER for WWER 440 spent fuel, we shall discuss the criteria that govern the choice of a given spent fuel interim storage system from the stand point of the operator. In conclusion, choosing and implementing an interim storage system is a complex process, whose implications can be far reaching for the long-term success of a spent fuel management policy. (author)

Extraction, -scrub, -strip test results from the interim salt disposition program macrobatch 10 tank 21H qualification samples

Energy Technology Data Exchange (ETDEWEB)

Peters, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-06-26

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 10 for the Interim Salt Disposition Program (ISDP). The Salt Batch 10 characterization results were previously reported.ii,iii An Extraction, -Scrub, -Strip (ESS) test was performed to determine cesium distribution ratios (D(Cs)) and cesium concentration in the strip effluent (SE) and decontaminated salt solution (DSS) streams; this data will be used by Tank Farm Engineering to project a cesium decontamination factor (DF). This test used actual Tank 21H material, and a sample of the NGS Blend solvent currently being used at the Modular Caustic-Side Solvent Extraction Unit (MCU). The ESS test showed acceptable performance with an extraction D(Cs) value of 110. This value is consistent with results from previous salt batch ESS tests using similar solvent formulations. This is better than the predicted value of 39.8 from a recently created D(Cs) model.

47 CFR 51.715 - Interim transport and termination pricing.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 3 2010-10-01 2010-10-01 false Interim transport and termination pricing. 51.715 Section 51.715 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER... Telecommunications Traffic § 51.715 Interim transport and termination pricing. (a) Upon request from a...

Colonie Interim Storage Site: Annual site environmental report, Colonie, New York, Calendar year 1986: Formerly Utilized Sites Remedial Action Program (FUSRAP)

International Nuclear Information System (INIS)

1987-06-01

During 1986, the environmental monitoring program continued at the Colonie Interim Storage Site (CISS), a US Department of Energy (DOE) facility located in Colonie, New York. The CISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has mandated DOE to remedy. As part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Appropriations Act, remedial action is being conducted at the site and at vicinity properties by Bechtel National Inc. (BNI), Project Management Contractor for FUSRAP. The environmental monitoring program is also carried out by BNI. The monitoring program at the CISS measures external gamma radiation levels as well as uranium and radium-226 concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard and to assess the potential effect of the site on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, the maximally exposed individual would receive an annual external exposure approximately equivalent to 5% of the DOE radiation protection standard of 100 mrem/y. Results of 1986 monitoring show that the CISS is in compliance with the DOE radiation protection standard. 14 refs., 9 figs., 9 tabs

A comparison of the value relevance of interim and annual financial statements

Directory of Open Access Journals (Sweden)

Mbalenhle Zulu

2017-03-01

Aim: It explores whether the value relevance of interim financial statements is higher than the value relevance of annual financial statements. Finally, it investigates whether accounting information published in interim and annual financial statements has incremental value relevance. Setting: Data for the period from 1999 to 2012 were collected from a sample of non-financial companies listed on the Johannesburg Stock Exchange. Method: The Ohlson model to investigate the value relevance of accounting information was used for the study. Results: The results show that interim book value of equity is value relevant while interim earnings are not. Interim financial statements appear to have higher value relevance than annual financial statements. The value relevance of interim and annual accounting information has remained fairly constant over the sample period. Incremental comparisons provide evidence that additional book value of equity and earnings that accrue to a company between interim and annual reporting dates are value relevant. Conclusion: The study was conducted over a long sample period (1999–2012, in an era when a technology-driven economy and more timely reporting media could have had an effect on the value relevance of published accounting information. To the best of our knowledge, this is the first study to evaluate and compare the value relevance of published interim and annual financial statements.

75 FR 21506 - Magnet Schools Assistance Program

Science.gov (United States)

2010-04-26

... DEPARTMENT OF EDUCATION 34 CFR Part 280 RIN 1855-AA07 [Docket ID ED-2010-OII-0003] Magnet Schools Assistance Program AGENCY: Office of Innovation and Improvement, Department of Education. ACTION: Interim... in the Federal Register an interim final rule and requested comments on that rule for the Magnet...

Single-shell tank interim stabilization risk analysis

International Nuclear Information System (INIS)

Basche, A.D.

1998-01-01

The purpose of the Single-Shell Tank (SST) Interim Stabilization Risk Analysis is to provide a cost and schedule risk analysis of HNF-2358, Rev. 1, Single-Shell Tank Interim Stabilization Project Plan (Project Plan) (Ross et al. 1998). The analysis compares the required cost profile by fiscal year (Section 4.2) and revised schedule completion date (Section 4.5) to the Project Plan. The analysis also evaluates the executability of the Project Plan and recommends a path forward for risk mitigation

TWRS HLW interim storage facility search and evaluation

Energy Technology Data Exchange (ETDEWEB)

Calmus, R.B., Westinghouse Hanford

1996-05-16

The purpose of this study was to identify and provide an evaluation of interim storage facilities and potential facility locations for the vitrified high-level waste (HLW) from the Phase I demonstration plant and Phase II production plant. In addition, interim storage facilities for solidified separated radionuclides (Cesium and Technetium) generated during pretreatment of Phase I Low-Level Waste Vitrification Plant feed was evaluated.

Interim report

Energy Technology Data Exchange (ETDEWEB)

NONE

1985-06-01

This Interim Report summarizes the research and development activities of the Superconducting Super Collider project carried out from the completion of the Reference Designs Study (May 1984) to June 1985. It was prepared by the SSC Central Design Group in draft form on the occasion of the DOE Annual Review, June 19--21, 1985. Now largely organized by CDG Divisions, the bulk of each chapter documents the progress and accomplishments to date, while the final section(s) describe plans for future work. Chapter 1, Introduction, provides a basic brief description of the SSC, its physics justification, its origins, and the R&D organization set up to carry out the work. Chapter 2 gives a summary of the main results of the R&D program, the tasks assigned to the four magnet R&D centers, and an overview of the future plans. The reader wishing a quick look at the SSC Phase I effort can skim Chapter 1 and read Chapter 2. Subsequent chapters discuss in more detail the activities on accelerator physics, accelerator systems, magnets and cryostats, injector, detector R&D, conventional facilities, and project planning and management. The magnet chapter (5) documents in text and photographs the impressive progress in successful construction of many model magnets, the development of cryostats with low heat leaks, and the improvement in current-carrying capacity of superconducting strand. Chapter 9 contains the budgets and schedules of the COG Divisions, the overall R&D program, including the laboratories, and also preliminary projections for construction. Appendices provide information on the various panels, task forces and workshops held by the CDG in FY 1985, a bibliography of COG and Laboratory reports on SSC and SSC-related work, and on private industrial involvement in the project.

78 FR 79567 - National School Lunch Program and School Breakfast Program: Nutrition Standards for All Foods...

Science.gov (United States)

2013-12-31

... Program: Nutrition Standards for All Foods Sold in Schools as Required by the Healthy, Hunger-Free Kids... interim rule entitled National School Lunch Program and School Breakfast Program: Nutrition Standards for..., 2013 / Rules and Regulations [[Page 79567

Gaz de France interim financial report 2007

International Nuclear Information System (INIS)

2007-01-01

This financial report contains the unaudited condensed financial statements of Gaz de France Group for the first half ended June 30, 2007, which were reviewed by the audit committee on August 27, 2007 and by the board of directors at its meeting on August 28, 2007. It includes forward-looking statements concerning the objectives, strategies, financial position, future operating results and the operations of Gaz de France Group. These statements reflect the Group's current perception of its activities and the markets in which it operates, as well as various estimates and assumptions considered to be reasonable. Content: interim management report (highlights of the first half of 2007, revenues and results for the period, financial structure, data on outstanding stock, outlook); interim consolidated financial statements (consolidated statements of income, consolidated balance sheets, consolidated statements of cash flows, recognized income and expenses, statements of changes in shareholders' equity, note to the consolidated financial statements); statement by the person responsible for the interim financial report; statutory auditors' report. (J.S.)

Climate change : we are at risk : interim report

International Nuclear Information System (INIS)

Oliver, D.; Wiebe, J.

2003-06-01

Between November 2002 and May 2003 the Standing Senate Committee on Agriculture and Forestry travelled across Canada to hear the views of farmer organizations, rural associations, ecotourism groups and environmental organizations regarding concerns about climate change and the impact it may have on the agriculture and forestry sectors and rural communities. The Committee also examined potential adaptation strategies focusing on primary production, practices, technologies, ecosystems and other related areas. Farmers and forest operators are already facing changes in market conditions, domestic regulations, trade policies and technology. This interim report expressed the concerns of farmers and forest operators. It includes a review of the Saguenay flood of 1996, the Red River flood of 1997, the ice storm of 1998, and droughts since 1999. It also includes a discussion on climate change and its biophysical and economic effects on agriculture, forestry, water resources, rural communities, and Aboriginal communities. This interim report also briefly outlines the Kyoto Protocol, the emissions trading system, and the decarbonization of global energy systems. It emphasized the need for integrated research and government policies and programs that encourage adaptation to climate change. The final report will be released in October 2003 and will provide specific recommendations to ensure that Canada responds to the concerns of farmers and forest operators and to ensure continued prosperity in these sectors. refs., figs

Climate change : we are at risk : interim report

Energy Technology Data Exchange (ETDEWEB)

Oliver, D.; Wiebe, J.

2003-06-01

Between November 2002 and May 2003 the Standing Senate Committee on Agriculture and Forestry travelled across Canada to hear the views of farmer organizations, rural associations, ecotourism groups and environmental organizations regarding concerns about climate change and the impact it may have on the agriculture and forestry sectors and rural communities. The Committee also examined potential adaptation strategies focusing on primary production, practices, technologies, ecosystems and other related areas. Farmers and forest operators are already facing changes in market conditions, domestic regulations, trade policies and technology. This interim report expressed the concerns of farmers and forest operators. It includes a review of the Saguenay flood of 1996, the Red River flood of 1997, the ice storm of 1998, and droughts since 1999. It also includes a discussion on climate change and its biophysical and economic effects on agriculture, forestry, water resources, rural communities, and Aboriginal communities. This interim report also briefly outlines the Kyoto Protocol, the emissions trading system, and the decarbonization of global energy systems. It emphasized the need for integrated research and government policies and programs that encourage adaptation to climate change. The final report will be released in October 2003 and will provide specific recommendations to ensure that Canada responds to the concerns of farmers and forest operators and to ensure continued prosperity in these sectors. refs., figs.

Fire Hazards Analysis for the 200 Area Interim Storage Area

International Nuclear Information System (INIS)

JOHNSON, D.M.

2000-01-01

This documents the Fire Hazards Analysis (FHA) for the 200 Area Interim Storage Area. The Interim Storage Cask, Rad-Vault, and NAC-1 Cask are analyzed for fire hazards and the 200 Area Interim Storage Area is assessed according to HNF-PRO-350 and the objectives of DOE Order 5480 7A. This FHA addresses the potential fire hazards associated with the Interim Storage Area (ISA) facility in accordance with the requirements of DOE Order 5480 7A. It is intended to assess the risk from fire to ensure there are no undue fire hazards to site personnel and the public and to ensure property damage potential from fire is within acceptable limits. This FHA will be in the form of a graded approach commensurate with the complexity of the structure or area and the associated fire hazards

Colonie Interim Storage Site environmental report for calendar year 1992, 1130 Central Avenue, Colonie, New York. Formerly Utilized Sites Remedial Action Program (FUSRAP)

Energy Technology Data Exchange (ETDEWEB)

1993-05-01

This report describes the environmental surveillance program at the Colonie Interim Storage Site (CISS) and provides the results for 1992. The site is located in eastern New York State, approximately 6.4 km (4.0 mi) northwest of downtown Albany. From 1958 to 1984, National Lead (NL) Industries used the facility to manufacture various components from depleted and enriched uranium natural thorium. Environmental monitoring of CISS began in 1984 when Congress added, the site to the US Department of Energy`s (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a program established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation`s atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental surveillance program at CISS includes sampling networks for external gamma radiation exposure and for thorium-232 and total uranium concentrations in surface water, sediment, and groundwater. Several chemical parameters are also measured in groundwater, including total metals, volatile organics, and water quality parameters. This surveillance program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Results are compared with applicable Environmental Protection Agency (EPA) and New York State Department of Environmental Conservation (NYSDEC) standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements.

Use of alternative dispute resolution--HHS. Notice of interim policy.

Science.gov (United States)

1992-10-27

The Department has developed an interim policy to address the use of alternative dispute resolution (ADR) as required by the Administrative Dispute Resolution Act (ADR Act), Public Law No. 101-552. This interim policy also responds to the Negotiated Rulemaking Act, Public Law No. 101-648, and relevant elements of the Executive Order on Civil Justice Reform (E.O. 12778). The Department is adopting an interim policy because we need a baseline of experience and knowledge from our own pilot activities and those of other agencies before finalizing a policy.

50 CFR 660.720 - Interim protection for sea turtles.

Science.gov (United States)

2010-10-01

... 50 Wildlife and Fisheries 9 2010-10-01 2010-10-01 false Interim protection for sea turtles. 660.720 Section 660.720 Wildlife and Fisheries FISHERY CONSERVATION AND MANAGEMENT, NATIONAL OCEANIC AND... Migratory Fisheries § 660.720 Interim protection for sea turtles. (a) Until the effective date of §§ 660.707...

Interim report and accounts 1993/94

International Nuclear Information System (INIS)

1993-01-01

An interim set of accounts and reports is presented here for 1993/1994 for the health science company Amersham International. The company's research programs focus on developments in life science research, nuclear medicine and industrial quality and safety assurance, with particular expertise in the application of radioactivity to labelling and detection at the molecular level. This report which covers the half-year to 30 September 1993 shows promising financial results, with turnover, operating profits and earnings per share all having risen. All life science markets report growth although difficult trading conditions are being reported in Europe. Two products in the Healthcare business have achieved progress, a pain palliation agent for bone metastases has been launched in the United States, and European approval has been gained for a new technetium based heart imaging agent. Further growth is expected for the company. (UK)

CMM Interim Check (U)

Energy Technology Data Exchange (ETDEWEB)

Montano, Joshua Daniel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-03-23

Coordinate Measuring Machines (CMM) are widely used in industry, throughout the Nuclear Weapons Complex and at Los Alamos National Laboratory (LANL) to verify part conformance to design definition. Calibration cycles for CMMs at LANL are predominantly one year in length. Unfortunately, several nonconformance reports have been generated to document the discovery of a certified machine found out of tolerance during a calibration closeout. In an effort to reduce risk to product quality two solutions were proposed – shorten the calibration cycle which could be costly, or perform an interim check to monitor the machine’s performance between cycles. The CMM interim check discussed makes use of Renishaw’s Machine Checking Gauge. This off-the-shelf product simulates a large sphere within a CMM’s measurement volume and allows for error estimation. Data was gathered, analyzed, and simulated from seven machines in seventeen different configurations to create statistical process control run charts for on-the-floor monitoring.

Interim process report for the safety assessment SR-Can

International Nuclear Information System (INIS)

Sellin, Patrick

2004-08-01

This report is a documentation of buffer processes identified as relevant to the long-term safety of a KBS-3 repository. The report is part of the interim reporting of the safety assessment SR-Can, see further the Interim main report. The final SR-Can reporting will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of this report is to document the scientific knowledge of the processes to a level required for an adequate treatment in the safety assessment. The documentation is thus from a scientific point of not exhaustive since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. The purpose is further to determine the handling of each process in the safety assessment and to demonstrate how uncertainties are taken care of, given the suggested handling. The process documentation in the SR 97 version of the Process report is a starting point for this SR-Can interim version. As further described in the Interim main report, the list of relevant processes has been reviewed and slightly extended by comparison to other databases. Furthermore, the backfill has been included as a system part of its own, rather than being described together with the buffer as in SR 97. Apart from giving an interim account of the documentation and handling of buffer processes in SR-Can, this report is meant to serve as a template for the forthcoming documentation of processes occurring in other parts of the repository system. A complete list of processes can be found in the Interim FEP report for the safety assessment SR-Can. All material presented in this document is preliminary in nature and will possibly be updated as the SR-Can project progresses

Interim process report for the safety assessment SR-Can

Energy Technology Data Exchange (ETDEWEB)

Sellin, Patrick (ed.)

2004-08-01

This report is a documentation of buffer processes identified as relevant to the long-term safety of a KBS-3 repository. The report is part of the interim reporting of the safety assessment SR-Can, see further the Interim main report. The final SR-Can reporting will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of this report is to document the scientific knowledge of the processes to a level required for an adequate treatment in the safety assessment. The documentation is thus from a scientific point of not exhaustive since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. The purpose is further to determine the handling of each process in the safety assessment and to demonstrate how uncertainties are taken care of, given the suggested handling. The process documentation in the SR 97 version of the Process report is a starting point for this SR-Can interim version. As further described in the Interim main report, the list of relevant processes has been reviewed and slightly extended by comparison to other databases. Furthermore, the backfill has been included as a system part of its own, rather than being described together with the buffer as in SR 97. Apart from giving an interim account of the documentation and handling of buffer processes in SR-Can, this report is meant to serve as a template for the forthcoming documentation of processes occurring in other parts of the repository system. A complete list of processes can be found in the Interim FEP report for the safety assessment SR-Can. All material presented in this document is preliminary in nature and will possibly be updated as the SR-Can project progresses.

Materials behavior in interim storage of spent fuel

International Nuclear Information System (INIS)

Johnson, A.B. Jr.; Bailey, W.J.; Gilbert, E.R.; Inman, S.C.

1982-01-01

Interim storage has emerged as the only current spent-fuel management method in the US and is essential in all countries with nuclear reactors. Materials behavior is a key aspect in licensing interim-storage facilities for several decades of spent-fuel storage. This paper reviews materials behavior in wet storage, which is licensed for light-water reactor (LWR) fuel, and dry storage, for which a licensing position for LWR fuel is developing

Interim Safety Basis for Fuel Supply Shutdown Facility

International Nuclear Information System (INIS)

BENECKE, M.W.

2000-01-01

This ISB, in conjunction with the IOSR, provides the required basis for interim operation or restrictions on interim operations and administrative controls for the facility until a SAR is prepared in accordance with the new requirements or the facility is shut down. It is concluded that the risks associated with tha current and anticipated mode of the facility, uranium disposition, clean up, and transition activities required for permanent closure, are within risk guidelines

78 FR 49782 - Interim Staff Guidance on Changes During Construction

Science.gov (United States)

2013-08-15

... Construction AGENCY: Nuclear Regulatory Commission. ACTION: Draft interim staff guidance; request for comment... During Construction.'' This ISG provides guidance to the NRC staff on the Preliminary Amendment Request...-ISG-025 ``Interim Staff Guidance on Changes during Construction under 10 CFR Part 52'' is available...

Spent fuel interim management: 1995 update

International Nuclear Information System (INIS)

Anderson, C.K.

1995-01-01

The problems of interim away-from-reactor spent fuel storage and storage in spent fuel pools at the reactor site are discussed. An overview of the state-of-the-art in the USA, Europe, and Japan is presented. The technical facilities for away-from-reactor storage are briefly described, including wet storage pools, interactive concrete systems, metallic containers, and passive concrete systems. Reprocessing technologies are mostly at the design stage only. It is predicted that during the 20 years to come, about 50 000 tonnes of spent fuel will be stored at reactor sites regardless of the advance of spent fuel reprocessing or interim storage projects. (J.B.). 4 tabs., 2 figs

A links manipulator simulation program interim report

International Nuclear Information System (INIS)

Noble, R.A.

1987-04-01

A computer program to simulate the performance of the Heysham II rail-following manipulator has been developed. The program is being used to develop and test the rail-following control algorithms which will be used to control movements of the manipulator when it is operating below the gas baffle dome. The simulation includes the dynamic responses of the manipulator joint drives, excluding friction, backlash and compliance. It also includes full details of the manipulator's geometry. A method is given whereby the actual manipulator dynamics can be written into the program once these have been established by measurement. The program is written in FORTRAN and runs on a Perkin-Elmer 3220 mini-computer. The simulation program responds to velocity demands on the individual joints. These will normally come from the control program, in which they will be manually controlled by a joystick. A sigma 5664 colour graphics generator is programmed to display the current position of the manipulator. (UK)

General certification procedure of enterprises and interim job enterprises

CERN Document Server

Int. At. Energy Agency, Wien

2002-01-01

This procedure defines the certification global process of enterprises employing workers of A or B category for nuclear facilities and interim job enterprises proposing workers of A or B category for nuclear facilities. This certification proves the enterprises ability to satisfy the specification ''E'' of the CEFRI and the interim job enterprises to satisfy the specification ''I'' of the CEFRI. (A.L.B.)

Sample Results from the Interim Salt Disposition Program Macrobatch 8 Tank 21H Qualification Samples

Energy Technology Data Exchange (ETDEWEB)

Peters, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Washington, A. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2015-01-01

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 8 for the Interim Salt Disposition Program (ISDP). An Actinide Removal Process (ARP) and several Extraction-Scrub- Strip (ESS) tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP and the Modular Caustic Side Solvent Extraction (CSSX) Unit (MCU). No issues with the projected Salt Batch 8 strategy are identified. A demonstration of the monosodium titanate (MST) (0.2 g/L) removal of strontium and actinides provided acceptable average decontamination factors for plutonium of 2.62 (4 hour) and 2.90 (8 hour); and average strontium decontamination factors of 21.7 (4 hour) and 21.3 (8 hour). These values are consistent with results from previous salt batch ARP tests. The two ESS tests also showed acceptable performance with extraction distribution ratios (D(Cs)) values of 52.5 and 50.4 for the Next Generation Solvent (NGS) blend (from MCU) and NGS (lab prepared), respectively. These values are consistent with results from previous salt batch ESS tests. Even though the performance is acceptable, SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed in order to improve our predictive capabilities for the ESS tests.

Sample results from the Interim Salt Disposition Program Macrobatch 8 Tank 21H qualification samples

Energy Technology Data Exchange (ETDEWEB)

Peters, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Washington, II, A. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2015-01-13

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 8 for the Interim Salt Disposition Program (ISDP). An Actinide Removal Process (ARP) and several Extraction-Scrub-Strip (ESS) tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP and the Modular Caustic Side Solvent Extraction (CSSX) Unit (MCU). No issues with the projected Salt Batch 8 strategy are identified. A demonstration of the monosodium titanate (MST) (0.2 g/L) removal of strontium and actinides provided acceptable average decontamination factors for plutonium of 2.62 (4 hour) and 2.90 (8 hour); and average strontium decontamination factors of 21.7 (4 hour) and 21.3 (8 hour). These values are consistent with results from previous salt batch ARP tests. The two ESS tests also showed acceptable performance with extraction distribution ratios (D_(Cs)) values of 52.5 and 50.4 for the Next Generation Solvent (NGS) blend (from MCU) and NGS (lab prepared), respectively. These values are consistent with results from previous salt batch ESS tests. Even though the performance is acceptable, SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed in order to improve our predictive capabilities for the ESS tests.

Interim salt disposition program macrobatch 6 tank 21H qualification monosodium titanate and cesium mass transfer tests

Energy Technology Data Exchange (ETDEWEB)

Washington, A. L. II; Peters, T. B.; Fink, S. D.

2013-02-25

Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 6 processing. This qualification material was a set of six samples from Tank 21H in October 2012. This sample was used as a real waste demonstration of the Actinide Removal Process (ARP) and the Extraction-Scrub-Strip (ESS) tests process. The Tank 21H sample was contacted with a reduced amount (0.2 g/L) of MST and characterized for strontium and actinide removal at 0 and 8 hour time intervals in this salt batch. {sup 237}Np and {sup 243}Am were both observed to be below detection limits in the source material, and so these results are not reported in this report. The plutonium and uranium samples had decontamination factor (DF) values that were on par or slightly better than we expected from Batch 5. The strontium DF values are slightly lower than expected but still in an acceptable range. The Extraction, Scrub, and Strip (ESS) testing demonstrated cesium removal, stripping and scrubbing within the acceptable range. Overall, the testing indicated that cesium removal is comparable to prior batches at MCU.

ITER interim design report package and relevant documents

International Nuclear Information System (INIS)

1996-01-01

This publication documents the technical basis which underlay the Interim Design Report, Cost Review and Safety Analysis submitted to the ITER Councils (IC-8 and IC-9) Records of decisions and the ''ITER Interim Design Report Package''. This publication contains ITER Site Requirements and ITER Site Design Assumptions, TAC-8 Report, SRG Report, CP's Report on Tentative Sequence of Events and Parties' Views on the IDR Package and Parties' Technical Comments on the IDR Package. Figs, tabs

Presidential Transition: The Experience of Two Community College Interim Presidents

Science.gov (United States)

Thompson, Matthew D.

2010-01-01

The purpose of this qualitative case study was to understand the experiences of two community college interim presidents, their characteristics, and how they led institutions following an abrupt presidential departure. There were two fundamental questions framing this research study, 1. How do two interim community college presidents lead…

30 CFR 827.13 - Coal preparation plants: Interim performance standards.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Coal preparation plants: Interim performance...-COAL PREPARATION PLANTS NOT LOCATED WITHIN THE PERMIT AREA OF A MINE § 827.13 Coal preparation plants: Interim performance standards. (a) Persons operating or who have operated coal preparation plants after...

Fast Flux Test Facility interim examination and maintenance cell: Past, present, and future

International Nuclear Information System (INIS)

Vincent, J.R.

1990-09-01

The Fast Flux Test Facility Interim Examination and Maintenance Cell was designed to perform interim examination and/or disassembly of experimental core components for final analysis elsewhere, as well as maintenance of sodium-wetted or neutron-activated internal reactor parts and plant support hardware. The Interim Examination and Maintenance Cell equipment developed and used for the first ten years of operation has been primarily devoted to the disassembly and examination of core component test assemblies. While no major reactor equipment has required remote repair or maintenance, the Interim Examina Examination and Maintenance Cell has served as the remote repair facility for its own in-cell equipment, and several innovative remote repairs have been accomplished. The Interim Examination and Maintenance Cell's demonstrated versatility has shown its capability to support a challenging future. 12 refs., 9 figs

New York State interim waste management cost evaluation

International Nuclear Information System (INIS)

Ma, M.S.; Watts, R.J.; Jorgensen, J.R.; Rochester Gas and Electric Corp., NY)

1985-01-01

The purpose of this study is to investigate and quantify the comparative costs associated with including or excluding Class A utility wastes at a centralized interim waste management facility in New York State. The objective of the study is to assess the unit costs and total statewide costs associated with two distinct scenarios: (1) the case where non-utility Class A LLRW is received, incinerated and stored at the centralized interim facility, and utility Class A wastes are held without incineration at respective nuclear power plant interim onsite facilities without incineration; and (2) the alternative case where both utility and non-utility Class A wastes are accepted, incinerated and stored at the centralized facility. Unit costs to waste generators are estimated for each of the two cases described. This is followed by an estimation of the statewide cost impact to the public. The cost impact represents the cost differential resulting from the exclusion of utility Class A waste from the centralized NYS interim waste management facility. The principal factors comprising the cost differential include (1) higher unit disposal fees charged to non-utility waste generators, which are passed along in the costs of products and services; and (2) costs to utilities due to construction of additional onsite storage capacity, which in turn are charged to electric rate payers

Interim long-term surveillance plan for the Cheney disposal site near, Grand Junction, Colorado

International Nuclear Information System (INIS)

1997-08-01

This interim long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Cheney Disposal Site in Mesa County near Grand Junction, Colorado. This LSTP describes the long-term surveillance program the DOE will implement to ensure the Cheney disposal site performs as designed and is cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed for custody and long-term care, the Nuclear Regulatory Commission (NRC) requires the DOE to submit such a site-specific LTSP

216-T-4 interim stabilization final report

International Nuclear Information System (INIS)

Smith, D.L.

1996-01-01

This report provides a general description of the activities performed for the interim stabilization of the 216-T-4-1 ditch, 216-T-4-2 ditch, and 216-T-4-2 pond. Interim stabilization was required to reduce the amount of surface-contaminated acres and to minimize the migration of radioactive contamination. Work associated with the 216-T4-1 ditch and 216-T-4-2 pond was performed by the Radiation Area Remedial Action (RARA) Project. Work associated with the 216-T-4-2 ditch was done concurrently but was funded by Westinghouse Hanford Company (WHC) Tank Waste Remediation Systems (TWRS)

Lessons for outsourcing and interim management relationships.

Science.gov (United States)

Macko, W; Kostyack, P T

1999-01-01

Few decisions can affect an organization more than the selection of an outsourcing or interim management partner. More and more health care organizations face such decisions in today's competitive market in order to face new business needs. Making these relationships successful can be important for health care organizations seeking competitive advantages or seeking immediately accessible management support. These relationships, however, require careful partner selection and development. Success in outsourcing and interim management relationships is contingent upon a thorough selection process, a strong contract that has clearly and explicitly detailed responsibilities and a culture-sensitive business rapport between the client and selected partner.

PROJECT W-551 INTERIM PRETREATMENT SYSTEM PRECONCEPTUAL CANDIDATE TECHNOLOGY DESCRIPTIONS

Energy Technology Data Exchange (ETDEWEB)

MAY TH

2008-08-12

The Office of River Protection (ORP) has authorized a study to recommend and select options for interim pretreatment of tank waste and support Waste Treatment Plant (WTP) low activity waste (LAW) operations prior to startup of all the WTP facilities. The Interim Pretreatment System (IPS) is to be a moderately sized system which separates entrained solids and 137Cs from tank waste for an interim time period while WTP high level waste vitrification and pretreatment facilities are completed. This study's objective is to prepare pre-conceptual technology descriptions that expand the technical detail for selected solid and cesium separation technologies. This revision includes information on additional feed tanks.

Do Interim Assessments Reduce the Race and SES Achievement Gaps?

Science.gov (United States)

Konstantopoulos, Spyros; Li, Wei; Miller, Shazia R.; van der Ploeg, Arie

2017-01-01

The authors examined differential effects of interim assessments on minority and low socioeconomic status students' achievement in Grades K-6. They conducted a large-scale cluster randomized experiment in 2009-2010 to evaluate the impact of Indiana's policy initiative introducing interim assessments statewide. The authors used 2-level models to…

Proposed plan for interim remedial measures at the 100-HR-1 Operable Unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1995-01-01

This proposed plan identifies the preferred alternative for interim remedial measures for remedial action of radioactive liquid waste disposal sites at the 100-HR-1 Operable Unit, located at the Hanford Site. It also summarizes other remedial alternatives evaluated for interim remedial measures in this operable unit. The intent of interim remedial measures is to speed up actions to address contaminated areas that historically received radioactive liquid waste discharges that pose a potential threat to human health and the environment. This proposed plan is being issued by the Washington State Department of Ecology (Ecology), the lead regulatory agency; the US Environmental Protection Agency (EPA), the support regulatory agency; and the US Department of Energy (DOE), the responsible agency. Ecology, EPA, and DOE are issuing this proposed plan as part of their public participation responsibilities under Section 117(a) of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), commonly known as the ''Superfund Program.'' The proposed plan is intended to be a fact sheet for public review that (1) briefly describes the remedial alternatives analyzed; (2) proposes a preferred alternative; (3) summarizes the information relied upon to recommend the preferred alternative; and (4) provides a basis for an interim action record of decision (ROD). The preferred alternative presented in this proposed plan is removal, treatment (as appropriate), and disposal of contaminated soil and associated structures. Treatment will be conducted if there is cost benefit

Interim Report by Asia International Grid Connection Study Group

Science.gov (United States)

Omatsu, Ryo

2018-01-01

The Asia International Grid Connection Study Group Interim Report examines the feasibility of developing an international grid connection in Japan. The Group has investigated different cases of grid connections in Europe and conducted research on electricity markets in Northeast Asia, and identifies the barriers and challenges for developing an international grid network including Japan. This presentation introduces basic contents of the interim report by the Study Group.

Implementation plan for deployment of Federal Interim Storage facilities for commercial spent nuclear fuel

International Nuclear Information System (INIS)

1985-01-01

This document is the second annual report on plans for providing Federal Interim Storage (FIS) capacity. References are made to the first annual report as necessary (DOE/RW-0003, 1984). Background factors and aspects that were considered in the development of this deployment plan and activities and interactions considered to be required to implement an FIS program are discussed. The generic approach that the Department plans to follow in deploying FIS facilities is also described

The Interim Financial Reporting in the Spirit of the IAS 34 Norm

OpenAIRE

Ovidia Doinea

2008-01-01

The role of an interim financial reporting is to allow the information users to acknowledge the activity of an entity on period shorter than financial exercise from the perspective of the available profits and cash flows generated as well as from the point of view of its financial position and liquidity. The interim financial reporting includes a complete or condensed set of financial statements which target to update the last financial reporting, usually the annual report. The interim financ...

Comparisons of Cooperative and Non-Cooperative Students: An Analysis of Student Accounting System Data. Interim Report, June, 1981.

Science.gov (United States)

Frazier, Don

The major purpose of this study was to identify unique effects of cooperative vocational education. This interim report is of results of the analyses of existing data bases. Comparisons of cooperative and non-cooperative vocational programs are made on the following variables: enrollments by age, sex and race, school status, work status,…

Wayne Interim Storage Site: Annual environmental report for calendar year 1990, Wayne, New Jersey

International Nuclear Information System (INIS)

1991-09-01

Environmental monitoring of the US Department of Energy's (DOE) Wayne Interim Storage Site (WISS) (a National Priorities List site) and surrounding area began in 1984. WISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental monitoring program at WISS includes sampling networks for radon and thoron concentrations in air; external gamma radiation exposure; and radium-226, thorium-232, and total uranium concentrations in surface water, sediment, and groundwater. Sediment samples were also analyzed for thorium-230, and several nonradiological parameters were measured in groundwater. 16 refs., 12 figs., 23 tabs

RCRA corrective action program guide (Interim)

Energy Technology Data Exchange (ETDEWEB)

1993-05-01

The US Department of Energy (DOE) is responsible for compliance with an increasingly complex spectrum of environmental regulations. One of the most complex programs is the corrective action program proposed by the US Environmental Protection Agency (EPA) under the authority of the Resource Conservation and Recovery Act (RCRA) as amended by the Hazardous and Solid Waste Amendments (HSWA). The proposed regulations were published on July 27, 1990. The proposed Subpart S rule creates a comprehensive program for investigating and remediating releases of hazardous wastes and hazardous waste constituents from solid waste management units (SWMUs) at facilities permitted to treat, store, or dispose of hazardous wastes. This proposed rule directly impacts many DOE facilities which conduct such activities. This guidance document explains the entire RCRA Corrective Action process as outlined by the proposed Subpart S rule, and provides guidance intended to assist those persons responsible for implementing RCRA Corrective Action at DOE facilities.

Transuranic waste storage and assay facility (TRUSAF) interim safety basis

International Nuclear Information System (INIS)

Gibson, K.D.

1995-09-01

The TRUSAF ISB is based upon current facility configuration and procedures. The purpose of the document is to provide the basis for interim operation or restrictions on interim operations and the authorization basis for the TRUSAF at the Hanford Site. The previous safety analysis document TRUSAF hazards Identification and Evaluation (WHC 1977) is superseded by this document

Interim Particulate Matter Test Method for the Determination of Particulate Matter from Gas Turbine Engines, SERDP Project WP-1538 Final Report

Science.gov (United States)

Under Project No. WP-1538 of the Strategic Environmental Research and Development Program, the U. S. Air Force's Arnold Engineering Development Center (AEDC) is developing an interim test method for non-volatile particulate matter (PM) specifically for the Joint Strike Fighter (J...

K basins interim remedial action health and safety plan

Energy Technology Data Exchange (ETDEWEB)

DAY, P.T.

1999-09-14

The K Basins Interim Remedial Action Health and Safety Plan addresses the requirements of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), as they apply to the CERCLA work that will take place at the K East and K West Basins. The provisions of this plan become effective on the date the US Environmental Protection Agency issues the Record of Decision for the K Basins Interim Remedial Action, currently planned in late August 1999.

Interim safety basis for fuel supply shutdown facility

International Nuclear Information System (INIS)

Brehm, J.R.; Deobald, T.L.; Benecke, M.W.; Remaize, J.A.

1995-01-01

This ISB in conjunction with the new TSRs, will provide the required basis for interim operation or restrictions on interim operations and administrative controls for the Facility until a SAR is prepared in accordance with the new requirements. It is concluded that the risk associated with the current operational mode of the Facility, uranium closure, clean up, and transition activities required for permanent closure, are within Risk Acceptance Guidelines. The Facility is classified as a Moderate Hazard Facility because of the potential for an unmitigated fire associated with the uranium storage buildings

Fusion tritium program in Japan

International Nuclear Information System (INIS)

Okamoto, M.; Yoshida, H.; Naruse, Y.

1988-01-01

Nuclear Fusion Council, Atomic Energy Commission of Japan, has started to review the nuclear fusion R and D plan for the next stage, post JT-60. The council launched a subcommittee on fundamental issues in the nuclear fusion development in 1985, for review of the basic strategy of a development plan. The subcommittee presented an interim report in Feb. 1986 after 6 months discussion and the report was approved by the Nuclear Fusion Council. Two major R and D programs described in the interim report are the development of a Tokamak type large facility and the comprehensive development of the fusion reactor technology. The latter means to promote the reactor technologies which will be essential in the future to construct not only a D/T burning but also a DEMO reactor. The Nuclear Fusion Development Program in Japan is shown. The interim report recommended to organize two subcommittees to establish an integrated national R and D plan; one was for the design of the next step large facility and the other was for the R and program of the fusion technology. The subcommittee for the latter consisted of 7 working groups; one of them was organized for the tritium technology

Implementation plan for deployment of Federal Interim Storage facilities for commercial spent nuclear fuel

International Nuclear Information System (INIS)

1986-12-01

This document is the third annual report on plans for providing Federal Interim Storage (FIS) capacity. References are made to the first and second annual reports, as necessary. Background factors and aspects that were considered in the development of this deployment plan and activities and interactions considered to be required to implement an FIS program are discussed. A generic description of the approach that the Department plans to follow in deploying FIS facilities is also described

Program Management Challenges in a Joint Service Environment

National Research Council Canada - National Science Library

Taneyhill, Dorothy E

2007-01-01

... or modifications of the same design. The Interim Defense Acquisition Guidebook defines a Joint Program Management Office as any defense acquisition system, subsystem, component, or technology program that involves formal management...

Interim report - geotechnical site assessment methodology. Vol.1

International Nuclear Information System (INIS)

Tunbridge, L.W.; Richards, L.R.

1983-05-01

An interim report summarizing the research conducted on geotechnical site assessment methodology at the Carwynnen test mine in Cornwall. The geological setting of the test site in the Cornubian granite batholith is described. The effect of structure imposed by discontinuities on the engineering behaviour of rock masses is discussed and the scanline survey method of obtaining data on discontinuities in the rock mass is described. The requirement for remote geophysical methods of characterizing the mass is discussed and initial experiments using seismic and ultrasonic velocity measurements are reported. Computer programs to perform statistical analysis of the discontinuity patterns are described. Overcoring and hydraulic fracturing methods of determining the in-situ stress are briefly described and the results of a programme of in-situ stress measurements using the overcoring method are reported. (author)

Hazelwood Interim Storage Site environmental surveillance report for calendar year 1993

International Nuclear Information System (INIS)

1994-06-01

This report summarizes the results of environmental surveillance activities conducted at the Hazelwood Interim Storage Site (HISS) during calendar year 1993. It includes an overview of site operations, the basis for monitoring for radioactive and non-radioactive parameters, summaries of environmental program at HISS, a summary of the results, and the calculated hypothetical radiation dose to the offsite population. Environmental surveillance activities were conducted in accordance with the site environmental monitoring plan, which describes the rationale and design criteria for the surveillance program, the frequency of sampling and analysis, specific sampling and analysis procedures, and quality assurance requirements. The US Department of Energy (DOE) began environmental monitoring of HISS in 1984, when the site was assigned to DOE by Congress through the energy and Water Development Appropriations Act and subsequent to DOE's Formerly Utilized Sites Remediation Action Program (FUSRAP). Contamination at HISS originated from uranium processing work conducted at Mallinckrodt Chemical Works at the St. Louis Downtown Site (SLDS) from 1942 through 1957

In vitro evaluation of the marginal integrity of CAD/CAM interim crowns.

Science.gov (United States)

Kelvin Khng, Kwang Yong; Ettinger, Ronald L; Armstrong, Steven R; Lindquist, Terry; Gratton, David G; Qian, Fang

2016-05-01

The accuracy of interim crowns made with computer-aided design and computer-aided manufacturing (CAD/CAM) systems has not been well investigated. The purpose of this in vitro study was to evaluate the marginal integrity of interim crowns made by CAD/CAM compared with that of conventional polymethylmethacrylate (PMMA) crowns. A dentoform mandibular left second premolar was prepared for a ceramic crown and scanned for the fabrication of 60 stereolithical resin dies, half of which were scanned to fabricate 15 Telio CAD-CEREC and 15 Paradigm MZ100-E4D-E4D crowns. Fifteen Caulk and 15 Jet interim crowns were made on the remaining resin dies. All crowns were cemented with Tempgrip under a 17.8-N load, thermocycled for 1000 cycles, placed in 0.5% acid fuschin for 24 hours, and embedded in epoxy resin before sectioning from the mid-buccal to mid-lingual surface. The marginal discrepancy was measured using a traveling microscope, and dye penetration was measured as a percentage of the overall length under the crown. The mean vertical marginal discrepancy of the conventionally made interim crowns was greater than for the CAD/CAM crowns (P=.006), while no difference was found for the horizontal component (P=.276). The mean vertical marginal discrepancy at the facial surface of the Caulk crowns was significantly greater than that of the other 3 types of interim crowns (Pmargin, the mean horizontal component of the Telio crowns was significantly larger than that of the other 3 types, with no difference at the lingual margins (P=.150). The mean percentage dye penetration for the Paradigm MZ100-E4D crowns was significantly greater and for Jet crowns significantly smaller than for the other 3 crowns (Pmarginal discrepancies of the Jet interim crowns at the facial surface and with the horizontal marginal discrepancies of the Caulk interim crowns at the lingual surface (Pmarginal discrepancy was found with the interim crowns fabricated by CAD/CAM as compared with PMMA crowns

Project management plan for Reactor 105-C Interim Safe Storage project

International Nuclear Information System (INIS)

Plagge, H.A.

1996-09-01

Reactor 105-C (located on the Hanford Site in Richland, Washington) will be placed into an interim safe storage condition such that (1) interim inspection can be limited to a 5-year frequency; (2) containment ensures that releases to the environmental are not credible under design basis conditions; and (3) final safe storage configuration shall not preclude or significantly increase the cost for any decommissioning alternatives for the reactor assembly.This project management plan establishes plans, organizational responsibilities, control systems, and procedures for managing the execution of Reactor 105-C interim safe storage activities to meet programmatic requirements within authorized funding and approved schedules

Interim FDG-PET Scan in Hodgkin's Lymphoma: Hopes and Caveats

Directory of Open Access Journals (Sweden)

M. André

2011-01-01

Full Text Available FDG-PET has recently emerged as an important tool for the management of Hodgkins lymphoma. Although its use for initial staging and response evaluation at the end of treatment is well established, the place of interim PET for response assessment and subsequent treatment tailoring is still quite controversial. The use of interim PET after a few cycles of chemotherapy may allow treatment reduction for good responders, leading to lesser treatment toxicities as well as early treatment adaptation for bad responders with a potential higher chance for cure. Interpretation of interim PET is a rapidly moving field. Actually, visual interpretation is preferred over quantitative interpretation in this situation. The notion of minimal residual uptake emerged for faint persisting FDG uptake, but has evolved during the recent years. Guidelines using mediastinum and liver as references have been proposed at the expert meeting in Deauville 2009. Actually, several trials are ongoing both for localised and advanced disease to evaluate the FDG-PET potential for early treatment monitoring and tailoring. Until the results of these prospective randomized trials become available, treatment changes according to the interim PET results should remain inappropriate and limited to well-conducted clinical trials.

42 CFR 93.401 - Interaction with other offices and interim actions.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Interaction with other offices and interim actions. 93.401 Section 93.401 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT OF HEALTH AND HUMAN SERVICES... Human Services General Information § 93.401 Interaction with other offices and interim actions. (a) ORI...

42 CFR 417.572 - Budget and enrollment forecast and interim reports.

Science.gov (United States)

2010-10-01

... 42 Public Health 3 2010-10-01 2010-10-01 false Budget and enrollment forecast and interim reports... PLANS, AND HEALTH CARE PREPAYMENT PLANS Medicare Payment: Cost Basis § 417.572 Budget and enrollment forecast and interim reports. (a) Annual submittal. The HMO or CMP must submit an annual operating budget...

Early interim 18F-FDG PET in Hodgkin's lymphoma: evaluation on 304 patients

International Nuclear Information System (INIS)

Zinzani, Pier Luigi; Stefoni, Vittorio; Broccoli, Alessandro; Argnani, Lisa; Baccarani, Michele; Rigacci, Luigi; Puccini, Benedetta; Castagnoli, Antonio; Vaggelli, Luca; Zanoni, Lucia; Fanti, Stefano

2012-01-01

The use of early (interim) PET restaging during first-line therapy of Hodgkin's lymphoma (HL) in clinical practice has considerably increased because of its ability to provide early recognition of treatment failure allowing patients to be transferred to more intensive treatment regimens. Between June 1997 and June 2009, 304 patients with newly diagnosed HL (147 early stage and 157 advanced stage) were treated with the ABVD regimen at two Italian institutions. Patients underwent PET staging and restaging at baseline, after two cycles of therapy and at the end of the treatment. Of the 304 patients, 53 showed a positive interim PET scan and of these only 13 (24.5%) achieved continuous complete remission (CCR), whereas 251 patients showed a negative PET scan and of these 231 (92%) achieved CCR. Comparison between interim PET-positive and interim PET-negative patients indicated a significant association between PET findings and 9-year progression-free survival and 9-year overall survival, with a median follow-up of 31 months. Among the early-stage patients, 19 had a positive interim PET scan and only 4 (21%) achieved CCR; among the 128 patients with a negative interim PET scan, 122 (97.6%) achieved CCR. Among the advanced-stage patients, 34 showed a persistently positive PET scan with only 9 (26.4%) achieving CCR, whereas 123 showed a negative interim PET scan with 109 (88.6%) achieving CCR. Our results demonstrate the role of an early PET scan as a significant step forward in the management of patients with early-stage or advanced-stage HL. (orig.)

10 CFR 431.401 - Petitions for waiver, and applications for interim waiver, of test procedure.

Science.gov (United States)

2010-01-01

... Renewable Energy, U.S. Department of Energy. Each Application for Interim Waiver must reference the Petition... Renewable Energy. (e) Provisions specific to interim waivers—(1) Disposition of application. If... 10 Energy 3 2010-01-01 2010-01-01 false Petitions for waiver, and applications for interim waiver...

Wayne Interim Storage Site environmental report for calendar year 1992, 868 Black Oak Ridge Road, Wayne, New Jersey. Formerly Utilized Sites Remedial Action Program (FUSRAP)

Energy Technology Data Exchange (ETDEWEB)

1993-05-01

This report describes the environmental surveillance program at the Wayne Interim Storage Site (WISS) and provides the results for 1992. The fenced, site, 32 km (20 mi) northwest of Newark, New Jersey, was used between 1948 and 1971 for commercial processing of monazite sand to separate natural radioisotopes - predominantly thorium. Environmental surveillance of WISS began in 1984 in accordance with Department of Energy (DOE) Order 5400.1 when Congress added the site to DOE`s Formerly Utilized Sites Remedial Action Program (FUSRAP). The environmental surveillance program at WISS includes sampling networks for radon and thoron in air; external gamma radiation exposure; radium-226, radium-228, thorium-230, thorium-232, total uranium, and several chemicals in surface water and sediment; and total uranium, radium-226, radium-228, thorium-230, thorium-232, and organic and inorganic chemicals in groundwater. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and state standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. This monitoring program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Results for environmental surveillance in 1992 show that the concentrations of all radioactive and most chemical contaminants were below applicable standards.

Fit of interim crowns fabricated using photopolymer-jetting 3D printing.

Science.gov (United States)

Mai, Hang-Nga; Lee, Kyu-Bok; Lee, Du-Hyeong

2017-08-01

The fit of interim crowns fabricated using 3-dimensional (3D) printing is unknown. The purpose of this in vitro study was to evaluate the fit of interim crowns fabricated using photopolymer-jetting 3D printing and to compare it with that of milling and compression molding methods. Twelve study models were fabricated by making an impression of a metal master model of the mandibular first molar. On each study model, interim crowns (N=36) were fabricated using compression molding (molding group, n=12), milling (milling group, n=12), and 3D polymer-jetting methods. The crowns were prepared as follows: molding group, overimpression technique; milling group, a 5-axis dental milling machine; and polymer-jetting group using a 3D printer. The fit of interim crowns was evaluated in the proximal, marginal, internal axial, and internal occlusal regions by using the image-superimposition and silicone-replica techniques. The Mann-Whitney U test and Kruskal-Wallis tests were used to compare the results among groups (α=.05). Compared with the molding group, the milling and polymer-jetting groups showed more accurate results in the proximal and marginal regions (P3D printing significantly enhanced the fit of interim crowns, particularly in the occlusal region. Copyright © 2016 Editorial Council for the Journal of Prosthetic Dentistry. Published by Elsevier Inc. All rights reserved.

Colonie Interim Storage Site: Annual environmental report for calendar year 1990, Colonie, New York

International Nuclear Information System (INIS)

1991-09-01

Environmental monitoring of the US Department of Energy's (DOE) Colonie Interim Storage Site (CISS) and surrounding area began in 1984. CISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sties where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The routine environmental monitoring program at CISS includes sampling networks for external gamma radiation exposures and for radium-226, throium-232, an total uranium concentrations in surface water, sediment, and groundwater. Additionally, the nonradiological parameters volatile and semivolatile organics, pesticides/polychlorinated biphenyls (PCBs), metals, total organic carbon (TOC), total organic halides (TOX), specific conductivity, and pH are measured in groundwater. 14 refs., 20 figs., 25 tabs

Overview of the US spent nuclear fuel program

International Nuclear Information System (INIS)

Hurt, W.L.

1999-01-01

This report, Overview of the United States Spent Nuclear Fuel Program, December, 1997, summarizes the U.S. strategy for interim management and ultimate disposition of spent nuclear fuel from research and test reactors. The key elements of this strategy include consolidation of this spent nuclear fuel at three sites, preparation of the fuel for geologic disposal in road-ready packages, and low-cost dry interim storage until the planned geologic repository is opened. The U.S. has a number of research programs in place that are intended to Provide data and technologies to support both characterization and disposition of the fuel. (author)

A Non-Traditional Interim Project.

Science.gov (United States)

Brown, Diane; Ward, Dorothy

1980-01-01

Describes a project initiated by the Foreign Language Department of Birmingham-Southern College for their Interim term and discusses an interdisciplinary course focusing on Medieval Europe. The course included presentations on German and French language and literature, as well as lectures on the arts, philosophy, and family life of the period.…

Maywood Interim Storage Site environmental report for calendar year 1992, 100 West Hunter Avenue, Maywood, New Jersey. Formerly Utilized Sites Remedial Action Program (FUSRAP)

Energy Technology Data Exchange (ETDEWEB)

1993-05-01

This report describes the environmental surveillance program at the Maywood Interim Storage Site (MISS) and provides the results for 1992. Environmental monitoring of MISS began in 1984, when the site was assigned to DOE by Congress through the Energy and Water Development Appropriations Act and was placed under DOE`s Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP was established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation`s atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. MISS is part of a National Priorities List (NPL) site. The environmental surveillance program at MISS includes sampling networks for radon and thoron in air; external gamma radiation exposure; and radium-226, radium-228, thorium-232, and total uranium in surface water, sediment, and groundwater. Additionally, chemical analysis includes metals and organic compounds in surface water and groundwater and metals in sediments. This program assists in fulfilling the DOE objective of measuring and monitoring effluents from DOE activities and calculating hypothetical doses to members of the general public. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and state standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. Environmental standards are established to protect public health and the environment. The radiological data for all media sampled support the conclusion that doses to the public are not distinguishable from natural background radiation.

Maywood Interim Storage Site: Annual site environmental report, Maywood, New Jersey, Calendar year 1986: Formerly Utilized Sites Remedial Action Program

Energy Technology Data Exchange (ETDEWEB)

None

1987-06-01

During 1986, the environmental monitoring program was continued at the Maywood Interim Storage Site (MISS), a US Department of Energy (DOE) facility located in the Borough of Maywood and the Township of Rochelle Park, New Jersey. The MISS is presently used for the storage of low-level radioactively contaminated soils. The MISS is part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). As part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Appropriations Act, remedial action and environmental monitoring programs are being conducted at this site and at vicinity properties by Bechtel National, Inc., Project Management Contractor for FUSRAP. The monitoring program at the MISS measures thoron and radon gas concentrations in air; external gamma radiation levels; and thorium, uranium, and radium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard (100 mrem/y) and to assess the potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the conservative scenario described in the report, the maximally exposed individual would receive an annual external exposure approximately equivalent to 1% of the DOE radiation protection standard of 100 mrem/y. This exposure is less than the exposure a person would receive during a round-trip flight from New York to Los Angeles (due to greater amounts of cosmic radiation at higher altitudes). The cumulative dose to the population within an 80-km (50-mi) radius of the MISS that would result from radioactive materials present at the site would be indistinguishable from the dose the same population would receive from naturally occurring radioactive sources. Results of the 1986 monitoring show that the MISS is in compliance with the DOE radiation protection standard. 16 refs., 8 figs., 15 tabs.

Interim and final storage casks

International Nuclear Information System (INIS)

Stumpfrock, L.; Kockelmann, H.

2012-01-01

The disposal of radioactive waste is a huge social challenge in Germany and all over the world. As is well known the search for a site for a final repository for high-level waste in Germany is not complete. Therefore, interim storage facilities for radioactive waste were built at plant sites in Germany. The waste is stored in these storage facilities in appropriate storage and transport casks until the transport in a final repository can be carried out. Licensing of the storage and transport casks aimed for use in the public space is done according to the traffic laws and for handling in the storage facility according to nuclear law. Taking into account the activity of the waste to be stored, different containers are in use, so that experience is available from the licensing and operation in interim storage facilities. The large volume of radioactive waste to be disposed of after the shut-down of power generation in nuclear power stations makes it necessary for large quantities of licensed storage and transport casks to be provided soon.

Interim storage report

International Nuclear Information System (INIS)

Rawlins, J.K.

1998-02-01

High-level radioactive waste (HLW) stored at the Idaho Chemical Processing Plant (ICPP) in the form of calcine and liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the waste to be transported to a permanent repository. Because a permanent repository will not be available when the waste is processed, the waste must be stored at ICPP in an Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options under consideration

75 FR 18095 - America's Marine Highway Program

Science.gov (United States)

2010-04-09

... Marine Highway Transportation. Authority: Energy Independence and Security Act of 2007, Sections 1121...] RIN 2133-AB70 America's Marine Highway Program AGENCY: Maritime Administration, Department of... interim final rule that established America's Marine Highway Program, under which the Secretary will...

ITER interim design report package documents

International Nuclear Information System (INIS)

1996-01-01

This publication contains the Excerpt from the ITER Council (IC-8), the ITER Interim Design Report, Cost Review and Safety Analysis, ITER Site Requirements and ITER Site Design Assumptions and the Excerpt from the ITER Council (IC-9). 8 figs, 2 tabs

Spent fuel interim storage

International Nuclear Information System (INIS)

Bilegan, Iosif C.

2003-01-01

The official inauguration of the spent fuel interim storage took place on Monday July 28, 2003 at Cernavoda NNP. The inaugural event was attended by local and central public authority representatives, a Canadian Government delegation as well as newsmen from local and central mass media and numerous specialists from Cernavoda NPP compound. Mr Andrei Grigorescu, State Secretary with the Economy and Commerce Ministry, underlined in his talk the importance of this objective for the continuous development of nuclear power in Romania as well as for Romania's complying with the EU practice in this field. Also the excellent collaboration between the Canadian contractor AECL and the Romanian partners Nuclear Montaj, CITON, UTI, General Concret in the accomplishment of this unit at the planned terms and costs. On behalf of Canadian delegation, spoke Minister Don Boudria. He underlined the importance which the Canadian Government affords to the cooperation with Romania aiming at specific objectives in the field of nuclear power such as the Cernavoda NPP Unit 2 and spent fuel interim storage. After traditional cutting of the inaugural ribbon by the two Ministers the festivities continued on the Cernavoda NPP Compound with undersigning the documents regarding the project completion and a press conference

Effectiveness of interim stage filter in the exhaust system of glove boxes

International Nuclear Information System (INIS)

Patre, D.K.; Vangara, H.; Thanamani, S.; Gopalakrishnan, R.K.; Mhatre, Amol M.

2018-01-01

All operations in radiochemical laboratories are carried out in containment systems like Glove boxes and Fume hoods. For controlling air contamination two separate air cleaning systems are incorporated. Laboratory has general ventilation system and glove boxes are provided with a negative pressure system (NPS). Glove box exhaust air is passed through three stage filtration systems: in situ, interim and final before discharging to the atmosphere. In addition to the individual HEPA filters of each glove box, there is an interim HEPA filter bank introduced at the laboratory end. This was introduced to reduce a load on main exhaust filter system. Finally the exhaust air is discharged through the final stage HEPA filter located in the filter house through the Stack. The interim HEPA filter bank provides additional protection for the release of particulate activity and reduces load on the final stage filters. In the present work efforts have been put to validate the interim stage filter, which has been introduced, to limit the environmental release

Development of a Computer Program for the Analysis Logistics of PWR Spent Fuels

International Nuclear Information System (INIS)

Choi, Heui Joo; Choi, Jong Won; Cha, Jeong Hun

2008-01-01

It is expected that the temporary storage facilities at the nuclear power plants will be full of the spent fuels within 10 years. Provided that a centralized interim storage facility is constructed along the coast of the Korean peninsula to solve this problem, a substantial amount of spent fuels should be transported by sea or by land every year. In this paper we developed a computer program for the analysis of transportation logistics of the spent fuels from 4 different nuclear power plant sites to the hypothetical centralized interim storage facility and the final repository. Mass balance equations were used to analyze the logistics between the nuclear power plants and the interim storage facility. To this end a computer program, CASK, was developed by using the VISUAL BASIC language. The annual transportation rates of spent fuels from the four nuclear power plant sites were determined by using the CASK program. The parameter study with the program illustrated the easiness of logistics analysis. The program could be used for the cost analysis of the spent fuel transportation as well.

Solar Simulation Laboratory Description and Manual.

Science.gov (United States)

1985-06-01

2000 was sent back to Cyborg Corp. three times over a five month period for repairs. The solar lab is presently using a loaner from Cyborg Corp. The IBM...PC/XT is connected to the ISAAC 2000 by a RS232 connection. All programs were written in advanced basic ("BASICA"). BASICA was used because Cyborg ...2067 CH/P Temperature.Control Bath TechnicalManual, November. 1980. A 30. Cyborg Corporation, Version 1.2, IS..AC.....Co..mpiut.er.liz e.d Data

LANDFILL BIOREACTOR PERFORMANCE, SECOND INTERIM REPORT

Science.gov (United States)

A bioreactor landfill is a landfill that is operated in a manner that is expected to increase the rate and extent of waste decomposition, gas generation, and settlement compared to a traditional landfill. This Second Interim Report was prepared to provide an interpretation of fie...

DOE UST interim subsurface barrier technologies workshop

International Nuclear Information System (INIS)

1992-09-01

This document contains information which was presented at a workshop regarding interim subsurface barrier technologies that could be used for underground storage tanks, particularly the tank 241-C-106 at the Hanford Reservation

A conservative method of retaining an interim obturator for a total maxillectomy patient

Directory of Open Access Journals (Sweden)

Nirmal Famila Bettie

2017-01-01

Full Text Available Interim obturators are indicated during the postsurgical phases. It promotes surgical healing and serves as a temporary prosthesis to rehabilitate a patient with intra-oral surgical defect. Retention is gained by wiring, surgical suturing, and other noninvasive methods to enable functional rehabilitation and easy replacement with a permanent obturator. Interim obturators serve as an easy guide for replacing with definitive obturators by indicating prosthesis extensions and the required method of retention. A more conservative and noninvasive method of retaining an interim obturator for a maxillectomy patient is described in this case report.

A Conservative Method of Retaining an Interim Obturator for a Total Maxillectomy Patient.

Science.gov (United States)

Bettie, Nirmal Famila

2017-11-01

Interim obturators are indicated during the postsurgical phases. It promotes surgical healing and serves as a temporary prosthesis to rehabilitate a patient with intra-oral surgical defect. Retention is gained by wiring, surgical suturing, and other noninvasive methods to enable functional rehabilitation and easy replacement with a permanent obturator. Interim obturators serve as an easy guide for replacing with definitive obturators by indicating prosthesis extensions and the required method of retention. A more conservative and noninvasive method of retaining an interim obturator for a maxillectomy patient is described in this case report.

International validation study for interim PET in ABVD-treated, advanced-stage hodgkin lymphoma

DEFF Research Database (Denmark)

Biggi, Alberto; Gallamini, Andrea; Chauvie, Stephane

2013-01-01

At present, there are no standard criteria that have been validated for interim PET reporting in lymphoma. In 2009, an international workshop attended by hematologists and nuclear medicine experts in Deauville, France, proposed to develop simple and reproducible rules for interim PET reporting...... in lymphoma. Accordingly, an international validation study was undertaken with the primary aim of validating the prognostic role of interim PET using the Deauville 5-point score to evaluate images and with the secondary aim of measuring concordance rates among reviewers using the same 5-point score...

Uranium exploration of the Colorado Plateau: interim staff report

International Nuclear Information System (INIS)

1980-10-01

This report is an issue of the original draft copy of the Interim Staff Report on Uranium Exploration on the Colorado Plateau, dated June 1951. The original draft copy was only recently located and is being published at this time because of the interest in the contained historical content. The table of contents of this report lists: history of uranium mining; geology; proposed program for the geologic investigations section; general activities of industry and government; and future exploration of sedimentary uranium deposits and anticipated results. Under the proposed program section are: future of the copper-uranium deposits as a source of uranium; uraniferous asphaltite deposits; and commission exploration and future possibilities. The section on general activities of industry and government includes: exploratory and development drilling; field investigations and mapping; early geologic investigations and investigations by the US geological survey; and geophysical exploration. Tables are also presented on: uranium production by districts; US Geological survey drilling statistics; Colorado Exploration Branch drilling statistics; summary of drilling projects; and comparative yearly core-drill statistics on the Colorado Plateau

78 FR 41125 - Interim Enforcement Policy for Permanent Implant Brachytherapy Medical Event Reporting

Science.gov (United States)

2013-07-09

... NUCLEAR REGULATORY COMMISSION [NRC-2013-0114] Interim Enforcement Policy for Permanent Implant Brachytherapy Medical Event Reporting AGENCY: Nuclear Regulatory Commission. ACTION: Policy statement; revision. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an interim Enforcement Policy that allows...

Predictive probability methods for interim monitoring in clinical trials with longitudinal outcomes.

Science.gov (United States)

Zhou, Ming; Tang, Qi; Lang, Lixin; Xing, Jun; Tatsuoka, Kay

2018-04-17

In clinical research and development, interim monitoring is critical for better decision-making and minimizing the risk of exposing patients to possible ineffective therapies. For interim futility or efficacy monitoring, predictive probability methods are widely adopted in practice. Those methods have been well studied for univariate variables. However, for longitudinal studies, predictive probability methods using univariate information from only completers may not be most efficient, and data from on-going subjects can be utilized to improve efficiency. On the other hand, leveraging information from on-going subjects could allow an interim analysis to be potentially conducted once a sufficient number of subjects reach an earlier time point. For longitudinal outcomes, we derive closed-form formulas for predictive probabilities, including Bayesian predictive probability, predictive power, and conditional power and also give closed-form solutions for predictive probability of success in a future trial and the predictive probability of success of the best dose. When predictive probabilities are used for interim monitoring, we study their distributions and discuss their analytical cutoff values or stopping boundaries that have desired operating characteristics. We show that predictive probabilities utilizing all longitudinal information are more efficient for interim monitoring than that using information from completers only. To illustrate their practical application for longitudinal data, we analyze 2 real data examples from clinical trials. Copyright © 2018 John Wiley & Sons, Ltd.

Pathways to deep decarbonization - Interim 2014 Report

International Nuclear Information System (INIS)

2014-01-01

The interim 2014 report by the Deep Decarbonization Pathways Project (DDPP), coordinated and published by IDDRI and the Sustainable Development Solutions Network (SDSN), presents preliminary findings of the pathways developed by the DDPP Country Research Teams with the objective of achieving emission reductions consistent with limiting global warming to less than 2 deg. C. The DDPP is a knowledge network comprising 15 Country Research Teams and several Partner Organizations who develop and share methods, assumptions, and findings related to deep decarbonization. Each DDPP Country Research Team has developed an illustrative road-map for the transition to a low-carbon economy, with the intent of taking into account national socio-economic conditions, development aspirations, infrastructure stocks, resource endowments, and other relevant factors. The interim 2014 report focuses on technically feasible pathways to deep decarbonization

Senior Program Officer, Evaluation | IDRC - International ...

International Development Research Centre (IDRC) Digital Library (Canada)

... provides technical assistance to program staff and partners on evaluation ... monitoring and evaluation approaches; working with colleagues to maintain the ... provides technical supervision and assistance, including analysis of interim ...

33 CFR 385.38 - Interim goals.

Science.gov (United States)

2010-07-01

..., monitoring and assessment; (ii) Be provided to the independent scientific review panel established in.... The interim goals shall be developed through the use of appropriate models and tools and shall provide... to be required to meet long-term hydrological and ecological restoration goals, based on best...

Interim guidelines for protecting fire-fighting personnel from multiple hazards at nuclear plant sites

International Nuclear Information System (INIS)

Klein, A.R.; Bloom, C.W.

1989-07-01

This report provides interim guidelines for reducing the impact to fire fighting and other supporting emergency response personnel from the multiple hazards of radiation, heat stress, and trauma when fighting a fire in a United States commercial nuclear power plant. Interim guidelines are provided for fire brigade composition, training, equipment, procedures, strategies, heat stress and trauma. In addition, task definitions are provided to evaluate and further enhance the interim guidelines over the long term. 19 refs

Environmental surveillance results for 1995 for the Hazelwood Interim Storage Site

International Nuclear Information System (INIS)

McCague, J.C.

1996-01-01

This memorandum presents and interprets analytical results and measurements obtained as part of the 1995 environmental surveillance program for the Hazelwood Interim Storage Site (HISS) under the Formerly Utilized Sites Remedial Action Program (FUSRAP). The discussion provides a comparative analysis of average historical background conditions and applicable regulatory criteria to the 1995 results reported for external gamma radiation and for samples from the media investigated (air, surface water, sediment, groundwater, and stormwater). Results from the 1995 environmental surveillance program at HISS indicate that, with the exception of thorium-230 in streambed sediment, applicable US Department of Energy (DOE) guidelines were not exceeded for any measured parameter or for any dose calculated for potentially exposed members of the general public. In the absence of sediment guidelines, DOE soil guidelines serve as a standard of comparison for data obtained from stream bed sediment; two samples from downstream locations contained concentrations of thorium-230 that exceeded DOE soil guidelines. All stormwater sample results were in compliance with permit-specified limits. Other radioactive materials include radium 226 and natural uranium

ASPECTS CONCERNING INTERIM FINANCIAL REPORTING IN ROMANIA: STANDARDS AND REGULATIONS

Directory of Open Access Journals (Sweden)

Aristita Rotila

2014-12-01

Full Text Available The mechanisms employed for the communication of accounting information that is necessary for users in their economic decision-making process consist of the financial statements of an entity. All legal entities, no matter the domain of their activity, have the obligation to draw up annual financial statements for every completed financial year. For certain categories of entities, reporting obligations are also required for periods other than the annual reporting, throughout the financial year. It is the case of interim financial reporting. At the level of the international accounting framework, the aspects related to interim financial reporting are the subject of a separate standard, namely, IAS 34 Interim Financial Reporting. In Romania, the current system of accounting regulations concerning the annual financial statements comprises accounting regulations that comply with the European directives and which apply to the various categories of entities, on the one hand and, on the other, accounting regulations in line with the IFRS, which are applicable to other classes of entities from certain activity sectors. The accounting regulations that apply to each category refer to, among other things, the contents and the format of financial statements that have to be presented. Analysing the system of norms and regulations, this article identifies the requirements concerning interim financial reporting in Romania, with reference to the different types of entities.

Interim data quality objectives for waste pretreatment and vitrification. Revision 1

International Nuclear Information System (INIS)

Kupfer, M.J.; Conner, J.M.; Kirkbride, R.A.; Mobley, J.R.

1994-01-01

The Tank Waste Remediation System (TWRS) is responsible for storing, processing, and immobilizing the Hanford Site tank wastes. Characterization information on the tank wastes is needed so that safety concerns can be addressed, and retrieval, pretreatment, and immobilization processes can be designed, permitted, and implemented. This document describes the near-term tank waste sampling and characterization needs of the Pretreatment, High-Level Waste (HLW) Disposal, and Low-Level Waste (LLW) Disposal Programs to support the TWRS disposal mission. The final DQO (Data Quality Objective) will define specific waste tanks to be sampled, sample timing requirements, an appropriate analytical scheme, and a list of required analytes. This interim DQO, however, focuses primarily on the required analytes since the tanks to be sampled in FY 1994 and early FY 1995 are being driven most heavily by other considerations, particularly safety. The major objective of this Interim DQO is to provide guidance for tank waste characterization requirements for samples taken before completion of the final DQO. The characterization data needs defined herein will support the final DQO to help perform the following: Support the TWRS technical strategy by identification of the chemical and physical composition of the waste in the tanks and Guide development efforts to define waste pretreatment processes, which will in turn define HLW and LLW feed to vitrification processes

Taking interim actions: Integrating CERCLA and NEPA to move ahead with site cleanup

International Nuclear Information System (INIS)

MacDonell, M.M.; Peterson, J.M.; Valett, G.L.; McCracken, S.H.

1991-01-01

The cleanup of contaminated sites can be expedited by using interim response actions in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended, and the National Oil and Hazardous Substances Pollution Contingency Plan (NCP). In fact, a major portion of some Superfund sites can be cleaned up using interim actions. For CERCLA sites being remediated by the US Department of Energy (DOE), such actions must also comply with the National Environmental Policy Act (NEPA) because the DOE has established a policy for integrating CERCLA and NEPA requirements. A strategy for the integrated documentation with implementation of interim actions has been applied successfully at the Weldon Spring site, and major cleanup projects are currently underway. This paper discusses some of the issues associated with integrating CERCLA and NEPA for interim actions and summarizes those actions that have been identified for the Weldon Spring site

Taking interim actions: Integrating CERCLA and NEPA to move ahead with site cleanup

International Nuclear Information System (INIS)

MacDonell, M.M.; Peterson, J.M.; Valett, G.L.; McCracken, S.H.

1991-01-01

The cleanup of contaminated sites can be expedited by using interim response actions in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended, and the National Oil and Hazardous Substances Pollution Contingency Plan (NCP). In fact, a major portion of some Superfund sites can be cleaned up using interim actions. For CERCLA sites being remediated by the US Department of Energy (DOE), such actions must also comply with the National Environmental Policy Act (NEPA) because the DOE has established a policy for integrating CERCLA and NEPA requirements. A strategy for the integrated documentation and implementation of interim actions has been applied successfully at the Weldon Spring site, and major cleanup projects are currently underway. This paper discusses some of the issues associated with integrating CERCLA and NEPA for interim actions and summarizes those actions that have been identified for the Weldon Spring site

19 CFR 354.8 - Interim sanctions.

Science.gov (United States)

2010-04-01

... reconsider imposition of interim sanctions on the basis of new and material evidence or other good cause... Secretary may petition a presiding official to impose such sanctions. (b) The presiding official may impose... person to return material previously provided by the Department and all other materials containing the...

Wayne Interim Storage Site annual environmental report for calendar year 1991, Wayne, New Jersey

International Nuclear Information System (INIS)

1992-09-01

This document describes the envirormental monitoring program at the Wayne Interim Storage Site (WISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring of WISS and surrounding area began in 1984 when Congress added the site to the US Department of Energy's (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. WISS is a National Priorities List site. The environmental monitoring program at WISS includes sampling networks for radon and thoron concentrations in air; external gamma radiation exposure; and radium-226, radium-228, thorium-232, and total uranium concentrations in surface water, sediment, and groundwater. Several nonradiological parameters are also measured in groundwater. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides, dose limits, and other requirements in DOE orders. Environmental standards are established to protect public health and the environment

Compilation of interim technical research memoranda. Volume I

International Nuclear Information System (INIS)

Shanahan, W.R.

1984-04-01

Four interim technical research memoranda are presented that describe the results of numerical simulations designed to investigate the dynamics of energetic plasma beams propagating across magnetic fields

Hazelwood Interim Storage Site annual environmental report for calendar year 1991, Hazelwood, Missouri

International Nuclear Information System (INIS)

1992-09-01

This document describes the environmental monitoring program at the Hazelwood Interim Storage Site (HISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring of HISS began in 1984 when the site was assigned to the US Department of Energy (DOE) as part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Development Appropriations Act. DOE placed responsibility for HISS under the Formerly Utilized Sites Remedial Action Program (FUSRAP), a DOE program to decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental monitoring program at HISS includes sampling networks for radon concentrations in air; external gamma radiation exposure; and radium-226, thorium-230, and total uranium concentrations in surface water, sediment, and groundwater. Additionally, several nonradiological parameters are measured in groundwater. Monitoring results are compared with applicable Environmental Protection Agency standards, DOE derived concentration guides (DCGs), dose limits, and other requirements in DOE orders. Environmental standards and DCGs are established to protect public health and the environment

Interim research assessment 2003-2005 - Computer Science

NARCIS (Netherlands)

Mouthaan, A.J.; Hartel, Pieter H.

This report primarily serves as a source of information for the 2007 Interim Research Assessment Committee for Computer Science at the three technical universities in the Netherlands. The report also provides information for others interested in our research activities.

An interim report on the State of Nevada socioeconomic studies

International Nuclear Information System (INIS)

1989-06-01

This Interim Report is a report on work in progress and presents findings from the research to date on the potential consequences of a repository for the citizens of Nevada. The research and findings in the Report have been subjected to rigorous peer review as part of the state's effort to insure independent, objective analysis that meets the highest professional standards. The basic research effort will continue through June 1990 and will enable the state to refine and clarify the findings presented in this Interim Report

Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification Samples

Energy Technology Data Exchange (ETDEWEB)

Peters, T. B.; Washington, A. L. II

2013-08-08

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 7 for the Interim Salt Disposition Program (ISDP). An ARP and several ESS tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP/MCU. No issues with the projected Salt Batch 7 strategy are identified, other than the presence of visible quantities of dark colored solids. A demonstration of the monosodium titanate (0.2 g/L) removal of strontium and actinides provided acceptable 4 hour average decontamination factors for Pu and Sr of 3.22 and 18.4, respectively. The Four ESS tests also showed acceptable behavior with distribution ratios (D(Cs)) values of 15.96, 57.1, 58.6, and 65.6 for the MCU, cold blend, hot blend, and Next Generation Solvent (NGS), respectively. The predicted value for the MCU solvent was 13.2. Currently, there are no models that would allow a prediction of extraction behavior for the other three solvents. SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed. While no outstanding issues were noted, the presence of solids in the samples should be investigated in future work. It is possible that the solids may represent a potential reservoir of material (such as potassium) that could have an impact on MCU performance if they were to dissolve back into the feed solution. This salt batch is intended to be the first batch to be processed through MCU entirely using the new NGS-MCU solvent.

75 FR 984 - Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA and RCRA Sites

Science.gov (United States)

2010-01-07

...The Environmental Protection Agency (EPA or the Agency) is announcing a 50-day public comment period for draft recommended interim preliminary remediation goals (PRGs) developed in the Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and Resource Conservation and Recovery Act (RCRA) Sites. EPA's Office of Solid Waste and Emergency and Emergency Response (OSWER) has developed the draft recommended interim PRGs for dioxin in soil. These draft recommended interim PRGs were calculated using existing, peer- reviewed toxicity values and current EPA equations and default exposure assumptions. This Federal Register notice is intended to provide an opportunity for public comment on the draft recommended interim PRGs. EPA will consider any public comments submitted in accordance with this notice and may revise the draft recommended interim PRGs thereafter.

Plutonium Finishing Plant. Interim plutonium stabilization engineering study

Energy Technology Data Exchange (ETDEWEB)

Sevigny, G.J.; Gallucci, R.H.; Garrett, S.M.K.; Geeting, J.G.H.; Goheen, R.S.; Molton, P.M.; Templeton, K.J.; Villegas, A.J. [Pacific Northwest Lab., Richland, WA (United States); Nass, R. [Nuclear Fuel Services, Inc. (United States)

1995-08-01

This report provides the results of an engineering study that evaluated the available technologies for stabilizing the plutonium stored at the Plutonium Finishing Plant located at the hanford Site in southeastern Washington. Further processing of the plutonium may be required to prepare the plutonium for interim (<50 years) storage. Specifically this document provides the current plutonium inventory and characterization, the initial screening process, and the process descriptions and flowsheets of the technologies that passed the initial screening. The conclusions and recommendations also are provided. The information contained in this report will be used to assist in the preparation of the environmental impact statement and to help decision makers determine which is the preferred technology to process the plutonium for interim storage.

Plutonium Finishing Plant. Interim plutonium stabilization engineering study

International Nuclear Information System (INIS)

Sevigny, G.J.; Gallucci, R.H.; Garrett, S.M.K.; Geeting, J.G.H.; Goheen, R.S.; Molton, P.M.; Templeton, K.J.; Villegas, A.J.; Nass, R.

1995-08-01

This report provides the results of an engineering study that evaluated the available technologies for stabilizing the plutonium stored at the Plutonium Finishing Plant located at the hanford Site in southeastern Washington. Further processing of the plutonium may be required to prepare the plutonium for interim (<50 years) storage. Specifically this document provides the current plutonium inventory and characterization, the initial screening process, and the process descriptions and flowsheets of the technologies that passed the initial screening. The conclusions and recommendations also are provided. The information contained in this report will be used to assist in the preparation of the environmental impact statement and to help decision makers determine which is the preferred technology to process the plutonium for interim storage

DATA MINING METHODOLOGY FOR DETERMINING THE OPTIMAL MODEL OF COST PREDICTION IN SHIP INTERIM PRODUCT ASSEMBLY

Directory of Open Access Journals (Sweden)

Damir Kolich

2016-03-01

Full Text Available In order to accurately predict costs of the thousands of interim products that are assembled in shipyards, it is necessary to use skilled engineers to develop detailed Gantt charts for each interim product separately which takes many hours. It is helpful to develop a prediction tool to estimate the cost of interim products accurately and quickly without the need for skilled engineers. This will drive down shipyard costs and improve competitiveness. Data mining is used extensively for developing prediction models in other industries. Since ships consist of thousands of interim products, it is logical to develop a data mining methodology for a shipyard or any other manufacturing industry where interim products are produced. The methodology involves analysis of existing interim products and data collection. Pre-processing and principal component analysis is done to make the data “user-friendly” for later prediction processing and the development of both accurate and robust models. The support vector machine is demonstrated as the better model when there are a lower number of tuples. However as the number of tuples is increased to over 10000, then the artificial neural network model is recommended.

77 FR 27593 - Exchange Visitor Program-Summer Work Travel

Science.gov (United States)

2012-05-11

...--Summer Work Travel AGENCY: Department of State. ACTION: Interim final rule with request for comment... Travel Program allows foreign post-secondary students (mostly between the ages of 18 and 30) to come to... students have participated in the Sumer Work Travel Program. The popularity of this Program--both with...

3013/9975 Surveillance Program Interim Summary Report

Energy Technology Data Exchange (ETDEWEB)

Dunn, K.; Hackney, B.; McClard, J.

2011-06-22

The K-Area Materials Storage (KAMS) Documented Safety Analysis (DSA) requires a surveillance program to monitor the safety performance of 3013 containers and 9975 shipping packages stored in KAMS. The SRS surveillance program [Reference 1] outlines activities for field surveillance and laboratory tests that demonstrate the packages meet the functional performance requirements described in the DSA. The SRS program also supports the complexwide Integrated Surveillance Program (ISP) [Reference 2] for 3013 containers. The purpose of this report is to provide a summary of the SRS portion of the surveillance program activities through fiscal year 2010 (FY10) and formally communicate the interpretation of these results by the Surveillance Program Authority (SPA). Surveillance for the initial 3013 container random sampling of the Innocuous bin and the Pressure bin has been completed and there has been no indication of corrosion or significant pressurization. The maximum pressure observed was less than 50 psig, which is well below the design pressure of 699 psig for the 3013 container [Reference 3]. The data collected during surveillance of these bins has been evaluated by the Materials Identification and Surveillance (MIS) Working Group and no additional surveillance is necessary for these bins at least through FY13. A decision will be made whether additional surveillance of these bins is needed during future years of storage and as additional containers are generated. Based on the data collected to date, the SPA concludes that 3013 containers in these bins can continue to be safely stored in KAMS. This year, 13 destructive examinations (DE) were performed on random samples from the Pressure & Corrosion bin. To date, DE has been completed for approximately 30% of the random samples from the Pressure & Corrosion bin. In addition, DE has been performed on 6 engineering judgment (EJ) containers, for a total of 17 to date. This includes one container that exceeded the 3013

18 CFR 300.20 - Interim acceptance and review of Bonneville Power Administration rates.

Science.gov (United States)

2010-04-01

... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Interim acceptance and review of Bonneville Power Administration rates. 300.20 Section 300.20 Conservation of Power and Water... Director of the Office of Energy Market Regulation; or (ii) Deny the Administrator's interim rate request...

Fuel Supply Shutdown Facility Interim Operational Safety Requirements

International Nuclear Information System (INIS)

BENECKE, M.W.

2000-01-01

The Interim Operational Safety Requirements for the Fuel Supply Shutdown (FSS) Facility define acceptable conditions, safe boundaries, bases thereof, and management of administrative controls to ensure safe operation of the facility

Interim Hanford Waste Management Plan

International Nuclear Information System (INIS)

1985-09-01

The September 1985 Interim Hanford Waste Management Plan (HWMP) is the third revision of this document. In the future, the HWMP will be updated on an annual basis or as major changes in disposal planning at Hanford Site require. The most significant changes in the program since the last release of this document in December 1984 include: (1) Based on studies done in support of the Hanford Defense Waste Environmental Impact Statement (HDW-EIS), the size of the protective barriers covering contaminated soil sites, solid waste burial sites, and single-shell tanks has been increased to provide a barrier that extends 30 m beyond the waste zone. (2) As a result of extensive laboratory development and plant testing, removal of transuranic (TRU) elements from PUREX cladding removal waste (CRW) has been initiated in PUREX. (3) The level of capital support in years beyond those for which specific budget projections have been prepared (i.e., fiscal year 1992 and later) has been increased to maintain Hanford Site capability to support potential future missions, such as the extension of N Reactor/PUREX operations. The costs for disposal of Hanford Site defense wastes are identified in four major areas in the HWMP: waste storage and surveillance, technology development, disposal operations, and capital expenditures

78 FR 28953 - William D. Ford Federal Direct Loan Program

Science.gov (United States)

2013-05-16

.... Ford Federal Direct Loan Program; Interim Final Rule #0;#0;Federal Register / Vol. 78, No. 95... [Docket ID ED-2013-OPE-0066] RIN 1840-AD13 William D. Ford Federal Direct Loan Program AGENCY: Office of... Secretary amends the William D. Ford Federal Direct Loan Program (Direct Loan Program) regulations to...

Subsurface Interim Measures/Interim Remedial Action Plan and Decision Document for the 903 Pad, Mound, and East Trenches Areas (Operable Unit No. 2)

International Nuclear Information System (INIS)

1992-01-01

The Department of Energy (DOE) is pursuing an Interim Measure/Interim Remedial Action (IM/IRA) at the 903 Pad, Mound, and East Trenches Areas (Operable Unit No. 2) at the Rocky Flats Plant (RFP). This MIRA is to be conducted to provide information that will aid in the selection and design of final remedial actions at OU2 that will address removal of suspected free-phase volatile organic compound (VOC) contamination. The Plan involves investigating the removal of residual free-phase VOCs by in situ vacuum-enhanced vapor extraction technology at 3 suspected VOC source areas within OU2. VOC-contaminated vapors extracted from the subsurface would be treated by granular activated carbon (GAC) adsorption and discharged. The Plan also includes water table depression, when applicable at the test sites, to investigate the performance of vapor extraction technology in the saturated zone. The Plan provides for treatment of any contaminated ground water recovered during the IM/IRA at existing RFP treatment facilities. The proposed MVIRA Plan is presented in the document entitled ''Proposed Subsurface Interim Measures/Interim Remedial Action Plan/Environmental Assessment and Decision Document, 903 Pad, Mound, and East Trenches Areas, Operable Unit No. 2, '' dated 20 March 1992. Information concerning the proposed Subsurface IM/IRA was presented during a DOE Quarterly Review meeting held on 07 April 1992 and a public meeting held on 07 May 1992, at the Marriott Hotel in Golden, Colorado. The Responsiveness Summary presents DOE's response to all comments received at the public meeting, as well as those mailed to date to DOE during the public comment period

Model environmental assessment for a property-cleanup/interim-storage remedial action at a formerly utilized site

International Nuclear Information System (INIS)

Merry-Libby, P.

1982-07-01

This document has been prepared as a model for the preparation of an Environmental Assessment (EA) for a property-cleanup/interim-storage type of remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the US Department of Energy (DOE). For major federal actions significantly affecting the quality of the human environment, an Environmental Impact Statement (EIS) must be prepared to aid DOE in making its decision. However, when it is not clear that an action is major and the impacts are significant, an EA may be prepared to determine whether to prepare an EIS or a finding of no significant impact (FONSI). If it is likely that an action may be major and the impacts significant, it is usually more cost-effective and timely to directly prepare an EIS. If it is likely that a FONSI can be reached after some environmental assessment, as DOE believes may be the case for most property-cleanup/interim-storage remedial actions, preparation of site-specific EAs is an effective means of compliance with NEPA

On-site interim storage of spent nuclear fuel: Emerging public issues

International Nuclear Information System (INIS)

Feldman, D.L.; Tennessee Univ., Knoxville, TN

1992-01-01

Failure to consummate plans for a permanent repository or above- ground interim Monitored Retrievable Storage (MRS) facility for spent nuclear fuel has spurred innovative efforts to ensure at-reactor storage in an environmentally safe and secure manner. This article examines the institutional and socioeconomic impacts of Dry Cask Storage Technology (DCST)-an approach to spent fuel management that is emerging as the preferred method of on-site interim spent fuel storage by utilities that exhaust existing storage capacity

Environmental assessment for 881 Hillside (High Priority Sites) interim remedial action

International Nuclear Information System (INIS)

1990-01-01

This Environmental Assessment evaluates the impact of an interim remedial action proposed for the High Priority Sites (881 Hillside Area) at the Rocky Flats Plant (RFP). This interim action is to be conducted to minimize the release of hazardous substances from the 881 Hillside Area that pose a potential long-term threat to public health and the environment. This document integrates current site characterization data and environmental analyses required by the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) or ''Superfund'' process, into an environmental assessment pursuant to the National Environmental Policy Act (NEPA). Characterization of the 881 Hillside Area is continuing. Consequently, a final remedial action has not yet been proposed. Environmental impacts associated with the proposed interim remedial action and reasonable alternatives designed to remove organic and inorganic contaminants, including radionuclides, from alluvial groundwater in the 881 Hillside Area are addressed. 24 refs., 5 figs., 23 tabs

Transitioning aluminum clad spent fuels from wet to interim dry storage

International Nuclear Information System (INIS)

Louthan, M.R. Jr.; Iyer, N.C.; Sindelar, R.L.; Peacock, H.B. Jr.

1994-01-01

The United States Department of Energy (DOE) currently owns several hundred metric tons of aluminum clad, spent nuclear fuel and target assemblies. The vast majority of these irradiated assemblies are currently stored in water basins that were designed and operated for short term fuel cooling prior to fuel reprocessing. Recent DOE decisions to severely limit the reprocessing option have significantly lengthened the time of storage, thus increasing the tendency for corrosion induced degradation of the fuel cladding and the underlying core material. The portent of continued corrosion, coupled with the age of existing wet storage facilities and the cost of continuing basin operations, including necessary upgrades to meet current facility standards, may force the DOE to transition these wet stored, aluminum clad spent fuels to interim dry storage. The facilities for interim dry storage have not been developed, partially because fuel storage requirements and specifications for acceptable fuel forms are lacking. In spite of the lack of both facilities and specifications, current plans are to dry store fuels for approximately 40 to 60 years or until firm decisions are developed for final fuel disposition. The transition of the aluminum clad fuels from wet to interim dry storage will require a sequence of drying and canning operations which will include selected fuel preparations such as vacuum drying and conditioning of the storage atmosphere. Laboratory experiments and review of the available literature have demonstrated that successful interim dry storage may also require the use of fuel and canister cleaning or rinsing techniques that preclude, or at least minimize, the potential for the accumulation of chloride and other potentially deleterious ions in the dry storage environment. This paper summarizes an evaluation of the impact of fuel transitioning techniques on the potential for corrosion induced degradation of fuel forms during interim dry storage

3013/9975 Surveillance Program Interim Summary Report

International Nuclear Information System (INIS)

Dunn, K.; Hackney, B.; McClard, J.

2011-01-01

The K-Area Materials Storage (KAMS) Documented Safety Analysis (DSA) requires a surveillance program to monitor the safety performance of 3013 containers and 9975 shipping packages stored in KAMS. The SRS surveillance program (Reference 1) outlines activities for field surveillance and laboratory tests that demonstrate the packages meet the functional performance requirements described in the DSA. The SRS program also supports the complexwide Integrated Surveillance Program (ISP) (Reference 2) for 3013 containers. The purpose of this report is to provide a summary of the SRS portion of the surveillance program activities through fiscal year 2010 (FY10) and formally communicate the interpretation of these results by the Surveillance Program Authority (SPA). Surveillance for the initial 3013 container random sampling of the Innocuous bin and the Pressure bin has been completed and there has been no indication of corrosion or significant pressurization. The maximum pressure observed was less than 50 psig, which is well below the design pressure of 699 psig for the 3013 container (Reference 3). The data collected during surveillance of these bins has been evaluated by the Materials Identification and Surveillance (MIS) Working Group and no additional surveillance is necessary for these bins at least through FY13. A decision will be made whether additional surveillance of these bins is needed during future years of storage and as additional containers are generated. Based on the data collected to date, the SPA concludes that 3013 containers in these bins can continue to be safely stored in KAMS. This year, 13 destructive examinations (DE) were performed on random samples from the Pressure and Corrosion bin. To date, DE has been completed for approximately 30% of the random samples from the Pressure and Corrosion bin. In addition, DE has been performed on 6 engineering judgment (EJ) containers, for a total of 17 to date. This includes one container that exceeded the 3013

Colonie Interim Storage Site environmental surveillance report for calendar year 1993

International Nuclear Information System (INIS)

1994-06-01

This report summarizes the results of environmental surveillance activities conducted at the Colonie Interim Storage Site (CISS) during calendar year 1993. It includes an overview of site operations, the basis for radiological and nonradiological monitoring, dose to the offsite population, and summaries of environmental programs at CISS. Environmental surveillance activities were conducted in accordance with the site environmental monitoring plan, which describes the rationale and design criteria for the surveillance program, the frequency of sampling and analysis, specific sampling and analysis procedures, and quality assurance requirements. Appendix A contains a discussion of the nature of radiation, the way it is measured, and common sources of it. The primary environmental guidelines and limits applicable to CISS are given in US Department of Energy (DOE) orders and mandated by six federal acts: the Clean Air Act; the Clean Water Act; the Resource Conservation and Recovery Act (RCRA); the Toxic Substances Control Act; the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA); and the National Environmental Policy Act (NEPA). DOE began environmental monitoring of CISS in 1984 when DOE was authorized by Congress through the Energy and Water Development Appropriations Act to conduct a decontamination research and development program at the site. The site was subsequently assigned to DOE's Formerly Utilized Sites Remedial Action Program (FUSRAP)

The EMEFS model evaluation. An interim report

Energy Technology Data Exchange (ETDEWEB)

Barchet, W.R. [Pacific Northwest Lab., Richland, WA (United States); Dennis, R.L. [Environmental Protection Agency, Research Triangle Park, NC (United States); Seilkop, S.K. [Analytical Sciences, Inc., Durham, NC (United States); Banic, C.M.; Davies, D.; Hoff, R.M.; Macdonald, A.M.; Mickle, R.E.; Padro, J.; Puckett, K. [Atmospheric Environment Service, Downsview, ON (Canada); Byun, D.; McHenry, J.N. [Computer Sciences Corp., Research Triangle Park, NC (United States); Karamchandani, P.; Venkatram, A. [ENSR Consulting and Engineering, Camarillo, CA (United States); Fung, C.; Misra, P.K. [Ontario Ministry of the Environment, Toronto, ON (Canada); Hansen, D.A. [Electric Power Research Inst., Palo Alto, CA (United States); Chang, J.S. [State Univ. of New York, Albany, NY (United States). Atmospheric Sciences Research Center

1991-12-01

The binational Eulerian Model Evaluation Field Study (EMEFS) consisted of several coordinated data gathering and model evaluation activities. In the EMEFS, data were collected by five air and precipitation monitoring networks between June 1988 and June 1990. Model evaluation is continuing. This interim report summarizes the progress made in the evaluation of the Regional Acid Deposition Model (RADM) and the Acid Deposition and Oxidant Model (ADOM) through the December 1990 completion of a State of Science and Technology report on model evaluation for the National Acid Precipitation Assessment Program (NAPAP). Because various assessment applications of RADM had to be evaluated for NAPAP, the report emphasizes the RADM component of the evaluation. A protocol for the evaluation was developed by the model evaluation team and defined the observed and predicted values to be used and the methods by which the observed and predicted values were to be compared. Scatter plots and time series of predicted and observed values were used to present the comparisons graphically. Difference statistics and correlations were used to quantify model performance. 64 refs., 34 figs., 6 tabs.

Administrative Court Stade, decision of March 22, 1985 (interim storage facility at Gorleben)

International Nuclear Information System (INIS)

Anon.

1985-01-01

This decision deals with the planned interim storage facility of Gorleben (F.R.G.). The provisions introduced by the 4th ammendment to sec. 5 para. 6 and 9a to 9c of the German Atomic Energy Act might contain a definite regulation of the 'Entsorgung' of nuclear power stations. Sec. 6 of the Atomic Energy Act is not applicable to interim storage facilities because irradiated nuclear fuel has a double nature: It is spent fuel and nuclear waste as well. Considering current licensing procedures of construction and operation of nuclear installations in the field of 'Entsorgung', special legal regulations for the construction and operation of an interim storage facility have to be required. (CW)

Interim storage study report

Energy Technology Data Exchange (ETDEWEB)

Rawlins, J.K.

1998-02-01

High-level radioactive waste (HLW) stored at the Idaho Chemical Processing Plant (ICPP) in the form of calcine and liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the waste to be transported to a permanent repository. Because a permanent repository will not be available when the waste is processed, the waste must be stored at ICPP in an Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options under consideration.

Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

International Nuclear Information System (INIS)

Burgard, K.C.

1998-01-01

The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis

Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

Energy Technology Data Exchange (ETDEWEB)

Burgard, K.C.

1998-04-09

The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

Agenda 21 interim balance, 1997

Energy Technology Data Exchange (ETDEWEB)

Van Vuuren, D.P.; Bakkes, J.A.

1997-10-01

Five years after the `United Nations Conference on Environment and Development (UNCED)`, an interim balance was drawn up to see what was done to meet the ambitious challenges adopted in Agenda 21 during this conference. Such a balance is presented in this report and the complementary brochure, `Developments in Sustainability 1992-1997`, reflecting societal developments and changes in environmental quality, as well as changes in responses to environmental concerns. 24 figs., 12 tabs., 68 refs.

Linear Programming for Vocational Education Planning. Interim Report.

Science.gov (United States)

Young, Robert C.; And Others

The purpose of the paper is to define for potential users of vocational education management information systems a quantitative analysis technique and its utilization to facilitate more effective planning of vocational education programs. Defining linear programming (LP) as a management technique used to solve complex resource allocation problems…

Waste management in Canadian nuclear programs

International Nuclear Information System (INIS)

Dyne, P.J.

1975-08-01

The report describes the wide-ranging program of engineering developments and applications to provide the Canadian nuclear industry with the knowledge and expertise it needs to conduct its waste management program. The need for interim dry storage of spent fuel, and the storage and ultimate disposal of waste from fuel reprocessing are examined. The role of geologic storage in AECL's current waste management program is also considered. (R.A.)

THE IMPORTANCE OF FINANCIAL INTERIM REPORTING FOR THE POSITION OF COMPANIES

Directory of Open Access Journals (Sweden)

Claudia‐Elena\tGRIGORAȘ‐ICHIM

2015-12-01

Full Text Available The importance that each company must grant to the strategic sources of information generates our concern for analysis of the interim financial reporting. In every enterprise, there are doubts on the usefulness of interim financial reports, given the following elements: the necessary time for their preparation (relatively long, their restricted character and the resources necessary to establish them. Finding a common solution to these problems and, implicitly, increasing the interest for interim financial reporting, can help to increase the economic performance of the company, either by reducing the unnecessary costs related to time, or by increasing communication and transparency with third parties. An appropriate management can act early in the direction of counteracting the negative effects in their company or prevention of any commercial or production failures, the overall economic trends in that field and increasing productivity. Starting from these premises, we propose a research in order to capture the main aspects related to the mentioned issues.

Long-term interim storage concepts with conditioning strategies ensuring compatibility with subsequent disposal or reprocessing

International Nuclear Information System (INIS)

Moitrier, C.; Tirel, I.; Villard, C.

2000-01-01

The objective of the CEA studies carried out under research topic 3 (long-term interim storage) of the 1991 French radioactive waste management law is to demonstrate the industrial feasibility of a comprehensive, flexible interim storage facility by thoroughly evaluating and comparing all the basic components of various interim storage concepts. In this context, the CEA is considering reference solutions or concepts based on three primary components (the package, the interim storage facility and the site) suitable for determining the specifications of a very long-term solution. Some aspects are examined in greater detail, such as the implementation of long-term technologies, conditioning processes ensuring the absence of water and contamination in the facility, or allowance for radioactive decay of the packages. The results obtained are continually compiled in reports substantiating the design options. These studies should also lead to an overall economic assessment in terms of the capital and operating cost requirements, thereby providing an additional basis for selecting the design options. The comparison with existing industrial facilities highlights the technical and economic progress represented by the new generation of interim storage units. (authors)

Software Verification and Validation Report for the 244-AR Vault Interim Stabilization Ventilation System

International Nuclear Information System (INIS)

YEH, T.

2002-01-01

This document reports on the analysis, testing and conclusions of the software verification and validation for the 244-AR Vault Interim Stabilization ventilation system. Automation control system will use the Allen-Bradley software tools for programming and programmable logic controller (PLC) configuration. The 244-AR Interim Stabilization Ventilation System will be used to control the release of radioactive particles to the environment in the containment tent, located inside the canyon of the 244-AR facility, and to assist the waste stabilization efforts. The HVAC equipment, ducts, instruments, PLC hardware, the ladder logic executable software (documented code), and message display terminal are considered part of the temporary ventilation system. The system consists of a supply air skid, temporary ductwork (to distribute airflow), and two skid-mounted, 500-cfm exhausters connected to the east filter building and the vessel vent system. The Interim Stabilization Ventilation System is a temporary, portable ventilation system consisting of supply side and exhaust side. Air is supplied to the containment tent from an air supply skid. This skid contains a constant speed fan, a pre-filter, an electric heating coil, a cooling coil, and a constant flow device (CFD). The CFD uses a passive component that allows a constant flow of air to pass through the device. Air is drawn out of the containment tent, cells, and tanks by two 500-cfm exhauster skids running in parallel. These skids are equipped with fans, filters, stack, stack monitoring instrumentation, and a PLC for control. The 500CFM exhaust skids were fabricated and tested previously for saltwell pumping activities. The objective of the temporary ventilation system is to maintain a higher pressure to the containment tent, relative to the canyon and cell areas, to prevent contaminants from reaching the containment tent

Application of dose evaluation of the MCNP code for interim spent fuel cask storage facility

International Nuclear Information System (INIS)

Kosako, Toshiso; Iimoto, Takeshi; Ishikawa, Satoshi; Tsuboi, Takafumi; Teramura, Masahiro; Okamura, Tomomi; Narumiya, Yoshiyuki

2007-01-01

The interim storage facility for spent fuel metallic cask is designed as a concrete building structure with air inlet and outlet for circulating the natural cooling. The feature of the interim storage facility is big capacity of spent fuel at several thousands MTU and restricted site usage. It is important to evaluate realistic dose rate in shielding design of the interim storage facility, therefore the three-dimensional continuous-energy Monte Carlo radiation transport code MCNP that exactly treating the complicated geometry was applied. The validation of dose evaluation for interim storage facility by MCNP code were performed by three kinds of neutron shielding benchmark experiments; cask shadow shielding experiment, duct streaming experiment and concrete deep penetration experiment. Dose rate distributions at each benchmark were measured and compared with the calculated results. The comparison showed a good consistency between calculation and experiment results. (author)

Interim data report for the safety assessment SR-Can

International Nuclear Information System (INIS)

Vahlund, Fredrik; Andersson, Johan

2004-08-01

This document is the interim data report in the project SR-Can. The purpose of the data report is to present input data, with uncertainty estimates, for the SR-Can assessment calculations. Besides input data, the report also describes the standardised procedures used when deriving the input data and the corresponding uncertainty estimates. However, in the present interim version of the report (written in the initial stage of the project when site characterisation has yet not been completed) the standardised procedures have not been possible to apply for most of the data and, in order to present a compilation of the data used in the assessment, much of the input data is presented without following the standardised procedures. This will however be changed for the final version of the SR-Can data report, in order to show the methodology that will be used in the final version one example of how input data will be presented is included (migration data for buffer) . The recommended input data for the assessment calculations are, for the interim version, mainly based on SR 97 Beberg data, these are merely presented without any background or uncertainty discussion (this is presented in the SR 97 data report)

Interim Storage Facility decommissioning. Final report

International Nuclear Information System (INIS)

Johnson, R.P.; Speed, D.L.

1985-01-01

Decontamination and decommissioning of the Interim Storage Facility were completed. Activities included performing a detailed radiation survey of the facility, removing surface and imbedded contamination, excavating and removing the fuel storage cells, restoring the site to natural conditions, and shipping waste to Hanford, Washington, for burial. The project was accomplished on schedule and 30% under budget with no measurable exposure to decommissioning personnel

14 CFR 136.41 - Interim operating authority.

Science.gov (United States)

2010-01-01

... AND NATIONAL PARKS AIR TOUR MANAGEMENT National Parks Air Tour Management § 136.41 Interim operating... terminate 180 days after the date on which an air tour management plan is established for the park and tribal lands; (6) Shall promote protection of national park resources, visitor experiences, and tribal...

Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 3. Alternatives for interim storage and transportation

International Nuclear Information System (INIS)

1976-05-01

Volume III of the five-volume report contains information on alternatives for interim storage and transportation. Section titles are: interim storage of spent fuel elements; interim storage of chop-leach fuel bundle residues; tank storage of high-level liquid waste; interim storage of solid non-high-level wastes; interim storage of solidified high-level waste; and, transportation alternatives

PROJECT W-551 INTERIM PRETREATMENT SYSTEM TECHNOLOGY SELECTION SUMMARY DECISION REPORT AND RECOMMENDATION

International Nuclear Information System (INIS)

CONRAD EA

2008-01-01

This report provides the conclusions of the tank farm interim pretreatment technology decision process. It documents the methodology, data, and results of the selection of cross-flow filtration and ion exchange technologies for implementation in project W-551, Interim Pretreatment System. This selection resulted from the evaluation of specific scope criteria using quantitative and qualitative analyses, group workshops, and technical expert personnel

Rosiglitazone evaluated for cardiovascular outcomes--an interim analysis

DEFF Research Database (Denmark)

Home, Philip D; Pocock, Stuart J; Beck-Nielsen, Henning

2007-01-01

BACKGROUND: A recent meta-analysis raised concern regarding an increased risk of myocardial infarction and death from cardiovascular causes associated with rosiglitazone treatment of type 2 diabetes. METHODS: We conducted an unplanned interim analysis of a randomized, multicenter, open...... group). The primary end point was hospitalization or death from cardiovascular causes. RESULTS: Because the mean follow-up was only 3.75 years, our interim analysis had limited statistical power to detect treatment differences. A total of 217 patients in the rosiglitazone group and 202 patients...... in the control group had the adjudicated primary end point (hazard ratio, 1.08; 95% confidence interval [CI], 0.89 to 1.31). After the inclusion of end points pending adjudication, the hazard ratio was 1.11 (95% CI, 0.93 to 1.32). There were no statistically significant differences between the rosiglitazone...

Poor predictive value of positive interim FDG-PET/CT in primary mediastinal large B-cell lymphoma

Energy Technology Data Exchange (ETDEWEB)

Lazarovici, Julien; Petrovanu, Cynthia; Danu, Alina; Ferme, Christophe; Ribrag, Vincent; Ghez, David [Gustave Roussy, Villejuif (France). Dept. of Hematology; Paris Saclay Univ., Saint-Aubin (France); Terroir, Marie [Gustave Roussy, Villejuif (France). Dept. of Nuclear Medicine and Endocrine Oncology; Paris Saclay Univ., Saint-Aubin (France); Arfi-Rouche, Julia [Gustave Roussy, Villejuif (France). Dept. of Radiology; Paris Saclay Univ., Saint-Aubin (France); Michot, Jean-Marie [Gustave Roussy, Villejuif (France). Dept. of Drug Development (DITEP); Paris Saclay Univ., Saint-Aubin (France); Mussot, Sacha; Florea, Valentina [Marie Lannelongue Hospital, Le Plessis Robinson (France). Dept. of Thoracic Surgery; Ghigna, Maria-Rosa [Marie Lannelongue Hospital, Le Plessis Robinson (France). Dept. of Pathology; Dartigues, Peggy [Gustave Roussy, Villejuif (France). Dept. of Pathology; Paris Saclay Univ., Saint-Aubin (France)

2017-11-15

Though commonly used to assess response to therapy, the prognostic value of interim FDG-PET/CT in Primary Mediastinal Large B-cell Lymphoma (PMBCL) is unclear. We conducted a retrospective study on 36 consecutive patients treated at our institution for a PMBCL between 2006 and 2014. All patients with a positive interim FDG-PET/CT had undergone histological restaging consisting either in a surgical debulking of the residual lesion (15 patients) or a CT-guided core needle biopsy (two patients). All FDG-PET/CT were secondarily reviewed according to the more recent Deauville criteria. Interim FDG-PET/CT was considered positive in 17/36 patients using visual evaluation. Among these patients, 14 had a Deauville score of 4. Histological restaging was negative in all but one case, showing inflammation and/or fibrosis. After a median follow-up of 48.5 months, a total of five patients have relapsed, two patients in the positive FDG-PET/CT group, and three patients in the negative FDG-PET/CT group, respectively. These data indicate that a positive interim FDG-PET/CT does not reflect persistence of active disease in the vast majority of PMBCL cases. The relapse rate appears similar regardless of interim FDG-PET/CT results and interpretation criteria. This suggests that interim FDG-PET/CT has a poor positive predictive value, thus kt should be used with caution in PMBCL. (orig.)

75 FR 13484 - Foreign-Trade Zone 22; Temporary/Interim Manufacturing Authority; LG Electronics Mobilecomm USA...

Science.gov (United States)

2010-03-22

... DEPARTMENT OF COMMERCE [Docket T-1-2010] Foreign-Trade Zones Board Foreign-Trade Zone 22; Temporary/Interim Manufacturing Authority; LG Electronics Mobilecomm USA, Inc. (Cell Phones); Notice of.../ interim manufacturing (T/IM) authority, on behalf of LG Electronics Mobilecomm USA, Inc. (LGEMU), to...

Interim Action Proposed Plan for the Chemicals, Metals, and Pesticides (CMP) Pits Operable Unit; FINAL

International Nuclear Information System (INIS)

Bradley, J.

2002-01-01

The purpose of this Interim Action Proposed Plan (IAPP) is to describe the preferred interim remedial action for addressing the Chemicals, Metals, and Pesticides (CMP) Pits Operable Unit and to provide an opportunity for public input into the remedial action selection process

340 waste handling facility interim safety basis

Energy Technology Data Exchange (ETDEWEB)

VAIL, T.S.

1999-04-01

This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people.

340 waste handling facility interim safety basis

International Nuclear Information System (INIS)

VAIL, T.S.

1999-01-01

This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people

Surface Water Interim Measures/Interim Remedial Action Plan/Environmental Assessment and Decision Document for South Walnut Creek Basin (Operable Unit No. 2)

International Nuclear Information System (INIS)

1991-01-01

The Department of Energy (DOE) is pursuing an Interim Measure/Interim Remedial Action (IM/IRA) at the 903 Pad, Mound, and East Trenches Areas (Operable Unit No. 2) at the Rocky Flats Plant (RFP). This IM/IRA is to be conducted to minimize the release from these areas of hazardous substances that pose a potential threat to the public health and environment. The Plan involved the collection of contaminated surface water at specific locations, treatment by chemical precipitation, cross-flow membrane filtration and granular activated carbon (GAC) adsorption, and surface discharge of treated water. Information for the initial configuration of the Plan is presented in the document entitled ''Proposed Interim Measures/Interim Remedial Action Plan and Decision Document, 903 Pad, Mound, and East Trenches Areas, Operable Unit No. 2'' (IM/IRAP) dated 26 September 1990. Information concerning the proposed Surface Water IM/IRA was presented during a public meeting held from 7 to 10 p.m., Tuesday, 23 October 1990, at the Westminster City Park Recreation Center in Westminster, Colorado. This Responsiveness Summary presents DOE's response to all comments received at the public meeting, as well as those mailed to DOE during the public comment period which ended 24 November 1990. There were a number of technical comments on the plan that DOE has addressed herein. It is noted that several major issues were raised by the comments. Regardless of the estimated low risk to the public from construction and water transport activities, the popular sentiment of the public, based on comments received, is strong concern over worker and public health risks from these activities. In the light of public and municipal concerns, DOE proposes to eliminate from this IM/IRA the interbasin transfer of Woman Creek seepage to the South Walnut Creek drainage and to address collection and treatment of contaminated South Walnut Creek and Woman Creek surface water under two separate IM/IRAs

Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage.

Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

International Nuclear Information System (INIS)

1995-06-01

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage

Federal Administrative Court confirms interim action for the Kruemmel power plant site

International Nuclear Information System (INIS)

Anon.

1982-01-01

The interim action concerning the reactor site was confirmed in 1972, the action of voidance because of the possible injuriousness to health was rejected in the first instance. In the appeal OVG Lueneburg had sharpened three clauses concerning the contents of the restrictions and injunctions included in the interim action to the disadvantage of the operator. Responding to a new appeal the BVerwG has eliminated these restrictions and dismissed the following appeals of the plaintiffs. (HP) [de

77 FR 34935 - Foreign-Trade Zone 161; Temporary/Interim Manufacturing Authority; Siemens Energy, Inc., (Wind...

Science.gov (United States)

2012-06-12

... DEPARTMENT OF COMMERCE Foreign-Trade Zones Board [Docket T-4-2012] Foreign-Trade Zone 161; Temporary/Interim Manufacturing Authority; Siemens Energy, Inc., (Wind Turbine Nacelles and Hubs); Notice of... temporary/interim manufacturing (T/IM) authority, on behalf of Siemens Energy, Inc., to manufacture wind...

Using ERA-Interim reanalysis for creating datasets of energy-relevant climate variables

Science.gov (United States)

Jones, Philip D.; Harpham, Colin; Troccoli, Alberto; Gschwind, Benoit; Ranchin, Thierry; Wald, Lucien; Goodess, Clare M.; Dorling, Stephen

2017-07-01

The construction of a bias-adjusted dataset of climate variables at the near surface using ERA-Interim reanalysis is presented. A number of different, variable-dependent, bias-adjustment approaches have been proposed. Here we modify the parameters of different distributions (depending on the variable), adjusting ERA-Interim based on gridded station or direct station observations. The variables are air temperature, dewpoint temperature, precipitation (daily only), solar radiation, wind speed, and relative humidity. These are available on either 3 or 6 h timescales over the period 1979-2016. The resulting bias-adjusted dataset is available through the Climate Data Store (CDS) of the Copernicus Climate Change Data Store (C3S) and can be accessed at present from climate.copernicus.eu" target="_blank">ftp://ecem.climate.copernicus.eu. The benefit of performing bias adjustment is demonstrated by comparing initial and bias-adjusted ERA-Interim data against gridded observational fields.

EPA's Revised Interim Financial Assistance Conflict of Interest Policy

Science.gov (United States)

EPA has established the following revised interim policy governing disclosure of actual and potential conflicts of interest (COI Policy) by applicants for, and recipients of, federal financial assistance awards from EPA.

39 CFR 211.4 - Interim personnel regulations.

Science.gov (United States)

2010-07-01

... 39 Postal Service 1 2010-07-01 2010-07-01 false Interim personnel regulations. 211.4 Section 211.4... under the Postal Reorganization Act. (b) Continuation of Personnel Provisions of Former title 39, U.S.C... collective bargaining agreement under the Postal Reorganization Act, all provisions of former title 39, U.S.C...

Dry interim storage of radioactive material in Germany

International Nuclear Information System (INIS)

Drobniewski, Christian; Palmes, Julia

2013-01-01

In accordance with the waste management concept in Germany, spent fuel is stored in interim storage facilities for a period of up to 40 years until deposition in a geological repository. In twelve on-site interim storages in the vicinity or directly on the sites of the nuclear power plants, spent fuel elements from reactor operation are stored after the necessary period of decay in wet storage basins inside the reactors. Additionally, three central interim storage facilities for storage of spent fuel of different origin are in operation. The German facilities realize the concept of dry interim storage in metallic transport and storage casks. The confinement of the radioactive material is ensured by the double lid system of the casks, of which the leak tightness is monitored constantly. The casks are constructed to provide adequate heat removal and shielding of gamma and neutron radiation. Usually the storage facilities are halls of thick concrete structures, which ensure the removal of the decay heat by natural convection. The main safety goal of the storage concept is to prevent unnecessary exposure of persons, material goods and environment to ionizing radiation. Moreover any exposure should be kept as low as reasonable achievable. To reach this goal the containment of the radioactive materials, the disposal of decay heat, the sub criticality and the shielding of ionizing radiation has to be demonstrated by the applicant and verified by the licensing authority. In particular accidents, incidents and disasters have to be considered in the facility and cask design. This includes mechanical impacts onto the cask, internal and external fire, and environmental effects like wind, rain, snowfall, flood, earthquakes and landslides. In addition civilizatoric influences like plane crashes and explosions have to be taken into account. In all mentioned cases the secure confinement of the radioactive materials has to be ensured. On-site storage facilities have to consider the

State child health; revisions to the regulations implementing the State Children's Health Insurance Program. Interim final rule with comment period; revisions, delay of effective date, and technical amendments to final rule.

Science.gov (United States)

2001-06-25

Title XXI authorizes the State Children's Health Insurance Program (SCHIP) to assist State efforts to initiate and expand the provision of child health assistance to uninsured, low-income children. On January 11, 2001 we published a final rule in the Federal Register to implement SCHIP that has not gone into effect. This interim final rule further delays the effective date, revises certain provisions and solicits public comment, and makes technical corrections and clarifications to the January 2001 final rule based on further review of the comments received and applicable law. Only the provisions set forth in this document have changed. All other provisions set forth in the January 2001 final rule will be implemented without change.

Guidelines for interim storage of low level waste

International Nuclear Information System (INIS)

Hornibrook, C.; Castagnacci, A.; Clymer, G.; Kelly, J.; Naughton, M.; Saunders, P.; Stoner, P.; Walker, N.; Cazzolli, R.; Dettenmeier, R.; Loucks, L.; Rigsby, M.; Spall, M.; Strum, M.

1992-12-01

This report presents an overview of on-site storage of Low Level Waste while providing guidelines for using the complete Interim On-Site Storage of Low Level Waste report series. Overall, this report provides a methodology for planning and implementing on-site storage

Deep Vadose Zone Treatability Test for the Hanford Central Plateau. Interim Post-Desiccation Monitoring Results, Fiscal Year 2015

Energy Technology Data Exchange (ETDEWEB)

Truex, Michael J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Strickland, Christopher E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Oostrom, Martinus [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Johnson, Christian D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Tartakovsky, Guzel D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Johnson, Timothy C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Clayton, Ray E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Chronister, Glen B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-09-01

A field test of desiccation is being conducted as an element of the Deep Vadose Zone Treatability Test Program. The active desiccation portion of the test has been completed. Monitoring data have been collected at the field test site during the post-desiccation period and are reported herein. This is an interim data summary report that includes about 4 years of post-desiccation monitoring data. The DOE field test plan proscribes a total of 5 years of post-desiccation monitoring.

Interim Feed The Future Population Based Assessment of Cambodia

Data.gov (United States)

US Agency for International Development — This is the interim population based survey of Feed the Future in Cambodia for 2015. The data is split into survey modules. Modules A through C includes location...

Fuel supply shutdown facility interim operational safety requirements

International Nuclear Information System (INIS)

Besser, R.L.; Brehm, J.R.; Benecke, M.W.; Remaize, J.A.

1995-01-01

These Interim Operational Safety Requirements (IOSR) for the Fuel Supply Shutdown (FSS) facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls to ensure safe operation. The IOSRs apply to the fuel material storage buildings in various modes (operation, storage, surveillance)

An allowable cladding peak temperature for spent nuclear fuels in interim dry storage

Science.gov (United States)

Cha, Hyun-Jin; Jang, Ki-Nam; Kim, Kyu-Tae

2018-01-01

Allowable cladding peak temperatures for spent fuel cladding integrity in interim dry storage were investigated, considering hydride reorientation and mechanical property degradation behaviors of unirradiated and neutron irradiated Zr-Nb cladding tubes. Cladding tube specimens were heated up to various temperatures and then cooled down under tensile hoop stresses. Cool-down specimens indicate that higher heat-up temperature and larger tensile hoop stress generated larger radial hydride precipitation and smaller tensile strength and plastic hoop strain. Unirradiated specimens generated relatively larger radial hydride precipitation and plastic strain than did neutron irradiated specimens. Assuming a minimum plastic strain requirement of 5% for cladding integrity maintenance in interim dry storage, it is proposed that a cladding peak temperature during the interim dry storage is to keep below 250 °C if cladding tubes are cooled down to room temperature.

17 CFR 210.8-03 - Interim financial statements.

Science.gov (United States)

2010-04-01

... 17 Commodity and Securities Exchanges 2 2010-04-01 2010-04-01 false Interim financial statements... AND CONTENT OF AND REQUIREMENTS FOR FINANCIAL STATEMENTS, SECURITIES ACT OF 1933, SECURITIES EXCHANGE... ADVISERS ACT OF 1940, AND ENERGY POLICY AND CONSERVATION ACT OF 1975 Article 8 Financial Statements of...

Options for the interim storage of spent fuel

International Nuclear Information System (INIS)

Kromar, M.; Kurincic, B.

1995-01-01

Different concepts for the interim storage of spent fuel arising from operation of a NPP are discussed. We considered at reactor as well as away from reactor storage options. Included are enhancements of existing storage capabilities and construction of a new wet or dry storage facility. (author)

Glass packages in interim storage

International Nuclear Information System (INIS)

Jacquet-Francillon, N.

1994-10-01

This report summarize the current state of knowledge concerning the behavior of type C waste packages consisting of vitrified high-level solutions produced by reprocessing spent fuel. The composition and the physical and chemical properties of the feed solutions are reviewed, and the vitrification process is described. Sodium alumino-borosilicate glass compositions are generally employed - the glass used at la Hague for LWR fuel solutions, for example, contains 45 % SiO 2 . The major physical, chemical, mechanical and thermal properties of the glass are reviewed. In order to allow their thermal power to diminish, the 3630 glass packages produced (as of January 1993) in the vitrification facilities at Marcoule and La Hague are placed in interim storage for several decades. The actual interim storage period has not been defined, as it is closely related to the concept and organization selected for the final destination of the packages: a geological repository. The glass behavior under irradiation is described. Considerable basic and applied research has been conducted to assess the aqueous leaching behavior of nuclear containment glass. The effects of various repository parameters (temperature, flow rate, nature of the environmental materials) have been investigated. The experimental findings have been used to specify a model describing the kinetics of aqueous corrosion of the glass. More generally all the ''source term'' models developed in France by the CEA or by ANDRA are summarized. (author). 152 refs., 33 figs

Replacement of a hopeless maxillary central incisor: a technique for the fabrication of an immediate implant-supported interim restoration.

Science.gov (United States)

Graiff, Lorenzo; Vigolo, Paolo

2012-04-01

Placement of a dental implant and an interim restoration in the esthetic zone immediately following tooth extraction is now a common procedure. However, in such clinical situations, the fabrication of an appropriate interim restoration may be challenging. The aim of this article is to present a technique for modifying the extracted tooth so it can be used as an implant-supported interim restoration.

Radioactivity standards distribution program, 1978--1979. Interim report, 1978--1979

International Nuclear Information System (INIS)

Ziegler, L.H.

1978-06-01

A program for the distribution of calibrated radioactive samples, as one function of EPA's quality assurance program for environmental radiation measurements, is described. Included is a discussion of the objectives of the distribution program and a description of the preparation, availability, and distribution of calibrated radioactive samples. Instructions and application forms are included for laboratories desiring to participate in the program. This document is not a research report. It is designed for use by personnel of laboratories participating or desiring to participate in the Radioactivity Standards Distribution Program, which is a part of the U.S. Environmental Protection Agency's quality assurance program

Effectiveness of interim remedial actions at the Niagara Falls Storage Site

International Nuclear Information System (INIS)

Devgun, J.S.; Beskid, N.J.; Seay, W.M.; McNamee, E.

1990-01-01

There are 190,000 m 3 of contaminated soils, wastes, and residues stored at the Niagara Falls Storage Site (NFSS). The residues have a volume of 18,000 m 3 and contain about 1,930 Ci of 226 Ra, which accounts for most of the radioactivity. Since 1980, actions have been taken to minimize potential radiological risks and prevent radionuclide migration. Interim actions included capping vents, sealing pipes, relocating the perimeter fence (to limit radon risk), transferring and consolidating wastes, upgrading storage buildings, constructing a clay cutoff wall (to limit potential ground-water transport of contaminants), treating and releasing contaminated water, using a synthetic liner, and using an interim clay cap. An interim waste containment facility was completed in 1986. Environmental monitoring showed a decrease in radon concentrations and in external gamma radiation from 1982 to 1986; levels have been stable since 1986. Uranium and radium concentrations in surface water have decreased; very low concentrations have been detected in stream sediments, and concentrations in ground water have remained stable. Recent monitoring showed that NFSS is in compliance with the U.S. Department of Energy's (DOE's) radiation protection standards

German Approach for the Transport of Spent Fuel Packages after Interim Storage

International Nuclear Information System (INIS)

Wille, Frank; Wolff, Dietmar; Droste, Bernhard; Voelzke, Holger

2014-01-01

In Germany the concept of dry interim storage of spent nuclear fuel in dual purpose metal casks is implemented, currently for periods of up to 40 years. The casks being used have an approved package design in accordance with the international transport regulations. The license for dry storage is granted on the German Atomic Energy Act with respect to the recently (in 2012) revised 'Guidelines for dry cask storage of spent nuclear fuel and heat-generating waste' by the German Waste management Commission (ESK) which are very similar to the former RSK (reactor safety commission) guidelines. For transport on public routes between or after long term interim storage periods, it has to be ensured that the transport and storage casks fulfil the specifications of the transport approval or other sufficient properties which satisfy the proofs for the compliance of the safety objectives at that time. In recent years the validation period of transport approval certificates for manufactured, loaded and stored packages were discussed among authorities and applicants. A case dependent system of 3, 5 and 10 years was established. There are consequences for the safety cases in the Package Design Safety Report including evaluation of long term behavior of components and specific operating procedures of the package. Present research and knowledge concerning the long term behavior of transport and storage cask components have to be consulted as well as experiences from interim cask storage operations. Challenges in the safety assessment are e.g. the behavior of aged metal and elastomeric seals under IAEA test conditions to ensure that the results of drop tests can be transferred to the compliance of the safety objectives at the time of transport after the interim storage period (aged package). Assessment methods for the material compatibility, the behavior of fuel assemblies and the aging behavior of shielding parts are issues as well. This paper describes the state

National climate change action plans: Interim report for developing and transition countries

Energy Technology Data Exchange (ETDEWEB)

Benioff, R.; Ness, E.; Hirst, J. [eds.

1997-10-01

Under its Support for National Action Plans (SNAP) initiative, the U.S. Country Studies Program is providing financial and technical assistance to 18 countries for the development of climate change action plans. Although most of the countries have not yet completed their plans, the important lessons learned thus far are valuable and should be shared with other countries and international institutions that have an interest in the process of action plan development. This interim report describes the experience of 11 countries that are the furthest along in their planning activity and who have offered to share their results to date with the larger community of interested nations. These action plans delineate specific mitigation and adaptation measures that the countries will implement and integrate into their ongoing development programs. This report focuses on the measures the countries have selected and the methods they used to prepare their action plans. This executive summary presents key lessons and common themes using a structure similar to that used in the individual country chapters.

105-C Reactor interim safe storage project technology integration plan

International Nuclear Information System (INIS)

Pulsford, S.K.

1997-01-01

The 105-C Reactor Interim Safe Storage Project Technology Integration Plan involves the decontamination, dismantlement, and interim safe storage of a surplus production reactor. A major goal is to identify and demonstrate new and innovative D and D technologies that will reduce costs, shorten schedules, enhance safety, and have the potential for general use across the RL complex. Innovative technologies are to be demonstrated in the following areas: Characterization; Decontamination; Waste Disposition; Dismantlement, Segmentation, and Demolition; Facility Stabilization; and Health and Safety. The evaluation and ranking of innovative technologies has been completed. Demonstrations will be selected from the ranked technologies according to priority. The contractor team members will review and evaluate the demonstration performances and make final recommendations to DOE

Development of a Computer Program (CASK) for the Analysis of Logistics and Transportation Cost of the Spent Fuels

International Nuclear Information System (INIS)

Cha, Jeong-Hun; Choi, Heui-Joo; Cho, Dong-Keun; Kim, Seong-Ki; Lee, Jong-Youl; Choi, Jong-Won

2008-07-01

The cost for the spent fuel management includes the costs for the interim storage, the transportation, and the permanent disposal of the spent fuels. The CASK(Cost and logistics Analysis program for Spent fuel transportation in Korea) program is developed to analyze logistics and transportation cost of the spent fuels. And the total amount of PWR spent fuels stored in four nuclear plant sites, a centralized interim storage facility near coast and a permanent disposal facility near the interim storage facility are considered in this program. The CASK program is developed by using Visual Basic language and coupled with an excel sheet. The excel sheet shows a change of logistics and transportation cost. Also transportation unit cost is easily changed in the excel sheet. The scopes of the report are explanation of parameters in the CASK program and a preliminary calculation. We have developed the CASK version 1.0 so far, and will update its parameters in transportation cost and transportation scenario. Also, we will incorporate it into the program which is used for the projection of spent fuels from the nuclear power plants. Finally, it is expected that the CASK program could be a part of the cost estimation tools which are under development at KAERI. And this program will be a very useful tool for the establishment of transportation scenario and transportation cost in Korean situations

Interim report on long range plan for nuclear physics

International Nuclear Information System (INIS)

Anon.

1995-01-01

The interim report on the updated NSAC Long Range Plan for Nuclear Physics will be presented to the community for discussion and comment before submission to the funding agencies. The presentation will be coordinated by E. Moniz chair of NSAC

Characterization of void volume VOC concentration in vented TRU waste drums - an interim report

International Nuclear Information System (INIS)

Liekhus, K.J.

1994-09-01

A test program is underway at the Idaho National Engineering Laboratory to determine if the concentration of volatile organic compounds (VOCs) in the drum headspace is representative of the VOC concentration in the entire drum void space and to demonstrate that the VOC concentration in the void space of each layer of confinement can be estimated using a model incorporating diffusion and permeation transport principles and limited waste drum sampling data. An experimental test plan was developed requiring gas sampling of 66 transuranic (TRU) waste drums. This interim report summarizes the experimental measurements and model predictions of VOC concentration in the innermost layer of confinement from waste drums sampled and analyzed in FY 1994

Design requirements document for Project W-465, immobilized low-activity waste interim storage

International Nuclear Information System (INIS)

Burbank, D.A.

1998-01-01

The scope of this Design Requirements Document (DRD) is to identify the functions and associated requirements that must be performed to accept, transport, handle, and store immobilized low-activity waste (ILAW) produced by the privatized Tank Waste Remediation System (TWRS) treatment contractors. The functional and performance requirements in this document provide the basis for the conceptual design of the TWRS ILAW Interim Storage facility project and provides traceability from the program level requirements to the project design activity. Technical and programmatic risk associated with the TWRS planning basis are discussed in the Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The design requirements provided in this document will be augmented by additional detailed design data documented by the project

How to Get Hearing Aids

Science.gov (United States)

... if desired. What questions should I ask before buying hearing aids? Before you buy a hearing aid, ... the period of warranty? Does the warranty cover future maintenance and repairs? Will loaner aids be provided ...

Tank Farm Interim Surface Barrier Materials And Runoff Alternatives Study

International Nuclear Information System (INIS)

Holm, M.J.

2009-01-01

This report identifies candidate materials and concepts for interim surface barriers in the single-shell tank farms. An analysis of these materials for application to the TY tank farm is also provided.

Development of Accident Scenario for Interim Spent Fuel Storage Facility Based on Fukushima Accident

Energy Technology Data Exchange (ETDEWEB)

Lee, Dongjin; Choi, Kwangsoon; Yoon, Hyungjoon; Park, Jungsu [KEPCO-E and C, Yongin (Korea, Republic of)

2014-05-15

700 MTU of spent nuclear fuel is discharged from nuclear fleet every year and spent fuel storage is currently 70.9% full. The on-site wet type spent fuel storage pool of each NPP(nuclear power plants) in Korea will shortly exceed its storage limit. Backdrop, the Korean government has rolled out a plan to construct an interim spent fuel storage facility by 2024. However, the type of interim spent fuel storage facility has not been decided yet in detail. The Fukushima accident has resulted in more stringent requirements for nuclear facilities in case of beyond design basis accidents. Therefore, there has been growing demand for developing scenario on interim storage facility to prepare for beyond design basis accidents and conducting dose assessment based on the scenario to verify the safety of each type of storage.

Model for low temperature oxidation during long term interim storage

Energy Technology Data Exchange (ETDEWEB)

Desgranges, Clara; Bertrand, Nathalie; Gauvain, Danielle; Terlain, Anne [Service de la Corrosion et du Comportement des Materiaux dans leur Environnement, CEA/Saclay - 91191 Gif-sur-Yvette Cedex (France); Poquillon, Dominique; Monceau, Daniel [CIRIMAT UMR 5085, ENSIACET-INPT, 31077 Toulouse Cedex 4 (France)

2004-07-01

For high-level nuclear waste containers in long-term interim storage, dry oxidation will be the first and the main degradation mode during about one century. The metal lost by dry oxidation over such a long period must be evaluated with a good reliability. To achieve this goal, modelling of the oxide scale growth is necessary and this is the aim of the dry oxidation studies performed in the frame of the COCON program. An advanced model based on the description of elementary mechanisms involved in scale growth at low temperatures, like partial interfacial control of the oxidation kinetics and/or grain boundary diffusion, is developed in order to increase the reliability of the long term extrapolations deduced from basic models developed from short time experiments. Since only few experimental data on dry oxidation are available in the temperature range of interest, experiments have also been performed to evaluate the relevant input parameters for models like grain size of oxide scale, considering iron as simplified material. (authors)

Model for low temperature oxidation during long term interim storage

International Nuclear Information System (INIS)

Desgranges, Clara; Bertrand, Nathalie; Gauvain, Danielle; Terlain, Anne; Poquillon, Dominique; Monceau, Daniel

2004-01-01

For high-level nuclear waste containers in long-term interim storage, dry oxidation will be the first and the main degradation mode during about one century. The metal lost by dry oxidation over such a long period must be evaluated with a good reliability. To achieve this goal, modelling of the oxide scale growth is necessary and this is the aim of the dry oxidation studies performed in the frame of the COCON program. An advanced model based on the description of elementary mechanisms involved in scale growth at low temperatures, like partial interfacial control of the oxidation kinetics and/or grain boundary diffusion, is developed in order to increase the reliability of the long term extrapolations deduced from basic models developed from short time experiments. Since only few experimental data on dry oxidation are available in the temperature range of interest, experiments have also been performed to evaluate the relevant input parameters for models like grain size of oxide scale, considering iron as simplified material. (authors)

Ad interim legal remedy in case of large projects

International Nuclear Information System (INIS)

Limberger, J.

1985-01-01

Action for ad interim judicial relief in response to large projects approved of by the authorities very frequently take several years until a decision is taken by the court. Experience has shown that this applies in particular to large projects such as the construction of nuclear power plants, large-size industrial plants, or airports. It has become regular practice by the authorities concerned to issue an order for immediate execution upon the plan approving decision and granting of licence for said projects, in accordance with section 80, sub-section (2), no.4 of the VwGO. The problems thus created with regard to interim legal remedy sought by the parties concerned are of great significance. The book in hand discusses the question as to whether the practice of the administrative authorities and the courts satisfies the requirements embodied in the law, to provide for efficient legal protection. (orig./HSCH) [de

49 CFR 37.169 - Interim requirements for over-the-road bus service operated by private entities.

Science.gov (United States)

2010-10-01

... of such devices, shall be permitted in the passenger compartment. When the bus is at rest at a stop... 49 Transportation 1 2010-10-01 2010-10-01 false Interim requirements for over-the-road bus service... Interim requirements for over-the-road bus service operated by private entities. (a) Private entities...

75 FR 7591 - Guidance on Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA and...

Science.gov (United States)

2010-02-22

... ENVIRONMENTAL PROTECTION AGENCY [EPA-HQ-SFUND-2009-0907; FRL-9114-6] RIN 2050-ZA05 Guidance on Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA and RCRA Sites; Extension of... Interim Preliminary Remediation Goals for Dioxin in Soil at Comprehensive Environmental Response...

Individual shareholders’ understanding of the content of interim reports of South African listed retail companies

Directory of Open Access Journals (Sweden)

Johan GI Oberholster

2015-05-01

Full Text Available A number of studies conducted, and reports published, by international and local accounting bodies have found that the proliferation of disclosures in financial reports has hampered users’ understanding of these reports. The reports by accounting bodies also indicate that these users prefer more concise financial reports. These findings, in conjunction with a dearth of recent questionnaire-based research on whether individual shareholders understand the content of financial reports, resulted in this study on whether individual shareholders understand the content of interim reports. The study provides empirical proof that a sound knowledge of business, accounting and economic matters is a prerequisite for understanding interim reports in the case of individual shareholders. The results of the study indicate that individual shareholders have a limited understanding of the content of interim reports as a whole, and that a good knowledge of business and economic matters and of accounting results in an improved understanding of the content of interim reports. In particular, specialisation in accounting in undergraduate and postgraduate degrees, professional qualifications, and work experience in the financial field improve the understanding of individual shareholders.

Strategic Review of Medical Training and Career Structure Interim Report

OpenAIRE

Department of Health (Ireland)

2013-01-01

Click here to download Strategic Review of Medical Training and Career Structure Interim Report PDF 44kb Click here to download Strategic Review of Medical Training and Career Structure Terms of Reference PDF 59KB

75 FR 43329 - Interim Final Rules for Group Health Plans and Health Insurance Issuers Relating to Internal...

Science.gov (United States)

2010-07-23

... 45 CFR Part 147 Interim Final Rules for Group Health Plans and Health Insurance Issuers Relating to... Interim Final Rules for Group Health Plans and Health Insurance Issuers Relating to Internal Claims and... of Labor; Office of Consumer Information and Insurance Oversight, Department of Health and Human...

Hazelwood Interim Storage Site environmental report for calendar year 1992, 9200 Latty Avenue, Hazelwood, Missouri

International Nuclear Information System (INIS)

1993-05-01

This report describes the environmental surveillance program at the Hazelwood Interim storage Site (HISS) and surrounding area, provides the results for 1992, and discusses applicable environmental standards and requirements with which the results were compared. HISS is located in eastern Missouri in the City of Hazelwood (St. Louis County) and occupies approximately 2.2 ha (5.5 acres). Environmental monitoring of HISS began in 1984 when the site was assigned to the US Department of Energy (DOE) as part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Development Appropriations Act. DOE placed responsibility for HISS under the Formerly Utilized Sites Remedial Action Program (FUSRAP), which was established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. In 1992 there were no environmental occurrences or unplanned contaminant releases as defined in DOE requirements and in the Superfund Amendment and Reauthorization Act (SARA) Title III of CERCLA

Hazelwood Interim Storage Site environmental report for calendar year 1992, 9200 Latty Avenue, Hazelwood, Missouri

Energy Technology Data Exchange (ETDEWEB)

1993-05-01

This report describes the environmental surveillance program at the Hazelwood Interim storage Site (HISS) and surrounding area, provides the results for 1992, and discusses applicable environmental standards and requirements with which the results were compared. HISS is located in eastern Missouri in the City of Hazelwood (St. Louis County) and occupies approximately 2.2 ha (5.5 acres). Environmental monitoring of HISS began in 1984 when the site was assigned to the US Department of Energy (DOE) as part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Development Appropriations Act. DOE placed responsibility for HISS under the Formerly Utilized Sites Remedial Action Program (FUSRAP), which was established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation`s atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. In 1992 there were no environmental occurrences or unplanned contaminant releases as defined in DOE requirements and in the Superfund Amendment and Reauthorization Act (SARA) Title III of CERCLA.

Report on the long-term interim storage of spent fuels and vitrified wastes; Gutachten zur Langzeitzwischenlagerung abgebrannter Brennelemente und verglaster Abfaelle

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-12-03

Long-term interim storage for several hundred years is an option on the management of high-level radioactive wastes. The decision on final disposal is postponed. Worldwide the long-term interim storage is not part of the disposal concept - a geologic final repository is the ultimate aim. Using today's technology the interim storage over several hundred years is supposed to be uncritical. Aging management is the most important challenge - the renewal of the facilities would have to be expected. Possible social change and their impact on the interim storage problem has not been considered.

46 CFR 308.303 - Amounts insured under interim binder.

Science.gov (United States)

2010-10-01

... 308.303 Shipping MARITIME ADMINISTRATION, DEPARTMENT OF TRANSPORTATION EMERGENCY OPERATIONS WAR RISK INSURANCE Second Seamen's War Risk Insurance § 308.303 Amounts insured under interim binder. The amounts insured are the amounts specified in the Second Seamen's War Risk Policy (1955) or as modified by shipping...

78 FR 48035 - Conservation Reserve Program, Re-Enrollment

Science.gov (United States)

2013-08-07

... longstanding USDA policy and existing handbooks. This technical amendment did not require Office of Management... Reserve Program (CRP) regulations to clarify that land with use restrictions that prohibit the production... other deed restrictions that restrict the production of agricultural commodities. A 2003 interim rule...

A Procedure for Structural Weight Estimation of Single Stage to Orbit Launch Vehicles (Interim User's Manual)

Science.gov (United States)

Martinovic, Zoran N.; Cerro, Jeffrey A.

2002-01-01

This is an interim user's manual for current procedures used in the Vehicle Analysis Branch at NASA Langley Research Center, Hampton, Virginia, for launch vehicle structural subsystem weight estimation based on finite element modeling and structural analysis. The process is intended to complement traditional methods of conceptual and early preliminary structural design such as the application of empirical weight estimation or application of classical engineering design equations and criteria on one dimensional "line" models. Functions of two commercially available software codes are coupled together. Vehicle modeling and analysis are done using SDRC/I-DEAS, and structural sizing is performed with the Collier Research Corp. HyperSizer program.

Assessment report on research and development activities. Activity: 'Advanced science research' (Interim report)

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-11-15

Japan Atomic Energy Agency (hereinafter referred to as 'JAEA') consulted an assessment committee, 'Evaluation Committee of Research Activities for Advanced Science Research' (hereinafter referred to as 'Committee') for interim assessment of 'Advanced Science Research,' in accordance with 'General Guideline for the Evaluation of Government Research and Development (R and D) Activities' by Cabinet Office, Government of Japan, 'Guideline for Evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology' and 'Regulation on Conduct for Evaluation of R and D Activities' by JAEA. In response to the JAEA's request, the Committee assessed the research programs and activities of the Advanced Science Research Center (hereinafter referred to as 'ASRC') for the period of two years from April 2010. The Committee evaluated the management and the research programs of the ASRC based on the explanatory documents prepared by the ASRC and the oral presentations with questions-and-answers by the Director and the research group leaders. This report summarizes the result of the assessment by the Committee with the Committee report attached from page 7. (author)

Sacramento Municipal Utility district's interim onsite storage building for low level radioactive waste

International Nuclear Information System (INIS)

Gillis, E.

1986-01-01

In order to meet current and anticipated needs for the low level radwaste management program at the Rancho Seco Nuclear Generating Station, the Sacramento Municipal Utility District has a design and construction program underway which will provide an onsite interim storage facility that can be expanded in two and one-half year increments. The design approach utilized allows capital investment to be minimized and still provides radwaste management flexibility in anticipation of delays in resolution of the nationwide long term radwaste disposal situation. The facility provides storage and material accountability for all low level radwastes generated by the plant. Wastes are segregated by radioactivity level and are stored in two separate storage areas located within one facility. Lower activity wastes are stored in a lightly shielded structure and handled by lift trucks, while the higher activity wastes are stored in a highly shielded structure and handled remotely by manual bridge crane. The layout of the structure provides for economy of operation and minimizes personnel radiation exposure. Design philosophy and criteria, building layout and systems, estimated costs and construction schedule are discussed

Deep Vadose Zone Treatability Test for the Hanford Central Plateau: Interim Post-Desiccation Monitoring Results

Energy Technology Data Exchange (ETDEWEB)

Truex, Michael J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Oostrom, Martinus [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Strickland, Christopher E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Johnson, Timothy C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Johnson, Christian D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Clayton, Ray E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Chronister, Glen B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2013-09-01

A field test of desiccation is being conducted as an element of the deep vadose zone treatability test program. Desiccation technology relies on removal of water from a portion of the subsurface such that the resultant low moisture conditions inhibit downward movement of water and dissolved contaminants. Previously, a field test report (Truex et al. 2012a) was prepared describing the active desiccation portion of the test and initial post-desiccation monitoring data. Additional monitoring data have been collected at the field test site during the post-desiccation period and is reported herein along with interpretation with respect to desiccation performance. This is an interim report including about 2 years of post-desiccation monitoring data.

Interim radiological safety standards and evaluation procedures for subseabed high-level waste disposal

International Nuclear Information System (INIS)

Klett, R.D.

1997-06-01

The Seabed Disposal Project (SDP) was evaluating the technical feasibility of high-level nuclear waste disposal in deep ocean sediments. Working standards were needed for risk assessments, evaluation of alternative designs, sensitivity studies, and conceptual design guidelines. This report completes a three part program to develop radiological standards for the feasibility phase of the SDP. The characteristics of subseabed disposal and how they affect the selection of standards are discussed. General radiological protection standards are reviewed, along with some new methods, and a systematic approach to developing standards is presented. The selected interim radiological standards for the SDP and the reasons for their selection are given. These standards have no legal or regulatory status and will be replaced or modified by regulatory agencies if subseabed disposal is implemented. 56 refs., 29 figs., 15 tabs

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

Mobile Launch Platform Vehicle Assembly Area (SWMU 056) Biosparge Expansion Interim Measures Work Plan

Science.gov (United States)

Burcham, Michael S.; Daprato, Rebecca C.

2016-01-01

This document presents the design details for an Interim Measure (IM) Work Plan (IMWP) for the Mobile Launch Platform/Vehicle Assembly Building (MLPV) Area, located at the John F. Kennedy Space Center (KSC), Florida. The MLPV Area has been designated Solid Waste Management Unit Number 056 (SWMU 056) under KSC's Resource Conservation and Recovery Act (RCRA) Corrective Action Program. This report was prepared by Geosyntec Consultants (Geosyntec) for the National Aeronautics and Space Administration (NASA) under contract number NNK09CA02B and NNK12CA13B, project control number ENV1642. The Advanced Data Package (ADP) presentation covering the elements of this IMWP report received KSC Remediation Team (KSCRT) approval at the December 2015 Team Meeting; the meeting minutes are included in Appendix A.

Separate issues of rights and obligations of loan agreement parties

Directory of Open Access Journals (Sweden)

О. В. Ночовкіна

2015-05-01

Paper main body. Peculiarities of rights and duties of loan agreement parties mainly connected to gratuitous nature of such relations. The scope and content of rights and duties of the counterparts according to the agreement depends upon its legal structure (real or consensus. At characterization of the loan agreement parties’ duties we should address as to the regulations of Chapter 60 of Ukrainian Civil Law and to the regulations governing hire (rent relations. The Clauses of Chapter 58 of Ukrainian Civil Law shall be applied only if the opposite not determined by Chapter “Loan” and does not contradict gratuitous nature of loan relations. The main responsibility of the loaner according to the agreement is the transfer of piece of property to a user for gratuitous usage. At real transaction the loaner performs this function at the moment of agreement conclusion. At consensus model of transaction the duty of the loaner to transfer piece of property arise first of all.Conclusions. In order to improve legal regulation of certain duties of loan agreement parties we should: 1 in legal regulations to determine such terms as “ordinary costs”, “capital repairs” and “minor repairs”; 2 we should clearly indicate which regulations of Clause 58 “Hire(rent” can be applied to govern the loan agreement. Such improvement will allow to eliminate any disputes at allocation of rights and duties of the parties during insurance of loaned property, at repair of property and reimbursement of repair expenses.

Development of dual-purpose metal cask for interim storage of spent nuclear fuel (1). Outline of cask structure

International Nuclear Information System (INIS)

Shimizu, Masashi; Hayashi, Makoto; Kashiwakura, Jun

2003-01-01

Spent fuels discharged from nuclear power plants in Japan are planed to be reprocessed at the nuclear fuel recycle plant under construction at Rokkasho-mura. Since the amount of the spent fuels exceeds that of recycled fuel, the spent fuels have to be properly stored and maintained as recycle fuel resource until the beginning of the reprocessing. For that sake, interim storage installations are being constructed outside the nuclear power plants by 2010. The storage dry casks have been practically used as the interim storage in the nuclear power plants. From this reason, the storage system using the storage dry casks is promising as the interim storage installations away form the reactors, which are under discussion. In the interim storage facilities, the storage using the dry cask of the storage metal cask with business showings, having the function of transportation is now under discussion. By employing transportation and storage dual-purpose cask, the repack equipments can be exhausted, and the reliability of the interim storage installations can be increased. Hitachi, Ltd. has been developing the high reliable and economical transportation and storage dry metal cask. In this report, the outline of our developing transportation and storage dry cask is described. (author)

Success of Two-Stage Reimplantation in Patients Requiring an Interim Spacer Exchange.

Science.gov (United States)

George, Jaiben; Miller, Evan M; Curtis, Gannon L; Klika, Alison K; Barsoum, Wael K; Mont, Michael A; Higuera, Carlos A

2018-03-23

Some patients undergoing a 2-stage revision for a periprosthetic joint infection require a repeat spacer in the interim (removal of existing spacer with insertion of a new spacer or spacer exchange) due to persistent infection. The objectives of this study are to (1) determine the factors associated with patients who receive a repeat spacer and (2) compare the infection-free survival (overall and stratified by joint type) of reimplantation in patients who did or did not receive a repeat spacer. From 2001 to 2014, 347 hip or knee 2-stage revisions that finally underwent reimplantation and had a minimum 2-year follow-up were identified. An interim spacer exchange was performed in 59 (17%) patients (exchange cohort). Patient-related and organism-related factors were compared between the exchange and non-exchange cohorts. Kaplan-Meier survival curves were performed to assess the success (absence of signs of infection, reoperation for infection, periprosthetic joint infection-related mortality) of both cohorts. Patients in the exchange group had higher comorbidity score (P = .020), prolonged time to reimplantation (P exchange cohort, and 78% (knee 77%, hip 78%) in the non-exchange cohort (P = .020). Patients requiring an interim spacer exchange were found to have more comorbidities, prolonged treatment period, and were more likely to be infected with a resistant organism. About one-third of such patients became reinfected within 5 years compared to only one-fifth of the patients without an interim spacer exchange. Copyright © 2018 Elsevier Inc. All rights reserved.

7 CFR 1710.109 - Reimbursement of general funds and interim financing.

Science.gov (United States)

2010-01-01

... LOANS AND GUARANTEES Loan Purposes and Basic Policies § 1710.109 Reimbursement of general funds and... replace interim financing used to finance equipment and facilities that were included in an RUS-approved...

Interim supply in the electricity industry

Energy Technology Data Exchange (ETDEWEB)

Strassburg, W

1977-06-01

The interim supply or the so-called 'condition without a contract' can occur within the framework of energy supply in the relationship between 1) public utility and tariff customer, 2) public utility and the special last-in-line consumer, 3) supplying and distributing public utility, 4) public utility and territorial administrative body. The present contribution deals with the cases named under (3) and (4). Cases (1) and (2) were dealt with in a previous article. Relevant contract clauses and laws and their effects on contracting partners are discussed.

Interim supply in the electricity industry

Energy Technology Data Exchange (ETDEWEB)

Strassburg, W

1977-05-01

The interim supply or the so-called 'condition without a contract' can occur within the framework of energy supply in the relationship between: 1) public utility and tariff customer, 2) public utility and the special last-in-line consumer, 3) supplying and distributing public utility, 4) public utility and territorial administrative body. The contribution at hand deals with the cases under 1) and 2); cases 3) and 4) are dealt with in an article to be published. Relevant contract clauses and laws and their effects on contracting partners are discussed. 41 references.

Central waste complex interim safety basis

International Nuclear Information System (INIS)

Cain, F.G.

1995-01-01

This interim safety basis provides the necessary information to conclude that hazards at the Central Waste Complex are controlled and that current and planned activities at the CWC can be conducted safely. CWC is a multi-facility complex within the Solid Waste Management Complex that receives and stores most of the solid wastes generated and received at the Hanford Site. The solid wastes that will be handled at CWC include both currently stored and newly generated low-level waste, low-level mixed waste, contact-handled transuranic, and contact-handled TRU mixed waste

33 CFR 96.360 - Interim Safety Management Certificate: what is it and when can it be used?

Science.gov (United States)

2010-07-01

...? § 96.360 Interim Safety Management Certificate: what is it and when can it be used? (a) A responsible... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Interim Safety Management Certificate: what is it and when can it be used? 96.360 Section 96.360 Navigation and Navigable Waters COAST...

Harvard University Program on Technology and Society 1964-1972. A Final Review.

Science.gov (United States)

Harvard Univ., Cambridge, MA. Program on Technology and Society.

Eight years of research by the Harvard University's Program on Technology and Society are summarized. Lengthy abstracts of the 29 books and 164 articles that resulted from the Program, as well as interim accounts of projects not yet completed are presented. The report is divided into four parts; institutions (including business, education, and…

Manipulation of natural subsurface processes: Field research and validation. Interim report

International Nuclear Information System (INIS)

Fruchter, J.S.; Spane, F.A.; Amonette, J.E.

1994-11-01

Often the only alternative for treating deep subsurface contamination is in situ manipulation of natural processes to change the mobility or form of contaminants. However, the complex interactions of natural subsurface physical, chemical, and microbial processes limit the predictability of the system-wide impact of manipulation based on current knowledge. This report is a summary of research conducted to examine the feasibility of controlling the oxidation-reduction (redox) potential of the unconfined aquifer at the Hanford Site in southeastern Washington State by introducing chemical reagents and microbial nutrients. The experiment would allow the testing of concepts and hypotheses developed from fundamental research in the US Department of Energy's (DOE's) Subsurface Science Program. Furthermore, the achievement of such control is expected to have implications for in situ remediation of dispersed aqueous contaminants in the subsurface environment at DOE sites nationwide, and particularly at the Hanford Site. This interim report summarizes initial research that was conducted between July 1990 and October 1991

Recommendations concerning an interim annual individual exposure limit for respirable quartz

International Nuclear Information System (INIS)

Stocker, H.; Horvath, F.J.; Napier, W.

1983-07-01

This paper presents AECB staff recommendations on the desirability of an annual individual occupational exposure limit for respirable quartz and on the magnitude of this limit, for uranium miners. Justifications are presented for the magnitude of this suggested limit for respirable quartz, drawing on experience gained in Ontario uranium and non-uranium mines and on that in other countries. The suggestion is made that an exposure limit be set for an interim period in order that additional information on the adequacy of the magnitude of the limit may be acquired. To complement the suggested exposure limit, it is proposed that a co-existing control program of action levels, to be triggered at various respirable quartz concentrations, be set up. It is the contention of this paper that the degree of protection afforded to individuals by the suggested exposure limit would be equivalent to the time-weighted average threshold limit value derived from recommendations, based on group average exposures, of the American Conference of Governmental Industrial Hygienists

Interim geotechnical data report

International Nuclear Information System (INIS)

1986-01-01

This issue, the Interim Geotechnical Field Data Report, presents information obtained from the geotechnical activities at the WIPP site underground facilities since the last quarterly report. It also includes cumulative plots which contain all previous data. Finally, it continues the geotechnical analyses and interpretations of the data. The GFDR is organized into two principal parts. The first part, Geotechnical Field Data, presents in graphical form all the data collected since April 1982 from the geomechanical instruments. Presented in the second part, Evaluation and Analyses, are preliminary interpretations and analyses of the data. In this report, continuing geotechnical assessment of all the facility features is presented. Also included in the second part are separate sections on evaluation and interpretation of the instrumentation measurements, and an updated description and evaluation of observed behavior of the underground openings

Interim results from UO2 fuel oxidation tests in air

International Nuclear Information System (INIS)

Campbell, T.K.; Gilbert, E.R.; Thornhill, C.K.; White, G.D.; Piepel, G.F.; Griffin, C.W.j.

1987-08-01

An experimental program is being conducted at Pacific Northwest Laboratory (PNL) to extend the characterization of spent fuel oxidation in air. To characterize oxidation behavior of irradiated UO 2 , fuel oxidation tests were performed on declad light-water reactor spent fuel and nonirradited UO 2 pellets in the temperature range of 135 to 250 0 C. These tests were designed to determine the important independent variables that might affect spent fuel oxidation behavior. The data from this program, when combined with the test results from other programs, will be used to develop recommended spent fuel dry-storage temperature limits in air. This report describes interim test results. The initial PNL investigations of nonirradiated and spent fuels identified the important testing variables as temperature, fuel burnup, radiolysis of the air, fuel microstructure, and moisture in the air. Based on these initial results, a more extensive statistically designed test matrix was developed to study the effects of temperature, burnup, and moisture on the oxidation behavior of spent fuel. Oxidation tests were initiated using both boiling-water reactor and pressurized-water reactor fuels from several different reactors with burnups from 8 to 34 GWd/MTU. A 10 5 R/h gamma field was applied to the test ovens to simulate dry storage cask conditions. Nonirradiated fuel was included as a control. This report describes experimental results from the initial tests on both the spent and nonirradiated fuels and results to date on the tests in a 10 5 R/h gamma field. 33 refs., 51 figs., 6 tabs

2005 Annual Operations Report for INTEC Operable Unit 3-13, Group 1, Tank Farm Interim Action

International Nuclear Information System (INIS)

D. Shanklin

2006-01-01

This annual operations report describes the requirements followed and activities conducted to inspect, monitor, and maintain the items installed during performance of the Waste Area Group 3, Operable Unit 3-13, Group 1, Tank Farm Interim Action, at the Idaho Nuclear Technology and Engineering Center. This report describes inspection and monitoring activities for the surface-sealed areas within the tank farm, concrete-lined ditches and culverts in and around the tank farm, the lift station, and the lined evaporation pond. These activities are intended to assure that the interim action is functioning adequately to meet the objectives stated in the Operable Unit 3-13, Record of Decision for the Group 1, Tank Farm Interim Action, (DOE/ID-10660) and as amended by the agreement to resolve dispute, which was effective in February 2003

75 FR 59105 - Procedures for Transportation Workplace Drug and Alcohol Testing Programs: Federal Drug Testing...

Science.gov (United States)

2010-09-27

... 2105-AE03 Procedures for Transportation Workplace Drug and Alcohol Testing Programs: Federal Drug... the Federal workplace drug testing program but also pointed out that ``* * * the Department of.... Executive Order 12866 and Regulatory Flexibility Act This Interim Final Rule is not significant for purposes...

Interim Stabilization Equipment Essential and Support Drawing Plan

International Nuclear Information System (INIS)

KOCH, M.R.

1999-01-01

The purpose of this document is to list the Interim Stabilization equipment drawings that are classified as Essential or Support drawings. Essential Drawings: Those drawings identified by the facility staff as necessary to directly support the safe operation of the facility or equipment. Support Drawings: Those drawings identified by the facility staff that further describe the design details of structures, systems or components shown on essential drawings

Effectiveness Monitoring Report, MWMF Tritium Phytoremediation Interim Measures.

Energy Technology Data Exchange (ETDEWEB)

Hitchcock, Dan; Blake, John, I.

2003-02-10

This report describes and presents the results of monitoring activities during irrigation operations for the calendar year 2001 of the MWMF Interim Measures Tritium Phytoremediation Project. The purpose of this effectiveness monitoring report is to provide the information on instrument performance, analysis of CY2001 measurements, and critical relationships needed to manage irrigation operations, estimate efficiency and validate the water and tritium balance model.

Environmental survey of two interim dumpsites, Middle Atlantic Bight from 05 November 1973 to 10 November 1973 (NODC Accession 7501280)

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — A second oceanographic survey cruise was made to an interim municipal sludge dumpsite and initially to an interim dumpsite for the disposal of industrial acid waste...

Final hazard classification and auditable safety analysis for the 105-C Reactor Interim Safe Storage Project

International Nuclear Information System (INIS)

Rodovsky, T.J.; Larson, A.R.; Dexheimer, D.

1996-12-01

This document summarizes the inventories of radioactive and hazardous materials present in the 105-C Reactor Facility and the operations associated with the Interim Safe Storage Project which includes decontamination and demolition and interim safe storage of the remaining facility. This document also establishes a final hazard classification and verifies that appropriate and adequate safety functions and controls are in place to reduce or mitigate the risk associated with those operations

Overview of management programs for plutonium-contaminated solid waste in the U.S.A

International Nuclear Information System (INIS)

Ramsey, R.W. Jr.; Daly, G.H.

1975-01-01

Programs for transuranium-contaminated solid wastes (TRU) in the U.S.A. are emphasizing a reduction in waste generation and the development of appropriate treatments to reduce the volume of wastes requiring interim storage and final disposal. Research and Development is emphasizing the establishment of sufficient information on treatment, hazards and storage to adopt a standardized procedure for handling wastes during an interim retrievable period and for final disposal. Federal responsibility for TRU waste is being proposed except for minimum amounts acceptable for commercial burial

BE (fuel element)/ZL (interim storage facility) module. Constituents of the fuel BE data base for BE documentation with respect to the disposal planning and the support of the BE container storage administration

International Nuclear Information System (INIS)

Hoffmann, V.; Deutsch, S.; Busch, V.; Braun, A.

2012-01-01

The securing of spent fuel element disposal from German nuclear power plants is the main task of GNS. This includes the container supply and the disposal analysis and planning. Therefore GNS operates a data base comprising all in Germany implemented fuel elements and all fuel element containers in interim storage facilities. With specific program modules the data base serves an optimized repository planning for all spent fuel elements from German NPPS and the supply of required data for future final disposal. The data base has two functional models: the BE (fuel element) and the ZL (interim storage) module. The contribution presents the data structure of the modules and details of the data base operation.

Kennedy Space Center Press Site (SWMU 074) Interim Measure Report

Science.gov (United States)

Applegate, Joseph L.

2015-01-01

This report summarizes the Interim Measure (IM) activities conducted at the Kennedy Space Center (KSC) Press Site ("the Press Site"). This facility has been designated as Solid Waste Management Unit 074 under KSC's Resource Conservation and Recovery Act Corrective Action program. The activities were completed as part of the Vehicle Assembly Building (VAB) Area Land Use Controls Implementation Plan (LUCIP) Elimination Project. The purpose of the VAB Area LUCIP Elimination Project was to delineate and remove soil affected with constituents of concern (COCs) that historically resulted in Land Use Controls (LUCs). The goal of the project was to eliminate the LUCs on soil. LUCs for groundwater were not addressed as part of the project and are not discussed in this report. This report is intended to meet the Florida Department of Environmental Protection (FDEP) Corrective Action Management Plan requirement as part of the KSC Hazardous and Solid Waste Amendments permit and the U.S. Environmental Protection Agency's (USEPA's) Toxic Substance Control Act (TSCA) self-implementing polychlorinated biphenyl (PCB) cleanup requirements of 40 Code of Federal Regulations (CFR) 761.61(a).

Acceptance criteria for interim dry storage of aluminum-clad fuels

International Nuclear Information System (INIS)

Sindelar, R.L.; Peacock, H.B. Jr.; Iyer, N.C.; Louthan, M.R. Jr.

1994-01-01

Direct repository disposal of foreign and domestic research reactor fuels owned by the United States Department of Energy is an alternative to reprocessing (together with vitrification of the high level waste and storage in an engineered barrier) for ultimate disposition. Neither the storage systems nor the requirements and specifications for acceptable forms for direct repository disposal have been developed; therefore, an interim storage strategy is needed to safely store these fuels. Dry storage (within identified limits) of the fuels received from wet-basin storage would avoid excessive degradation to assure post-storage handleability, a full range of ultimate disposal options, criticality safety, and provide for maintaining confinement by the fuel/clad system. Dry storage requirements and technologies for US commercial fuels, specifically zircaloy-clad fuels under inert cover gas, are well established. Dry storage requirements and technologies for a system with a design life of 40 years for dry storage of aluminum-clad foreign and domestic research reactor fuels are being developed by various groups within programs sponsored by the DOE

High Temperature Materials Interim Data Qualification Report

International Nuclear Information System (INIS)

Lybeck, Nancy

2010-01-01

Projects for the very high temperature reactor (VHTR) Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are qualified for use, stored in a readily accessible electronic form, and analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the High Temperature Materials characterization data stream, the processing of these data within NDMAS, and reports the interim FY2010 qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. The High Temperature Materials data are being collected under NQA-1 guidelines, and will be qualified data. For NQA-1 qualified data, the qualification activities include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing to confirm that the data are an accurate representation of the system or object being measured, and (3) documenting that the data were collected under an NQA-1 or equivalent Quality Assurance program. Currently, data from two test series within the High Temperature Materials data stream have been entered into the NDMAS vault: (1) Tensile Tests for Sm (i.e., Allowable Stress) Confirmatory Testing - 1,403,994 records have been inserted into the NDMAS database. Capture testing is in process. (2) Creep-Fatigue Testing to Support Determination of Creep-Fatigue Interaction Diagram - 918,854 records have been processed and inserted into the NDMAS database. Capture testing is in process.

Next Generation Melter Optioneering Study - Interim Report

International Nuclear Information System (INIS)

Gray, M.F.; Calmus, R.B.; Ramsey, G.; Lomax, J.; Allen, H.

2010-01-01

The next generation melter (NOM) development program includes a down selection process to aid in determining the recommended vitrification technology to implement into the WTP at the first melter change-out which is scheduled for 2025. This optioneering study presents a structured value engineering process to establish and assess evaluation criteria that will be incorporated into the down selection process. This process establishes an evaluation framework that will be used progressively throughout the NGM program, and as such this interim report will be updated on a regular basis. The workshop objectives were achieved. In particular: (1) Consensus was reached with stakeholders and technology providers represented at the workshop regarding the need for a decision making process and the application of the D 2 0 process to NGM option evaluation. (2) A framework was established for applying the decision making process to technology development and evaluation between 2010 and 2013. (3) The criteria for the initial evaluation in 2011 were refined and agreed with stakeholders and technology providers. (4) The technology providers have the guidance required to produce data/information to support the next phase of the evaluation process. In some cases it may be necessary to reflect the data/information requirements and overall approach to the evaluation of technology options against specific criteria within updated Statements of Work for 2010-2011. Access to the WTP engineering data has been identified as being very important for option development and evaluation due to the interface issues for the NGM and surrounding plant. WRPS efforts are ongoing to establish precisely data that is required and how to resolve this Issue. It is intended to apply a similarly structured decision making process to the development and evaluation of LAW NGM options.

Surface Water Interim Measures/Interim Remedial Action Plan/ Environmental and Decision Document, South Walnut Creek Basin, Operable Unit No.2

International Nuclear Information System (INIS)

1991-01-01

Water quality investigations have identified the presence of volatile organic compound (VOC) and radionuclide contamination of surface water at the Rocky Flats Plant (RFP). The subject interim Measures/Interim Remedial Action Plan/Environmental Assessment (IM/IRAP/EA) addresses contaminated surface water in a portion of the South Walnut Creek drainage basin located within an area identified as Operable Unit No. 2 (OU 2). There is no immediate threat to public health and the environment posed by this surface water contamination. The affected surface water is contained within the plant boundary by existing detention ponds, and is treated prior to discharge for removal of volatile contaminants and suspended particulates to which radionuclides, if present, are likely to absorb. However, there is a potential threat and the Department of Energy (DOE) is implementing this Surface Water IM/IRAP at the request of the US Environmental Protection Agency (EPA) and Colorado Department of Health (CDH). Implementation of the Surface Water IM/IRA will enhance the DOE's efforts towards containing and managing contaminated surface water, and will mitigate downgradient migration of contaminants. Another factor in implementing this IM/IRA is the length of time it will take to complete the investigations and engineering studies necessary to determine the final remedy for OU 2. 44 refs., 23 figs., 14 tabs

Early rehabilitation of facial defects using interim removable prostheses: A clinical case report

Directory of Open Access Journals (Sweden)

Vivekanandhan Ramkumar

2013-01-01

Full Text Available Surgical resection of neoplasms or malformations of the face may result in defects that are not amenable to immediate surgical reconstruction. Such defects can have a severe adverse effect on patient perceptions of body image and self-esteem. In these cases, the use of an interim removable facial prosthesis can offer a rapid alternative treatment solution. The patient may then resume social interactions more comfortably while permitting easy access to the facial defect to observe tissue healing while awaiting definitive rehabilitation. This article presents a case report describing the use of interim nasal prostheses to provide rapid patient rehabilitation of facial defects.

Basis for Interim Operation for the K-Reactor in Cold Standby

Energy Technology Data Exchange (ETDEWEB)

Shedrow, B.

1998-10-19

The Basis for Interim Operation (BIO) document for K Reactor in Cold Standby and the L- and P-Reactor Disassembly Basins was prepared in accordance with the draft DOE standard for BIO preparation (dated October 26, 1993).

Basis for Interim Operation for the K-Reactor in Cold Standby

International Nuclear Information System (INIS)

Shedrow, B.

1998-01-01

The Basis for Interim Operation (BIO) document for K Reactor in Cold Standby and the L- and P-Reactor Disassembly Basins was prepared in accordance with the draft DOE standard for BIO preparation (dated October 26, 1993)

Overview: Defense high-level waste technology program

International Nuclear Information System (INIS)

Shupe, M.W.; Turner, D.A.

1987-01-01

Defense high-level waste generated by atomic energy defense activities is stored on an interim basis at three U.S. Department of Energy (DOE) operating locations; the Savannah River Plant in South Carolina, the Hanford Site in Washington, and the Idaho National Engineering Laboratory in Idaho. Responsibility for the permanent disposal of this waste resides with DOE's Office of Defense Waste and Transportation Management. The objective of the Defense High-Level Wast Technology Program is to develop the technology for ending interim storage and achieving permanent disposal of all U.S. defense high-level waste. New and readily retrievable high-level waste are immobilized for disposal in a geologic repository. Other high-level waste will be stabilized in-place if, after completion of the National Environmental Policy Act (NEPA) process, it is determined, on a site-specific basis, that this option is safe, cost effective and environmentally sound. The immediate program focus is on implementing the waste disposal strategy selected in compliance with the NEPA process at Savannah River, while continuing progress toward development of final waste disposal strategies at Hanford and Idaho. This paper presents an overview of the technology development program which supports these waste management activities and an assessment of the impact that recent and anticipated legal and institutional developments are expected to have on the program

Lessons learned from the Siting Process of an Interim Storage Facility in Spain - 12024

Energy Technology Data Exchange (ETDEWEB)

Lamolla, Meritxell Martell [MERIENCE Strategic Thinking, 08734 Olerdola, Barcelona (Spain)

2012-07-01

On 29 December 2009, the Spanish government launched a site selection process to host a centralised interim storage facility for spent fuel and high-level radioactive waste. It was an unprecedented call for voluntarism among Spanish municipalities to site a controversial facility. Two nuclear municipalities, amongst a total of thirteen municipalities from five different regions, presented their candidatures to host the facility in their territories. For two years the government did not make a decision. Only in November 30, 2011, the new government elected on 20 November 2011 officially selected a non-nuclear municipality, Villar de Canas, for hosting this facility. This paper focuses on analysing the factors facilitating and hindering the siting of controversial facilities, in particular the interim storage facility in Spain. It demonstrates that involving all stakeholders in the decision-making process should not be underestimated. In the case of Spain, all regional governments where there were candidate municipalities willing to host the centralised interim storage facility, publicly opposed to the siting of the facility. (author)

System Specification for Immobilized High-Level Waste Interim Storage

International Nuclear Information System (INIS)

CALMUS, R.B.

2000-01-01

This specification establishes the system-level functional, performance, design, interface, and test requirements for Phase 1 of the IHLW Interim Storage System, located at the Hanford Site in Washington State. The IHLW canisters will be produced at the Hanford Site by a Selected DOE contractor. Subsequent to storage the canisters will be shipped to a federal geologic repository

Interim safety basis compliance matrix for Trenches 31 and 34

International Nuclear Information System (INIS)

Ames, R.R.

1994-01-01

The tables provided in this document identify the specific requirements and basis for the administrative controls established in the Westinghouse Hanford Company (WHC) Solid Waste Burial Ground (SWBG) Interim Safety Basis (ISB) for operation of the Project W-025, Mixed Waste Lined Landfill (Trenches 31 and 34). The tables document the necessary controls and implementing procedures to ensure compliance with the requirements of the ISB. These requirements provide a basis for future Unreviewed Safety Questions (USQ) screening of applicable procedure changes, proposed physical modifications, tests, experiments, and occurrences. Table 1 provides the SWBG interim Operational Safety Requirements administrative controls matrix. The specific assumptions and commitments used in the safety analysis documents applicable to disposal of mixed wastes in Trenches 31 and 34 are provided in Table 2. Table 3 is provided to document the potential engineered and administrative mitigating features identified in the Preliminary Hazard Analysis (PHA) for disposal of mixed waste

Colonie Interim Storage Site environmental report for calendar year 1992, 1130 Central Avenue, Colonie, New York

International Nuclear Information System (INIS)

1993-05-01

This report describes the environmental surveillance program at the Colonie Interim Storage Site (CISS) and provides the results for 1992. The site is located in eastern New York State, approximately 6.4 km (4.0 mi) northwest of downtown Albany. From 1958 to 1984, National Lead (NL) Industries used the facility to manufacture various components from depleted and enriched uranium natural thorium. Environmental monitoring of CISS began in 1984 when Congress added, the site to the US Department of Energy's (DOE) Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP is a program established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. The environmental surveillance program at CISS includes sampling networks for external gamma radiation exposure and for thorium-232 and total uranium concentrations in surface water, sediment, and groundwater. Several chemical parameters are also measured in groundwater, including total metals, volatile organics, and water quality parameters. This surveillance program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Results are compared with applicable Environmental Protection Agency (EPA) and New York State Department of Environmental Conservation (NYSDEC) standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements

Cancer early detection program based on awareness and clinical breast examination: Interim results from an urban community in Mumbai, India.

Science.gov (United States)

Gadgil, Anita; Sauvaget, Catherine; Roy, Nobhojit; Muwonge, Richard; Kantharia, Surita; Chakrabarty, Anuradha; Bantwal, Kanchan; Haldar, Indrani; Sankaranarayanan, Rengaswamy

2017-02-01

Indian women with breast cancer are usually diagnosed in advanced stages leading to poor survival. Improving breast awareness and increasing access to early diagnosis and adequate treatment has been advocated for breast cancer control. We implemented a program to increase awareness on breast cancer and access to its early detection in an occupational health care scheme in Mumbai, India. Breast awareness brochures were mailed annually between June 2013 and June 2016 to a cohort of 22,500 eligible women aged 30-69 years old receiving universal health care from an occupational health care scheme comprising of primary health centres and a referral secondary care hospital in Mumbai. Women with suspected breast cancers were provided with diagnostic investigations and treatment. Socio-demographic information and tumour characteristics were compared between the breast awareness pre-intervention period (Jan 2005-May 2013) and the breast awareness intervention period after four rounds of mailers (June 2013-June 2016). The proportion of women with early tumours and axillary lymph node negative cancers increased from 74% to 81% and 46% to 53% respectively, between the two periods. While the proportion of patients receiving breast conserving surgery increased from 39% to 51%, the proportion receiving chemotherapy decreased from 84% to 56%. Interim results following efforts to improve breast awareness and access to care in a cohort of women in an occupational health care scheme indicate early detection and more conservative treatment of breast cancers. Creating awareness and improving access to care may result in cancer down-staging. Copyright © 2016 Elsevier Ltd. All rights reserved.

A pilot videoconference group stress management program in cancer survivors: lessons learned.

Science.gov (United States)

Zhou, Eric S; Partridge, Ann H; Blackmon, Jaime E; Morgan, Evan; Recklitis, Christopher J

2016-01-01

Cancer is a challenging experience and there is evidence that psychosocial interventions are effective at improving adjustment following treatment. At our cancer center, 14 cancer survivors (breast, prostate and blood cancers) completed a four-session cognitive-behavioral stress program. The first session was delivered at the survivor's local cancer center, where they were provided with a loaner tablet. The three subsequent sessions were delivered through group-based videoconference on the tablet. Session content was supplemented with a tailored ebook, designed specifically for this program. Participants provided feedback about the program as well as a standardized measure of perceived stress. Despite evidence that psychosocial programs are effective, there are significant barriers to dissemination, particularly for those residing in rural areas who do not live near academic medical centers where such programming is more readily available. Our experiences delivering a group-based videoconference program in cancer survivors are described, including positives and challenges associated with its design and implementation. Study participants enrolled from across four different US states, and the majority reported at least a 30-minute commute to their cancer center. This travel burden played a meaningful role in their desire to participate in our videoconference-based program. Although participants reported that session content was well suited to addressing stress management concerns, and session facilitators were able to effectively teach program techniques (eg progressive muscle relaxation, cognitive-reframing) and that the program was helpful overall, only modest improvements in perceived stress were seen. Participants noted challenges of the delivery including feeling disconnected from others, difficulty focusing, technical problems, and a desire for a longer program. Thus, although the novel delivery of a group-based, psychosocial program using tablet

How the University of Texas system responded to the need for interim storage of low-level radioactive waste materials.

Science.gov (United States)

Emery, Robert J

2012-11-01

Faced with the prospect of being unable to permanently dispose of low-level radioactive wastes (LLRW) generated from teaching, research, and patient care activities, component institutions of the University of Texas System worked collaboratively to create a dedicated interim storage facility to be used until a permanent disposal facility became available. Located in a remote section of West Texas, the University of Texas System Interim Storage Facility (UTSISF) was licensed and put into operation in 1993, and since then has provided safe and secure interim storage for up to 350 drums of dry solid LLRW at any given time. Interim storage capability provided needed relief to component institutions, whose on-site waste facilities could have possibly become overburdened. Experiences gained from the licensing and operation of the site are described, and as a new permanent LLRW disposal facility emerges in Texas, a potential new role for the storage facility as a surge capacity storage site in times of natural disasters and emergencies is also discussed.

Repacking of Cobalt 60 spent sources in the central interim storage

International Nuclear Information System (INIS)

Zeleznik, N.

2003-01-01

After the transfer of the responsibility for the management of the Central interim storage for waste from small producers, located at the reactor centre in Brinje near Ljubljana, Slovenia, the national Agency for radwaste management (ARAO) started with most urgent activities to improve the utilization of the storage facility. One of the main tasks has also been the rearrangement of the already stored radioactive waste in order to reduce volume of the waste and to collect same radioisotopes in the containers. The latest campaign, performed in 2002/2003, was repacking of all Co-60 spent sealed sources in the storage facility and also at the producer's premises which were after conditioning put into two drums with concrete matrix and stored back to the Central interim storage. The preparation works together with the implementation are described in the paper. (author)

Radiation shielding and dose rate evaluation at the interim storage facility for spent fuel from Cernavoda NPP

International Nuclear Information System (INIS)

Stanciu, Marcela; Mateescu, Silvia; Pantazi, Doina; Penescu, Maria

2000-01-01

At present studies necessary to license the Interim Storage Facility for the Spent Fuel (CANDU type) from Cernavoda NPP are developed in our country.The spent fuel from Cernavoda NPP is discharged into Spent Fuel Bay in Service Building of the plant, where it remains several years for cooling. After this period, the bundles of spent fuel are to be transferred to the Interim Storage Facility.The dry interim storage solution seems to be the most appropriate variant for Cernavoda NPP.The design of the Spent Fuel Interim Storage Facility must meet the applicable safety requirements in order to ensure radiological protection of the personnel, public and environment during all phases of the facility achievement. In this paper we intend to present the calculation of radiation shielding at the spent fuel interim storage facility for two technical solutions: - Concrete Monolithic Module and Concrete Storage Cask. In order to quantify the fuel composition after irradiation, the isotope generation and depletion code ORIGEN 2.1 has been used, taking into account a cooling time of 7 years and 9 years, respectively, for these two variants. The shielding calculations have been performed using the computer codes QAD-5K and MICROSHIELD-4. The evaluations refer only to gamma radiation because the resulting neutron source (from (α,n) reactions and spontaneous fission) is insignificant as compared to the gamma source. The final results consist in the minimum thickness of the shielding and the corresponding external dose rates, ensuring a design average dose rate based on national and international regulations. (authors)

Immobilized High-Level Waste (HLW) Interim Storage Alternative Generation and analysis and Decision Report - second Generation Implementing Architecture

International Nuclear Information System (INIS)

CALMUS, R.B.

2000-01-01

Two alternative approaches were previously identified to provide second-generation interim storage of Immobilized High-Level Waste (IHLW). One approach was retrofit modification of the Fuel and Materials Examination Facility (FMEF) to accommodate IHLW. The results of the evaluation of the FMEF as the second-generation IHLW interim storage facility and subsequent decision process are provided in this document

Report of the Fourth interim meeting of the Seabed Working Group Engineering Studies Task Group, 3-6 October 1983, at Rijks Geologische Dienst, Haarlem, The Netherlands

International Nuclear Information System (INIS)

Talbert, D.M.

1984-06-01

This report presents the results of the fourth interim meeting of the Seabed Working Group's (SWG) Engineering Studies Task Group (ESTG). This task group is charged with determining whether the engineering technology exists to emplace waste canisters in deep ocean sediments. The fourth interim meeting, held at Rijks Geologische Dienst, Haarlem, The Netherlands, 3-6 October 1983, reviewed progress made by the various national programs since the ESTG third interim meeting (July 1982) and developed a table of requirements for processing samples for a geotechnical properties data base. Other items addressed were (1) potential methods of instrumenting penetrators to obtain in situ measurements, (2) procedures for evaluating and quantifying the disturbed zone created by an emplaced penetrator, (3) review and modification of the current draft version of the SWG Five-Year Plan, (4) review and extension of the ESTG detailed plan for penetrator tests, and (5) details of the penetrator tests scheduled for March 1984 in the Nares Abyssal Plain using the research vessel M/V TYRO. The review of the national programs indicated significant progress when measured against the integrated ESTG five-year plan which results in a joint evaluation of engineering feasibility of subseabed disposal based upon (1) a demonstration of an emplacement capability, (2) an evaluation of the zone of sediment disturbance created during emplacement, (3) the existence of acceptable emplacement models, and (4) an acceptable engineering data base. A table of geotechnical sample-processing requirements is being developed to provide guidance for the other task groups that may have the opportunity to furnish suitable geotechnical samples to the ESTG as well as to provide some measure of consistency within the ESTG for the development of the engineering data base for the SWG study areas

Assessment report on research and development activities. Activity: 'Advanced science research' (Interim report)

International Nuclear Information System (INIS)

2012-11-01

Japan Atomic Energy Agency (hereinafter referred to as “JAEA”) consulted an assessment committee, “Evaluation Committee of Research Activities for Advanced Science Research” (hereinafter referred to as “Committee”) for interim assessment of “Advanced Science Research,” in accordance with “General Guideline for the Evaluation of Government Research and Development (R and D) Activities” by Cabinet Office, Government of Japan, “Guideline for Evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology” and “Regulation on Conduct for Evaluation of R and D Activities” by JAEA. In response to the JAEA's request, the Committee assessed the research programs and activities of the Advanced Science Research Center (hereinafter referred to as “ASRC”) for the period of two years from April 2010. The Committee evaluated the management and the research programs of the ASRC based on the explanatory documents prepared by the ASRC and the oral presentations with questions-and-answers by the Director and the research group leaders. This report summarizes the result of the assessment by the Committee with the Committee report attached from page 7. (author)

In-situ storage: An approach to interim remedial action - recent case studies in Canada

International Nuclear Information System (INIS)

Zelmer, R.L.

1991-01-01

The Low-Level Radioactive Waste Management Office (LLRWMO) acts on behalf of the federal government to manage historic low-level radioactive wastes. Recent interim remedial work in the Town of Port Hope, Ontario has included the consolidation of radium and uranium contaminated soils into temporary storage facilities on two sites to await final disposal elsewhere. Simple containments constructed and sited on already contaminated sites have been found effective as part of an interim remedial strategy. The approach has been accepted and supported by the local public. Lessons have been learned from a project management, environmental remediation and engineering design point of view

Conceptual design report for regional low-level waste interim storage site

International Nuclear Information System (INIS)

Bird, M.V.; Thompson, J.D.

1981-08-01

An interim storage site design concept was developed for receiving 100,000 ft 3 low-level waste per year, in the form of solidified wastes in 55-gallon drums with a dose rate of < 200 mrem per hour at contact

Interim Design Report

CERN Document Server

Choubey, S.; Goswami, S.; Berg, J.S.; Fernow, R.; Gallardo, J.C.; Gupta, R.; Kirk, H.; Simos, N.; Souchlas, N.; Ellis, M.; Kyberd, P.; Benedetto, E.; Fernandez-Martinez, E.; Efthymiopoulos, I.; Garoby, R.; Gilardoni, S.; Martini, M.; Prior, G.; Ballett, P.; Pascoli, S.; Bross, A.; Geer, S.; Johnstone, C.; Kopp, J.; Mokhov, N.; Morfin, J.; Neuffer, D.; Parke, S.; Popovic, M.; Strait, J.; Striganov, S.; Blondel, A.; Dufour, F.; Laing, A.; Soler, F.J.P; Lindner, M.; Schwetz, T.; Alekou, A.; Apollonio, M.; Aslaninejad, M.; Bontoiu, C.; Dornan, P.; Eccleston, R.; Kurup, A.; Long, K.; Pasternak, J.; Pozimski, J.; Bogacz, A.; Morozov, V.; Roblin, Y.; Bhattacharya, S.; Majumdar, D.; Mori, Y.; Planche, T.; Zisman, M.; Cline, D.; Stratakis, D.; Ding, X.; Coloma, P.; Donini, A.; Gavela, B.; Lopez Pavon, J.; Maltoni, M.; Bromberg, C.; Bonesini, M.; Hart, T.; Kudenko, Y.; Mondal, N.; Antusch, S.; Blennow, M.; Ota, T.; Abrams, R.J.; Ankenbrandt, C.M.; Beard, K.B.; Cummings, M.A.C.; Flanagan, G.; Johnson, R.P.; Roberts, T.J.; Yoshikawa, C.Y.; Migliozzi, P.; Palladino, V.; de Gouvea, A.; Graves, V.B.; Kuno, Y.; Peltoniemi, J.; Blackmore, V.; Cobb, J.; Witte, H.; Mezzetto, M.; Rigolin, S.; McDonald, K.T.; Coney, L.; Hanson, G.; Snopok, P.; Tortora, L.; Andreopoulos, C.; Bennett, J.R.J.; Brooks, S.; Caretta, O.; Davenne, T.; Densham, C.; Edgecock, R.; Kelliher, D.; Loveridge, P.; McFarland, A.; Machida, S.; Prior, C.; Rees, G.; Rogers, C.; Thomason, J.W.G.; Booth, C.; Skoro, G.; Karadzhov, Y.; Matev, R.; Tsenov, R.; Samulyak, R.; Mishra, S.R.; Petti, R.; Dracos, M.; Yasuda, O.; Agarwalla, S.K.; Cervera-Villanueva, A.; Gomez-Cadenas, J.J.; Hernandez, P.; Li, T.; Martin-Albo, J.; Huber, P.; Back, J.; Barker, G.; Harrison, P.; Meloni, D.; Tang, J.; Winter, W.

2011-01-01

The International Design Study for the Neutrino Factory (the IDS-NF) was established by the community at the ninth "International Workshop on Neutrino Factories, super-beams, and beta- beams" which was held in Okayama in August 2007. The IDS-NF mandate is to deliver the Reference Design Report (RDR) for the facility on the timescale of 2012/13. In addition, the mandate for the study [3] requires an Interim Design Report to be delivered midway through the project as a step on the way to the RDR. This document, the IDR, has two functions: it marks the point in the IDS-NF at which the emphasis turns to the engineering studies required to deliver the RDR and it documents baseline concepts for the accelerator complex, the neutrino detectors, and the instrumentation systems. The IDS-NF is, in essence, a site-independent study. Example sites, CERN, FNAL, and RAL, have been identified to allow site-specific issues to be addressed in the cost analysis that will be presented in the RDR. The choice of example sites shou...

Safety of interim storage solutions of used nuclear fuel during extended term

Energy Technology Data Exchange (ETDEWEB)

Shelton, C.; Bader, S.; Issard, H.; Arslan, M. [AREVA, 7135 Minstrel Way, Suite 300 Columbia, MD 21045 (United States)

2013-07-01

In 2013, the total amount of stored used nuclear fuel (UNF) in the world will reach 225,000 T HM. The UNF inventory in wet storage will take up over 80% of the available total spent fuel pool (SFP) capacity. Interim storage solutions are needed. They give flexibility to the nuclear operators and ensure that nuclear reactors continue to operate. However, we need to keep in mind that they are also an easy way to differ final decision and implementation of a UNF management approach (recycling or final disposal). In term of public perception, they can have a negative impact overtime as it may appear that nuclear industry may have significant issues to resolve. In countries lacking an integrated UNF management approach, the UNF are being discharged from the SFPs to interim storage (mostly to dry storage) at the same rate as UNF is being discharged from reactors, as the SFPs at the reactor sites are becoming full. This is now the case in USA, Taiwan, Switzerland, Spain, South Africa and Germany. For interim storage, AREVA has developed different solutions in order to allow the continued operation of reactors while meeting the current requirements of Safety Authorities: -) Dry storage canisters on pads, -) Dual-purpose casks (dry storage and transportation), -) Vault dry storage, and -) Centralized pool storage.

2006 Annual Operations Report for INTEC Operable Unit 3-13, Group 1, Tank Farm Interim Action

International Nuclear Information System (INIS)

D. E. Shanklin

2007-01-01

This annual operations report describes the requirements followed and activities conducted to inspect, monitor, and maintain the items installed during performance of the Waste Area Group 3, Operable Unit 3-13, Group 1, Tank Farm Interim Action, at the Idaho Nuclear Technology and Engineering Center. This report covers the time period from January 1 through December 31, 2006, and describes inspection and monitoring activities for the surface-sealed areas within the tank farm, concrete-lined ditches and culverts in and around the tank farm, the lift station, and the lined evaporation pond. These activities are intended to assure that the interim action is functioning adequately to meet the objectives stated in the Operable Unit 3-13, Record of Decision for the Group 1, Tank Farm Interim Action (DOE/ID-10660) as described in the Group 1 Remedial Design/Remedial Action Work Plan (DOE/ID-10772)

Heavy-Section Steel Technology program overview

International Nuclear Information System (INIS)

Pennell, W.E.

1990-01-01

This paper presents a status review of ongoing HSST program tasks aimed at refining the technology used in analysis of reactor pressure vessel fracture margins under pressurized thermal-shock (PTS) loading. Specific fracture-technology issues addressed include vessel flaw density and distribution, shallow flaws, fracture-toughness data transfer, circumferential cracks, ductile tearing and the influence of low-tearing toughness in stainless steel cladding. Preliminary results from the analysis and test programs are presented, together with interim assessments of their potential impact on a reactor vessel PTS analysis. 31 refs., 23 figs., 1 tab

Overview of DOE's Transuranic Waste Program

International Nuclear Information System (INIS)

McFadden, M.H.; Detamore, J.A.

1987-01-01

The US Department of Energy has assigned to Albuquerque Operations the Defense Transuranic Waste Program responsibility for long-range planning and management of defense transuranic (TRU) waste. The Transuranic Waste Lead Organization (TLO) has divided the Program into seven elements which support it's primary goal of ending interim storage and achieving permanent disposal. These are: waste generation site activities, storage site activities, burial site activities, technology development, transportation, institutional activities, and permanent disposal. This paper will briefly discuss these seven elements and how they are integrated to provide for successful achievement of the primary goal

Interim FEP report for the safety assessment SR-Can

Energy Technology Data Exchange (ETDEWEB)

Skagius, Kristina (ed.) [Kemakta Konsult AB, Stockholm (Sweden)

2004-08-01

This report describes the work with identification and structuring of features, events and processes (FEPs) that has been carried out within the scope of the SR-Can safety assessment up to the time of the interim reporting of the project. The overall objective of the work is to develop a database of features, events and processes in a format that would facilitate both a systematic analysis of FEPs and documentation of the FEP analysis as well as facilitate revisions and updates to be made in connection with new safety assessments. This overall objective also includes the development of procedures for a systematic FEP analysis as well as to apply these procedures in order to arrive at an SR-Can version of the FEP database. The work started by implementing the content of the SR 97 Process report into a database format suitable for import and processing of FEP information from other sources. The SR 97 version of the database was systematically audited against the NEA database with Project FEPs, version 1.2. In addition, an earlier audit of the SR 97 process report against the interaction matrices developed for a deep repository of the KBS-3 type was revisited and updated. Relevant FEPs from the audit were sorted into three main categories in the SR-Can database i) FEPs related to the initial states of the repository system, ii) FEPs related to internal processes of the repository system, and iii) FEPs related to external impacts on the repository system. These groups of FEPs were further processed for making decisions on how to handle these FEPs in the assessment. Biosphere processes were not included in the SR 97 Process report and there is thus not the same basis for updating these descriptions as for the engineered barriers and the geosphere. All biosphere FEPs from the audit have therefore been compiled in a single category in the database, but remain to be further handled. FEPs were also categorised as irrelevant or as being related to methodology on a general

Interim FEP report for the safety assessment SR-Can

International Nuclear Information System (INIS)

Skagius, Kristina

2004-08-01

This report describes the work with identification and structuring of features, events and processes (FEPs) that has been carried out within the scope of the SR-Can safety assessment up to the time of the interim reporting of the project. The overall objective of the work is to develop a database of features, events and processes in a format that would facilitate both a systematic analysis of FEPs and documentation of the FEP analysis as well as facilitate revisions and updates to be made in connection with new safety assessments. This overall objective also includes the development of procedures for a systematic FEP analysis as well as to apply these procedures in order to arrive at an SR-Can version of the FEP database. The work started by implementing the content of the SR 97 Process report into a database format suitable for import and processing of FEP information from other sources. The SR 97 version of the database was systematically audited against the NEA database with Project FEPs, version 1.2. In addition, an earlier audit of the SR 97 process report against the interaction matrices developed for a deep repository of the KBS-3 type was revisited and updated. Relevant FEPs from the audit were sorted into three main categories in the SR-Can database i) FEPs related to the initial states of the repository system, ii) FEPs related to internal processes of the repository system, and iii) FEPs related to external impacts on the repository system. These groups of FEPs were further processed for making decisions on how to handle these FEPs in the assessment. Biosphere processes were not included in the SR 97 Process report and there is thus not the same basis for updating these descriptions as for the engineered barriers and the geosphere. All biosphere FEPs from the audit have therefore been compiled in a single category in the database, but remain to be further handled. FEPs were also categorised as irrelevant or as being related to methodology on a general

Waste Management Program. Technical progress report, Aporil-June 1983

Energy Technology Data Exchange (ETDEWEB)

None

1984-02-01

This quarterly report provides current information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant. The studies on environmental and safety assessments, process and equipment development, TRU waste, and low-level waste are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations Program: surveillance and maintenance, waste concentration, low-level effluent waste, tank replacement/waste transfer, and solid waste storage and related activities.

Alloy development for irradiation performance: program strategy

International Nuclear Information System (INIS)

Bloom, E.E.; Stiegler, J.O.; Wiffen, F.W.; Dalder, E.N.C.; Reuther, T.C.; Gold, R.E.; Holmes, J.J.; Kummer, D.L.; Nolfi, F.V.

1978-01-01

The objective of the Alloy Development for Irradiation Performance Program is the development of structural materials for use in the first wall and blanket region of fusion reactors. The goal of the program is a material that will survive an exposure of 40 MWyr/m 2 at a temperature which will allow use of a liquid-H 2 O heat transport system. Although the ultimate aim of the program is development of materials for commercial reactors by the end of this century, activities are organized to provide materials data for the relatively low performance interim machines that will precede commercial reactors

40 CFR 57.302 - Performance level of interim constant controls.

Science.gov (United States)

2010-07-01

... correction of the effects of any serious deficiencies in the system. For the purpose of this paragraph, at... system if the smelter owner has not upgraded serious deficiencies in the constant control system in... 40 Protection of Environment 5 2010-07-01 2010-07-01 false Performance level of interim constant...

FRACTIONAL CRYSTALLIZATION TESTING WITH INTERIM PRETREATMENT SYSTEM FEEDS

International Nuclear Information System (INIS)

HERTING DL

2008-01-01

The fractional crystallization process was developed as a pretreatment method for saltcake waste retrieved from Hanford single-shell tanks (SST). The process separates the retrieved SST waste into a high-level waste stream containing the bulk of the radionuclides and a low-activity waste stream containing the bulk of the nonradioactive sodium salts. The Interim Pretreatment System project shifted the focus on pretreatment planning from SST waste to double-shell tank waste

Dry storage of spent fuel elements: interim facility

International Nuclear Information System (INIS)

Quihillalt, O.J.

1993-01-01

Apart from the existing facilities to storage nuclear fuel elements at Argentina's nuclear power stations, a new interim storage facility has been planned and projected by the Argentinean Atomic Energy Commission (CNEA) that will be constructed by private group. This article presents the developments and describes the activities undertaken until the national policy approach to the final decision for the most suitable alternative to be adopted. (B.C.A.). 09 refs, 01 fig, 09 tabs

Interim Stabilization Equipment Essential and Support Drawing Plan

International Nuclear Information System (INIS)

HORNER, T.M.

2000-01-01

The purpose of this document is to list the Interim Stabilization equipment drawings that are classified as Essential or Support drawings. Essential Drawings are those drawings identified by the facility staff as necessary to directly support the safe operation of the facility or equipment. [CHG 2000a]. Support Drawings are those drawings identified by the facility staff that further describe the design details of structures, systems or components shown on essential drawings. [CHG 2000a

Functions and requirements document for interim store solidified high-level and transuranic waste

Energy Technology Data Exchange (ETDEWEB)

Smith-Fewell, M.A., Westinghouse Hanford

1996-05-17

The functions, requirements, interfaces, and architectures contained within the Functions and Requirements (F{ampersand}R) Document are based on the information currently contained within the TWRS Functions and Requirements database. The database also documents the set of technically defensible functions and requirements associated with the solidified waste interim storage mission.The F{ampersand}R Document provides a snapshot in time of the technical baseline for the project. The F{ampersand}R document is the product of functional analysis, requirements allocation and architectural structure definition. The technical baseline described in this document is traceable to the TWRS function 4.2.4.1, Interim Store Solidified Waste, and its related requirements, architecture, and interfaces.

Financial compensation for municipalities hosting interim or final disposal facilities for radioactive waste

International Nuclear Information System (INIS)

Barboza, Alex; Vicente, Roberto

2005-01-01

Brazilian Law No. 10308 issued November 20, 2001, establishes in its 34th article that 'those municipalities hosting interim or final disposal facilities for radioactive waste are eligible to receive a monthly payment as compensation'. The values of due payments depend on parameters such as volume of wastes and activity and half-lives of the radionuclides. The method to calculating those values was established by the National Commission on Nuclear Energy, the Brazilian regulatory authority, by Resolution No. 10, issued in the August 18, 2003. In this paper we report the application of that method to a low- and intermediate-level radioactive waste interim storage facility at the Nuclear Energy Research Institute. (author)

ETF interim design review

International Nuclear Information System (INIS)

Steiner, D.; Rutherford, P.H.

1980-01-01

A three-day ETF Interim Design Review was conducted on July 23-25, 1980, at the Sheraton Potomac Inn in Rockville, Maryland. The intent of the review was to provide a forum for an in-depth assessment and critique of all facets of the ETF design by members of the fusion community. The review began with an opening plenary session at which an overview of the ETF design was presented by D. Steiner, manager of the ETF Design Center, complemented by a physics overview by P.H. Rutherford, chairman of the ETF/INTOR Physics Committee. This was followed by six concurrent review sessions over the next day and a half. The review closed with a plenary session at which the Design Review Board presented its findings. This document consists of the viewgraphs for the opening plenary session and an edited version of the presentations made by Steiner and Rutherford

Annex D-200 Area Interim Storage Area Final Safety Analysis Report [FSAR] [Section 1 & 2

Energy Technology Data Exchange (ETDEWEB)

CARRELL, R D

2002-07-16

The 200 Area Interim Storage Area (200 Area ISA) at the Hanford Site provides for the interim storage of non-defense reactor spent nuclear fuel (SNF) housed in aboveground dry cask storage systems. The 200 Area ISA is a relatively simple facility consisting of a boundary fence with gates, perimeter lighting, and concrete and gravel pads on which to place the dry storage casks. The fence supports safeguards and security and establishes a radiation protection buffer zone. The 200 Area ISA is nominally 200,000 ft{sup 2} and is located west of the Canister Storage Building (CSB). Interim storage at the 200 Area ISA is intended for a period of up to 40 years until the materials are shipped off-site to a disposal facility. This Final Safety Analysis Report (FSAR) does not address removal from storage or shipment from the 200 Area ISA. Three different SNF types contained in three different dry cask storage systems are to be stored at the 200 Area ISA, as follows: (1) Fast Flux Test Facility Fuel--Fifty-three interim storage casks (ISC), each holding a core component container (CCC), will be used to store the Fast Flux Test Facility (FFTF) SNF currently in the 400 Area. (2) Neutron Radiography Facility (NRF) TRIGA'--One Rad-Vault' container will store two DOT-6M3 containers and six NRF TRIGA casks currently stored in the 400 Area. (3) Commercial Light Water Reactor Fuel--Six International Standards Organization (ISO) containers, each holding a NAC-I cask4 with an inner commercial light water reactor (LWR) canister, will be used for commercial LWR SNF from the 300 Area. An aboveground dry cask storage location is necessary for the spent fuel because the current storage facilities are being shut down and deactivated. The spent fuel is being transferred to interim storage because there is no permanent repository storage currently available.

Release of radionuclides following severe accident in interim storage facility. Source term determination

International Nuclear Information System (INIS)

Morandi, S.; Mariani, M.; Giacobbo, F.; Covini, R.

2006-01-01

Among the severe accidents that can cause the release of radionuclides from an interim storage facility, with a consequent relevant radiological impact on the population, there is the impact of an aircraft on the facility. In this work, a safety assessment analysis for the case of an aircraft crash into an interim storage facility is tackled. To this aim a methodology, based upon DOE, IAEA and NUREG standard procedures and upon conservative yet realistic hypothesis, has been developed in order to evaluate the total radioactivity, source term, released to the biosphere in consequence of the impact, without recurring to the use of complicated numerical codes. The procedure consists in the identification of the accidental scenarios, in the evaluation of the consequent damage to the building structures and to the waste packages and in the determination of the total release of radionuclides through the building-atmosphere interface. The methodology here developed has been applied to the case of an aircraft crash into an interim storage facility currently under design. Results show that in case of perforation followed by a fire incident the total released activity would be greater of some orders of magnitude with respect to the case of mere perforation. (author)

Experience with the licensing of the interim spent fuel storage facility modification

International Nuclear Information System (INIS)

Bezak, S.; Beres, J.

1999-01-01

After political and economical changes in the end of eighties, the utility operating the nuclear power plants in the Slovak Republic (SE, a.s.) decided to change the original scheme of the back-end of the nuclear fuel cycle; instead of reprocessing in the USSR/Russian Federation spent fuel will be stored in an interim spent fuel storage facility until the time of the final decision. As the best solution, a modification of the existing interim spent fuel storage facility has been proposed. Due to lack of legal documents for this area, the Regulatory Authority of the Slovak Republic (UJD SR) performed licensing procedures of the modification on the basis of recommendations by the IAEA, the US NRC and the relevant parts of the US CFR Title 10. (author)

Interim Service ISDN Satellite (ISIS) simulator development for advanced satellite designs and experiments

Science.gov (United States)

Pepin, Gerard R.

1992-01-01

The simulation development associated with the network models of both the Interim Service Integrated Services Digital Network (ISDN) Satellite (ISIS) and the Full Service ISDN Satellite (FSIS) architectures is documented. The ISIS Network Model design represents satellite systems like the Advanced Communications Technology Satellite (ACTS) orbiting switch. The FSIS architecture, the ultimate aim of this element of the Satellite Communications Applications Research (SCAR) Program, moves all control and switching functions on-board the next generation ISDN communications satellite. The technical and operational parameters for the advanced ISDN communications satellite design will be obtained from the simulation of ISIS and FSIS engineering software models for their major subsystems. Discrete event simulation experiments will be performed with these models using various traffic scenarios, design parameters, and operational procedures. The data from these simulations will be used to determine the engineering parameters for the advanced ISDN communications satellite.

Development of a Computer Program for an Analysis of the Logistics and Transportation Costs of the PWR Spent Fuels in Korea

International Nuclear Information System (INIS)

Cha, Jeong Hun; Choi, Heui Joo; Lee, Jong Youl; Choi, Jong Won

2009-01-01

It is expected that a substantial amount of spent fuels will be transported from the four nuclear power plant (NPP) sites in Korea to a hypothetical centralized interim storage facility or a final repository in the near future. The cost for the transportation is proportional to the amount of spent fuels. In this paper, a cost estimation program is developed based on the conceptual design of a transportation system and a logistics analysis. Using the developed computer program, named as CASK, the minimum capacity of a centralized interim storage facility (CISF) and the transportation cost for PWR spent fuels are calculated. The PWR spent fuels are transported from 4 NPP sites to a final repository (FR) via the CISF. Since NPP sites and the CISF are located along the coast, a sea-transportation is considered and a road-transportation is considered between the CISF and the FR. The result shows that the minimum capacity of the interim storage facility is 15,000 MTU

Global Spent Fuel Logistics Systems Study (GSFLS). Volume 2. GSFLS visit findings and evaluations. Interim report

International Nuclear Information System (INIS)

1978-01-01

This report is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. This report describes a global framework that evaluates spent fuel disposition requirements, influencing factors and strategies. A broad sampling of foreign governmental officials, electric utility spokesmen and nuclear power industry officials responsible for GSFLS policies, plans and programs were surveyed as to their views with respect to national and international GSFLS related considerations. The results of these GSFLS visit findings are presented herein. These findings were then evaluated in terms of technical, institutional and legal/regulatory implications. The GSFLS evaluations, in conjunction with perceived US spent fuel objectives, formed the basis for selecting a set of GSFLS strategies which are reported herein

Global Spent Fuel Logistics Systems Study (GSFLS). Volume 2. GSFLS visit findings and evaluations. Interim report

Energy Technology Data Exchange (ETDEWEB)

None

1978-01-31

This report is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. This report describes a global framework that evaluates spent fuel disposition requirements, influencing factors and strategies. A broad sampling of foreign governmental officials, electric utility spokesmen and nuclear power industry officials responsible for GSFLS policies, plans and programs were surveyed as to their views with respect to national and international GSFLS related considerations. The results of these GSFLS visit findings are presented herein. These findings were then evaluated in terms of technical, institutional and legal/regulatory implications. The GSFLS evaluations, in conjunction with perceived US spent fuel objectives, formed the basis for selecting a set of GSFLS strategies which are reported herein.

Safety of Long-term Interim Storage Facilities - Workshop Proceedings

International Nuclear Information System (INIS)

2014-01-01

The objective of this workshop was to discuss and review current national activities, plans and regulatory approaches for the safety of long term interim storage facilities dedicated to spent nuclear fuel (SF), high level waste (HLW) and other radioactive materials with prolonged storage regimes. It was also intended to discuss results of experiments and to identify necessary R and D to confirm safety of fuel and cask during the long-term storage. Safety authorities and their Technical Support Organisation (TSO), Fuel Cycle Facilities (FCF) operating organisations and international organisations were invited to share information on their approaches, practices and current developments. The workshop was organised in an opening session, three technical sessions, and a conclusion session. The technical sessions were focused on: - National approaches for long term interim storage facilities; - Safety requirements, regulatory framework and implementation issues; - Technical issues and operational experience, needs for R and D. Each session consisted of a number of presentations followed by a panel discussion moderated by the session Chairs. A summary of each session and subsequent discussion that ensued are provided as well as a summary of the results of the workshop with the text of the papers given and presentations made

Application of NUREG/CR-5999 interim fatigue curves to selected nuclear power plant components

International Nuclear Information System (INIS)

Ware, A.G.; Morton, D.K.; Nitzel, M.E.

1995-03-01

Recent test data indicate that the effects of the light water reactor (LWR) environment could significantly reduce the fatigue resistance of materials used in the reactor coolant pressure boundary components of operating nuclear power plants. Argonne National Laboratory has developed interim fatigue curves based on test data simulating LWR conditions, and published them in NUREG/CR-5999. In order to assess the significance of these interim fatigue curves, fatigue evaluations of a sample of the components in the reactor coolant pressure boundary of LWRs were performed. The sample consists of components from facilities designed by each of the four U.S. nuclear steam supply system vendors. For each facility, six locations were studied, including two locations on the reactor pressure vessel. In addition, there are older vintage plants where components of the reactor coolant pressure boundary were designed to codes that did not require an explicit fatigue analysis of the components. In order to assess the fatigue resistance of the older vintage plants, an evaluation was also conducted on selected components of three of these plants. This report discusses the insights gained from the application of the interim fatigue curves to components of seven operating nuclear power plants

Development of a road materials database: Interim Report: 1st draft

CSIR Research Space (South Africa)

Jones, DJ

2003-03-01

Full Text Available The data required for a road materials database has been identified and a basic structure formulated. A set of Excel workbooks and associated worksheets has been developed as a foundation for the database and as an interim means of gathering test...

Interim Restorative Approach for the Management of Congenitally Missing Permanent Mandibular Incisors: Presentation of Three Cases

Directory of Open Access Journals (Sweden)

Prashanth Prakash

2011-01-01

Full Text Available Congenital missing of mandibular permanent incisors with retained primary incisors may jeopardize the esthetic appearance and psychological development of children, especially during the years of transition into adolescence. The retained primary teeth are necessary for the maintenance and normal development of alveolar bone, which in turn is essential for future definitive rehabilitation. In such situations, an interim restoration may be provided before any definitive treatment is given to comfort the young patient during this transition period. Interim restorations may include resin-modified additions to the existing teeth as well as more sophisticated restorations such as resin-retained bridge and removable partial dentures. However, this restoration differs for different clinical situations based on various factors such as age and patient compliance, and also consideration has to be given for the growth changes of the child. The aim of this present paper is to discuss the esthetic management of three cases with bilateral agenesis of permanent mandibular incisors and retained primary incisors with composite interim restoration.

Waste Management Program. Technical progress report, July-December, 1984

International Nuclear Information System (INIS)

1986-10-01

This report provides information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant and offplant participants. The studies on environmental and safety assessments, other support, in situ storage or disposal, waste form development and characterization, process and equipment development, and the Defense Waste Processing Facility are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations: tank farm operation, inspection program, burial ground operations, and waste transfer/tank replacement

Students' interim literacies as a dynamic resource for teaching and ...

African Journals Online (AJOL)

This article explores the notion of 'interim literacies'by drawing on data from a research project which used linguistic and intertextual analysis of first year student writing in economics to investigate the intersection of academic discourse and student voice. This research has provided a rich set of data to illustrate the ways in ...

Quality assurance program plan for FRG sealed isotopic heat sources project (C-229)

International Nuclear Information System (INIS)

Tanke, J.M.

1997-01-01

This QAPP implements the Quality Assurance Program Plan for the FRG Sealed Isotopic Heat Sources Project (C-229). The heat source will be relocated from the 324 Building and placed in interim storage at the Central Waste Complex (CWC)

Impacts of the Interim Federal Health Program reforms: A stakeholder analysis of barriers to health care access and provision for refugees.

Science.gov (United States)

Antonipillai, Valentina; Baumann, Andrea; Hunter, Andrea; Wahoush, Olive; O'Shea, Timothy

2017-11-09

Changes to the Interim Federal Health Program (IFHP) in 2012 reduced health care access for refugees and refugee claimants, generating concerns among key stakeholders. In 2014, a new IFHP temporarily reinstated access to some health services; however, little is known about these changes, and more information is needed to map the IFHP's impact. This study explores barriers occurring during the time period of the IFHP reforms to health care access and provision for refugees. A stakeholder analysis, using 23 semi-structured interviews, was conducted to obtain insight into stakeholder perceptions of the 2014 reforms, as well as stakeholders' position and their influence to assess the acceptability of the IFHP changes. The majority of stakeholders expressed concerns about the 2014 IFHP changes as a result of the continuing barriers posed by the 2012 retrenchments and the emergence of new barriers to health care access and provision for refugees. Key barriers identified included lack of communication and awareness, lack of continuity and comprehensive care, negative political discourse and increased costs. A few stakeholders supported the reforms as they represented some, but limited, access to health care. Overall, the reforms to the IFHP in 2014 generated barriers to health care access and provision that contributed to confusion among stakeholders, the transfer of refugee health responsibility to provincial authorities and the likelihood of increased health outcome disparities, as refugees and refugee claimants chose to delay seeking health care. The study recommends that policy-makers engage with refugee health stakeholders to formulate a policy that improves health care provision and access for refugee populations.

Failsafe automation of Phase II clinical trial interim monitoring for stopping rules.

Science.gov (United States)

Day, Roger S

2010-02-01

In Phase II clinical trials in cancer, preventing the treatment of patients on a study when current data demonstrate that the treatment is insufficiently active or too toxic has obvious benefits, both in protecting patients and in reducing sponsor costs. Considerable efforts have gone into experimental designs for Phase II clinical trials with flexible sample size, usually implemented by early stopping rules. The intended benefits will not ensue, however, if the design is not followed. Despite the best intentions, failures can occur for many reasons. The main goal is to develop an automated system for interim monitoring, as a backup system supplementing the protocol team, to ensure that patients are protected. A secondary goal is to stimulate timely recording of patient assessments. We developed key concepts and performance needs, then designed, implemented, and deployed a software solution embedded in the clinical trials database system. The system has been in place since October 2007. One clinical trial tripped the automated monitor, resulting in e-mails that initiated statistician/investigator review in timely fashion. Several essential contributing activities still require human intervention, institutional policy decisions, and institutional commitment of resources. We believe that implementing the concepts presented here will provide greater assurance that interim monitoring plans are followed and that patients are protected from inadequate response or excessive toxicity. This approach may also facilitate wider acceptance and quicker implementation of new interim monitoring algorithms.

Medicare and Medicaid programs; physicians' referrals to health care entities with which they have financial relationships: partial delay of effective date. Interim final rule with comment period; partial delay in effective date.

Science.gov (United States)

2001-12-03

This interim final rule with comment period delays for 1 year the effective date of the last sentence of 42 CFR 411.354(d)(1). Section 411.354(d)(1) was promulgated in the final rule entitled "Medicare and Medicaid Programs; Physicians' Referrals to Health Care Entities With Which They Have Financial Relationships," published in the Federal Register on January 4, 2001 (66 FR 856). A 1-year delay in the effective date of the last sentence in Section 411.354(d)(1) will give Department officials the opportunity to reconsider the definition of compensation that is "set in advance" as it relates to percentage compensation methodologies in order to avoid unnecessarily disrupting existing contractual arrangements for physician services. Accordingly, the last sentence of Section 411.354(d)(1), which would have become effective January 4, 2002, will not become effective until January 6,2003.

Scientific criteria document for the development of an interim provincial water quality objective for aniline

Energy Technology Data Exchange (ETDEWEB)

Angelow, R.V.; Bazinet, N.

1996-11-01

The purpose of this document is to develop an interim provincial water quality objective for aniline for the protection of aquatic life in Ontario. It reviews the sources of aniline in the environment, its environmental fate and properties, acute and chronic toxicity as determined from results reported in the literature on toxicity tests using vertebrates and invertebrates, the bioaccumulation of aniline in the environment, mutagenic effects, and threshold aniline concentrations affecting fish odour and taste. The document then explains the derivation of the interim water quality objective. Water quality criteria for aniline developed in other jurisdictions are noted.

Continuous Covariate Imbalance and Conditional Power for Clinical Trial Interim Analyses

Science.gov (United States)

Ciolino, Jody D.; Martin, Renee' H.; Zhao, Wenle; Jauch, Edward C.; Hill, Michael D.; Palesch, Yuko Y.

2014-01-01

Oftentimes valid statistical analyses for clinical trials involve adjustment for known influential covariates, regardless of imbalance observed in these covariates at baseline across treatment groups. Thus, it must be the case that valid interim analyses also properly adjust for these covariates. There are situations, however, in which covariate adjustment is not possible, not planned, or simply carries less merit as it makes inferences less generalizable and less intuitive. In this case, covariate imbalance between treatment groups can have a substantial effect on both interim and final primary outcome analyses. This paper illustrates the effect of influential continuous baseline covariate imbalance on unadjusted conditional power (CP), and thus, on trial decisions based on futility stopping bounds. The robustness of the relationship is illustrated for normal, skewed, and bimodal continuous baseline covariates that are related to a normally distributed primary outcome. Results suggest that unadjusted CP calculations in the presence of influential covariate imbalance require careful interpretation and evaluation. PMID:24607294

Reinforcement of a PMMA resin for fixed interim prostheses with nanodiamonds.

Science.gov (United States)

Protopapa, Popi; Kontonasaki, Eleana; Bikiaris, Dimitrios; Paraskevopoulos, Konstantinos M; Koidis, Petros

2011-01-01

The aim of this study was to investigate the possible reinforcement of Nanodiamonds (ND) in a PMMA resin for fixed interim restorations. The fracture toughness (K(Ic)), impact strength and the dynamic thermomechanical properties (T(g), E´, E´´, tanδ) of a series of PMMA-ND nanocomposites with different amounts of ND were evaluated. The fracture toughness increased as the ND percentage increased up to 0.38% wt but a greater amount of ND induced a decrease in K(Ic). Impact strength and Young's modulus were also increased by increasing nanoparticles content, indicating the reinforcing effect of ND. Dynamic mechanical properties were also affected. By increasing the ND content an increase of storage modulus was recorded, while glass transition was shifted at higher temperatures. Under the limitations of this study, it can be suggested that reinforcing PMMA with ND nanoparticles -especially at low concentrations- may increase the overall performance of fixed interim prostheses.

Interim Measures Work Plan Expanded Bioventing System SWMU 55 (IRP Site FT-03)

National Research Council Canada - National Science Library

1997-01-01

This interim measures work plan (IMWP) presents the scope for an expanded bioventing system to conduct in situ treatment of the remaining fuel-contaminated soils at solid waste management unit (SWMU...

On the pathway towards disposal. The need for long-term interim storage of high-level nuclear waste

International Nuclear Information System (INIS)

Budelmann, Harald; Koehnke, Dennis; Reichardt, Manuel

2017-01-01

The disposal of spent nuclear fuel is a still unsolved problem with social, ethical, economical, ecological and political dimensions. The stagnating decision process on the final repository concept in several countries has the consequence of the inclusion of long-term interim storage into the disposal concept. The contribution discusses several approaches. This opens the question whether the long-term interim storage is a matter of delaying tactic or a pragmatic solution on the way to a final repository.

Low-level waste management program and interim waste operations technologies

International Nuclear Information System (INIS)

Mezga, L.J.

1983-01-01

The Department of Energy currently supports an integrated technology development and transfer program aimed at ensuring that the technology necessary for the safe management and disposal of LLW by the commercial and defense sectors is available. The program focuses on five technical areas: (1) corrective measures technology, (2) improved shallow land burial technology, (3) greater confinement disposal technology, (4) model development and validation, and (5) treatment methods for problem wastes. The results of activities in these areas are reported in the open literature and the Proceedings of the LLWMP Annual Participants Information Meeting

Interim Hanford Waste Management Technology Plan

International Nuclear Information System (INIS)

1985-09-01

The Interim Hanford Waste Management Technology Plan (HWMTP) is a companion document to the Interim Hanford Waste Management Plan (HWMP). A reference plan for management and disposal of all existing and certain projected future radioactive Hanford Site Defense Wastes (HSDW) is described and discussed in the HWMP. Implementation of the reference plan requires that various open technical issues be satisfactorily resolved. The principal purpose of the HWMTP is to present detailed descriptions of the technology which must be developed to close each of the technical issues associated with the reference plan identified in the HWMP. If alternative plans are followed, however, technology development efforts including costs and schedules must be changed accordingly. Technical issues addressed in the HWMTP and HWMP are those which relate to disposal of single-shell tank wastes, contaminated soil sites, solid waste burial sites, double-shell tank wastes, encapsulated 137 CsCl and 90 SrF 2 , stored and new solid transuranic (TRU) wastes, and miscellaneous wastes such as contaminated sodium metal. Among the high priority issues to be resolved are characterization of various wastes including early determination of the TRU content of future cladding removal wastes; completion of development of vitrification (Hanford Waste Vitrification Plant) and grout technology; control of subsidence in buried waste sites; and development of criteria and standards including performance assessments of systems proposed for disposal of HSDW. Estimates of the technology costs shown in this report are made on the basis that all identified tasks for all issues associated with the reference disposal plan must be performed. Elimination of, consolidation of, or reduction in the scope of individual tasks will, of course, be reflected in corresponding reduction of overall technology costs

Interim Policy Options for Commercialization of Solar Heating and Cooling Systems.

Science.gov (United States)

Bezdek, Roger

This interim report reviews the major incentive policy options available to accelerate market penetration of solar heating and cooling (SHAC) systems. Feasible policy options designed to overcome existing barriers to commercial acceptance and market penetration are identified and evaluated. The report is divided into seven sections, each dealing…

Safety evaluation for the interim stabilization of Tank 241-C-103

Energy Technology Data Exchange (ETDEWEB)

Geschke, G.R.

1995-03-01

This document provides the basis for interim stabilization of tank 241-C-103. The document covers the removal of the organic liquid layer and the aqueous supernatant from tank 241-C-103. Hazards are identified, consequences are calculated and controls to mitigate or prevent potential accidents are developed.

Safety evaluation for the interim stabilization of Tank 241-C-103

International Nuclear Information System (INIS)

Geschke, G.R.

1995-03-01

This document provides the basis for interim stabilization of tank 241-C-103. The document covers the removal of the organic liquid layer and the aqueous supernatant from tank 241-C-103. Hazards are identified, consequences are calculated and controls to mitigate or prevent potential accidents are developed

Overview of DOE's transuranic waste program

International Nuclear Information System (INIS)

McFadden, M.H.; Detamore, J.A.

1988-01-01

The United States Department of Energy (DOE) has assigned to Albuquerque Operations the Defense Transuranic Waste Program (DTWP) responsibility for long-range planning and management for defense transuranic (TRU) waste. The Transuranic Waste Lead Organization (TLO) has divided the Program into seven elements that support its primary goal of ending interim storage and achieving permanent disposal. These elements include waste generation site activities, storage site activities, burial site activities, technology development, transportation, institutional activities and permanent disposal. This paper briefly discusses these seven elements and how they are integrated to provide for successful achievement of the primary goal

400-MWe Consolidated Nuclear Steam System (CNSS). 1200-MWt Phase 2A interim studies

International Nuclear Information System (INIS)

1978-09-01

The Phase 2A interim studies of the Consolidated Nuclear Steam System (CNSS) consisted of a number of separate task studies addressing the design concepts developed during the Phase 1 study reported in BAW--1445. The purpose of the interim studies was to better establish overall concept feasibility from both a hardware and economic standpoint, to make modification and additions to the design where appropriate, and to understand and reduce the technical risks in critical areas of the design. The work on these task studies included input from Barberton, Mt. Vernon, and the Alliance Research Center as well as United Engineers and Constructors (UE and C). The UE and C work was carried out under a separate DOE contract

Annex D-200 Area Interim Storage Area Final Safety Analysis Report [FSAR] [Section 1 and 2

International Nuclear Information System (INIS)

CARRELL, R.D.

2002-01-01

The 200 Area Interim Storage Area (200 Area ISA) at the Hanford Site provides for the interim storage of non-defense reactor spent nuclear fuel (SNF) housed in aboveground dry cask storage systems. The 200 Area ISA is a relatively simple facility consisting of a boundary fence with gates, perimeter lighting, and concrete and gravel pads on which to place the dry storage casks. The fence supports safeguards and security and establishes a radiation protection buffer zone. The 200 Area ISA is nominally 200,000 ft 2 and is located west of the Canister Storage Building (CSB). Interim storage at the 200 Area ISA is intended for a period of up to 40 years until the materials are shipped off-site to a disposal facility. This Final Safety Analysis Report (FSAR) does not address removal from storage or shipment from the 200 Area ISA. Three different SNF types contained in three different dry cask storage systems are to be stored at the 200 Area ISA, as follows: (1) Fast Flux Test Facility Fuel--Fifty-three interim storage casks (ISC), each holding a core component container (CCC), will be used to store the Fast Flux Test Facility (FFTF) SNF currently in the 400 Area. (2) Neutron Radiography Facility (NRF) TRIGA'--One Rad-Vault' container will store two DOT-6M3 containers and six NRF TRIGA casks currently stored in the 400 Area. (3) Commercial Light Water Reactor Fuel--Six International Standards Organization (ISO) containers, each holding a NAC-I cask4 with an inner commercial light water reactor (LWR) canister, will be used for commercial LWR SNF from the 300 Area. An aboveground dry cask storage location is necessary for the spent fuel because the current storage facilities are being shut down and deactivated. The spent fuel is being transferred to interim storage because there is no permanent repository storage currently available

Data Analysis of GPM Constellation Satellites-IMERG and ERA-Interim precipitation products over West of Iran

Science.gov (United States)

Sharifi, Ehsan; Steinacker, Reinhold; Saghafian, Bahram

2016-04-01

Precipitation is a critical component of the Earth's hydrological cycle. The primary requirement in precipitation measurement is to know where and how much precipitation is falling at any given time. Especially in data sparse regions with insufficient radar coverage, satellite information can provide a spatial and temporal context. Nonetheless, evaluation of satellite precipitation is essential prior to operational use. This is why many previous studies are devoted to the validation of satellite estimation. Accurate quantitative precipitation estimation over mountainous basins is of great importance because of their susceptibility to hazards. In situ observations over mountainous areas are mostly limited, but currently available satellite precipitation products can potentially provide the precipitation estimation needed for meteorological and hydrological applications. One of the newest and blended methods that use multi-satellites and multi-sensors has been developed for estimating global precipitation. The considered data set known as Integrated Multi-satellitE Retrievals (IMERG) for GPM (Global Precipitation Measurement) is routinely produced by the GPM constellation satellites. Moreover, recent efforts have been put into the improvement of the precipitation products derived from reanalysis systems, which has led to significant progress. One of the best and a worldwide used model is developed by the European Centre for Medium Range Weather Forecasts (ECMWF). They have produced global reanalysis daily precipitation, known as ERA-Interim. This study has evaluated one year of precipitation data from the GPM-IMERG and ERA-Interim reanalysis daily time series over West of Iran. IMERG and ERA-Interim yield underestimate the observed values while IMERG underestimated slightly and performed better when precipitation is greater than 10mm. Furthermore, with respect to evaluation of probability of detection (POD), threat score (TS), false alarm ratio (FAR) and probability

Interim Storage of Spent Nuclear Fuel before Final Disposal in Germany - Regulator's view

International Nuclear Information System (INIS)

Arens, G.; Goetz, Ch.; Geupel, Sandra; Gmal, B.; Mester, W.

2014-01-01

For spent nuclear fuel management in Germany the concept of dry interim storage in dual purpose casks before direct disposal is applied. The Federal Office for Radiation Protection (BfS) is the competent authority for licensing of interim storage facilities. The competent authority for surveillance of operation is the responsible authority of the respective federal state (Land). Currently operation licenses for storage facilities have been granted for a storage time of 40 years and are based on safety demonstrations for all safety issues as safe enclosure, shielding, sub-criticality and decay heat removal under consideration of operation conditions. In addition, transportability of the casks for the whole storage period has to be provided. Due to current delay in site selection and exploration of a disposal site, an extension of the storage time beyond 40 years could be needed. This will cause appropriate actions by the licensee and the competent authorities as well. A brief description of the regulatory base of licensing and surveillance of interim storage is given from the regulators view. Furthermore the current planning for final disposal of spent nuclear fuel and high level waste and its interconnections between storage and disposal concepts are shortly explained. Finally the relevant aspects for licensing of extended storage time beyond 40 years will be discussed. Current activities on this issue, which have been initiated by the Federal Government, will be addressed. On the regulatory side a review and amendment of the safety guideline for interim storage of spent fuel has been performed and the procedure of periodic safety review is being implemented. A guideline for implementing an ageing management programme is available in a draft version. Regarding safety of long term storage a study focussing on the identification and evaluation of long term effects as well as gaps of knowledge has been finished in 2010. A continuation and update is currently underway

Proposed plan for interim remedial measures at the 100-KR-1 Operable Unit. Revision 1

International Nuclear Information System (INIS)

1995-09-01

This proposed plan identifies the preferred alternative for interim remedial measures for remedial action of radioactive liquid waste disposal sites that include contaminated soils and structures at the 100-KR-1 Operable Unit, located at the Hanford Site. It also summarizes other remedial alternatives evaluated for interim remedial measures in this Operable Unit. The intent of interim remedial measures is to speed up actions to address contaminated areas that pose potential threats to human health and the environment. This proposed plan is being issued by the US Environmental Protection Agency (EPA), the lead regulatory agency; the Washington State Department of Ecology (Ecology), the support regulatory agency; and the US Department of Energy (DOE), the responsible agency. The EPA, Ecology, and the DOE are issuing this proposed plan as part of their public participation responsibilities under Section 117(a) of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), commonly known as the ''Superfund Law.'' This proposed plan is intended to be a fact sheet for public review which briefly describes the remedial alternatives analyzed, identifies a preferred alternative, and summarizes the information relied upon to recommend the preferred alternative

Interim policy on establishment and operation of internet open, anonymous information servers and services

OpenAIRE

Acting Dean of Computer and Information Services

1995-01-01

Purpose. To establish interim NPS general policy regarding establishment and operation of Open, Anonymous Information Servers and Services, such as World Wide Web (http), Gopher, Anonymous FTP, etc...

FedEx Gasoline Hybrid Electric Delivery Truck Evaluation: 6-Month Interim Report

Energy Technology Data Exchange (ETDEWEB)

Barnitt, R.

2010-05-01

This interim report presents partial (six months) results for a technology evaluation of gasoline hybrid electric parcel delivery trucks operated by FedEx in and around Los Angeles, CA. A 12 month in-use technology evaluation comparing in-use fuel economy and maintenance costs of GHEVs and comparative diesel parcel delivery trucks was started in April 2009. Comparison data was collected and analyzed for in-use fuel economy and fuel costs, maintenance costs, total operating costs, and vehicle uptime. In addition, this interim report presents results of parcel delivery drive cycle collection and analysis activities as well as emissions and fuel economy results of chassis dynamometer testing of a gHEV and a comparative diesel truck at the National Renewable Energy Laboratory's (NREL) ReFUEL laboratory. A final report will be issued when 12 months of in-use data have been collected and analyzed.

T-TY Tank Farm Interim Surface Barrier Demonstration - Vadose Zone Monitoring Plan

International Nuclear Information System (INIS)

Zhang, Z.F.; Strickland, Christopher E.; Field, Jim G.; Parker, Danny L.

2010-01-01

The Hanford Site has 149 underground single-shell tanks that store hazardous radioactive waste. Many of these tanks and their associated infrastructure (e.g., pipelines, diversion boxes) have leaked. Some of the leaked waste has entered the groundwater. The largest known leak occurred from the T-106 Tank of the 241-T Tank Farm in 1973. Five tanks are assumed to have leaked in the TY Farm. Many of the contaminants from those leaks still reside within the vadose zone within the T and TY Tank Farms. The Department of Energy's Office of River Protection seeks to minimize the movement of these contaminant plumes by placing interim barriers on the ground surface. Such barriers are expected to prevent infiltrating water from reaching the plumes and moving them further. The soil water regime is monitored to determine the effectiveness of the interim surface barriers. Soil-water content and water pressure are monitored using off-the-shelf equipment that can be installed by the hydraulic hammer technique. Four instrument nests were installed in the T Farm in fiscal year (FY) 2006 and FY2007; two nests were installed in the TY Farm in FY2010. Each instrument nest contains a neutron probe access tube, a capacitance probe, and four heat-dissipation units. A meteorological station has been installed at the north side of the fence of the T Farm. This document summarizes the monitoring methods, the instrument calibration and installation, and the vadose zone monitoring plan for interim barriers in T farm and TY Farm.

Current status of the first interim spent fuel storage facility in Japan

International Nuclear Information System (INIS)

Shinbo, Hitoshi; Kondo, Mitsuru

2008-01-01

In Japan, storage of spent fuels outside nuclear power plants was enabled as a result of partial amendments to the Nuclear Reactor Regulation Law in June 2000. Five months later, Mutsu City in Aomori Prefecture asked the Tokyo Electric Power Company (TEPCO) to conduct technical surveys on siting of the interim spent fuel storage facility (we call it 'Recyclable-Fuel Storage Center'). In April 2003, TEPCO submitted the report on siting feasibility examination, concluded that no improper engineering data for siting, construction of the facility will be possible from engineering viewpoint. Siting Activities for publicity and public acceptance have been continued since then. After these activities, Aomori Prefecture and Mutsu City approved siting of the Recyclable Fuel Storage Center in October 2005. Aomori Prefecture, Mutsu City, TEPCO and Japan Atomic Power Company (JAPC) signed an agreement on the interim spent fuel storage Facility. A month later, TEPCO and JAPC established Recyclable-Fuel Storage Company (RFS) in Mutsu City through joint capital investment, specialized in the first interim spent fuel storage Facility in Japan. In May 2007, we made an application for establishment permit, following safety review by regulatory authorities. In March 2008, we started the preparatory construction. RFS will safely store of spent fuels of TEPCO and JAPC until they will be reprocessed. Final storage capacity will be 5,000 ton-U. First we will construct the storage building of 3,000 ton-U to be followed by second building. We aim to start operation by 2010. (author)

Basis for Interim Operation for Fuel Supply Shutdown Facility

International Nuclear Information System (INIS)

BENECKE, M.W.

2003-01-01

This document establishes the Basis for Interim Operation (BIO) for the Fuel Supply Shutdown Facility (FSS) as managed by the 300 Area Deactivation Project (300 ADP) organization in accordance with the requirements of the Project Hanford Management Contract procedure (PHMC) HNF-PRO-700, ''Safety Analysis and Technical Safety Requirements''. A hazard classification (Benecke 2003a) has been prepared for the facility in accordance with DOE-STD-1027-92 resulting in the assignment of Hazard Category 3 for FSS Facility buildings that store N Reactor fuel materials (303-B, 3712, and 3716). All others are designated Industrial buildings. It is concluded that the risks associated with the current and planned operational mode of the FSS Facility (uranium storage, uranium repackaging and shipment, cleanup, and transition activities, etc.) are acceptable. The potential radiological dose and toxicological consequences for a range of credible uranium storage building have been analyzed using Hanford accepted methods. Risk Class designations are summarized for representative events in Table 1.6-1. Mitigation was not considered for any event except the random fire event that exceeds predicted consequences based on existing source and combustible loading because of an inadvertent increase in combustible loading. For that event, a housekeeping program to manage transient combustibles is credited to reduce the probability. An additional administrative control is established to protect assumptions regarding source term by limiting inventories of fuel and combustible materials. Another is established to maintain the criticality safety program. Additional defense-in-depth controls are established to perform fire protection system testing, inspection, and maintenance to ensure predicted availability of those systems, and to maintain the radiological control program. It is also concluded that because an accidental nuclear criticality is not credible based on the low uranium enrichment

Waste Management Program. Technical progress report, October-December 1982

International Nuclear Information System (INIS)

1983-07-01

This quarterly report provides current information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant and offplant participants. The studies on environmental and safety assessments, in situ storage or disposal, waste from development and characterization, process and equipment development, and low-level waste management are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations Program: surveillance and maintenance, waste concentration, low-level effluent waste, tank replacement/waste transfer, and solid waste storage and related activities

Nuclear waste: Is there a need for federal interim storage

International Nuclear Information System (INIS)

1989-01-01

The Congress created the Monitored Retrievable Storage Review Commission to provide a report on the need for a Federal monitored retrievable storage facility (MRS) as part of the Nation's nuclear waste management system. The Commission concludes that the MRS as presently described in the law, which links the capacity and schedule of operation of the MRS to a permanent geologic repository, cannot be justified. The Commission finds, however, that while no single factor would favor an MRS over the No-MRS option, cumulatively the advantages of an MRS would justify the building of an MRS if: there were no linkages between the MRS and the repository; the MRS could be constructed at an early date; and the opening of the repository were delayed considerably beyond its presently scheduled date of operation. The Commission therefore recommends that the Congress take the following actions: Authorize construction of a Federal Emergency Storage facility with a capacity limit of 2,000 metric tons of uranium; Authorize construction of a User-Funded Interim Storage facility with a capacity limit of 5,000 metric tons of uranium; Reconsider the subject of interim storage by the year 2000

Annex D 200 Area Interim Storage Area Final Safety Analysis Report Volume 5 (FSAR) (Section 1 and 2)

International Nuclear Information System (INIS)

CARRELL, R.D.

2003-01-01

The 200 Area Interim Storage Area (200 Area ISA) at the Hanford Site provides for the interim storage of non-defense reactor spent nuclear fuel (SNF) housed in aboveground dry cask storage systems. The 200 Area ISA is a relatively simple facility consisting of a boundary fence with gates, perimeter lighting, and concrete and gravel pads on which to place the dry storage casks. The fence supports safeguards and security and establishes a radiation protection buffer zone. The 200 Area ISA is nominally 200,000 ft 2 and is located west of the Canister Storage Building (CSB). Interim storage at the 200 Area ISA is intended for a period of up to 40 years until the materials are shipped offsite to a disposal facility. This Final Safety Analysis Report (FSAR) does not address removal from storage or shipment from the 200 Area ISA. Three different SNF types contained in three different dry cask storage systems are to be stored at the 200 Area ISA, as follows: (1) Fast Flux Test Facility (FFTF) Fuel--Fifty-three interim storage casks (ISC), each holding a core component container (CCC), will be used to store the FFTF SNF currently in the 400 Area. (2) Neutron Radiography Facility (NRF)TRIGA--One Rad-Vault container stores two DOT-6M 3 containers and six NRF TRIGA casks. (3) Commercial Light Water Reactor Fuel--Six International Standards Organization (ISO) containers, each holding a NAC-1 cask with an inner commercial light water reactor (LWR) canister, are used for storing commercial LWR SNF from the 300 Area. An aboveground dry cask storage location is necessary for the spent fuel because the current storage facilities are being shut down and deactivated. The spent fuel is being transferred to interim storage because there is no permanent repository storage currently available

Concepts for the interim storage of spent fuel elements from research reactors in the Federal Republic of Germany

International Nuclear Information System (INIS)

Niephaus, D.; Bensch, D.; Quaassdorff, P.; Plaetzer, S.

1997-01-01

Research reactors have been operated in the Federal Republic of Germany since the late fifties. These are Material Test Reactors (MTR) and training, Research and Isotope Facilities of General Atomic (TRIGA). A total of seven research reactors, i.e. three TRIGA and four MTR facilities were still in operation at the beginning of 1996. Provisions to apply to the back-end of the fuel cycle are required for their continued operation and for already decommissioned plants. This was ensured until the end of the eighties by the reprocessing of spent fuel elements abroad. In view of impeding uncertainties in connection with waste management through reprocessing abroad, the development of a national back-end fuel cycle concept was commissioned by the Federal Minister of Education, Science, Research and Technology in early 1990. Development work was oriented along the lines of the disposal concept for irradiated light-water reactor fuel elements from nuclear power plants. Analogously, the fuel elements from research reactors are to be interim-stored on a long-term basis in adequately designed transport and storage casks and then be directly finally disposed without reprocessing after up to forty years of interim storage. As a first step in the development of a concept for interim storage, several sites with nuclear infrastructure were examined and assessed with respect to their suitability for interim storage. A reasonably feasible reference concept for storing the research reactor fuel elements in CASTOR MTR 2 transport and storage casks at the Ahaus interim storage facility (BZA) was evaluated and the hot cell facility and AVR store of Forschungszentrum Juelich (KFA) were proposed as an optional contingency concept for casks that cannot be repaired at Ahaus. Development work was continued with detailed studies on these two conceptual variants and the results are presented in this paper. (author)

Implementation of the Ryan Haight Online Pharmacy Consumer Protection Act of 2008. Interim final rule with request for comments.

Science.gov (United States)

2009-04-06

The Ryan Haight Online Pharmacy Consumer Protection Act, which was enacted on October 15, 2008, amended the Controlled Substances Act and Controlled Substances Import and Export Act by adding several new provisions to prevent the illegal distribution and dispensing of controlled substances by means of the Internet. DEA is hereby issuing an interim rule to amend its regulations to implement the legislation and is requesting comments on the interim rule.

Colonie Interim Storage Site annual environmental report for calendar year 1991, Colonie, New York

International Nuclear Information System (INIS)

1992-09-01

This document describes the environmental monitoring program at the Colonie Interim Storage Site (CISS) and surrounding area, implementation of the program, and monitoring results for 1991. Environmental monitoring at CISS began in 1984 when Congress added the site to the US Department of Energy's Formerly Utilized Sites Remedial Action Program. CISS property and surrounding areas were radioactively contaminated by operations conducted by National Lead Industries, which manufactured various components from uranium and thorium from 1958 to 1984. The environmental monitoring program at CISS includes sampling networks for external gamma radiation exposure and for radium-226, thorium-232, and total uranium concentrations in surface water, sediment, and groundwater. Additionally, several nonradiological parameters are measured in groundwater. In 1992 the program will also include sampling networks for radioactive and chemical contaminants in stormwater to meet permit application requirements under the Clean Water Act. Monitoring results are compared with applicable Environmental Protection Agency (EPA) standards, DOE derived concentration guides (DCGs), dose limits, and other requirements in DOE.orders. Environmental standards are established to protect public health and the environment. Results of environmental monitoring during 1991 indicate that average concentrations of radioactive contaminants of concern were well below applicable standards and DCGS. Concentrations of some chemical contaminants in groundwater were above-the New York State Department of Environmental Conservation (Class GA) and EPA guidelines for drinking water. The potential annual radiation exposure (excluding background) calculated for a hypothetical maximally exposed individual is 0.23 mrem (milliroentgen equivalent man), which is less than an individual would receive while traveling in an airplane at 12,000 meters (39,000 feet) for one hour

Criticality safety evaluation for long term storage of FFTF fuel in interim storage casks

International Nuclear Information System (INIS)

Richard, R.F.

1995-01-01

It has been postulated that a degradation phenomenon, referred to as ''hot cell rot'', may affect irradiated FFTF mixed plutonium-uranium oxide (MOX) fuel during dry interim storage. ''Hot cell rot'' refers to a variety of phenomena that degrade fuel pin cladding during exposure to air and inert gas environments. It is thought to be a form of caustic stress corrosion cracking or environmentally assisted cracking. Here, a criticality safety analysis was performed to address the effect of the ''hot cell rot'' phenomenon on the long term storage of irradiated FFTF fuel in core component containers. The results show that seven FFTF fuel assemblies or six Ident-69 pin containers stored in core component containers within interim storage casks will remain safely subcritical

Report of the first interim meeting of the Seabed Working Group Engineering Studies Task Group

International Nuclear Information System (INIS)

Talbert, D.M.

1982-02-01

The first interim meeting of the Engineering Studies Task Group (ESTG) was held at the Delft Soil Mechanics Laboratory, Delft, The Netherlands, on 21-24 September 1981. The main business of the meeting was the development of a network analysis for the ESTG. Significant progress was made; however, substantial further development remains to be accomplished. Other items discussed were (1) progress relevant to engineering studies made in the various national programs since the sixth annual meeting of the Seabed Working Group (SWG) held in Paris, February, 1981; (2) the ESTG Boundary Conditions and Scope of Work as previously defined at the Paris meeting; (3) the Draft II SWG Five-Year Plan; (4) the deep ocean drilling proposal made by the Site Selection Task Group at the Paris meeting and expanded upon at their May, 1981, meeting; and (5) a recent compilation of data from the Nares Abyssal Plain arising from the US Program studies. Finally, consideration was given to a plan for continued work by the ESTG. A brief discussion of the principal items is given. The current state of the network analysis is shown

46 CFR 308.302 - Issuance of interim binder; terms and conditions.

Science.gov (United States)

2010-10-01

... OPERATIONS WAR RISK INSURANCE Second Seamen's War Risk Insurance § 308.302 Issuance of interim binder; terms..., conditions, and warranties contained in the application for Second Seamen's war risk insurance (set forth in § 308.3) and the Second Seamen's War Risk Policy (1955) (set forth in § 308.306) to the same extent as...

Safety evaluation of interim stabilization of non-stabilized single-shell watch list tanks

Energy Technology Data Exchange (ETDEWEB)

Stahl, S.M.

1994-12-30

The report provides a summation of the status of safety issues associated with interim stabilization of Watch List SSTs (organic, ferrocyanide, and flammable gas), as extracted from recent safety analyses, including the Tank Farms Accelerated Safety Analysis efforts.

Safety evaluation of interim stabilization of non-stabilized single-shell watch list tanks

International Nuclear Information System (INIS)

Stahl, S.M.

1994-01-01

The report provides a summation of the status of safety issues associated with interim stabilization of Watch List SSTs (organic, ferrocyanide, and flammable gas), as extracted from recent safety analyses, including the Tank Farms Accelerated Safety Analysis efforts

National NIF Diagnostic Program Fiscal Year 2002 Second Quarter Report

International Nuclear Information System (INIS)

MacGowan, B

2002-01-01

Since October 2001 the development of the facility diagnostics for NIF has been funded by the NIF Director through the National NIF Diagnostic Program (NNDP). The current emphasis of the NNDP is on diagnostics for the early NIF quad scheduled to be available for experiment commissioning in FY03. During the past six months the NNDP has set in place processes for funding diagnostics, developing requirements for diagnostics, design reviews and monthly status reporting. Those processes are described in an interim management plan for diagnostics (National NIF Diagnostic Program Interim Plan, NIF-008 13 15, April 2002) and a draft Program Execution Plan (Program Execution Plan for the National NlF Diagnostic Program, NIF-0072083, October 2001) and documents cited therein. Work has been funded at Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Naval Research Laboratory (NRL), Sandia National Laboratories (SNL), Bechtel Nevada at Los Alamos and Santa Barbara. There are no major technical risks with the early diagnostics. The main concerns relate to integration of the diagnostics into the facility, all such issues are being worked. This report is organized to show the schedule and budget status and a summary of Change Control Board actions for the past six months. The following sections then provide short descriptions of the status of each diagnostic. Where design reviews or requirements documents are cited, the documents are available on the Diagnostics file server or on request

Cna 1 spent fuel element interim dry storage system thermal analysis

International Nuclear Information System (INIS)

Hilal, R. E; Garcia, J. C; Delmastro, D. F

2006-01-01

At the moment, the Atucha I Nuclear Power Plant (Cnea-I) located in the city of Lima, has enough room to store its spent fuel (Sf) in their two pools spent fuel until about 2015.In case of life extension a spend fuel element interim dry storage system is needed.Nucleolectrica Argentina S.A. (N A-S A) and the Comision Nacional de Energia Atomica (Cnea), have proposed different interim dry storage systems.These systems have to be evaluated in order to choose one of them.The present work's objective is the thermal analysis of one dry storage alternative for the Sf element of Cna 1.In this work a simple model was developed and used to perform the thermal calculations corresponding to the system proposed by Cnea.This system considers the store of sealed containers with 37 spent fuels in concrete modules.Each one of the containers is filled in the pool houses and transported to the module in a transference cask with lead walls.Fulfill the maximum cladding temperature requirement ( [es

Hanford low-level tank waste interim performance assessment

International Nuclear Information System (INIS)

Mann, F.M.

1997-01-01

The Hanford Low-Level Tank Waste Interim Performance Assessment examines the long-term environmental and human health effects associated with the disposal of the low-level fraction of the Hanford single and double-shell tank waste in the Hanford Site 200 East Area. This report was prepared as a good management practice to provide needed information about the relationship between the disposal system design and performance early in the disposal system project cycle. The calculations in this performance assessment show that the disposal of the low-level fraction can meet environmental and health performance objectives

Wayne Interim Storage Site environmental report for calendar year 1992, 868 Black Oak Ridge Road, Wayne, New Jersey

International Nuclear Information System (INIS)

1993-05-01

This report describes the environmental surveillance program at the Wayne Interim Storage Site (WISS) and provides the results for 1992. The fenced, site, 32 km (20 mi) northwest of Newark, New Jersey, was used between 1948 and 1971 for commercial processing of monazite sand to separate natural radioisotopes - predominantly thorium. Environmental surveillance of WISS began in 1984 in accordance with Department of Energy (DOE) Order 5400.1 when Congress added the site to DOE's Formerly Utilized Sites Remedial Action Program (FUSRAP). The environmental surveillance program at WISS includes sampling networks for radon and thoron in air; external gamma radiation exposure; radium-226, radium-228, thorium-230, thorium-232, total uranium, and several chemicals in surface water and sediment; and total uranium, radium-226, radium-228, thorium-230, thorium-232, and organic and inorganic chemicals in groundwater. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and state standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. This monitoring program assists in fulfilling the DOE policy of measuring and monitoring effluents from DOE activities and calculating hypothetical doses. Results for environmental surveillance in 1992 show that the concentrations of all radioactive and most chemical contaminants were below applicable standards

Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

International Nuclear Information System (INIS)

Pickett, W.W.

1997-01-01

This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations

Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

Energy Technology Data Exchange (ETDEWEB)

Pickett, W.W.

1997-12-30

This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations.

EFFECT OF REHABILITATION DURING INTERIM STAY IN AALBORG MUNICIPALITY, DENMARK: A STUDY PROTOCOL

DEFF Research Database (Denmark)

Villumsen, Sidsel Maria Monrad; Villumsen, Morten

2016-01-01

Background: In the municipality of Aalborg, Denmark, the aim is to support citizens’ rehabilitation through training and learning in order to be self-reliant. This effort is supported at interim stays at the nursing homes [1]. A recent external report has outlined that citizen are highly satis ed...... are available in the systems, containing information on rehabilitation services rendered during interim stays. However, available data on the effect of the rehabilitation are currently unstructured in free-text, which impedes the assessment of rehabilitation effect and thereby the quality assurance. Objectives...... on rehabilitation of the citizen. The rehabilitation effect will be extracted from the free-text in the records. The free-text will be categorized into rehabilitation effects of i) deterioration, ii) no effect, iii) effect of rehabilitation, or iv) not possible to classify from the text. Results: This study...

Reinforcement of a PMMA resin for interim fixed prostheses with silica nanoparticles.

Science.gov (United States)

Topouzi, Marianthi; Kontonasaki, Eleana; Bikiaris, Dimitrios; Papadopoulou, Lambrini; Paraskevopoulos, Konstantinos M; Koidis, Petros

2017-05-01

Fractures in long span provisional/interim restorations are a common complication. Adequate fracture toughness is necessary to resist occlusal forces and crack propagation, so these restorations should be constructed with materials of improved mechanical properties. The aim of this study was to investigate the possible reinforcement of neat silica nanoparticles and trietoxyvinylsilane-modified silica nanoparticles in a PMMA resin for fixed interim restorations. Composite PMMA-Silica nanoparticles powders were mixed with PMMA liquid and compact bar shaped specimens were fabricated according to the British standard BS EN ISO 127337:2005. The single-edge notched method was used to evaluate fracture toughness (three-point bending test), while the dynamic thermomechanical properties (Storage Modulus, Loss Modulus, tanδ) of a series of nanocomposites with different amounts of nanoparticles (0.25%, 0.50%, 0.75%, 1% w.t.) were evaluated. Statistical analysis was performed and the statistically significant level was set to pPMMA resins used in fixed provisional restorations. Copyright © 2017 Elsevier Ltd. All rights reserved.

Analysis of the interim safe storage of reactors at the Hanford site

International Nuclear Information System (INIS)

Wang Hailiang

2014-01-01

The nine production reactors, i.e. B, C, D, DR, F, H, KE, KW and N, at the Hanford site are all water-cooled and graphite-moderated reactors with natural uranium fuel. In 1993, the U.S. Department of Energy (DOE) decided to put eight production reactors (except for B) into Interim Safe Storage (ISS) for 75 years followed by deferred one-piece removal. Reactor B will remain as a national historical landmark. By the end of 2013, six reactors C, F, D, DR, H and N had been successfully put into the ISS. Reactors KE and KW will be put into the ISS in the coming years. Taking reactor C as an example, this paper mainly talks about how to put the production reactors in the Interim Safe Storage, e.g. how to make site preparation, how to construct the safe storage enclosure (SSE) and how to perform surveillance and maintenance during the ISS period, etc. (authors)

Transport casks help solve spent fuel interim storage problems

International Nuclear Information System (INIS)

Dierkes, P.; Janberg, K.; Baatz, H.; Weinhold, G.

1980-01-01

Transport casks can be used as storage modules, combining the inherent safety of passive cooling with the absence of secondary radioactive waste and the flexibility to build up storage capacity according to actual requirements. In the Federal Republic of Germany, transport casks are being developed as a solution to its interim storage problems. Criteria for their design and licensing are outlined. Details are given of the casks and the storage facility. Tests are illustrated. (U.K.)

Interim report on nodel evaluation methodology and the evaluation of LEAP

Energy Technology Data Exchange (ETDEWEB)

Alsmiller, R.G. Jr.; Barish, J.; Bjornstad, D.

1980-04-01

This report describes progress made at ORNL toward development and demonstration of a methodology for evaluating energy-economic modeling codes and important results derived from these codes. To bolster traditional evaluation methods with more-quantitative procedures of interest to the Energy Information Administration, ORNL is applying sensitivity theory as part of a comprehensive effort to quantify the importance of various data and model parameters to the key results that are of interest. The Long-Term Energy Analysis Program (LEAP) was chosen as the initial focus for the research. LEAP is an energy-economy model which resides in the Long-Term Energy Analysis Division (LTEAD) of the Integrative Analysis Group in the Office of Applied Analysis, EIA. LTEAD developed Model 22C of LEAP for two reasons: (1) to prepare projections through the year 2020, which were needed for the 1978 EIA Annual Report to Congress and (2) to develop a base for analyses of specific options for Federal action. LEAP Model 22C and its uses are described to provide the background for this interim description of the model evaluation effort at ORNL. 19 figures, 10 tables.

400-MWe Consolidated Nuclear Steam System (CNSS). 1200-MWt Phase 2A interim studies. [PWR

Energy Technology Data Exchange (ETDEWEB)

1978-09-01

The Phase 2A interim studies of the Consolidated Nuclear Steam System (CNSS) consisted of a number of separate task studies addressing the design concepts developed during the Phase 1 study reported in BAW--1445. The purpose of the interim studies was to better establish overall concept feasibility from both a hardware and economic standpoint, to make modification and additions to the design where appropriate, and to understand and reduce the technical risks in critical areas of the design. The work on these task studies included input from Barberton, Mt. Vernon, and the Alliance Research Center as well as United Engineers and Constructors (UE and C). The UE and C work was carried out under a separate DOE contract.

Safety report for Central Interim Storage facility for radioactive waste from small producers

International Nuclear Information System (INIS)

Zeleznik, N.; Mele, I.

2004-01-01

In 1999 the Agency for Radwaste Management took over the management of the Central Interim Storage (CIS) in Brinje, intended only for radioactive waste from industrial, medical and research applications. With the transfer of the responsibilities for the storage operation, ARAO, the new operator of the facility, received also the request from the Slovenian Nuclear Safety Administration for refurbishment and reconstruction of the storage and for preparation of the safety report for the storage with the operational conditions and limitations. In order to fulfill these requirements ARAO first thoroughly reviewed the existing documentation on the facility, the facility itself and the stored inventory. Based on the findings of this review ARAO prepared several basic documents for improvement of the current conditions in the storage facility. In October 2000 the Plan for refurbishment and modernization of the CIS was prepared, providing an integral approach towards remediation and refurbishment of the facility, optimization of the inventory arrangement and modernization of the storage and storing utilization. In October 2001 project documentation for renewal of electric installations, water supply and sewage system, ventilation system, the improvements of the fire protection and remediation of minor defects discovered in building were completed according to the Act on Construction. In July 2003 the safety report was prepared, based on the facility status after the completion of the reconstruction works. It takes into account all improvements and changes introduced by the refurbishment and reconstruction of the facility according to project documentation. Besides the basic characteristics of the location and its surrounding, it also gives the technical description of the facility together with proposed solutions for the renewal of electric installations, renovation of water supply and sewage system, refurbishment of the ventilation system, the improvement of fire

Fabrication of an interim complete removable dental prosthesis with an in-office digital light processing three-dimensional printer: A proof-of-concept technique.

Science.gov (United States)

Lin, Wei-Shao; Harris, Bryan T; Pellerito, John; Morton, Dean

2018-04-30

This report describes a proof of concept for fabricating an interim complete removable dental prosthesis with a digital light processing 3-dimensional (3D) printer. Although an in-office 3D printer can reduce the overall production cost for an interim complete removable dental prosthesis, the process has not been validated with clinical studies. This report provided a preliminary proof of concept in developing a digital workflow for the in-office additively manufactured interim complete removable dental prosthesis. Copyright © 2018 Editorial Council for the Journal of Prosthetic Dentistry. Published by Elsevier Inc. All rights reserved.

Cost Implications of an Interim Storage Facility in the Waste Management System

Energy Technology Data Exchange (ETDEWEB)

Jarrell, Joshua J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Joseph, III, Robert Anthony [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Howard, Rob L [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Petersen, Gordon M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Nutt, Mark [Argonne National Lab. (ANL), Argonne, IL (United States); Carter, Joe [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Cotton, Thomas [Complex Systems Group, Bozeman, MT (United States)

2016-09-01

This report provides an evaluation of the cost implications of incorporating a consolidated interim storage facility (ISF) into the waste management system (WMS). Specifically, the impacts of the timing of opening an ISF relative to opening a repository were analyzed to understand the potential effects on total system costs.

Medicare and Medicaid programs; advance directives--HCFA. Final rule.

Science.gov (United States)

1995-06-27

This final rule responds to public comments on the March 6, 1992 interim final rule with comment period that amended the Medicare and Medicaid regulations governing provider agreements and contracts to establish requirements for States, hospitals, nursing facilities, skilled nursing facilities, providers of home health care or personal care services, hospice programs and managed care plans concerning advance directives. An advance directive is a written instruction, such as a living will or durable power of attorney for health care, recognized under State law, relating to the provision of health care when an individual's condition makes him or her unable to express his or her wishes. The intent of the advance directives provisions is to enhance an adult individual's control over medical treatment decisions. This rule confirms the interim final rule with several minor changes based on our review and consideration of public comments.

Hazelwood Interim Storage Site annual site environmental report: Calendar year 1986

International Nuclear Information System (INIS)

1987-06-01

During 1986, the environmental monitoring program was continued at the Hazelwood Interim Storage Site (HISS), a US Department of Energy (DOE) facility located in the City of Hazelwood, Missouri. Originally known as the Cotter Corporation site on Latty Avenue in Hazelwood, the HISS is presently used for the storage of soils contaminated with residual radioactive material. As part of the decontamination research and development project authorized by Congress under the 1984 Energy and Water Appropriations Act, remedial action and environmental monitoring program are being conducted at the site and at vicinity properties by Bechtel National, Inc., Project Management Contractor for FUSRAP. The monitoring program at the HISS measures radon gas concentrations in air; external gamma radiation levels; and uranium, radium, and thorium concentrations in surface water, groundwater, and sediment. To verify that the site is in compliance with the DOE radiation protection standard (100 mrem/yr) and assess its potential effect on public health, the radiation dose was calculated for the maximally exposed individual. Based on the scenario described in this report, the maximally exposed individual at the HISS would receive an annual external exposure approximately equivalent to 2% of the DOE radiation protection standard of 100 mrem/yr. This exposure is less than the exposure a person would receive during a round-trip flight from New York to Los Angeles. The cumulative dose to the population within an 80-km (50-mi) radius of the HISS that would result from radioactive materials present at the site would be indistinguishable from the dose that the same population would receive from naturally occurring radioactive sources. Results of the 1986 monitoring show that the HISS is in compliance with the DOE radiation protection standard. 11 refs., 6 figs., 10 tabs

High Temperature Materials Interim Data Qualification Report FY 2011

International Nuclear Information System (INIS)

Lybeck, Nancy

2011-01-01

Projects for the very high temperature reactor (VHTR) Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) to ensure that VHTR data are qualified for use, stored in a readily accessible electronic form, and analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the High Temperature Materials characterization data stream, the processing of these data within NDMAS, and reports the interim fiscal year (FY) 2011 qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. The High Temperature Materials data are being collected under the Nuclear Quality Assurance (NQA)-1 guidelines and will be qualified data. For NQA-1 qualified data, the qualification activities include: (1) capture testing to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing to confirm that the data are an accurate representation of the system or object being measured, and (3) documenting that the data were collected under an NQA-1 or equivalent Quality Assurance program. Currently, data from seven test series within the High Temperature Materials data stream have been entered into the NDMAS vault, including tensile tests, creep tests, and cyclic tests. Of the 5,603,682 records currently in the vault, 4,480,444 have been capture passed, and capture testing is in process for the remaining 1,123,238.

First interim examination of defected BWR and PWR rods tested in unlimited air at 2290C

International Nuclear Information System (INIS)

Einziger, R.E.; Cook, J.A.

1983-01-01

A five-year whole rod test was initiated to investigate the long-term stability of spent fuel rods under a variety of possible dry storage conditions. Both PWR and BWR rods were included in the test. The first interim examination was conducted after three months of testing to determine if there was any degradation in those defected rods stored in an unlimited air atmosphere. Visual observations, diametral measurements and radiographic smears were used to assess the degree of cladding deformation and particulate dispersal. The PWR rod showed no measurable change from the pre-test condition. The two original artificial defects had not changed in appearance and there was no diametral growth of the cladding. One of the defects in BWR rod showed significant deformation. There was approximately 10% cladding strain at the defect site and a small axial crack had formed. The fuel in the defect did not appear to be friable. The second defect showed no visible change and no cladding strain. Following examination, the test was continued at 230 0 C. Another interim examination is planned during the summer of 1983. This paper discusses the details and meaning of the data from the first interim examination

Maywood Interim Storage Site environmental report for calendar year 1992, 100 West Hunter Avenue, Maywood, New Jersey

International Nuclear Information System (INIS)

1993-05-01

This report describes the environmental surveillance program at the Maywood Interim Storage Site (MISS) and provides the results for 1992. Environmental monitoring of MISS began in 1984, when the site was assigned to DOE by Congress through the Energy and Water Development Appropriations Act and was placed under DOE's Formerly Utilized Sites Remedial Action Program (FUSRAP). FUSRAP was established to identify and decontaminate or otherwise control sites where residual radioactive materials remain from the early years of the nation's atomic energy program or from commercial operations causing conditions that Congress has authorized DOE to remedy. MISS is part of a National Priorities List (NPL) site. The environmental surveillance program at MISS includes sampling networks for radon and thoron in air; external gamma radiation exposure; and radium-226, radium-228, thorium-232, and total uranium in surface water, sediment, and groundwater. Additionally, chemical analysis includes metals and organic compounds in surface water and groundwater and metals in sediments. This program assists in fulfilling the DOE objective of measuring and monitoring effluents from DOE activities and calculating hypothetical doses to members of the general public. Monitoring results are compared with applicable Environmental Protection Agency (EPA) and state standards, DOE derived concentration guides (DCGs), dose limits, and other DOE requirements. Environmental standards are established to protect public health and the environment. The radiological data for all media sampled support the conclusion that doses to the public are not distinguishable from natural background radiation

A web-based endpoint adjudication system for interim analyses in clinical trials.

Science.gov (United States)

Nolen, Tracy L; Dimmick, Bill F; Ostrosky-Zeichner, Luis; Kendrick, Amy S; Sable, Carole; Ngai, Angela; Wallace, Dennis

2009-02-01

A data monitoring committee (DMC) is often employed to assess trial progress and review safety data and efficacy endpoints throughout a trail. Interim analyses performed for the DMC should use data that are as complete and verified as possible. Such analyses are complicated when data verification involves subjective study endpoints or requires clinical expertise to determine each subject's status with respect to the study endpoint. Therefore, procedures are needed to obtain adjudicated data for interim analyses in an efficient manner. In the past, methods for handling such data included using locally reported results as surrogate endpoints, adjusting analysis methods for unadjudicated data, or simply performing the adjudication as rapidly as possible. These methods all have inadequacies that make their sole usage suboptimal. For a study of prophylaxis for invasive candidiasis, adjudication of both study eligibility criteria and clinical endpoints prior to two interim analyses was required. Because the study was expected to enroll at a moderate rate and the sponsor required adjudicated endpoints to be used for interim analyses, an efficient process for adjudication was required. We created a web-based endpoint adjudication system (WebEAS) that allows for expedited review by the endpoint adjudication committee (EAC). This system automatically identifies when a subject's data are complete, creates a subject profile from the study data, and assigns EAC reviewers. The reviewers use the WebEAS to review the subject profile and submit their completed review form. The WebEAS then compares the reviews, assigns an additional review as a tiebreaker if needed, and stores the adjudicated data. The study for which this system was originally built was administratively closed after 10 months with only 38 subjects enrolled. The adjudication process was finalized and the WebEAS system activated prior to study closure. Some website accessibility issues presented initially. However

105-H Reactor Interim Safe Storage Project Final Report

International Nuclear Information System (INIS)

Ison, E.G.

2008-01-01

The following information documents the decontamination and decommissioning of the 105-H Reactor facility, and placement of the reactor core into interim safe storage. The D and D of the facility included characterization, engineering, removal of hazardous and radiologically contaminated materials, equipment removal, decontamination, demolition of the structure, and restoration of the site. The ISS work also included construction of the safe storage enclosure, which required the installation of a new roofing system, power and lighting, a remote monitoring system, and ventilation components.

Interim dry storage system technologies and innovations VARNA 2002

International Nuclear Information System (INIS)

Chollet, P.; Guenon, Y.

2002-01-01

The main concepts of the TN24 Family and NUHOMS System are explained in the paper. It is discussed how the NPPs specific requirements and economics trends contributes to the growing families of interim dry storage systems delivered under COGEMA LOGICTICS license. It is concluded that modular solutions are currently dominating because they are derived from main concepts evolved over time, benefited from both the transport aspects with internationally recognised stringent regulations, and various specific ISFSI requirements and economic trends

Waste Encapsulation and Storage Facility interim operational safety requirements

CERN Document Server

Covey, L I

2000-01-01

The Interim Operational Safety Requirements (IOSRs) for the Waste Encapsulation and Storage Facility (WESF) define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation during receipt and inspection of cesium and strontium capsules from private irradiators; decontamination of the capsules and equipment; surveillance of the stored capsules; and maintenance activities. Controls required for public safety, significant defense-in-depth, significant worker safety, and for maintaining radiological consequences below risk evaluation guidelines (EGs) are included.

Interim Report on the Investigation of the Fresh Properties of Synthetic Fiber-Reinforced Concrete for the Richardson Landing Casting Field

Science.gov (United States)

2017-04-01

ER D C/ G SL S R- 17 -1 Interim Report on the Investigation of the Fresh Properties of Synthetic Fiber - Reinforced Concrete for the...default. ERDC/GSL SR-17-1 April 2017 Interim Report on the Investigation of the Fresh Properties of Synthetic Fiber - Reinforced Concrete for... reinforced concrete mixtures containing 3-, 2-, and 1-lb(s)/yd3, respectively, of synthetic (polypropylene) fiber into the current mixture proportion

Idaho Chemical Processing Plant Spent Fuel and Waste Management Technology Development Program Plan

International Nuclear Information System (INIS)

1993-09-01

The Department of Energy (DOE) has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage and reprocessing since 1953. Reprocessing of SNF has resulted in an existing inventory of 1.5 million gallons of radioactive sodium-bearing liquid waste and 3800 cubic meters (m 3 ) of calcine, in addition to the 768 metric tons (MT) of SNF and various other fuel materials in inventory. To date, the major activity of the ICPP has been the reprocessing of SNF to recover fissile uranium; however, recent changes in world events have diminished the demand to recover and recycle this material. As a result, DOE has discontinued reprocessing SNF for uranium recovery, making the need to properly manage and dispose of these and future materials a high priority. In accordance with the Nuclear Waste Policy Act (NWPA) of 1982, as amended, disposal of SNF and high-level waste (HLW) is planned for a geological repository. Preparation of SNF, HLW, and other radioactive wastes for disposal may include mechanical, physical, and/or chemical processes. This plan outlines the program strategy of the ICPP Spent Fuel and Waste Management Technology Development Program (SF ampersand WMTDP) to develop and demonstrate the technology required to ensure that SNF and radioactive waste will properly stored and prepared for final disposal. Program elements in support of acceptable interim storage and waste minimization include: developing and implementing improved radioactive waste treatment technologies; identifying and implementing enhanced decontamination and decommissioning techniques; developing radioactive scrap metal (RSM) recycle capabilities; and developing and implementing improved technologies for the interim storage of SNF

Safety evaluation of interim stabilization of non-stabilized single-shell watch list tanks

International Nuclear Information System (INIS)

Stahl, S.M.

1994-01-01

This report provides results of a review of recently completed safety analyses related to hazards associated with Interim Stabilization of Single analyses related to hazards included oh the Hanford Site Waste Tank-Watch Shell Tanks (SSTs) that are included on the Hanford List. The purpose of the review was to identify and summarize conclusions regarding the safety of interim stabilization of Watch List SSTs, and to highlight applicable limitations, restrictions, and controls. The scope of this review was restricted to SSTs identified List in the categories of flammable gas ferrocyanide, and organic salts. High heat tanks were not included in the scope. A Watch List tank is defined as an underground storage tank containing waste that requires special safety precautions because it may have a serious potential for release of high level radioactive waste because of uncontrolled increases in temperature or pressure. Special restrictions have been placed on these tanks

Spent fuel sabotage test program, characterization of aerosol dispersal : interim final report

International Nuclear Information System (INIS)

Gregson, Michael Warren; Brockmann, John E.; Loiseau, Olivier; Klennert, Lindsay A.; Nolte, Oliver; Molecke, Martin Alan; Autrusson, Bruno A.; Koch, Wolfgang; Pretzsch, Gunter Guido; Brucher, Wenzel; Steyskal, Michele D.

2008-01-01

This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program provides source-term data that are relevant to plausible sabotage scenarios in relation to spent fuel transport and storage casks and associated risk assessments. We present details and significant results obtained from this program from 2001 through 2007. Measured aerosol results include: respirable fractions produced; amounts, nuclide content, and produced particle size distributions and morphology; measurements of volatile fission product species enhanced sorption--enrichment factors onto respirable particles; and, status on determination of the spent fuel ratio, SFR, needed for scaling studies. Emphasis is provided on recent Phase 3 tests using depleted uranium oxide pellets plus non-radioactive fission product dopants in surrogate spent fuel test rodlets, plus the latest surrogate cerium oxide results and aerosol laboratory supporting calibration work. The DUO 2 , CeO 2 , plus fission product dopant aerosol particle results are compared with available historical data. We also provide a status review on continuing preparations for the final Phase 4 in this program, tests using individual short rodlets containing actual spent fuel from U.S. PWR reactors, with both high- and lower-burnup fuel. The source-term data, aerosol results, and program design have been tailored to support and guide follow-on computer modeling of aerosol dispersal hazards and radiological consequence assessments. This spent fuel sabotage, aerosol test program was performed primarily at Sandia National Laboratories, with support provided by both the U.S. Department of Energy and the Nuclear Regulatory Commission. This program has significant input from, and is cooperatively supported and

Spent fuel sabotage test program, characterization of aerosol dispersal : interim final report.

Energy Technology Data Exchange (ETDEWEB)

Gregson, Michael Warren; Brockmann, John E.; Loiseau, Olivier (Institut de Radioprotection et de Surete Nucleaire, France); Klennert, Lindsay A.; Nolte, Oliver (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Molecke, Martin Alan; Autrusson, Bruno A. (Institut de Radioprotection et de Surete Nucleaire, France); Koch, Wolfgang (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Pretzsch, Gunter Guido (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Brucher, Wenzel (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Steyskal, Michele D.

2008-03-01

This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program provides source-term data that are relevant to plausible sabotage scenarios in relation to spent fuel transport and storage casks and associated risk assessments. We present details and significant results obtained from this program from 2001 through 2007. Measured aerosol results include: respirable fractions produced; amounts, nuclide content, and produced particle size distributions and morphology; measurements of volatile fission product species enhanced sorption--enrichment factors onto respirable particles; and, status on determination of the spent fuel ratio, SFR, needed for scaling studies. Emphasis is provided on recent Phase 3 tests using depleted uranium oxide pellets plus non-radioactive fission product dopants in surrogate spent fuel test rodlets, plus the latest surrogate cerium oxide results and aerosol laboratory supporting calibration work. The DUO{sub 2}, CeO{sub 2}, plus fission product dopant aerosol particle results are compared with available historical data. We also provide a status review on continuing preparations for the final Phase 4 in this program, tests using individual short rodlets containing actual spent fuel from U.S. PWR reactors, with both high- and lower-burnup fuel. The source-term data, aerosol results, and program design have been tailored to support and guide follow-on computer modeling of aerosol dispersal hazards and radiological consequence assessments. This spent fuel sabotage, aerosol test program was performed primarily at Sandia National Laboratories, with support provided by both the U.S. Department of Energy and the Nuclear Regulatory Commission. This program has significant input from, and is cooperatively

Hierarchies of belief and interim rationalizability

Directory of Open Access Journals (Sweden)

Jeffrey C. Ely

2006-03-01

Full Text Available In games with incomplete information, conventional hierarchies of belief are incomplete as descriptions of the players' information for the purposes of determining a player's behavior. We show by example that this is true for a variety of solution concepts. We then investigate what is essential about a player's information to identify behavior. We specialize to two player games and the solution concept of interim rationalizability. We construct the universal type space for rationalizability and characterize the types in terms of their beliefs. Infinite hierarchies of beliefs over conditional beliefs, which we call Delta-hierarchies, are what turn out to matter. We show that any two types in any two type spaces have the same rationalizable sets in all games if and only if they have the same Delta-hierarchies.

NEPA implementation: The Department of Energy's program to manage spent nuclear fuel

International Nuclear Information System (INIS)

Shipler, D.B.

1994-05-01

The Department of Energy (DOE) is implementing the National Environmental Protection Act (NEPA) in its management of spent nuclear fuel. The DOE strategy is to address the short-term safety concerns about existing spent nuclear fuel, to study alternatives for interim storage, and to develop a long-range program to manage spent nuclear fuel. This paper discusses the NEPA process, the environmental impact statements for specific sites as well as the overall program, the inventory of DOE spent nuclear fuel, the alternatives for managing the fuel, and the schedule for implementing the program

The PDF4LHC Working Group Interim Report

CERN Document Server

Alekhin, Sergey; Ball, Richard D.; Bertone, Valerio; Blumlein, Johannes; Botje, Michiel; Butterworth, Jon; Cerutti, Francesco; Cooper-Sarkar, Amanda; de Roeck, Albert; Del Debbio, Luigi; Feltesse, Joel; Forte, Stefano; Glazov, Alexander; Guffanti, Alberto; Gwenlan, Claire; Huston, Joey; Jimenez-Delgado, Pedro; Lai, Hung-Liang; Latorre, Jose I.; McNulty, Ronan; Nadolsky, Pavel; Olaf Moch, Sven; Pumplin, Jon; Radescu, Voica; Rojo, Juan; Sjostrand, Torbjorn; Stirling, W.J.; Stump, Daniel; Thorne, Robert S.; Ubiali, Maria; Vicini, Alessandro; Watt, Graeme; Yuan, C.-P.

2011-01-01

This document is intended as a study of benchmark cross sections at the LHC (at 7 TeV) at NLO using modern parton distribution functions currently available from the 6 PDF fitting groups that have participated in this exercise. It also contains a succinct user guide to the computation of PDFs, uncertainties and correlations using available PDF sets. A companion note, also submitted to the archive, provides an interim summary of the current recommendations of the PDF4LHC working group for the use of parton distribution functions and of PDF uncertainties at the LHC, for cross section and cross section uncertainty calculations.

AACP Special Taskforce on Diversifying Our Investment in Human Capital Interim Update.

Science.gov (United States)

White, Carla; Adams, Jennifer

2016-09-25

The 2015-2017 AACP Special Taskforce on Diversifying our Investment in Human Capital was appointed for a two-year term, therefore the interim update from the Taskforce. A full report will be provided in 2017 in the form of a white paper for academic pharmacy on diversifying our investment in human capital.

Interim storage is not long-term disposal

International Nuclear Information System (INIS)

Vincenti, J.R.

1994-01-01

Starting in June 30, 1994 South Carolina enforced an embargo on regular shipments of low-level radioactive waste to the Barnwell repository. The failure of 31 states and their respective compacts to provide access to a long-term disposal facility as stipulated by the low-level radioactive Waste Policy Act of 1980 promotes waste disposal gridlock and anticipates another waste disposal crisis. This article discusses the problem using the following topics: Appalachian Compact Users of Radioactive Isotopes (ACURI) Association's interest; the problem of denial of access to Barnwell; pro and contra interim storage; vital services and benefits at risk; issues at the ACURI meeting; nobel Prize winners use radioactive materials; if perception is reality, politics is prevalent

Assessment report of research and development activities. Activity: advanced science research' (Interim report)

International Nuclear Information System (INIS)

2008-08-01

Japan Atomic Energy Agency (hereinafter referred to as 'JAEA') consults an assessment committee, 'Evaluation Committee of Research Activities for Advanced Science Research' (hereinafter referred to as 'Committee') for interim assessment of 'Advanced Science Research,' in accordance with General Guideline for the Evaluation of Government Research and Development (R and D) Activities' by Cabinet Office, Government of Japan, 'Guideline for Evaluation of R and D in Ministry of Education, Culture, Sports, Science and Technology' and 'Regulation on Conduct for Evaluation of R and D Activities' by JAEA. In response to the JAEA's request, the Committee assessed the research program of the Advanced Science Research Center (hereinafter referred to as 'ASRC') during the period of two years from October 2005 to September 2007. The Committee evaluated the management and research activities of the ASRC based on the explanatory documents prepared by the ASRC, the oral presentations with questions-and-answers by the Director and the research group leaders, and interviews from group members through on-site visits by the Committee members. One CD-ROM is attached as an appendix. (J.P.N.)

Characterization program, management and isotopic inventory calculation, radiological and fuel thermal irradiated in nuclear power Cofrentes

International Nuclear Information System (INIS)

Albendea, M.; Diego, J. L. de; Urrea, M.

2012-01-01

Characterization is a very detailed and user-friendly program takes into account the history of irradiation individualized and real all the fuel, even taking into account the interim periods are periods of discharge and recharge cycles and which have not been used.

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

Energy Technology Data Exchange (ETDEWEB)

T. A. Lee

2005-09-15

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

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

International Nuclear Information System (INIS)

Lee, T.A.

2005-01-01

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

Breaking the Cycle of Drug Abuse. 1993 Interim National Drug Control Strategy.

Science.gov (United States)

Office of National Drug Control Policy, Washington, DC.

This Interim Drug Strategy is intended to give a new sense of direction and to reinvigorate the nation's efforts against drug trafficking and abuse. The preface to the report lists eight new strategies that the Administration will implement: (1) make drug policy a cornerstone of domestic and social policy; (2) target pregnant women, children, and…

Fast Flux Test Facility interim examination and maintenance cell - past, present, and future

International Nuclear Information System (INIS)

Vincent, J.R.

1990-01-01

The Fast Flux Test Facility (FFTF) interim examination and maintenance (IEM) cell was designed to perform interim examination and/or disassembly of experimental core components for final analysis elsewhere, as well as maintenance of sodium-wetted or neutron-activated internal reactor parts and plant support hardware. The first 10 yr of operation were mainly devoted to the disassembly and examination of core component test assemblies. While some maintenance was performed on reactor support equipment, such as the closed-loop ex-vessel machine (CLEM) sodium-wetted grapple, 90% of IEM cell availability has been devoted to core component tests. Some test assemblies originally considered for processing in the IEM cell have not been irradiated; others, not originally planned, have been designed, irradiated, and processed. While no major reactor equipment has required remote repair or maintenance, the IEM cell has served as the remote repair facility for its own in-cell equipment, and several innovative remote repairs have been accomplished and are described

200-ZP-1 phase 2 interim remedial measure quarterly report, August--October 1996

International Nuclear Information System (INIS)

Freeman-Pollard, J.R.; Jacques, I.D.; McMahon, W.J.; Singleton, K.M.; Strope, S.A.; Swanson, L.C.; Windmueller, C.R.

1996-11-01

A groundwater pump-and-treat system is being operated in the 200-ZP-1 Operable Unit under authority of the Hanford Federal Facility Agreement and Consent Order . The purpose of the pump-and-treat system is to accomplish the following: Minimize further migration of the high-concentration portion of the carbon tetrachloride plume and co-contaminants chloroform and trichlorethylene in the 200-ZP-1 Operable Unit Provide data for evaluation of final remedy selection. The 200-ZP-1 pump-and-treat operations were conducted as a pilot-scale treatability test and interim remedial measure treatment system between August 1994 and July 1996 to assess the effectiveness of liquid-phase granular activated carbon carbon tetrachloride removal. The pilot-scale treatability test's removal efficiently was determined to be 99.96% for carbon tetrachloride, chloroform, and trichloroethylene. This report summarizes and evaluates treatment, hydraulic, and hydrochemistry data collected for the 200-ZP-1 interim remedial measure from August through September 1996

ISOE EG-SAM interim report - Report on behalf of the Sub expert Group

International Nuclear Information System (INIS)

Harris, Willie; Miller, David W.; Djeffal, Salah; Anderson, Ellen; Couasnon, Olivier; Hagemeyer, Derek; Sovijarvi, Jukka; Amaral, Marcos A.; Tarzia, J.P.; Schmidt, Claudia; Fritioff, Karin; Kaulard, Joerg; Lance, Benoit; Fritioff, Karin; Schieber, Caroline; Hayashida, Yoshihisa; Doty, Rick

2014-01-01

During its November 2012 meeting, the expert group decided to develop an interim (preliminary) report before the end of 2013 (with a general perspective and discussion of specific severe accident management worker dose issues), and to finalize the report by organizing the international workshop of 2014 to address national experiences, which will be incorporated to the report. The work of the EG-SAM focuses on radiation protection management and organization, radiation protection training and exercises related to severe accident management, facility configuration and readiness, worker protection, radioactive materials, contamination controls and logistics and key lessons learned especially from the TMI, Chernobyl and Fukushima Dai-ichi accidents. This interim report was completed through intensive work of all Group members nominated by the ISOE, and was accomplished during EG-SAM meetings through 2012-2013. This document gathers the different presentations given by the sub expert groups in charge of each chapter of the report

78 FR 13443 - Child Nutrition Programs: Nondiscretionary Amendments Related to the Healthy, Hunger-Free Kids...

Science.gov (United States)

2013-02-28

... exist'' in SFSP. Clarify revenue and accrual requirements from foods sold in schools outside of the... must accrue to the nonprofit school food service. The interim rule addressed these revenue and accrual... and recordkeeping requirements. 7 CFR Part 226 Accounting, Aged, Day care, Food assistance programs...

Re-use of pilot data and interim analysis of pivotal data in MRMC studies: a simulation study

Science.gov (United States)

Chen, Weijie; Samuelson, Frank; Sahiner, Berkman; Petrick, Nicholas

2017-03-01

Novel medical imaging devices are often evaluated with multi-reader multi-case (MRMC) studies in which radiologists read images of patient cases for a specified clinical task (e.g., cancer detection). A pilot study is often used to measure the effect size and variance parameters that are necessary for sizing a pivotal study (including sizing readers, non-diseased and diseased cases). Due to the practical difficulty of collecting patient cases or recruiting clinical readers, some investigators attempt to include the pilot data as part of their pivotal study. In other situations, some investigators attempt to perform an interim analysis of their pivotal study data based upon which the sample sizes may be re-estimated. Re-use of the pilot data or interim analyses of the pivotal data may inflate the type I error of the pivotal study. In this work, we use the Roe and Metz model to simulate MRMC data under the null hypothesis (i.e., two devices have equal diagnostic performance) and investigate the type I error rate for several practical designs involving re-use of pilot data or interim analysis of pivotal data. Our preliminary simulation results indicate that, under the simulation conditions we investigated, the inflation of type I error is none or only marginal for some design strategies (e.g., re-use of patient data without re-using readers, and size re-estimation without using the effect-size estimated in the interim analysis). Upon further verifications, these are potentially useful design methods in that they may help make a study less burdensome and have a better chance to succeed without substantial loss of the statistical rigor.

Preparation for tritiated waste management of fusion facilities: Interim storage WAC

Energy Technology Data Exchange (ETDEWEB)

Decanis, C., E-mail: christelle.decanis@cea.fr [CEA, DEN, Centre de Cadarache, F-13108 Saint-Paul-lez-Durance (France); Canas, D. [CEA, DEN/DADN, Centre de Saclay, F-91191 Gif-sur-Yvette cedex (France); Derasse, F. [CEA, DEN, Centre de Cadarache, F-13108 Saint-Paul-lez-Durance (France); Pamela, J. [CEA, Agence ITER-France, F-13108 Saint-Paul-lez-Durance (France)

2016-11-01

Highlights: • Fusion devices including ITER will generate tritiated waste. • Interim storage is the reference solution offering an answer for all types of tritiated radwaste. • Interim storage is a buffer function in the process management and definition of the waste acceptance criteria (WAC) is a key milestone in the facility development cycle. • Defining WAC is a relevant way to identify ahead of time the studies to be launched and the required actions to converge on a detailed design for example material specific studies, required treatment, interfaces management, modelling and monitoring studies. - Abstract: Considering the high mobility of tritium through the package in which it is contained, the new 50-year storage concepts proposed by the French Alternative Energies and Atomic Energy Commission (CEA) currently provide a solution adapted to the management of waste with tritium concentrations higher than the accepted limits in the disposals. The 50-year intermediate storage corresponds to 4 tritium radioactive periods i.e., a tritium reduction by a factor 16. This paper details the approach implemented to define the waste acceptance criteria (WAC) for an interim storage facility that not only takes into account the specificity of tritium provided by the reference scheme for the management of tritiated waste in France, but also the producers’ needs, the safety analysis of the facility and Andra’s disposal requirements. This will lead to define a set of waste specifications that describe the generic criteria such as acceptable waste forms, general principles and specific issues, e.g. conditioning, radioactive content, tritium content, waste tracking system, and quality control. This approach is also a way to check in advance, during the design phase of the waste treatment chain, how the future waste could be integrated into the overall waste management routes and identify possible key points that need further investigations (design changes, selection

Hydrogeology of the 200 Areas low-level burial grounds: An interim report: Volume 1, Text

Energy Technology Data Exchange (ETDEWEB)

Last, G.V.; Bjornstad, B.N.; Bergeron, M.P.; Wallace, D.W.; Newcomer, D.R.; Schramke, J.A.; Chamness, M.A.; Cline, C.S.; Airhart, S.P.; Wilbur, J.S.

1989-01-01

This report presents information derived from the installation of 35 ground-water monitoring wells around six low-level radioactive/hazardous waste burial grounds located in the 200 Areas of the Hanford Site in southeastern Washington State. This information was collected between May 20, 1987 and August 1, 1988. The contents of this report have been divided into two volumes. This volume contains the main text. Volume 2 contains the appendixes, including data and supporting information that verify content and results found in the main text. This report documents information collected by the Pacific Northwest Laboratory at the request of Westinghouse Hanford Company. Presented in this report are the preliminary interpretations of the hydrogeologic environment of six low-level burial grounds, which comprise four waste management areas (WMAs) located in the 200 Areas of the Hanford Site. This information and its accompanying interpretations were derived from sampling and testing activities associated with the construction of 35 ground-water monitoring wells as well as a multitude of previously existing boreholes. The new monitoring wells were installed as part of a ground-water monitoring program initiated in 1986. This ground-water monitoring program is based on requirements for interim status facilities in compliance with the Resource Conservation and Recovery Act (1976).

Interim Guidance for the Sanitary Control and Surveillance of Field Water Supplies

Science.gov (United States)

2005-07-15

on field water site/area restoration , including the removal and disposal of waste (see chapter 11 and FM 4-02.17). CHAPTER 3 INTRODUCTION TO...chemical addition, coagulation, sedimentation, and various kinds of filtration including multimedia filtration, cartridge filtration, microfiltration ... microfiltration membrane-based pretreatment system. Interim Guidance Pending Publication of TBMED 577 15 July 2005 53 Figure 9-1

Interim report on the TMI-2 purification filter examination

International Nuclear Information System (INIS)

Mason, R.E.; Hobbins, R.R.; Cook, B.A.; MacDonald, P.E.

1983-02-01

Filters from the purification/makeup system of the Three Mile Island Unit 2 Reactor were examined after the March 28, 1979, accident to determine the character of the debris transported to the filters. The general condition of the filters is presented. Material was removed from the filters and examined. The elemental and radionuclide makeup of the debris is discussed. Distribution of particle size and shape is presentd for some of the material examined. This is an interim report. When the investigation is completed, another report summarizing all of the data will be issued

T Tank Farm Interim Cover Test - Design Plan

International Nuclear Information System (INIS)

Zhang, Z. F.; Keller, Jason M.

2006-01-01

The Hanford Site has 149 underground single-shell tanks that store hazardous radioactive waste. Many of these tanks and their associated infrastructure (e.g., pipelines, diversion boxes) have leaked. Some of the leaked waste has entered the groundwater. The largest known leak occurred from the T-106 Tank in 1973. Many of the contaminants from that leak still reside within the vadose zone beneath the T Tank Farm. CH2M Hill Hanford Group, Inc. seeks to minimize movement of this residual contaminant plume by placing an interim cover on the surface. Such a cover is expected to prevent infiltrating water from reaching the plume and moving it further. Pacific Northwest National Laboratory has prepared a design plan to monitor and determine the effectiveness of the interim cover. A three-dimensional numerical simulation of water movement beneath a cover was conducted to guide the design of the plan. Soil water content, water pressure, and temperature will be monitored using off-the-shelf equipment that can be installed by the hydraulic hammer technique. In fiscal year 2006, two instrument nests will be installed, one inside and one outside of the proposed cover. In fiscal year 2007, two additional instrument nests, both inside the proposed cover, will be installed. Each instrument nest contains a neutron access tube and a capacitance probe (to measure water content), and four heat-dissipation units (to measure pressure head and temperature). A datalogger and a meteorological station will be installed outside of the fence. Two drain gauges will be installed in locations inside and outside the cover for the purpose of measuring soil water flux.

Interim Control Strategy for the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond - Two-year Update

International Nuclear Information System (INIS)

L. V. Street

2007-01-01

The Idaho Cleanup Project has prepared this interim control strategy for the U.S. Department of Energy Idaho Operations Office pursuant to DOE Order 5400.5, Chapter 11.3e (1) to support continued discharges to the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond. In compliance with DOE Order 5400.5, a 2-year review of the Interim Control Strategy document has been completed. This submittal documents the required review of the April 2005 Interim Control Strategy. The Idaho Cleanup Project's recommendation is unchanged from the original recommendation. The Interim Control Strategy evaluates three alternatives: (1) re-route the discharge outlet to an uncontaminated area of the TSF-07; (2) construct a new discharge pond; or (3) no action based on justification for continued use. Evaluation of Alternatives 1 and 2 are based on the estimated cost and implementation timeframe weighed against either alternative's minimal increase in protection of workers, the public, and the environment. Evaluation of Alternative 3, continued use of the TSF-07 Disposal Pond under current effluent controls, is based on an analysis of four points: - Record of Decision controls will protect workers and the public - Risk of increased contamination is low - Discharge water will be eliminated in the foreseeable future - Risk of contamination spread is acceptable. The Idaho Cleanup Project recommends Alternative 3, no action other than continued implementation of existing controls and continued deactivation, decontamination, and dismantlement efforts at the Test Area North/Technical Support Facility

75 FR 30372 - Foreign-Trade Zone 196 Temporary/Interim Manufacturing Authority ATC Logistics & Electronics...

Science.gov (United States)

2010-06-01

... DEPARTMENT OF COMMERCE Foreign-Trade Zones Board [Docket T-2-2010] Foreign-Trade Zone 196 Temporary/Interim Manufacturing Authority ATC Logistics & Electronics (Cell Phone Kitting and Distribution... filed an application submitted by the ATC Logistics & Electronics, operator of Site 2, FTZ 196...

Prognostic value of interim FDG-PET in Hodgkin lymphoma : systematic review and meta-analysis

NARCIS (Netherlands)

Adams, Hugo J A; Nievelstein, Rutger A J; Kwee, Thomas C.

2015-01-01

This study aimed to systematically review and meta-analyse the value of interim (18) F-fluoro-2-deoxy-d-glucose positron emission tomography (FDG-PET) in predicting treatment failure in Hodgkin lymphoma. MEDLINE was systematically searched for original studies that used standardized international

Prognostic value of negative interim 2-["1"8F]-fluoro-2-deoxy-D-glucose PET/CT in diffuse large B-cell lymphoma

International Nuclear Information System (INIS)

Kwon, S.H.; Kang, D.R.; Kim, J.; Yoon, J.-K.; Lee, S.J.; Jeong, S.H.; Lee, H.W.; An, Y.-S.

2016-01-01

Aim: To assess the prognostic value of negative interim combined 2-["1"8F]-fluoro-2-deoxy-D-glucose ("1"8F-FDG) positron-emission tomography/computed tomography (PET/CT) in patients with diffuse large B-cell lymphoma (DLBCL). Materials and methods: Ninety-two patients with histologically proven DLBCL were enrolled. All of the patients underwent "1"8F-FDG PET/CT at diagnosis, and interim PET/CT after the second cycle of chemotherapy with rituximab, cyclophosphamide, hydroxydaunorubicin, vincristine, and prednisolone (R-CHOP). Negative interim PET/CT was defined as the disappearance of all abnormal "1"8F-FDG uptake compared to the pretreatment PET/CT image, as determined by visual assessment. The clinical outcome of patients was estimated as progression-free survival (PFS), and the prognostic significance of clinicopathological and imaging parameters were assessed using the Cox proportional hazards model. Results: Thirty-six patients (39.1%) showed lymphoma progression within a median follow-up of 30.8 months. According to univariate analysis, Ann Arbor stage, serum lactate dehydrogenase level, Eastern Cooperative Oncology Group scale, International Prognostic Index (IPI) score, and maximum standardised uptake values on initial PET/CT were significant prognostic factors for PFS (all p<0.05). Among these parameters, only the IPI score was an independent predictor for PFS (p=0.044). Survival of patients with a high IPI score (≥3) was poorer than those with a low IPI score (0–2; p<0.001). Conclusion: Despite a negative interim "1"8F-FDG PET/CT, approximately 39% of DLBCL patients showed progression during follow-up. Although the negative PET/CT was obtained during chemotherapy, it is important to closely follow-up patients, especially those with a high IPI score. - Highlights: • About 39% of patients showed progression after negative interim PET/CT. • The IPI score was an independent predictor for PFS. • It is important to closely follow-up with high IPI score

Data management implementation plan for interim action at the Gunite and Associated Tanks, Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1998-03-01

The Gunite and Associated Tanks (GAAT) Project is currently conducting a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Interim Remedial Action to reduce uncertainties on the potential cost and effectiveness of remote tank cleaning equipment being produced jointly between the US Department of Energy (DOE); Oak Ridge National Laboratory (ORNL); Lockheed Martin Energy Systems, Inc.; and associated subcontractors with the DOE EM-50 Program. The goal of this document is to ensure that all procedures have been followed to provide reliable, verifiable data that are technically defensible. The data collected will be used to support closure of the tanks, compare the expected versus actual waste volume and curies to aid in conducting operations, and verify the performance of developmental equipment

Conduct of the Persian Gulf Conflict: An Interim Report to Congress

Science.gov (United States)

1991-07-01

a danger that we will assume that this war is a paradigm for the next, that subconsciously we’ll presume all future wars can be relatively pain free...CENTCOM. The experience elicited arecmmndtin o hagethe threshold for reprogram - JSTARS was an integral part of the system used to recommendation to...This Includes the realignment, reprogramming , or transfer of funds appropriated for activities unrelated to the Persian Gulf conflict. Interim Report

Interim Consequence Management Guidance for a Wide-Area Biological Attack

Energy Technology Data Exchange (ETDEWEB)

Raber, Ellen [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Kirvel, Robert [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); MacQueen, Don [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Love, Adam [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dombroski, Matthew [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); McGrann, Thomas [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Richards, John [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Melius, Carl [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bunt, Thomas [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hibbard, Wilthea [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Greenwalt, Robert [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Miles, Robin [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dillon, Michael [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mancieri, Sav [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Harris, Steve [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Michalik, Richard [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wheeler, Richard [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hoppes, Bill [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Tucker, Mark [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Krauter, Paula [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Knowlton, Robert [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Yang, Lynn [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Franco, Dave [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Einfeld, Wayne [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brockman, John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Betty, Rita [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2011-05-17

The Interagency Biological Restoration Demonstration (IBRD) program is a collaborative, interagency effort co-chaired by the Department of Homeland Security and Department of Defense aimed at improving the nation‘s ability to respond to and recover from a large-scale, wide-area, domestic attack involving the release of an environmentally persistent biological warfare agent. The program is focused on understanding interactions between the civilian and military sectors, and in building mutual support to carry out such remediations. This Interim Consequence Management Guidance document provides guidance for decisionmakers in executing activities required to respond to and recover from a biological incident affecting a wide urban area insofar as information is currently available. The spore-forming bacterium Bacillus anthracis is discussed as the biological agent of primary concern because it is the most difficult of known bioterrorism agents to inactivate and is considered to be one of the key threat agents. Most other biological threat agents are much easier to remediate, and in many cases, inactivation would occur naturally within days as a result of environmental exposure; however, the framework and operational questions that need to be addressed are expected to remain the same. The guidance in this document is applicable to (1) enclosed facilities, such as commercial, residential, and continental U.S. military facilities; (2) semi-enclosed facilities, such as subways and public transit facilities; (3) outdoor areas (both localized and wide area), such as building exteriors, streets, parks, and other open spaces; (4) drinking water facilities; and (5) drinking water sources. This document follows an interagency framework [Planning Guidance for Recovery Following Biological Incidents (DHS and EPA 2009)]—which considered Raber et al. (2002) in its development—but takes the framework to a more operational level and provides guidance at key action and decision

Assessment report of research and development activities in FY2006 activity. 'Fast reactor cycle technology development project' (Interim report)

International Nuclear Information System (INIS)

2007-08-01

Japan Atomic Energy Agency (hereinafter referred to as 'JAEA') asked the advisory committee 'evaluation Committee of Research and Development (R and D) Activities for Advanced Nuclear System/Nuclear Fuel Cycle Technology' (hereinafter referred to as 'Committee') to assess the interim report on Fast Reactor Cycle Technology Development Project ' (former 'Feasibility Study on Commercialized Fast Reactor Cycle Systems') in FY2006, in accordance with 'General Guideline for the Evaluation of Government R and D Activities' by Japanese Cabinet Office, 'Guideline for Evaluation of R and D in Ministry of Education, Culture Sports, Science and Technology' and 'Regulation on Conduct for Evaluation of R and D Activities' by JAEA. In response to JAEA's request, the Committee assessed the R and D program over five years, the criteria for adoption judgment on innovative technologies at the end of 2010 (Project Review), and the organization structure for R and D. etc. (Management Review). As a result of review, the Committee concluded that this R and D program and its organization structure are almost reasonable. (author)

Interim technical evaluation report of testing procedures for activated carbon adsorbers in ventilation filter assemblies in nuclear power plants

International Nuclear Information System (INIS)

Sill, C.W.; Scarpellino, C.D.; Tkachyk, J.W.; Grey, A.E.; Frank, C.W.

1985-05-01

Laboratory analysis of activated carbon is required by nuclear power plant technical specifications for use in Engineered Safety Feature (ESF) ventilation systems to determine the capability of those systems to remove radioiodines from air during normal operation and following a design basis accident (DBA). The lask of agreement of laboratory results from a recent round robin raised concerns regarding the adequacy of the analyses, using the ASTM D3803-79 standard, to assure compliance with plant technical specifications. EG and G Idaho was contracted by the NRC to conduct a program to provide the bases for resolving these concerns. This EG and G report serves as an interim Technical Evaluation Report (TER) of the program and presents reviews of the ASTM D3803-79 standard and the commercial testing laboratories. Results of EG and G laboratory studies and the NRC/EG and G Interlaboratory Comparison are presented with conclusions and recommendations concerning changes required to improve the standard and its application. Possible revisions to plant technical specifications required to reflect the true capability of activated carbon to remove radioiodines are also presented

Continuous solvent extraction feed adjustment for HTGR fuel reprocessing. Interim development report

International Nuclear Information System (INIS)

Olguin, L.J.

1978-06-01

The two-cycle Acid-Thorex solvent extraction process requires that the feed stream to each thorium cycle be processed to reduce its nitric acid concentration (feed adjustment). This interim development report presents the results of bench-scale and pilot-plant-scale feed adjustment experiments using a continuous mode of operation. An examination of formic acid denitration and fluoride ion volatilization is also included

Environmental assessment of radiological effluents from data gathering and maintenance operation on Three Mile Island Unit 2: interim criteria approved by the Commission on April 7,1980

International Nuclear Information System (INIS)

1980-05-01

The staff is currently in the process of preparing a programmatic environmental impact statement (PEIS) for TMI-2 which will address all radiological releases that may occur as a result of the cleanup and recovery operations. These operations will begin after the PEIS is published in final form provided the proposed cleanup programs have been found to be environmentally acceptable. In the interim period it is necessary for the licensee to conduct data gathering and maintenance operations on the damaged reactor. The action of approval of these interim operations does not foreclose any of the options of the PEIS. In addition, regardless of what cleanup choice is made in the PEIS, the approval of these data gathering and maintenance operations enhance the ability of the licensee to maintain the reactor in a safe configuration and to plan effectively for recovery operations. This Environmental Impact Appraisal evaluates the effects on the environment of allowing these data gathering and maintenance operations to be conducted. These data gathering and maintenance operations do not include purging of the containment atmosphere, disposal of EPICOR-II water, or the treatment and disposal of high level radioactively contaminated water in the reactor building

40 CFR 265.383 - Interim status thermal treatment devices burning particular hazardous waste.

Science.gov (United States)

2010-07-01

... status thermal treatment devices burning particular hazardous waste. (a) Owners or operators of thermal treatment devices subject to this subpart may burn EPA Hazardous Wastes FO20, FO21, FO22, FO23, FO26, or... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Interim status thermal treatment...

Frequency and Type of Prosthetic Complications Associated with Interim, Immediately Loaded Full-Arch Prostheses: A 2-Year Retrospective Chart Review.

Science.gov (United States)

Drago, Carl

2016-08-01

The purpose of this report was to retrospectively evaluate implant and immediate full-arch prosthesis survival rates over a 24-month period; patients were consecutively treated with immediate occlusal loading. Dental arch, gender, and implant orientation (vertical vs. tilted) were also noted. All Brånemark System implants (Nobel Active) and interim, all-acrylic resin prostheses placed in patients following an All-on-Four™ protocol, in a single private practice were assessed by retrospective patient chart review. The amount of space provided surgically for implant restorative components and prostheses was determined from measurements of the vertical heights of the interim prostheses in the right/left anterior and posterior segments. These measurements were made in the laboratory. Interim prosthetic repairs (type, frequency, length of time from insertion) were analyzed by type, arch, gender, and implant orientation. Implant survival and insertion torque values were also measured. Inclusion criteria consisted of all Brånemark System implants placed with the All-on-Four protocol from September 1, 2011, until August 31, 2013. Specific dietary instructions were given for the first 7 days immediately postoperatively and for the weeks prior to insertion of the definitive prostheses. One hundred twenty-nine patients, comprising 191 arches (766 implants) from September 1, 2011, until August 31, 2013, were included in the study. One patient experienced implant failure yielding an overall implant survival rate (SR) of 99.5% (762 of 766). Four hundred twenty-six of 430 maxillary implants and 336 of 336 mandibular implants survived for SRs of 99.1% and 100%, respectively. Regarding implant orientation, 415 of 417 tilted implants (SR 99.5%) and 343 of 345 (CSR 95.6%) vertical implants were noted to be clinically stable. Interim, all-acrylic resin prostheses were in place for a mean of 199.2 days; mandibular prostheses were in place for an average of 195.4 days; maxillary

T Tank Farm Interim Surface Barrier Demonstration--Vadose Zone Monitoring Plan

International Nuclear Information System (INIS)

Zhang, Z. F.; Keller, Jason M.; Strickland, Christopher E.

2007-01-01

The Hanford Site has 149 underground single-shell tanks that store hazardous radioactive waste. Many of these tanks and their associated infrastructure (e.g., pipelines, diversion boxes) have leaked. Some of the leaked waste has entered the groundwater. The largest known leak occurred from the T-106 Tank in 1973. Many of the contaminants from that leak still reside within the vadose zone beneath the T Tank Farm. CH2M Hill Hanford Group, Inc. seeks to minimize movement of this residual contaminant plume by placing an interim barrier on the surface. Such a barrier is expected to prevent infiltrating water from reaching the plume and moving it further. A plan has been prepared to monitor and determine the effectiveness of the interim surface barrier. Soil water content and water pressure will be monitored using off-the-shelf equipment that can be installed by the hydraulic hammer technique. In fiscal year 2006, two instrument nests were installed. Each instrument nest contains a neutron probe access tube, a capacitance probe, four heat-dissipation units, and a drain gauge to measure soil water flux. A meteorological station has been installed outside of the fence. In fiscal year 2007, two additional instrument nests are planned to be installed beneath the proposed barrier.

Description of mathematical models and computer programs

International Nuclear Information System (INIS)

1977-01-01

The paper gives a description of mathematical models and computer programs for analysing possible strategies for spent fuel management, with emphasis on economic analysis. The computer programs developed, describe the material flows, facility construction schedules, capital investment schedules and operating costs for the facilities used in managing the spent fuel. The computer programs use a combination of simulation and optimization procedures for the economic analyses. Many of the fuel cycle steps (such as spent fuel discharges, storage at the reactor, and transport to the RFCC) are described in physical and economic terms through simulation modeling, while others (such as reprocessing plant size and commissioning schedules, interim storage facility commissioning schedules etc.) are subjected to economic optimization procedures to determine the approximate lowest-cost plans from among the available feasible alternatives

Advantages on dry interim storage for spent nuclear fuel

International Nuclear Information System (INIS)

Romanato, L.S.; Rzyski, B.M.

2006-01-01

When the nuclear fuel lose its ability to efficiently create energy it is removed from the core reactor and moved to a storage unit waiting for a final destination. Generally, the spent nuclear fuel (SNF) remains inside concrete basins with water within the reactors facility for the radioactive activity decay. Water cools the generated heat and shields radioactivity emissions. After some period of time in water basins the SNF can be sent to a definitive deposition in a geological repository and handled as radioactive waste or to reprocessing installations, or still wait for a future solution. Meanwhile, SNF remains stored for a period of time in dry or wet installations, depending on the method adopted by the nuclear power plant or other plans of the country. In many SNF wet storage sites the capacity can be fulfilled very quickly. If so, additional area or other alternative storage system should be given. There are many options to provide capacity increase in the wet storage area, but dry storages are worldwide preferred since it reduces corrosion concerns. In the wet storage the temperature and water purity should be constantly controlled whereas in the dry storage the SNF stands protected in specially designed canisters. Dry interim storages are practical and approved in many countries especially that have the 'wait and see' philosophy (wait to see new technologies development). This paper shows the advantages of dry interim storages sites in comparison with the wet ones and the nowadays problems as terrorism. (Author)

Engineering study: disposition of terminal liquors for interim storage

International Nuclear Information System (INIS)

Metz, W.P.; Ogren, W.E.

1975-02-01

Eight alternative processes were chosen as being technologically feasible within the time frame dictated by budgeting procedures and terminal liquor availability. Solidified waste products acceptable for single-shell tank storage were assumed to be placed in available single-shell tanks. Double-shell tanks were used only for the more mobile terminal liquors or semi-solid mush products. The mush, chemical neutralization, and clay in-tank processes offer potential savings of tens of millions of dollars over double-shell tank storage of terminal liquors. In order to achieve this cost savings, the process development and demonstration must be completed prior to the beginning of double-shell tank construction (Dec. 1976) expected to be funded from a fiscal year 1977 line item. Budgeting for these additional double-shell tanks must proceed since the processing options discussed here are not yet available and may not prove to be available at the required time. This study indicates the following topics for additional study: Process technology development to achieve interim storage of terminal liquor products receives the greatest emphasis as a means of reducing capital expenditures. Interim storage product criteria, waste inventory, and conversion to final form require definition to allow comparison of the alternatives for disposition of terminal liquors. The pseudotechnical nature of product acceptability criteria is important to the evaluation of the partial neutralization and aluminum removal alternatives. More accurate estimates of terminal liquor quantity and composition are required to give a sound technical basis for choosing the appropriate processing alternative. Retrieval and reprocessing operations may affect the comparisons presented by this study

Advantages on dry interim storage for spent nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Romanato, L.S. [Centro Tecnologico da Marinha em Sao Paulo, Av. Professor Lineu Prestes 2468, 05508-900 Sao Paulo (Brazil); Rzyski, B.M. [IPEN/ CNEN-SP, 05508-000 Sao Paulo (Brazil)]. e-mail: romanato@ctmsp.mar.mil.br

2006-07-01

When the nuclear fuel lose its ability to efficiently create energy it is removed from the core reactor and moved to a storage unit waiting for a final destination. Generally, the spent nuclear fuel (SNF) remains inside concrete basins with water within the reactors facility for the radioactive activity decay. Water cools the generated heat and shields radioactivity emissions. After some period of time in water basins the SNF can be sent to a definitive deposition in a geological repository and handled as radioactive waste or to reprocessing installations, or still wait for a future solution. Meanwhile, SNF remains stored for a period of time in dry or wet installations, depending on the method adopted by the nuclear power plant or other plans of the country. In many SNF wet storage sites the capacity can be fulfilled very quickly. If so, additional area or other alternative storage system should be given. There are many options to provide capacity increase in the wet storage area, but dry storages are worldwide preferred since it reduces corrosion concerns. In the wet storage the temperature and water purity should be constantly controlled whereas in the dry storage the SNF stands protected in specially designed canisters. Dry interim storages are practical and approved in many countries especially that have the 'wait and see' philosophy (wait to see new technologies development). This paper shows the advantages of dry interim storages sites in comparison with the wet ones and the nowadays problems as terrorism. (Author)

76 FR 11506 - Fisheries and Habitat Conservation and Migratory Birds Programs; Draft Land-Based Wind Energy...

Science.gov (United States)

2011-03-02

...] RIN 1018-AX45 Fisheries and Habitat Conservation and Migratory Birds Programs; Draft Land-Based Wind... Impacts from Wind Turbines (Interim Guidance). As stated in the notice, the comment period on the draft... Minimizing Wildlife Impacts from Wind Turbines. We expect to issue final Guidelines for public use after...

DEMONSTRATION OF THE DOE INTERIM ENERGY CONSERVATION STANDARDS FOR NEW FEDERAL RESIDENTIAL BUILDINGS

Energy Technology Data Exchange (ETDEWEB)

Lee, A. D.; Baechler, H. C.; Di Massa, F. V.; Lucas, R. G.; Shankle, D. L.

1992-01-01

In accordance with federal legislation, the U.S. Department of Energy (DOE) has sponsored a study to demonstrate use of its Interim Energy Conservation Standards for New Federal Residential Buildings. The demonstration study was conducted by DOE and the Pacific Northwest Laboratory (PNL). The demonstration is the second step in a three-step process: I) development of interim standards, 2) demonstration of the interim standards, and 3) development of final standards. The standards are mandatory for federal agency housing procurements. Nevertheless, PNL found at the start of the demonstration that agency use of the interim standards had been minimal. The purpose of the standards is to improve the energy efficiency of federal housing and increase the use of nondepletable energy sources. In accordance with the legislation, the standards were to be performance-based rather than prescribing specific energy conservation measures. To fulfill this aspect of the legislation, the standards use a computer software program called COSTSAFR which generates a point system that individualizes the standards to specific projects based on climate, housing type, and fuel costs. The standards generate minimum energy-efficiency requirements by applying the life-cycle cost methodology developed for federal projects. For the demonstration, PNL and DOE chose five federal agency housing projects which had been built in diverse geographic and climate regions. Participating agencies were the Air Force, the Army (which provided two case studies), the Navy, and the Department of Health and Human Services. PNL worked with agency housing procurement officials and designers/architects to hypothetically apply the interim standards to the procurement and design of each housing project. The demonstration started at the point in the project where agencies would establish their energyefficiency requirements for the project and followed the procurement process through the designers' use of the point

75 FR 35510 - License Renewal Interim Staff Guidance Process, Revision 2 Notice of Availability

Science.gov (United States)

2010-06-22

... Related Regulatory Functions.'' An electronic copy of the revised LR-ISG process is available in the NRC's Agencywide Documents Access and Management System (ADAMS) under Accession No. ML100920158. The revised LR-ISG... interim changes to certain NRC license renewal guidance documents. These guidance documents facilitate the...

Interim Control Strategy for the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond - Two-year Update

Energy Technology Data Exchange (ETDEWEB)

L. V. Street

2007-04-01

The Idaho Cleanup Project has prepared this interim control strategy for the U.S. Department of Energy Idaho Operations Office pursuant to DOE Order 5400.5, Chapter 11.3e (1) to support continued discharges to the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond. In compliance with DOE Order 5400.5, a 2-year review of the Interim Control Strategy document has been completed. This submittal documents the required review of the April 2005 Interim Control Strategy. The Idaho Cleanup Project's recommendation is unchanged from the original recommendation. The Interim Control Strategy evaluates three alternatives: (1) re-route the discharge outlet to an uncontaminated area of the TSF-07; (2) construct a new discharge pond; or (3) no action based on justification for continued use. Evaluation of Alternatives 1 and 2 are based on the estimated cost and implementation timeframe weighed against either alternative's minimal increase in protection of workers, the public, and the environment. Evaluation of Alternative 3, continued use of the TSF-07 Disposal Pond under current effluent controls, is based on an analysis of four points: - Record of Decision controls will protect workers and the public - Risk of increased contamination is low - Discharge water will be eliminated in the foreseeable future - Risk of contamination spread is acceptable. The Idaho Cleanup Project recommends Alternative 3, no action other than continued implementation of existing controls and continued deactivation, decontamination, and dismantlement efforts at the Test Area North/Technical Support Facility.

Glass-ionomer-silver-cermet interim Class I restorations for permanent teeth.

Science.gov (United States)

Croll, T P; Killian, C M

1992-11-01

Glass-ionomer-silver-cermet cement has proved to be a worthy alternative to silver amalgam for restoring certain Class I lesions in primary teeth. Such restorations are now known to last up to 8 years without need for repair or replacement. Cermet cement has also been used for interim restoration of permanent teeth in special cases, with ideal results. The procedure for placing a glass-ionomer-silver-cermet cement Class I restoration is described.

Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 1

International Nuclear Information System (INIS)

Wuschke, D.M.; Gillespie, P.A.; Main, D.E.

1985-07-01

The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second assessment was performed in 1984 and is documented in the Second Interim assessment of the Canadian Concept for Nuclear Fuel Waste Disposal Volumes 1 to 4. This volume, entitled Summary, is a condensation of Volumes 2, 3 and 4. It briefly describes the Canadian nuclear fuel waste disposal concept, and the methods and results of the second interim pre-closure and post-closure assessments of that concept. 46 refs

International long-term interim storage for spent fuel. An independent storage service investor model

International Nuclear Information System (INIS)

Leister, P.

1999-01-01

Thinking globally the obvious world-wide demands for large storage capacities for spent fuel within the next decades and the newly arising demands for long-term interim storage of spent fuel urges to respond by international interim storage facilities of high capacity. Low cost storage can be achieved only by arranging the storage facility underground in a suitable host rock formation and by selecting the geographical are by an international competition under those countries, who are willing to offer their land. The investor and operator of an international storage facility selected and realised by a competition on the free market as well as the country where the storage is built are both bound by two different kinds of contacts. The main contract is between the offering country/region and the independent operator. The independent operator has in addition a series of contracts with various utilities, which are interested to have their spent fuel stored for a longer period

Plutonium stabilization and storage research in the DNFSB 94-1 core technology program

International Nuclear Information System (INIS)

Eller, P.G.; Avens, L.R.; Roberson, G.D.

1998-04-01

Recommendation 94-1 of the Defense Nuclear Facility Safety Board (DNFSB) addresses legacy actinide materials left in the US nuclear defense program pipeline when the production mission ended in 1989. The Department of Energy (DOE) Implementation Plan responding to this recommendation instituted a Core Technology program to augment the knowledge base about general chemical and physical processing and storage behavior and to assure safe interim nuclear material storage, until disposition policies are formulated. The Core Technology program focuses on plutonium, in concert with a complex-wide applied R/D program administered by Los Alamos National Laboratory. This paper will summarize the Core Technology program's first two years, describe the research program for FY98, and project the overall direction of the program in the future

Hanford radiochemical site decommissioning demonstration program

International Nuclear Information System (INIS)

Nelson, D.C.

1971-01-01

A program is proposed for the innovation, development, and demonstration of technologies necessary to decommission the Hanford radiochemical plant area to the extent that the sites can have unrestricted public access. The five tasks selected for development and demonstration of restoration techniques were restoration of a burial ground, decommissioning of a separations plant, restoration of a separations plant waste interim storage tank farm, restoration of a liquid disposal area, and disposal of large contaminated equipment. Process development requirements are tabulated and discussed. A proposed schedule and estimated costs are given

Pre-conceptual study on the review framework for the radiation shielding safety of the PWR spent fuel cask interim storage in Korea

International Nuclear Information System (INIS)

Kim, Byeong-Soo; Jeong, Jae-Hak; Jeong, Chan-Woo

2006-01-01

In Korea, 20 nuclear power plants are in operation and lots of spent fuels are on the onsite storage. The onsite storage capacity in Korea is supposed to be full around at the year of 2016 and interim storage facilities could be considered to be constructed before 2016. A review framework to evaluate the radiation shielding safety of the interim storage facilities is developed in this study. It includes acceptance criteria, review procedures and activities of independent analyses. A case study is performed to apply the review framework. Modeling the review reference storage, evaluating the source terms and calculating the photon fluxes are performed. It is shown that the application of the review framework could satisfy the regulatory demand that would arise in the near future in the review area of the radiation shielding safety of the interim storage in Korea. (author)