Waste Acceptance Decisions and Uncertainty Analysis at the Oak Ridge Environmental Management Waste Management Facility

International Nuclear Information System (INIS)

Redus, K. S.; Patterson, J. E.; Hampshire, G. L.; Perkins, A. B.

2003-01-01

The Waste Acceptance Criteria (WAC) Attainment Team (AT) routinely provides the U.S. Department of Energy (DOE) Oak Ridge Operations with Go/No-Go decisions associated with the disposition of over 1.8 million yd3 of low-level radioactive, TSCA, and RCRA hazardous waste. This supply of waste comes from 60+ environmental restoration projects over the next 15 years planned to be dispositioned at the Oak Ridge Environmental Management Waste Management Facility (EMWMF). The EMWMF WAC AT decision making process is accomplished in four ways: (1) ensure a clearly defined mission and timeframe for accomplishment is established, (2) provide an effective organization structure with trained personnel, (3) have in place a set of waste acceptance decisions and Data Quality Objectives (DQO) for which quantitative measures are required, and (4) use validated risk-based forecasting, decision support, and modeling/simulation tools. We provide a summary of WAC AT structure and performance. We offer suggestions based on lessons learned for effective transfer to other DOE

Waste Acceptance Decisions and Uncertainty Analysis at the Oak Ridge Environmental Management Waste Management Facility

Energy Technology Data Exchange (ETDEWEB)

Redus, K. S.; Patterson, J. E.; Hampshire, G. L.; Perkins, A. B.

2003-02-25

The Waste Acceptance Criteria (WAC) Attainment Team (AT) routinely provides the U.S. Department of Energy (DOE) Oak Ridge Operations with Go/No-Go decisions associated with the disposition of over 1.8 million yd3 of low-level radioactive, TSCA, and RCRA hazardous waste. This supply of waste comes from 60+ environmental restoration projects over the next 15 years planned to be dispositioned at the Oak Ridge Environmental Management Waste Management Facility (EMWMF). The EMWMF WAC AT decision making process is accomplished in four ways: (1) ensure a clearly defined mission and timeframe for accomplishment is established, (2) provide an effective organization structure with trained personnel, (3) have in place a set of waste acceptance decisions and Data Quality Objectives (DQO) for which quantitative measures are required, and (4) use validated risk-based forecasting, decision support, and modeling/simulation tools. We provide a summary of WAC AT structure and performance. We offer suggestions based on lessons learned for effective transfer to other DOE.

Assessing WAC Elements in Business Syllabi

Science.gov (United States)

Nicolas, Maureen O’Day; Annous, Samer

2013-01-01

This study investigates syllabi for evidence of the principles of writing across the curriculum (WAC) in courses offered by the Faculty of Business (FOB) at a university operating in a non–English-speaking country. The research analyzed all syllabi of FOB courses offered in the spring 2010 semester for evidence of WAC looking for indications of…

Development of very low-level radioactive waste sequestration process criteria

Energy Technology Data Exchange (ETDEWEB)

Chan, N.; Wong, P., E-mail: nicholas.chan@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada)

2015-12-15

Segregating radioactive waste at the source and reclassifying radioactive waste to lower waste classes are the key activities to reduce the environmental footprint and long-term liability. In the Canadian Standards Association's radioactive waste classification system, there are 2 sub-classes within low-level radioactive waste: very short-lived radioactive waste and very low-level radioactive waste (VLLW). VLLW has a low hazard potential but is above the Canadian unconditional clearance criteria as set out in Schedule 2 of Nuclear Substances and Devices Regulations. Long-term waste management facilities for VLLW do not require a high degree of containment and isolation. In general, a relatively low-cost near-surface facility with limited regulatory control is suitable for VLLW. At Canadian Nuclear Laboratories' Chalk River Laboratories site an initiative, VLLW Sequestration, was implemented in 2013 to set aside potential VLLW for temporary storage and to be later dispositioned in the planned VLLW facility. As of May 2015, a total of 236m{sup 3} resulting in approximately $1.1 million in total savings have been sequestered. One of the main hurdles in implementing VLLW Sequestration is the development of process criteria. Waste Acceptance Criteria (WAC) are used as a guide or as requirements for determining whether waste is accepted by the waste management facility. Establishment of the process criteria ensures that segregated waste materials have a high likelihood to meet the VLLW WAC and be accepted into the planned VLLW facility. This paper outlines the challenges and various factors which were considered in the development of interim process criteria. (author)

Hanford Site solid waste acceptance criteria

International Nuclear Information System (INIS)

Ellefson, M.D.

1998-01-01

Order 5820.2A requires that each treatment, storage, and/or disposal facility (referred to in this document as TSD unit) that manages low-level or transuranic waste (including mixed waste and TSCA PCB waste) maintain waste acceptance criteria. These criteria must address the various requirements to operate the TSD unit in compliance with applicable safety and environmental requirements. This document sets forth the baseline criteria for acceptance of radioactive waste at TSD units operated by WMH. The criteria for each TSD unit have been established to ensure that waste accepted can be managed in a manner that is within the operating requirements of the unit, including environmental regulations, DOE Orders, permits, technical safety requirements, waste analysis plans, performance assessments, and other applicable requirements. Acceptance criteria apply to the following TSD units: the Low-Level Burial Grounds (LLBG) including both the nonregulated portions of the LLBG and trenches 31 and 34 of the 218-W-5 Burial Ground for mixed waste disposal; Central Waste Complex (CWC); Waste Receiving and Processing Facility (WRAP); and T Plant Complex. Waste from all generators, both from the Hanford Site and from offsite facilities, must comply with these criteria. Exceptions can be granted as provided in Section 1.6. Specific waste streams could have additional requirements based on the 1901 identified TSD pathway. These requirements are communicated in the Waste Specification Records (WSRds). The Hanford Site manages nonradioactive waste through direct shipments to offsite contractors. The waste acceptance requirements of the offsite TSD facility must be met for these nonradioactive wastes. This document does not address the acceptance requirements of these offsite facilities

History of Uranium-233(233U)Processing at the Rocky Flats Plant. In support of the RFETS Acceptable Knowledge Program

International Nuclear Information System (INIS)

Moment, R.L.; Gibbs, F.E.; Freiboth, C.J.

1999-01-01

This report documents the processing of Uranium-233 at the Rocky Flats Plant (Rocky Flats Environmental Technology Site). The information may be used to meet Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC)and for determining potential Uranium-233 content in applicable residue waste streams

Waste acceptance and waste loading for vitrified Oak Ridge tank waste

International Nuclear Information System (INIS)

Harbour, J.R.; Andrews, M.K.

1997-01-01

The Office of Science and Technology of the DOE has funded a joint project between the Oak Ridge National Laboratory (ORNL) and the Savannah River Technology Center (SRTC) to evaluate vitrification and grouting for the immobilization of sludge from ORNL tank farms. The radioactive waste is from the Gunite and Associated Tanks (GAAT), the Melton Valley Storage Tanks (MVST), the Bethel Valley Evaporator Service Tanks (BVEST), and the Old Hydrofractgure Tanks (OHF). Glass formulation development for sludge from these tanks is discussed in an accompanying article for this conference (Andrews and Workman). The sludges contain transuranic radionuclides at levels which will make the glass waste form (at reasonable waste loadings) TRU. Therefore, one of the objectives for this project was to ensure that the vitrified waste form could be disposed of at the Waste Isolation Pilot Plant (WIPP). In order to accomplish this, the waste form must meet the WIPP Waste Acceptance Criteria (WAC). An alternate pathway is to send the glass waste forms for disposal at the Nevada Test Site (NTS). A sludge waste loading in the feed of 6 wt percent will lead to a waste form which is non-TRU and could potentially be disposed of at NTS. The waste forms would then have to meet the requirements of the NTS WAC. This paper presents SRTC''s efforts at demonstrating that the glass waste form produced as a result of vitrification of ORNL sludge will meet all the criteria of the WIPP WAC or NTS WAC

Hanford Site Solid Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

1993-11-17

This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities.

Hanford Site Solid Waste Acceptance Criteria

International Nuclear Information System (INIS)

1993-01-01

This manual defines the Hanford Site radioactive, hazardous, and sanitary solid waste acceptance criteria. Criteria in the manual represent a guide for meeting state and federal regulations; DOE Orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to acceptance of radioactive and hazardous solid waste at the Hanford Site. It is not the intent of this manual to be all inclusive of the regulations; rather, it is intended that the manual provide the waste generator with only the requirements that waste must meet in order to be accepted at Hanford Site TSD facilities

Waste acceptance product specifications for vitrified high-level waste forms

International Nuclear Information System (INIS)

Applewhite-Ramsey, A.; Sproull, J.F.

1993-01-01

The Nuclear Waste Policy Act of 1982 mandated that all high-level waste (HLW) be sent to a federal geologic repository for permanent disposal. DOE published the Environmental Assessment in 1982 which identified borosilicate glass as the chosen HLW form. 1 In 1985 the Department of Energy instituted a Waste Acceptance Process to assure that DWPF glass waste forms would be acceptable to such a repository. This assurance was important since production of waste forms will precede repository construction and licensing. As part of this Waste Acceptance Process, the DOE Office of Civilian Radioactive Waste Management (RW) formed the Waste Acceptance Committee (WAC). The WAC included representatives from the candidate repository sites, the waste producing sites and DOE. The WAC was responsible for developing the Waste Acceptance Preliminary Specifications (WAPS) which defined the requirements the waste forms must meet to be compatible with the candidate repository geologies

A comparison of real-time radiography results and visual characterization results with emphasis on WIPP WAC and TRAMPAC compliance issues

International Nuclear Information System (INIS)

Hailey, S.M.

1994-01-01

Visual characterization provides a means of confirming the real-time radiography (RTR) certification process and process knowledge. RTR and visual characterization have been conducted on thirty-three drums containing transuranic (TRU) waste in support of the Waste Isolation Pilot Plant (WIPP) Experimental Test Program (WETP) at the Idaho National Engineering Laboratory. Argonne National Laboratory - West (ANL-W) detected a small can of liquid in one of these drums during the visual examination, resulting in a WIPP Waste Acceptance Criteria (WIPP-WAC) miscertification. The remaining thirty-two drums were certified correctly by the RTR system at the Stored Waste Examination Pilot Plant (SWEPP) for WIPP-WAC and TRUPACT-II Authorized Methods for Payload Control (TRAMPAC) requirements. TRAMPAC contains restrictions on the weights of specific materials allowed in the waste, based on the shipping category. Items on the restricted list for a given shipping category are allowed in quantities less than 1 percent of the weight of the waste. RTR can estimate the weights of certain broad categories in homogeneous waste forms, however, the capability to estimate weights at the 1 percent level is not presently realistic. Process knowledge forms the basis of conformance to these weight requirements. Visual characterization suggests process knowledge is not completely adequate at this level

The State of WAC/WID in 2010: Methods and Results of the U.S. Survey of the International WAC/WID Mapping Project

Science.gov (United States)

Thaiss, Chris; Porter, Tara

2010-01-01

As writing across the curriculum (WAC) has matured and diversified as a concept and as an organizational structure in U.S. higher education, there has arisen a need for accurate, up-to-date information on the presence and characteristics of WAC and writing-in-the-disciplines (WID) programs. Following on the only previous nationwide survey of…

Nevada Test Site Waste Acceptance Criteria, December 2000

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-12-01

This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal.

Nevada Test Site Waste Acceptance Criteria, December 2000

International Nuclear Information System (INIS)

2000-01-01

This document establishes the US Department of Energy, Nevada Operations Office waste acceptance criteria. The waste acceptance criteria provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive waste and mixed waste for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the Nevada Test Site Area 3 and Area 5 Radioactive Waste Management Sites for storage or disposal

Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

W. Mahlon Heileson

2006-10-01

The Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) has been designed to accept CERCLA waste generated within the Idaho National Laboratory. Hazardous, mixed, low-level, and Toxic Substance Control Act waste will be accepted for disposal at the ICDF. The purpose of this document is to provide criteria for the quantities of radioactive and/or hazardous constituents allowable in waste streams designated for disposal at ICDF. This ICDF Complex Waste Acceptance Criteria is divided into four section: (1) ICDF Complex; (2) Landfill; (3) Evaporation Pond: and (4) Staging, Storage, Sizing, and Treatment Facility (SSSTF). The ICDF Complex section contains the compliance details, which are the same for all areas of the ICDF. Corresponding sections contain details specific to the landfill, evaporation pond, and the SSSTF. This document specifies chemical and radiological constituent acceptance criteria for waste that will be disposed of at ICDF. Compliance with the requirements of this document ensures protection of human health and the environment, including the Snake River Plain Aquifer. Waste placed in the ICDF landfill and evaporation pond must not cause groundwater in the Snake River Plain Aquifer to exceed maximum contaminant levels, a hazard index of 1, or 10-4 cumulative risk levels. The defined waste acceptance criteria concentrations are compared to the design inventory concentrations. The purpose of this comparison is to show that there is an acceptable uncertainty margin based on the actual constituent concentrations anticipated for disposal at the ICDF. Implementation of this Waste Acceptance Criteria document will ensure compliance with the Final Report of Decision for the Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. For waste to be received, it must meet the waste acceptance criteria for the specific disposal/treatment unit (on-Site or off-Site) for which it is destined.

Risk acceptance criteria of the Nuclear Regulatory Authority

International Nuclear Information System (INIS)

Felizia, Eduardo R.

2005-01-01

This report describes some of the regulatory and control functions legally conferred upon the Argentine Nuclear Regulatory Authority concerning radiological risks, as well as a critical analysis of the radiological risk acceptance criteria contained in the Argentine regulatory system. A summary of the application of regulatory standards AR 3.1.3. - 'Radiological criteria related to accidents in nuclear power reactors' and AR 4.1.3. - 'Radiological criteria related to accidents in research reactors' to concrete cases is made, while the favourable and unfavourable aspects of the risk acceptance criteria are discussed. The conclusion is that the Argentine regulatory system contains adequate radiological risk acceptance criteria, that the latter are consistent with the radiological protection principles applicable to man and that, for the moment, there is no need to perform any modifications that would broaden the conceptual framework on which such criteria are based. (author) [es

Inelastic analysis acceptance criteria for radioactive material transportation containers

International Nuclear Information System (INIS)

Ammerman, D.J.; Ludwigsen, J.S.

1993-01-01

The design criteria currently used in the design of radioactive material (RAM) transportation containers are taken from the ASME Boiler and Pressure Vessel Code (ASME, 1992). These load-based criteria are ideally suited for pressure vessels where the loading is quasistatic and all stresses are in equilibrium with externally applied loads. For impact events, the use of load-based criteria is less supportable. Impact events tend to be energy controlled, and thus, energy-based acceptance criteria would appear to be more appropriate. Determination of an ideal design criteria depends on what behavior is desired. Currently there is not a design criteria for inelastic analysis for RAM nation packages that is accepted by the regulatory agencies. This lack of acceptance criteria is one of the major factors in limiting the use of inelastic analysis. In this paper inelastic analysis acceptance criteria based on stress and strain-energy density will be compared for two stainless steel test units subjected to impacts onto an unyielding target. Two different material models are considered for the inelastic analysis, a bilinear fit of the stress-strain curve and a power law hardening model that very closely follows the stress-strain curve. It is the purpose of this paper to stimulate discussion and research into the area of strain-energy density based inelastic analysis acceptance criteria

Assessment of LANL transuranic mixed waste management documentation

International Nuclear Information System (INIS)

Davis, K.D.; Hoevemeyer, S.S.; McCance, C.H.; Jennrich, E.A.; Lund, D.M.

1991-04-01

The objective of this report is to present findings from the evaluation of the Los Alamos National Laboratory (LANL) TRU Mixed Waste Acceptance Criteria to determine its compliance with applicable DOE requirements. The driving requirements for s TRU Mixed Waste Acceptance Criteria are essentially those contained in the ''TRU Waste Acceptance Criteria for the Waste Isolation Pilot Plant'' or WIPP WAC (DOE Report WIPP-DOE-069), 40 CFR 261-270, and DOE Order 5820.2A (Radioactive Waste Management), specifically Chapter II which is entitled ''Management of Transuranic Waste''. The primary purpose of the LANL WAC is the establishment of those criteria that must be met by generators of TRU mixed waste before such waste can be accepted by the Waste Management Group. An annotated outline of a genetic TRU mixed waste acceptance criteria document was prepared from those requirements contained in the WIPP WAC, 40 CFR 261-270, and 5820.2A, and is based solely upon those requirements

Reality check on girth weld defect acceptance criteria

Energy Technology Data Exchange (ETDEWEB)

Brust, Bud; Kalyanam, Suresh; Shim, Do-Jun; Wilkowski, Gery [Engineering Mechanics Corporation of Columbus, Columbus, OH, (United States)

2010-07-01

Girth weld defect tolerance criteria for pipeline construction has evolved with time. Recently, ERPG recommended a new Tier 2 girth weld defect acceptance criterion. This paper described the new development on girth weld defect acceptance criteria. The inherent conservatisms of alternative girth weld defect acceptance criteria from the 2007 API 1104 Appendix A, CSA Z662 Appendix K, are compared to those from the proposed EPRG Tier 2 criteria. It is found that the API and CSA codes have the same empirical limit-load criteria. As well, there are conservatisms in the proposed EPRG Tier 2. The results showed that there are various reasons why large amounts of conservatism in the allowable flaw lengths in the CSA Appendix K,2007 API 1104 Appendix A, and proposed EPRG Tier 2 girth weld defect criterion exist. Small conservatisms on failure stress can result in large conservatisms in flaw size.

Risk Acceptance Criteria and/or Decision optimization

DEFF Research Database (Denmark)

Ditlevsen, Ove Dalager

1996-01-01

Acceptance criteria applied in practical risk analysis are recapitulated including the concept of rist profile. Modelling of risk profiles is illustrated on the basis of compound Poisson process models. The current practice of authoritative acceptance criteria formulation is discussed from...... a decision theoretical point of view. It is argued that the phenomenon of risk aversion rather than being of concern to the authority should be of concern to the owner. Finally it is discussed whether there is an ethical problem when formally capitalising human lives with a positive interest rate. Keywords......: Risk acceptance, Risk profile, Compound Poisson model for risk profile, Capitalization of human life, Risk aversion....

Fragment screening for drug leads by weak affinity chromatography (WAC-MS).

Science.gov (United States)

Ohlson, Sten; Duong-Thi, Minh-Dao

2018-02-23

Fragment-based drug discovery is an important tool for design of small molecule hit-to-lead compounds against various biological targets. Several approved drugs have been derived from an initial fragment screen and many such candidates are in various stages of clinical trials. Finding fragment hits, that are suitable for optimisation by medicinal chemists, is still a challenge as the binding between the small fragment and its target is weak in the range of mM to µM of K d and irrelevant non-specific interactions are abundant in this area of transient interactions. Fortunately, there are methods that can study weak interactions quite efficiently of which NMR, surface plasmon resonance (SPR) and X-ray crystallography are the most prominent. Now, a new technology based on zonal affinity chromatography, weak affinity chromatography (WAC), has been introduced which has remedied many of the problems with other technologies. By combining WAC with mass spectrometry (WAC-MS), it is a powerful tool to identify binders quantitatively in terms of affinity and kinetics either from fragment libraries or from complex mixtures of biological extracts. As WAC-MS can be multiplexed by analysing mixtures of fragments (20-100 fragments) in one sample, this approach yields high throughput, where a whole library of e.g. >2000 fragments can be analysed quantitatively within a day. WAC-MS is easy to perform, where the robustness and quality of HPLC is fully utilized. This review will highlight the rationale behind the application of WAC-MS for fragment screening in drug discovery. Copyright © 2018 Elsevier Inc. All rights reserved.

Design Criteria for Achieving Acceptable Indoor Radon Concentration

DEFF Research Database (Denmark)

Rasmussen, Torben Valdbjørn

2016-01-01

Design criteria for achieving an acceptable indoor radon concentration are presented in this paper. The paper suggests three design criteria. These criteria have to be considered at the early stage of the building design phase to meet the latest recommendations from the World Health Organization...... in most countries. The three design criteria are; first, establishing a radon barrier facing the ground; second, lowering the air pressure in the lower zone of the slab on ground facing downwards; third, diluting the indoor air with outdoor air. The first two criteria can prevent radon from infiltrating...... from the ground, and the third criteria can dilute the indoor air. By combining these three criteria, the indoor radon concentration can be lowered achieving an acceptable level. In addition, a cheap and reliable method for measuring the radon concentration in the indoor air is described. The provision...

Structural acceptance criteria Remote Handling Building Tritium Extraction Facility

Energy Technology Data Exchange (ETDEWEB)

Mertz, G.

1999-12-16

This structural acceptance criteria contains the requirements for the structural analysis and design of the Remote Handling Building (RHB) in the Tritium Extraction Facility (TEF). The purpose of this acceptance criteria is to identify the specific criteria and methods that will ensure a structurally robust building that will safely perform its intended function and comply with the applicable Department of Energy (DOE) structural requirements.

Structural acceptance criteria Remote Handling Building Tritium Extraction Facility

International Nuclear Information System (INIS)

Mertz, G.

1999-01-01

This structural acceptance criteria contains the requirements for the structural analysis and design of the Remote Handling Building (RHB) in the Tritium Extraction Facility (TEF). The purpose of this acceptance criteria is to identify the specific criteria and methods that will ensure a structurally robust building that will safely perform its intended function and comply with the applicable Department of Energy (DOE) structural requirements

Assessment of LANL PCB waste management documentation

International Nuclear Information System (INIS)

David, K.D.; Hoevemeyer, S.S.; Stirrup, T.S.; Jennrich, E.A.; Lund, D.M.

1991-04-01

The objective of this report is to present findings from evaluating the Los Alamos National Laboratory (LANL) Polychlorinated Biphenyls (PCB) Waste Acceptance Criteria (WAC) to determine if it meets applicable DOE and Code of Federal Regulation (CFR) requirements. DOE Order 5820.2A and 40 CFR 761 (Polychlorinated Biphenyls Manufacturing, Processing, Distribution in Commerce, and Use Prohibitions) set forth requirements and guidelines for the establishment of Waste Acceptance Criteria. The primary purpose of a PCB WAC is to provide generators and waste management with established criteria that must be met before PCB wastes can be accepted for treatment, storage, and/or disposal. An annotated outline for a generic PCB WAC was developed based on the requirements of 5820.2A and 40 CFR 761. The major elements that should be addressed by a PCB WAC were determined to be as follows: Waste Package/Container, Waste Forms, PCB Concentrations, Labeling, and Data Package Certification

Photometric normalization of LROC WAC images

Science.gov (United States)

Sato, H.; Denevi, B.; Robinson, M. S.; Hapke, B. W.; McEwen, A. S.; LROC Science Team

2010-12-01

The Lunar Reconnaissance Orbiter Camera (LROC) Wide Angle Camera (WAC) acquires near global coverage on a monthly basis. The WAC is a push frame sensor with a 90° field of view (FOV) in BW mode and 60° FOV in 7-color mode (320 nm to 689 nm). WAC images are acquired during each orbit in 10° latitude segments with cross track coverage of ~50 km. Before mosaicking, WAC images are radiometrically calibrated to remove instrumental artifacts and to convert at sensor radiance to I/F. Images are also photometrically normalized to common viewing and illumination angles (30° phase), a challenge due to the wide angle nature of the WAC where large differences in phase angle are observed in a single image line (±30°). During a single month the equatorial incidence angle drifts about 28° and over the course of ~1 year the lighting completes a 360° cycle. The light scattering properties of the lunar surface depend on incidence(i), emission(e), and phase(p) angles as well as soil properties such as single-scattering albedo and roughness that vary with terrain type and state of maturity [1]. We first tested a Lommel-Seeliger Correction (LSC) [cos(i)/(cos(i) + cos(e))] [2] with a phase function defined by an exponential decay plus 4th order polynomial term [3] which did not provide an adequate solution. Next we employed a LSC with an exponential 2nd order decay phase correction that was an improvement, but still exhibited unacceptable frame-to-frame residuals. In both cases we fitted the LSC I/F vs. phase angle to derive the phase corrections. To date, the best results are with a lunar-lambert function [4] with exponential 2nd order decay phase correction (LLEXP2) [(A1exp(B1p)+A2exp(B2p)+A3) * cos(i)/(cos(e) + cos(i)) + B3cos(i)]. We derived the parameters for the LLEXP2 from repeat imaging of a small region and then corrected that region with excellent results. When this correction was applied to the whole Moon the results were less than optimal - no surprise given the

Nevada National Security Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

2012-01-01

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept DOE non-radioactive classified waste, DOE non-radioactive hazardous classified waste, DOE low-level radioactive waste (LLW), DOE mixed low-level waste (MLLW), and U.S. Department of Defense (DOD) classified waste for permanent disposal. Classified waste is the only waste accepted for disposal that may be non-radioactive and will be required to meet the waste acceptance criteria for radioactive waste as specified in this document. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project (WMP) at (702) 295-7063, and your call will be directed to the appropriate contact.

Nevada National Security Site Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2012-02-28

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept DOE non-radioactive classified waste, DOE non-radioactive hazardous classified waste, DOE low-level radioactive waste (LLW), DOE mixed low-level waste (MLLW), and U.S. Department of Defense (DOD) classified waste for permanent disposal. Classified waste is the only waste accepted for disposal that may be non-radioactive and will be required to meet the waste acceptance criteria for radioactive waste as specified in this document. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project (WMP) at (702) 295-7063, and your call will be directed to the appropriate contact.

Waste-acceptance criteria for greater confinement disposal

International Nuclear Information System (INIS)

Gilbert, T.L.; Meshkov, N.K.

1987-01-01

A methodology for establishing waste-acceptance criteria based on quantitative performance factors that characterize the confinement capabilities of a waste disposal site and facility has been developed. The methodology starts from the basic objective of protecting public health and safety by providing assurance that disposal of the waste will not result in a radiation dose to any member of the general public, in either the short or long term, in excess of an established basic dose limit. The method is based on an explicit, straight-forward, and quantitative relationship among individual risk, confinement capabilities, and waste characteristics. A key aspect of the methodology is introduction of a confinement factor that characterizes the overall confinement capability of a particular facility and can be used for quantitative assessments of the performance of different disposal sites and facilities, as well as for establishing site-specific waste acceptance criteria. Confinement factors are derived by means of site-specific pathway analyses. They make possible a direct and simple conversion of a basic dose limit into waste-acceptance criteria, specified as concentration limits on radionuclides in the waste streams and expressed in quantitative form as a function of parameters that characterize the site, facility design, waste containers, and waste form. Waste acceptance criteria can be represented visually as activity/time plots for various waste streams. These plots show the concentrations of radionuclides in a waste stream as a function of time and permit a visual, quantitative assessment of long-term performance, relative risks from different radionuclides in the waste stream, and contributions from ingrowth. 13 references, 7 figures

Waste-acceptance criteria for greater-confinement disposal

International Nuclear Information System (INIS)

Gilbert, T.L.; Meshkov, N.K.

1986-01-01

A methodology for establishing waste-acceptance criteria based on quantitative performance factors that characterize the confinement capabilities of a waste-disposal site and facility has been developed. The methodology starts from the basic objective of protecting public health and safety by providing assurance that dispsoal of the waste will not result in a radiation dose to any member of the general public, in either the short or long term, in excess of an established basic dose limit. The method is based on an explicit, straightforward, and quantitative relationship among individual risk, confinement capabilities, and waste characteristics. A key aspect of the methodology is the introduction of a confinement factor that characterizes the overall confinement capability of a particular facility and can be used for quantitative assessments of the performance of different disposal sites and facilities, as well as for establishing site-specific waste-acceptance criteria. Confinement factors are derived by means of site-specific pathway analyses. They make possible a direct and simple conversion of a basic dose limit into waste-acceptance criteria, specified as concentration limits on radionuclides in the waste streams and expressed in quantitative form as a function of parameters that characterize the site, facility design, waste containers, and waste form. Waste-acceptance criteria can be represented visually as activity/time plots for various waste streams. These plots show the concentrations of radionuclides in a waste stream as a function of time and permit a visual, quantitative assessment of long-term performance, relative risks from different radionuclides in the waste stream, and contributions from ingrowth. 13 refs

Nevada Test Site Waste Acceptance Criteria (NTSWAC)

Energy Technology Data Exchange (ETDEWEB)

NNSA/NSO Waste Management Project

2008-06-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal.

Nevada Test Site Waste Acceptance Criteria (NTSWAC)

International Nuclear Information System (INIS)

NNSA/NSO Waste Management Project

2008-01-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal

Toxic chemical risk acceptance criteria

International Nuclear Information System (INIS)

Craig, D.K.; Davis, J.; Lee, L.; Lein, P.; Omberg, S.

1992-01-01

This paper presents recommendations of a subcommittee of the Westinghouse M ampersand 0 Nuclear Facility Safety Committee concerning toxic chemical risk acceptance criteria. Two sets of criteria have been developed, one for use in the hazard classification of facilities, and the second for use in comparing risks in DOE non-reactor nuclear facility Safety Analysis Reports. The Emergency Response Planning Guideline (ERPG) values are intended to provide estimates of concentration ranges for specific chemicals above which exposure would be expected to lead to adverse heath effects of increasing severity for ERPG-1, -2, and -3s. The subcommittee recommends that criteria for hazard class or risk range be based on ERPGs for all chemicals. Probability-based Incremental Cancer Risk (ICR) criteria are recommended for additional analyses of risks from all known or suspected human carcinogens. Criteria are given for both on-site and off-site exposure. The subcommittee also recommends that the 5-minute peak concentration be compared with the relevant criterion with no adjustment for exposure time. Since ERPGs are available for only a limited number of chemicals, the subcommittee has developed a proposed hierarchy of concentration limit parameters for the different criteria

Notes from the Margins: WAC, WID, and the Politics of Place(ment)

Science.gov (United States)

Cook, Paul G.

2014-01-01

This institutional autoethnography (IAE) explores the political and pedagogical dynamics of WPA and WAC/WID work within an exceedingly small, resolutely single-sex, and assuredly rural liberal arts campus ecology. Working within a theoretical framework informed by WAC/WID's historical commitment to increasing literacy in students from diverse…

Application of trial risk acceptance criteria

International Nuclear Information System (INIS)

Johnson, D.H.; Kastenberg, W.E.; Okrent, D.

1982-01-01

The objective of this paper is to investigate some of the implications inherent in the application of various proposed sets of risk acceptance criteria. A power-law model of risk aversion is utilized to estimate the equivalent number of individual deaths and is treated parametrically. The implications of ALARA requirements for cost-effective improvements are also illustrated. The risks assessed for various technological endeavors, as well as some estimated natural background risks, are compared to the trial criteria

Assessment of LANL hazardous waste management documentation

International Nuclear Information System (INIS)

Davis, K.D.; Hoevemeyer, S.S.; Stirrup, T.S.; Jennrich, E.A.; Lund, D.M.

1991-04-01

The objective of this report is to present findings from evaluating the Los Alamos National Laboratory (LANL) ''Hazardous Waste Acceptance Criteria Receipt at TA-54, Area L'' to determine if it meets applicable DOE requirements. The guidelines and requirements for the establishment of a Hazardous Waste Acceptance Criteria (HW-WAC) are found in 40 CFR 260 to 270 and DOE Order 5820.2A. Neither set of requirements specifically require a WAC for the management of hazardous waste; however, the use of such documentation is logical and is consistent with the approach required for the management of radioactive waste. The primary purpose of a HW-WAC is to provide generators and waste management with established criteria that must be met before hazardous waste can be acceptable for treatment, storage and/or disposal. An annotated outline for a generic waste acceptance criteria was developed based on the requirements of 40 CFR 260 to 270 and DOE Order 5820.2A. The outline contains only requirements for hazardous waste, it does not address the radiological components of low-level mixed waste. The outline generated from the regulations was used for comparison to the LANL WAC For Chemical and Low-level Mixed Waste Receipt at TA-54, Area L. The major elements that should be addressed by a hazardous waste WAC were determined to be as follows: Waste Package/Container Requirements, Waste Forms, Land Disposal Restrictions, and Data Package-Certification ampersand Documentation

LROC WAC 100 Meter Scale Photometrically Normalized Map of the Moon

Science.gov (United States)

Boyd, A. K.; Nuno, R. G.; Robinson, M. S.; Denevi, B. W.; Hapke, B. W.

2013-12-01

The Lunar Reconnaissance Orbiter Camera (LROC) Wide Angle Camera (WAC) monthly global observations allowed derivation of a robust empirical photometric solution over a broad range of incidence, emission and phase (i, e, g) angles. Combining the WAC stereo-based GLD100 [1] digital terrain model (DTM) and LOLA polar DTMs [2] enabled precise topographic corrections to photometric angles. Over 100,000 WAC observations at 643 nm were calibrated to reflectance (I/F). Photometric angles (i, e, g), latitude, and longitude were calculated and stored for each WAC pixel. The 6-dimensional data set was then reduced to 3 dimensions by photometrically normalizing I/F with a global solution similar to [3]. The global solution was calculated from three 2°x2° tiles centered on (1°N, 147°E), (45°N, 147°E), and (89°N, 147°E), and included over 40 million WAC pixels. A least squares fit to a multivariate polynomial of degree 4 (f(i,e,g)) was performed, and the result was the starting point for a minimum search solving the non-linear function min[{1-[ I/F / f(i,e,g)] }2]. The input pixels were filtered to incidence angles (calculated from topography) shadowed pixels, and the output normalized I/F values were gridded into an equal-area map projection at 100 meters/pixel. At each grid location the median, standard deviation, and count of valid pixels were recorded. The normalized reflectance map is the result of the median of all normalized WAC pixels overlapping that specific 100-m grid cell. There are an average of 86 WAC normalized I/F estimates at each cell [3]. The resulting photometrically normalized mosaic provides the means to accurately compare I/F values for different regions on the Moon (see Nuno et al. [4]). The subtle differences in normalized I/F can now be traced across the local topography at regions that are illuminated at any point during the LRO mission (while the WAC was imaging), including at polar latitudes. This continuous map of reflectance at 643 nm

Environmental Restoration Disposal Facility Waste Acceptance Criteria

International Nuclear Information System (INIS)

Dronen, V.R.

1998-06-01

The Hanford Site is operated by the U. S. Department of Energy (DOE) with a primary mission of environmental cleanup and restoration. The Environmental Restoration Disposal Facility (ERDF) is an integral part of the DOE environmental restoration effort at the Hanford Site. The purpose of this document is to establish the ERDF waste acceptance criteria for disposal of materials resulting from Hanford Site cleanup activities. Definition of and compliance with the requirements of this document will enable implementation of appropriate measures to protect human health and the environment, ensure the integrity of the ERDF liner system, facilitate efficient use of the available space in the ERDF, and comply with applicable environmental regulations and DOE orders. To serve this purpose, the document defines responsibilities, identifies the waste acceptance process, and provides the primary acceptance criteria and regulatory citations to guide ERDF users. The information contained in this document is not intended to repeat or summarize the contents of all applicable regulations

Nevada National Security Site Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

none,

2013-06-01

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: • DOE hazardous and non-hazardous non-radioactive classified waste • DOE low-level radioactive waste (LLW) • DOE mixed low-level waste (MLLW) • U.S. Department of Defense (DOD) classified waste The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

Nevada National Security Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

2013-01-01

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: DOE hazardous and non-hazardous non-radioactive classified waste; DOE low-level radioactive waste (LLW); DOE mixed low-level waste (MLLW); and, U.S. Department of Defense (DOD) classified waste. The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

De novo loss-of-function mutations in WAC cause a recognizable intellectual disability syndrome and learning deficits in Drosophila.

Science.gov (United States)

Lugtenberg, Dorien; Reijnders, Margot R F; Fenckova, Michaela; Bijlsma, Emilia K; Bernier, Raphael; van Bon, Bregje W M; Smeets, Eric; Vulto-van Silfhout, Anneke T; Bosch, Danielle; Eichler, Evan E; Mefford, Heather C; Carvill, Gemma L; Bongers, Ernie M H F; Schuurs-Hoeijmakers, Janneke Hm; Ruivenkamp, Claudia A; Santen, Gijs W E; van den Maagdenberg, Arn M J M; Peeters-Scholte, Cacha M P C D; Kuenen, Sabine; Verstreken, Patrik; Pfundt, Rolph; Yntema, Helger G; de Vries, Petra F; Veltman, Joris A; Hoischen, Alexander; Gilissen, Christian; de Vries, Bert B A; Schenck, Annette; Kleefstra, Tjitske; Vissers, Lisenka E L M

2016-08-01

Recently WAC was reported as a candidate gene for intellectual disability (ID) based on the identification of a de novo mutation in an individual with severe ID. WAC regulates transcription-coupled histone H2B ubiquitination and has previously been implicated in the 10p12p11 contiguous gene deletion syndrome. In this study, we report on 10 individuals with de novo WAC mutations which we identified through routine (diagnostic) exome sequencing and targeted resequencing of WAC in 2326 individuals with unexplained ID. All but one mutation was expected to lead to a loss-of-function of WAC. Clinical evaluation of all individuals revealed phenotypic overlap for mild ID, hypotonia, behavioral problems and distinctive facial dysmorphisms, including a square-shaped face, deep set eyes, long palpebral fissures, and a broad mouth and chin. These clinical features were also previously reported in individuals with 10p12p11 microdeletion syndrome. To investigate the role of WAC in ID, we studied the importance of the Drosophila WAC orthologue (CG8949) in habituation, a non-associative learning paradigm. Neuronal knockdown of Drosophila CG8949 resulted in impaired learning, suggesting that WAC is required in neurons for normal cognitive performance. In conclusion, we defined a clinically recognizable ID syndrome, caused by de novo loss-of-function mutations in WAC. Independent functional evidence in Drosophila further supported the role of WAC in ID. On the basis of our data WAC can be added to the list of ID genes with a role in transcription regulation through histone modification.

Automated Transportation Management System (ATMS) V2.0 logistics module PBI acceptance criteria

International Nuclear Information System (INIS)

Weidert, R.S.

1995-01-01

This document defines the acceptance criteria for the Automated Transportation Management System V2.0 Logistics Module Performance Based Incentive (PBI). This acceptance criteria will be the primary basis for the generation of acceptance test procedures. The purpose of this document is to define the minimum criteria that must be fulfilled to guarantee acceptance of the Logistics Module

Acceptance criteria for the evaluation of nuclear power reactor security plans

International Nuclear Information System (INIS)

1982-08-01

This guidance document contains acceptance criteria to be used in the NRC license review process. It contains specific criteria for use in evaluating the acceptability of nuclear power reactor security programs as detailed in security plans

Human factors engineering design review acceptance criteria for the safety parameter display

International Nuclear Information System (INIS)

McGevna, V.; Peterson, L.R.

1981-01-01

This report contains human factors engineering design review acceptance criteria developed by the Human Factors Engineering Branch (HFEB) of the Nuclear Regulatory Commission (NRC) to use in evaluating designs of the Safety Parameter Display System (SPDS). These criteria were developed in response to the functional design criteria for the SPDS defined in NUREG-0696, Functional Criteria for Emergency Response Facilities. The purpose of this report is to identify design review acceptance criteria for the SPDS installed in the control room of a nuclear power plant. Use of computer driven cathode ray tube (CRT) displays is anticipated. General acceptance criteria for displays of plant safety status information by the SPDS are developed. In addition, specific SPDS review criteria corresponding to the SPDS functional criteria specified in NUREG-0696 are established

Anticipating Potential Waste Acceptance Criteria for Defense Spent Nuclear Fuel

International Nuclear Information System (INIS)

Rechard, R.P.; Lord, M.E.; Stockman, C.T.; McCurley, R.D.

1997-01-01

The Office of Environmental Management of the U.S. Department of Energy is responsible for the safe management and disposal of DOE owned defense spent nuclear fuel and high level waste (DSNF/DHLW). A desirable option, direct disposal of the waste in the potential repository at Yucca Mountain, depends on the final waste acceptance criteria, which will be set by DOE's Office of Civilian Radioactive Waste Management (OCRWM). However, evolving regulations make it difficult to determine what the final acceptance criteria will be. A method of anticipating waste acceptance criteria is to gain an understanding of the DOE owned waste types and their behavior in a disposal system through a performance assessment and contrast such behavior with characteristics of commercial spent fuel. Preliminary results from such an analysis indicate that releases of 99Tc and 237Np from commercial spent fuel exceed those of the DSNF/DHLW; thus, if commercial spent fuel can meet the waste acceptance criteria, then DSNF can also meet the criteria. In large part, these results are caused by the small percentage of total activity of the DSNF in the repository (1.5%) and regulatory mass (4%), and also because commercial fuel cladding was assumed to provide no protection

Nevada National Security Site Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2010-09-03

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

Nevada National Security Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

2010-01-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

Nevada National Security Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

2011-01-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

A Study on the Acceptance Criteria for DTrip Frequency

International Nuclear Information System (INIS)

Kim, Kil Yoo; Lee, Hyun Woo; Jae, Moo Sung

2011-01-01

Many risk informed regulation and applications (RIR and A) are approved, and more RIR and A will be actively applied in Korea. The acceptance criteria for the RIR and A have been DCDF, and DLERF. However, in the economical point of view, the change of the reactor trip frequency (hereafter, it is called Dtrip) are important element to monitor in the RIR and A. A reactor trip causes a huge economical loss, and causes a bad reputation in the social acceptance which causes eventually a social cost, and could induce a safety problem by giving a severe stress on the operators. Usually, the chief managers of nuclear power plants are reluctant to increase the trip frequency by a RIR and A, even though the RIR and A could bring an economical benefit, and could not threaten the safety. Because, if a reactor trip occurs, it would be reflected in his performance assessment. Therefore, it is necessary to set up an acceptance criteria for Dtrip in the RIR and A without depending on the personal preference of the chief manager. This paper introduces the acceptance criteria for Dtrip in the RIR and A

Acceptance criteria for radioactive waste deposition

International Nuclear Information System (INIS)

Rzyski, B.M.

1989-01-01

The disposal of low-and intermediate level radioactive waste in either shallow ground or rock cavities must be subjected to special guidelines which are used by national authorities and implementing bodies when establishing and regulating respositories. These informations are given by the acceptance criteria and will depend on specific site conditions and optmized procedures. (author) [pt

DISPOSABLE CANISTER WASTE ACCEPTANCE CRITERIA

Energy Technology Data Exchange (ETDEWEB)

R.J. Garrett

2001-07-30

The purpose of this calculation is to provide the bases for defining the preclosure limits on radioactive material releases from radioactive waste forms to be received in disposable canisters at the Monitored Geologic Repository (MGR) at Yucca Mountain. Specifically, this calculation will provide the basis for criteria to be included in a forthcoming revision of the Waste Acceptance System Requirements Document (WASRD) that limits releases in terms of non-isotope-specific canister release dose-equivalent source terms. These criteria will be developed for the Department of Energy spent nuclear fuel (DSNF) standard canister, the Multicanister Overpack (MCO), the naval spent fuel canister, the High-Level Waste (HLW) canister, the plutonium can-in-canister, and the large Multipurpose Canister (MPC). The shippers of such canisters will be required to demonstrate that they meet these criteria before the canisters are accepted at the MGR. The Quality Assurance program is applicable to this calculation. The work reported in this document is part of the analysis of DSNF and is performed using procedure AP-3.124, Calculations. The work done for this analysis was evaluated according to procedure QAP-2-0, Control of Activities, which has been superseded by AP-2.21Q, Quality Determinations and Planning for Scientific, Engineering, and Regulatory Compliance Activities. This evaluation determined that such activities are subject to the requirements of DOE/RW/0333P, Quality Assurance Requirements and Description (DOE 2000). This work is also prepared in accordance with the development plan titled Design Basis Event Analyses on DOE SNF and Plutonium Can-In-Canister Waste Forms (CRWMS M&O 1999a) and Technical Work Plan For: Department of Energy Spent Nuclear Fuel Work Packages (CRWMS M&O 2000d). This calculation contains no electronic data applicable to any electronic data management system.

On the consistency of risk acceptance criteria with normative theories for decision-making

Energy Technology Data Exchange (ETDEWEB)

Abrahamsen, E.B. [University of Stavanger, 4036 Stavanger (Norway)], E-mail: eirik.abrahamsen@uis.no; Aven, T. [University of Stavanger, 4036 Stavanger (Norway)

2008-12-15

In evaluation of safety in projects it is common to use risk acceptance criteria to support decision-making. In this paper, we discuss to what extent the risk acceptance criteria is in accordance with the normative theoretical framework of the expected utility theory and the rank-dependent utility theory. We show that the use of risk acceptance criteria may violate the independence axiom of the expected utility theory and the comonotonic independence axiom of the rank-dependent utility theory. Hence the use of risk acceptance criteria is not in general consistent with these theories. The level of inconsistency is highest for the expected utility theory.

On the consistency of risk acceptance criteria with normative theories for decision-making

International Nuclear Information System (INIS)

Abrahamsen, E.B.; Aven, T.

2008-01-01

In evaluation of safety in projects it is common to use risk acceptance criteria to support decision-making. In this paper, we discuss to what extent the risk acceptance criteria is in accordance with the normative theoretical framework of the expected utility theory and the rank-dependent utility theory. We show that the use of risk acceptance criteria may violate the independence axiom of the expected utility theory and the comonotonic independence axiom of the rank-dependent utility theory. Hence the use of risk acceptance criteria is not in general consistent with these theories. The level of inconsistency is highest for the expected utility theory

Nevada test site defense waste acceptance criteria, certification, and transfer requirements

International Nuclear Information System (INIS)

1988-10-01

The Nevada Test Site (NTS) Defense Waste Acceptance Criteria, Certification and Transfer Requirements establishes procedures and criteria for safe transfer, disposal, and storage of defense transuranic, low-level, and mixed waste at the NTS. Included are an overview of the NTS defense waste management program; the NTS waste acceptance criteria for transuranic, low-level, and mixed wastes; waste certification requirements and guidance; application to submit waste; and requirements for waste transfer and receipt. 5 figs., 16 tabs

Measurement methodology for fulfilling of waste acceptance criteria for low and intermediate level radioactive waste in storages - 59016

International Nuclear Information System (INIS)

Sokcic-Kostic, M.; Langer, F.; Schultheis, R.

2012-01-01

Low and intermediate level radioactive waste must be sorted and treated before it can be sent to radioactive waste storage. The waste must fulfil an extensive amount of acceptance criteria (WAC) to guarantee a safe storage period. NUKEM Technologies has a broad experience with the building and management of radioactive waste treatment facilities and has developed methods and equipment to produce the waste packages and to gather all the required information. In this article we consider low and intermediate level radioactive waste excluding nuclear fuel material, even fresh fuel with low radiation. Only solid radioactive waste (RAW) will be considered. (Liquid RAW is usually processed and solidified before storage. Exception is the reprocessing of nuclear fuel.) Low and intermediate level radioactive waste has to be kept in storage facilities until isotopes are decayed sufficiently and the waste can be released. The storage has to fulfil certain conditions regarding the possible radiological impact and the possible chemical impact on the environment. With the inventory of nuclear waste characterised, the radiological impact can be estimated. RAW mainly originates from the operation of nuclear power plants. A small amount comes from reprocessing installations or from research entities. Chemical safety aspects are of qualitative nature, excluding substances in whole but not compared to limit values. Therefore they have minor influence on the storage conditions. Hereby corrosion and immobilisation of the waste play important roles. The storage concept assumes that the waste will be released if the radioactivity has decreased to an acceptable level. NUKEM Technologies has been specialised on collecting all data needed for the fulfilling of waste acceptance criteria (WAC). The classification as low or intermediate level waste is made on base of surface dose rate of the waste package as well as on the mass specific beta activity. Low level waste must not include isotopes

Criteria for accepting piping vibrations measured during FFTF plant startup

International Nuclear Information System (INIS)

Huang, S.N.

1981-03-01

Piping in the Fast Flux Test Facility is subjected to low-amplitude, high cycle vibration over the plant lifetime. Excitation sources include the mechanical vibration induced by main centrifugal pumps, auxiliary reciprocating pumps, EM pumps and possible flow oscillations. Vibration acceptance criteria must be established which will prevent excessive pipe and support fatigue damage when satified. This paper describes the preparation of such criteria against pipe failure used for acceptance testing of the Fast Flux Test Facility main heat transport piping

Hanford Site solid waste acceptance criteria

International Nuclear Information System (INIS)

Willis, N.P.; Triner, G.C.

1991-09-01

Westinghouse Hanford Company manages the Hanford Site solid waste treatment, storage, and disposal facilities for the US Department of Energy Field Office, Richland under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites, radioactive solid waste storage areas and hazardous waste treatment, storage, and/or disposal facilities. This manual defines the criteria that must be met by waste generators for solid waste to be accepted by Westinghouse Hanford Company for treatment, storage and/or disposal facilities. It is to be used by all waste generators preparing radioactive solid waste for storage or disposal at the Hanford Site facilities and for all Hanford Site generators of hazardous waste. This manual is also intended for use by Westinghouse Hanford Company solid waste technical staff involved with approval and acceptance of solid waste. The criteria in this manual represent a compilation of state and federal regulations; US Department of Energy orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to management of solid waste. Where appropriate, these requirements are included in the manual by reference. It is the intent of this manual to provide guidance to the waste generator in meeting the applicable requirements

Nevada Test Site Waste Acceptance Criteria (NTSWAC), Rev. 7-01

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2009-05-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NTSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex for disposal.

Nevada Test Site Waste Acceptance Criteria (NTSWAC), Rev. 7-01

International Nuclear Information System (INIS)

2009-01-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NTSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex for disposal.

WAC: A Point of Departure to Full Literacy.

Science.gov (United States)

Flanigan, Michael C.

The problem with various versions of Writing across the Curriculum (WAC) that have emerged since the turn of the century is that they are not self sustaining--they seemed unable to overcome the destructive forces of departmentalization and the entrenched attitudes in the university both toward writing and toward interdepartmental programs. If WAC…

Acceptance criteria for disposal of radioactive wastes in shallow ground and rock cavities

International Nuclear Information System (INIS)

1985-01-01

This document provides an overview of basic information related to waste acceptance criteria for disposal in shallow ground and rock cavity repositories, consisting of a discussion of acceptable waste types. The last item includes identification of those waste characteristics which may influence the performance of the disposal system and as such are areas of consideration for criteria development. The material is presented in a manner similar to a safety assessment. Waste acceptance criteria aimed at limiting the radiation exposure to acceptable levels are presented for each pathway. Radioactive wastes considered here are low-level radioactive wastes and intermediate-level radioactive wastes from nuclear fuel cycle operations and applications of radionuclides in research, medicine and industry

Implementation of Writing across the Curriculum (WAC) Learning Approaches in Social Work and Sociology Gerontology Courses

Science.gov (United States)

Kolb, Patricia

2013-01-01

This article describes the goals and methods of the international Writing Across the Curriculum (WAC) movement in higher education, and WAC-enriched learning approaches that the author used in teaching a social work gerontology practice course and a sociological theories of aging course. The author's in-class, low-stakes, nongraded writing…

Acceptability criteria for final underground disposal of radioactive waste

International Nuclear Information System (INIS)

Sousselier, Y.

1984-01-01

Specialists now generally agree that the underground disposal of suitably immobilized radioactive waste offers a means of attaining the basic objective of ensuring the immediate and long-term protection of man and the environment throughout the requisite period of time and in all foreseeable circumstances. Criteria of a more general as well as a more specific nature are practical means through which this basic protection objective can be reached. These criteria, which need not necessarily be quantified, enable the authorities to gauge the acceptability of a given project and provide those responsible for waste management with a basis for making decisions. In short, these principles constitute the framework of a suitably safety-oriented waste management policy. The more general criteria correspond to the protection objectives established by the national authorities on the basis of principles and recommendations formulated by international organizations, in particular the ICRP and the IAEA. They apply to any underground disposal system considered as a whole. The more specific criteria provide a means of evaluating the degree to which the various components of the disposal system meet the general criteria. They must also take account of the interaction between these components. As the ultimate aim is the overall safety of the disposal system, individual components can be adjusted to compensate for the performance of others with respect to the criteria. This is the approach adopted by the international bodies and national authorities in developing acceptability criteria for the final underground radioactive disposal systems to be used during the operational and post-operational phases respectively. The main criteria are reviewed and an attempt is made to assess the importance of the specific criteria according to the different types of disposal systems. (author)

Development on inelastic analysis acceptance criteria for radioactive material transportation packages

International Nuclear Information System (INIS)

Ammerman, D.J.; Ludwigsen, J.S.

1995-01-01

The response of radioactive material transportation packages to mechanical accident loadings can be more accurately characterized by non-linear dynamic analysis than by the ''Equivalent dynamic'' static elastic analysis typically used in the design of these packages. This more accurate characterization of the response can lead to improved package safety and design efficiency. For non-linear dynamic analysis to become the preferred method of package design analysis, an acceptance criterion must be established that achieves an equivalent level of safety as the currently used criterion defined in NRC Regulatory Guide 7.6 (NRC 1978). Sandia National Laboratories has been conducting a study of possible acceptance criteria to meet this requirement. In this paper non-linear dynamic analysis acceptance criteria based on stress, strain, and strain-energy-density will be discussed. An example package design will be compared for each of the design criteria, including the approach of NRC Regulatory Guide 7.6

A Method to Improve the Software Acceptance Criteria for Nuclear Power Plants

International Nuclear Information System (INIS)

Suh, Yong Suk; Park, Heui Youn; Son, Ki Sung; Lee, Ki Hyun; Kim, Hyeon Soo

2005-01-01

The license is a mandatory process required by a governmental authority and the certification is a voluntary process administrated by a professional community. A software certification is a result of an assessment that the certified software conforms to required criteria or standards. The certification is used as a committed promise to produce a high quality software, so software acquirers are requiring it from their suppliers. For example, US DoD (Department of Defense) requires an achievement of CMMI-SW (Capability Maturity Model Integration-Software) certification for participating in a major military software project. It is commonly said that the purpose of achieving a certification is to improve the product quality. In the nuclear area, a software certification has been rarely concerned with or required for the software used in a safety function of NPPs (Nuclear Power Plants). The safety critical software for NPPs is accepted by the nuclear regulators when the following three criteria are met: acceptable plans should be prepared to control the software development activities, the plans should be followed in an acceptable software life cycle, and the process should produce acceptable design outputs. The acceptance criteria are so abstractive that the nuclear regulators may assess the software development plans, activities, outputs based on their subjective engineering judgments. This is inevitable because a software has invisible or intangible characteristics. It is hard to assess the totality of a software prior to running it. These have caused the judgments to be biased. The regulators may want some objectiveness in assessing how much capability for software development the supplier possesses. In that case, the software certification can assist them for such an assessment. This paper proposes a method to improve the software acceptance criteria by applying the software certification to the criteria. This will assist the regulators to assess the supplier

On the use of risk acceptance criteria in the offshore oil and gas industry

International Nuclear Information System (INIS)

Aven, Terje; Vinnem, Jan Erik

2005-01-01

Risk acceptance criteria, as upper limits of acceptable risks, have been used for offshore activities on the Norwegian Continental Shelf for more than 20 years. The common thinking has been that risk analyses and assessments cannot be conducted in a meaningful way without the use of such criteria. The ALARP principle also applies, but the risk acceptance criteria have played a more active role in the assessment processes than seen for example in the UK. Recently there has, however, been a discussion about the suitability of risk acceptance criteria to assess and control risks. The purpose of this paper is to contribute to this discussion by presenting and discussing a risk analysis regime that is not based on the use of risk acceptance criteria at all. We believe that we can do better if cost-effectiveness (in a wide sense) is the ruling thinking rather than adoption of pre-defined risk acceptance limits. This means a closer resemblance with the ALARP principle as adopted in the UK and other countries, but is not a direct application of this practice. Also the building blocks of the common way of applying the ALARP principle are reviewed. The Norwegian offshore oil and gas industry is the starting point, but the discussion is to large extent general

MCO combustible gas management leak test acceptance criteria; TOPICAL

International Nuclear Information System (INIS)

SHERRELL, D.L.

1999-01-01

Existing leak test acceptance criteria for mechanically sealed and weld sealed multi-canister overpacks (MCO) were evaluated to ensure that MCOs can be handled and stored in stagnant air without compromising the Spent Nuclear Fuel Project's overall strategy to prevent accumulation of combustible gas mixtures within MCO's or within their surroundings. The document concludes that the integrated leak test acceptance criteria for mechanically sealed and weld sealed MCOs (1 x 10(sup -5) std cc/sec and 1 x 10(sup -7) std cc/sec, respectively) are adequate to meet all current and foreseeable needs of the project, including capability to demonstrate compliance with the NFPA 60 Paragraph 3-3 requirement to maintain hydrogen concentrations[within the air atmosphere CSB tubes] t or below 1 vol% (i.e., at or below 25% of the LFL)

Nilai Kalor Bakar Limbah Padat (HuWAC Sebagai Bahan Bakar Alternatif dalam Produksi Batu Bata

Directory of Open Access Journals (Sweden)

Soeparjono Soeparjono

2009-02-01

Full Text Available Menipisnya persediaan minyak bumi dan sulitnya mendapatkan kayu bakar dengan harga murah sebagai bahan bakar untuk kalangan industri kecil produksi batu bata, diperlukan adanya pemikiran mencari bahan bakar alternatif dan murah. Penelitian ini bertujuan mengetahui nilai kalor bakar limbah HuWAC sebagai bahan bakar alternatif untuk produksi batu merah. Sasarannya limbah HuWAC pabrik monosodium glutamat AJINOMOTO Mojokerto dengan sampel acak yang dikeringkan panas matahari. Penelitian menggunakan pendekatan kuantitatif rancangan deskriptif. Unsur-unsur yang terbakar dalam sampel dilakukan koreksi. Pengambilan data dilakukan secara langsung dengan alat Kalorimeter. Hasil penelitian menunjukkan bahwa nilai kalor bakar yang dihitung dengan formula Dulong, LVH = 2614 kcal/kg dan HHV = 2745 kcal/kg, sedangkan dari alat Kalorimeter Hgr = 2728 kcal/kg. Hal ini menunjukkan bahwa HuWAC dapat digunakan sebagai bahan bakar alternatif di kalangan industri kecil produksi batu bata.

Review of issues relevant to acceptable risk criteria for nuclear waste management

International Nuclear Information System (INIS)

Cohen, J.J.

1978-01-01

Development of acceptable risk criteria for nuclear waste management requires the translation of publicly determined goals and objectives into definitive issues which, in turn, require resolution. Since these issues are largely of a subjective nature, they cannot be resolved by technological methods. Development of acceptable risk criteria might best be accomplished by application of a systematic methodology for the optimal implementation of subjective values. Multi-attribute decision analysis is well suited for this purpose

WAC Bennett Dam - the characterization of a crest sinkhole

Energy Technology Data Exchange (ETDEWEB)

Stewart, R.A.; Gaffran, P.C. [British Columbia Hydro, Burnaby, BC (Canada); Watts, B.D. [Klohn-Crippen Consultants Ltd., Richmond, BC (Canada); Sobkowicz, J.C. [Thurber Engineering Ltd., Vancouver, BC (Canada); Kupper, A.G. [AGRA Earth and Environmental, Edmonton, AB (Canada)

1998-11-01

In June, 1996, a small hole was discovered in the asphaltic concrete road on the crest of the 183 m high WAC Bennett Dam on the Peace River in northeastern British Columbia. Examination of the hole resulted in a sinkhole on the dam crest. The sinkhole was 2.5 m in diameter and 7 m deep. Speculation was that the cavity was likely associated in some way with a buried survey benchmark tube. An investigation was immediately planned and executed to characterize the sinkhole, to determine the extent of damage and the safety status of this very large dam. British Columbia`s Dam Safety Regulator made the decision to lower the reservoir level. During the reservoir drawdown, various surface geophysical techniques were used to investigate the condition of the dam beyond the sinkholes. Intrusive investigations of the sinkhole were also planned. This involved trial drilling and downhole geophysical surveys in intact portions of the core at locations far from the sinkhole. The objectives and criteria developed for the investigation program are summarized. Scope of key activities at the sinkhole and important lessons learned during the investigation are also described. 9 refs., 15 figs.

Waste-acceptance criteria and risk-based thinking for radioactive-waste classification

International Nuclear Information System (INIS)

Lowenthal, M.D.

1998-01-01

The US system of radioactive-waste classification and its development provide a reference point for the discussion of risk-based thinking in waste classification. The official US system is described and waste-acceptance criteria for disposal sites are introduced because they constitute a form of de facto waste classification. Risk-based classification is explored and it is found that a truly risk-based system is context-dependent: risk depends not only on the waste-management activity but, for some activities such as disposal, it depends on the specific physical context. Some of the elements of the official US system incorporate risk-based thinking, but like many proposed alternative schemes, the physical context of disposal is ignored. The waste-acceptance criteria for disposal sites do account for this context dependence and could be used as a risk-based classification scheme for disposal. While different classes would be necessary for different management activities, the waste-acceptance criteria would obviate the need for the current system and could better match wastes to disposal environments saving money or improving safety or both

Why risk acceptance criteria need to be defined by the authorities and not the industry?

International Nuclear Information System (INIS)

Abrahamsen, Eirik Bjorheim; Aven, Terje

2012-01-01

In various industries it is common to use risk acceptance criteria to support decision-making. The criteria are seen as absolute in the sense that measures need to be implemented if the criteria are not met. In Norway the petroleum regulations state that the operator has a duty to formulate risk acceptance criteria relating to major accidents and to the environment. This practice is in line with the internal control principle, which states that the operator has the full responsibility for identifying the hazards and seeing that they are controlled. In this paper we discuss the rationale for this practice. The expected utility theory, which is the backbone for all economic thinking, is used as a basis for the discussion. We show that if risk acceptance criteria are to be introduced as a risk management tool, they should be formulated by the authorities, as is the common scheme seen in many countries and industries, for example in the UK. Risk acceptance criteria formulated by the industry would not in general serve the interest of the society as a whole.

78 FR 65007 - Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3

Science.gov (United States)

2013-10-30

... NUCLEAR REGULATORY COMMISSION [Docket No. 052-00026; NRC-2008-0252] Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3 AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria completion...

78 FR 53483 - Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3

Science.gov (United States)

2013-08-29

... NUCLEAR REGULATORY COMMISSION [Docket No. 052-00025; NRC-2008-0252] Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 3 AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria (ITAAC) completion...

78 FR 53484 - Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 4

Science.gov (United States)

2013-08-29

... NUCLEAR REGULATORY COMMISSION [Docket No. 052-00026; NRC-2008-0252] Inspections, Tests, Analyses, and Acceptance Criteria; Vogtle Electric Generating Plant, Unit 4 AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria (ITAAC) completion...

78 FR 38411 - Vogtle Electric Generating Plant, Unit 4; Inspections, Tests, Analyses, and Acceptance Criteria

Science.gov (United States)

2013-06-26

... Plant, Unit 4; Inspections, Tests, Analyses, and Acceptance Criteria AGENCY: Nuclear Regulatory Commission. ACTION: Determination of inspections, tests, analyses, and acceptance criteria completion. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) staff has determined that the inspections, tests...

Synthetic seismic acceleration time-histories and their acceptance criteria

International Nuclear Information System (INIS)

Xu Hong

1996-01-01

In seismic dynamic response analysis of structures and equipment, time-history analysis is now widely used. The 3-D seismic acceleration time-histories or 3-D seismic displacement time-histories are required in the 3-D seismic dynamic response analysis as the seismic excitation input data. Because of the lack of actual acceleration time-histories for the field where the structures or equipment are installed, the general practice is to use the synthetic seismic acceleration time-histories, which are derived from the design seismic response spectra of the field, as the seismic excitation input data. However, from one specified design response spectrum indefinite solutions of acceleration time-histories can be derived depending on the values of the input parameters. Not all the derived synthetic time-histories can be used as seismic excitation input data. Only those which meet the acceptance criteria can be used. The factors (input parameters), which will affect the time-history solution from a specified seismic response spectrum, and the acceptance criteria are discussed

Establishing seismic design criteria to achieve an acceptable seismic margin

International Nuclear Information System (INIS)

Kennedy, R.P.

1997-01-01

In order to develop a risk based seismic design criteria the following four issues must be addressed: (1) What target annual probability of seismic induced unacceptable performance is acceptable? (2). What minimum seismic margin is acceptable? (3) Given the decisions made under Issues 1 and 2, at what annual frequency of exceedance should the Safe Shutdown Earthquake ground motion be defined? (4) What seismic design criteria should be established to reasonably achieve the seismic margin defined under Issue 2? The first issue is purely a policy decision and is not addressed in this paper. Each of the other three issues are addressed. Issues 2 and 3 are integrally tied together so that a very large number of possible combinations of responses to these two issues can be used to achieve the target goal defined under Issue 1. Section 2 lays out a combined approach to these two issues and presents three potentially attractive combined resolutions of these two issues which reasonably achieves the target goal. The remainder of the paper discusses an approach which can be used to develop seismic design criteria aimed at achieving the desired seismic margin defined in resolution of Issue 2. Suggestions for revising existing seismic design criteria to more consistently achieve the desired seismic margin are presented

HWVP compliance with the Hanford site solid waste acceptance criteria

International Nuclear Information System (INIS)

Bromm, R.; Ornelas, J.; Fundingsland, S.; Shah, K.

1993-01-01

In order to ensure that the Hanford Waste Vitrification Project (HWVP) will meet solid waste acceptance criteria, a review of the criteria was performed. The primary purpose of the study was to evaluate the modifications that will be required to bring the HWVP into compliance for secondary waste which will be generated during normal operations of the facility. To accomplish this objective, the current HWVP design was evaluated based on the criteria established. Once the non-compliance areas and potentially non-compliance areas were identified, alternative plant design modifications were proposed. This paper summarizes the results and recommendations of that study

Statistical Methods and Tools for Hanford Staged Feed Tank Sampling

Energy Technology Data Exchange (ETDEWEB)

Fountain, Matthew S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Brigantic, Robert T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Peterson, Reid A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2013-10-01

This report summarizes work conducted by Pacific Northwest National Laboratory to technically evaluate the current approach to staged feed sampling of high-level waste (HLW) sludge to meet waste acceptance criteria (WAC) for transfer from tank farms to the Hanford Waste Treatment and Immobilization Plant (WTP). The current sampling and analysis approach is detailed in the document titled Initial Data Quality Objectives for WTP Feed Acceptance Criteria, 24590-WTP-RPT-MGT-11-014, Revision 0 (Arakali et al. 2011). The goal of this current work is to evaluate and provide recommendations to support a defensible, technical and statistical basis for the staged feed sampling approach that meets WAC data quality objectives (DQOs).

Criteria for risk acceptance: a health physicist's view

International Nuclear Information System (INIS)

Hull, A. P.

1977-01-01

While energy need (or demand) and the risks of energy production and use may be objectively quantified, risk acceptance embodies a subjective element of preferences and values. Yet, as demonstrated by the nuclear controversy in the United States, public acceptance is essential to the beneficial uses of radiation. The statement of the objectives and purposes of the Health Physics Society and our application of it are proposed as offering useful criteria for risk acceptance. The principle of comparing risk with a number of those regularly accepted in everyday life is emphasized. On this basis, it is concluded that the expenditures to attain currently applicable or proposed 'as low as practicable' (or 'as low as readily achievable') levels for the nuclear fuel cycle are disproportionate to those addressed to other sources of general public exposure to radiation. They are also disproportionate compared to those addressed to a variety of public health risks. It is suggested that sensible priorities for radiation and public health protection might be achieved by the application of a de minimus negligible (but nonzero) level of probable risk. (Research supported by the U.S. Energy Research and Development Administration.)

Typical design/qualification acceptance criteria for newly installed pipelines and equipment components of VVER-type NPPs

International Nuclear Information System (INIS)

Masopust, R.

2003-01-01

This paper describes in general the typical design/qualification acceptance criteria and seismic acceptance criteria in particular that are applicable for important to safety newly installed pipelines and equipment components of VVER-type already existing NPPs, specifically during the design verification phase of this newly installed equipment. These criteria are currently used for VVER 440-213 and VVER 1000 NPPs in Czech Republic and in Slovakia. The similar criteria are also used in Hungary. (author)

A de novo 10p11.23-p12.1 deletion recapitulates the phenotype observed in WAC mutations and strengthens the role of WAC in intellectual disability and behavior disorders.

Science.gov (United States)

Abdelhedi, Fatma; El Khattabi, Laila; Essid, Nouha; Viot, Geraldine; Letessier, Dominique; Lebbar, Aziza; Dupont, Jean-Michel

2016-07-01

Chromosomal microarray analysis has become a powerful diagnostic tool in the investigation of patients with intellectual disability leading to the discovery of dosage sensitive genes implicated in the manifestation of various genomic disorders. Interstitial deletions of the short arm of chromosome 10 represent rare genetic abnormalities, especially those encompassing the chromosomal region 10p11-p12. To date, only 10 postnatal cases with microdeletion of this region have been described, and all patients shared a common phenotype, including intellectual disability, abnormal behavior, distinct dysmorphic features, visual impairment, and cardiac malformations. WAC was suggested to be the main candidate gene for intellectual disability associated with 10 p11-p12 deletion syndrome. Here, we describe a new case of de novo 10p11.23-p12.1 microdeletion in a patient with intellectual disability, abnormal behavior, and distinct dysmorphic features. Our observation allows us to redefine the smallest region of overlap among patients reported so far, with a size of 80 Kb and which contains only the WAC gene. These findings strengthen the hypothesis that haploinsufficency of WAC gene might be likely responsible for intellectual disability and behavior disorders. Our data also led us to propose a clinical pathway for patients with this recognizable genetic syndrome depending on the facial dysmorphisms. © 2016 Wiley Periodicals, Inc. © 2016 Wiley Periodicals, Inc.

A comparison and cross-reference of commercial low-level radioactive waste acceptance criteria

International Nuclear Information System (INIS)

Kerr, T.A.

1997-04-01

This document, prepared by the National Low-Level Waste Management Program at the Idaho National Engineering and Environmental Laboratory, is a comparison and cross-reference of commercial low-level radioactive waste acceptance criteria. Many of these are draft or preliminary criteria as well as implemented criteria at operating low-level radioactive waste management facilities. Waste acceptance criteria from the following entities are included: US Nuclear Regulatory Commission, South Carolina, Washington, Utah, Nevada, California, illinois, Texas, North Carolina, Nebraska, Pennsylvania, New York, and the Midwest Compact Region. Criteria in the matrix include the following: physical form, chemical form, liquid limits, void space in packages, concentration averaging, types of packaging, chelating agents, solidification media, stability requirements, sorptive media, gas, oil, biological waste, pyrophorics, source material, special nuclear material, package dimensions, incinerator ash, dewatered resin, transuranics, and mixed waste. Each criterion in the matrix is cross-referenced to its source document so that exact requirements can be determined

Systematic handling of requirements and conditions (in compliance with waste acceptance requirements for a radioactive waste disposal facility)

International Nuclear Information System (INIS)

Keyser, Peter; Helander, Anita

2012-01-01

environment; iv) Aiding decision making on the authorization / licensing of radioactive waste disposal; and v) Facilitating communication amongst stakeholders on issues relating to the disposal facility. How can we ensure and control compliance with WAC during Pre-disposal activities? The link between the safety cases of Pre-disposal activities and the Disposal facility is primarily the Waste Acceptance Criteria (WAC), defined as 'those requirements that are to be met by conditioned radioactive wastes, forming packages, to be accepted at an Interim Storage or a Disposal Facility'. It is advised that also WAC should be set up for each stage of the pre-disposal activities in the Waste Management Plan or Strategy. Waste characterization requirements are typically developed from disposal performance assessment in addition to waste acceptance criteria (WAC), process control and quality assurance requirements, transportation requirements, and worker safety requirements. A matrix showing where each WAC originates can greatly assist with understanding the philosophy behind the overall characterization program and put the elements into context. The complexity of waste categorization requires the need for systematic handling of requirements and conditions during pre-disposal activities. How can we ensure the fulfillment of WAC for a radioactive waste disposal facility? Requirements management, sometimes called configuration management, is an area that recently has received increasing attention in the project management context. There exist international guidelines on the use of configuration management within an organization and it is applicable to the support of products from concept to disposal. It first outlines the responsibilities and authorities before describing the configuration management process that includes configuration management planning, configuration identification, change control, configuration status accounting and configuration audit. The methodology develops a

Waste acceptance criteria study: Volume 2, Appendixes: Final report

International Nuclear Information System (INIS)

Johnson, E.R.; McLeod, N.B.; McBride, J.A.

1988-09-01

These appendices to the report on Waste Acceptance Criteria have been published as a separate volume for the convenience of the reader. They consist of the text of the 10CFR961 Contract for disposal of spent fuel, estimates of the cost (savings) to the DOE system of accepting different forms of spent fuel, estimates of costs of acceptance testing/inspection of spent fuel, illustrative specifications and procedures, and the resolution of comments received on a preliminary draft of the report. These estimates of costs contained herein preliminary and are intended only to demonstrate the trends in costs, the order of magnitude involved, and the methodology used to develop the costs. The illustrative specifications and procedures included herein have been developed for the purpose of providing a starting point for the development of a consensus on such matters between utilities and DOE

Acceptance criteria for the ITER divertor vertical target

International Nuclear Information System (INIS)

Fouquet, S.; Schlosser, J.; Merola, M.; Durocher, A.; Escourbiac, F.; Grosman, A.; Missirlian, M.; Portafaix, C.

2006-01-01

In the frame of the toroidal pump limiter fabrication for Tore Supra, CEA developed a large experience of infrared test for acceptance of high heat flux components armoured with carbon fibre composite flat tiles. The test is based on a thermal transient induced by an alternative hot/cold water flow in the heat sink structure. The tile surface temperature transients are compared with those of a reference element, the maximum difference for each tile leading to a value called ΔT ref m ax . This method is proposed for the commissioning of plasma facing components for the ITER divertor vertical target. This paper describes the determination of the best acceptance criteria for the 'monoblock' geometry of the carbon part. First, it has been shown that the location and the extension of the defects could reliably be determined by monitoring both top and lateral surfaces during the test. Second, it was possible to fix an acceptance method based on ΔT ref m ax . Samples with calibrated defects are now under fabrication to validate the results

Assessment of LANL asbestos waste management documentation

International Nuclear Information System (INIS)

Davis, K.D.; Hoevemeyer, S.S.; Stirrup, T.S.; Jennrich, E.A.; Lund, D.M.

1991-04-01

The intent of this effort is to evaluate the Los Alamos National Laboratory (LANL) Waste Acceptance Criteria (WAC) for asbestos to determine if it meets applicable DOE, EPA, and OSHA requirements. There are numerous regulations that provide specific guidelines on the management of asbestos waste. An annotated outline for a generic asbestos WAC was developed using the type of information specified by 5820.2A. The outline itself is included in Appendix A. The major elements that should be addressed by the WAC were determined to be as follows: Waste Forms; Waste Content/Concentration; Waste Packaging; and Waste Documentation/Certification

Procedures and acceptance criteria for PAS-1 cask inspections

International Nuclear Information System (INIS)

Mercado, J.E.

1998-01-01

The procedures and acceptance criteria that comprise this document were prepared to support a one-time test to certify two PAS-1 casks in accordance with US Department of Energy Certificate of Compliance US A/9184/B(U), which was issued in 1998. The specific inspections addressed in this document are the visual weld inspection and a dimensional inspection of the primary containment vessel

Hanford site transuranic waste certification plan

International Nuclear Information System (INIS)

GREAGER, T.M.

1999-01-01

As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of U.S. Department of Energy (DOE) Order 5820.2A, ''Radioactive Waste Management, and the Waste Acceptance Criteria for the Waste Isolation Pilot Plant' (DOE 1996d) (WIPP WAC). The WIPP WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WIPP WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their management of TRU waste and TRU waste shipments before transferring waste to WIPP. The Hanford Site must also ensure that its TRU waste destined for disposal at WIPP meets requirements for transport in the Transuranic Package Transporter41 (TRUPACT-11). The U.S. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-I1 requirements in the ''Safety Analysis Report for the TRUPACT-II Shipping Package'' (NRC 1997) (TRUPACT-I1 SARP)

21 CFR 212.70 - What controls and acceptance criteria must I have for my finished PET drug products?

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 4 2010-04-01 2010-04-01 false What controls and acceptance criteria must I have... POSITRON EMISSION TOMOGRAPHY DRUGS (Eff. 12-12-2011) Finished Drug Product Controls and Acceptance § 212.70 What controls and acceptance criteria must I have for my finished PET drug products? (a) Specifications...

Testing the validity and acceptability of the diagnostic criteria for Hoarding Disorder: a DSM-5 survey.

Science.gov (United States)

Mataix-Cols, D; Fernández de la Cruz, L; Nakao, T; Pertusa, A

2011-12-01

The DSM-5 Obsessive-Compulsive Spectrum Sub-Workgroup is recommending the creation of a new diagnostic category named Hoarding Disorder (HD). The validity and acceptability of the proposed diagnostic criteria have yet to be formally tested. Obsessive-compulsive disorder/hoarding experts and random members of the American Psychiatric Association (APA) were shown eight brief clinical vignettes (four cases meeting criteria for HD, three with hoarding behaviour secondary to other mental disorders, and one with subclinical hoarding behaviour) and asked to decide the most appropriate diagnosis in each case. Participants were also asked about the perceived acceptability of the criteria and whether they supported the inclusion of HD in the main manual. Altogether, 211 experts and 48 APA members completed the survey (30% and 10% response rates, respectively). The sensitivity and specificity of the HD diagnosis and the individual criteria were high (80-90%) across various types of professionals, irrespective of their experience with hoarding cases. About 90% of participants in both samples thought the criteria would be very/somewhat acceptable for professionals and sufferers. Most experts (70%) supported the inclusion of HD in the main manual, whereas only 50% of the APA members did. The proposed criteria for HD have high sensitivity and specificity. The criteria are also deemed acceptable for professionals and sufferers alike. Training of professionals and the development and validation of semi-structured diagnostic instruments should improve diagnostic accuracy even further. A field trial is now needed to confirm these encouraging findings with real patients in real clinical settings.

Strain-based plastic instability acceptance criteria for ferritic steel safety class 1 nuclear components under level D

International Nuclear Information System (INIS)

Kim, Ji Su; Lee, Han Sang; Kim, Yun Jae; Kim, Jong Sung; Kim, Jin Won

2015-01-01

This paper proposes strain-based acceptance criteria for assessing plastic instability of the safety class 1 nuclear components made of ferritic steel during level D service loads. The strain-based criteria were proposed with two approaches: (1) a section average approach and (2) a critical location approach. Both approaches were based on the damage initiation point corresponding to the maximum load-carrying capability point instead of the fracture point via tensile tests and finite element analysis (FEA) for the notched specimen under uni-axial tensile loading. The two proposed criteria were reviewed from the viewpoint of design practice and philosophy to select a more appropriate criterion. As a result of the review, it was found that the section average approach is more appropriate than the critical location approach from the viewpoint of design practice and philosophy. Finally, the criterion based on the section average approach was applied to a simplified reactor pressure vessel (RPV) outlet nozzle subject to SSE loads. The application shows that the strain-based acceptance criteria can consider cumulative damages caused by the sequential loads unlike the stress-based acceptance criteria and can reduce the over conservatism of the stress-based acceptance criteria, which often occurs for level D service loads.

Strain-based plastic instability acceptance criteria for ferritic steel safety class 1 nuclear components under level D

Energy Technology Data Exchange (ETDEWEB)

Kim, Ji Su; Lee, Han Sang; Kim, Yun Jae [Dept. of Mechanical Engineering, Korea University, Seoul (Korea, Republic of); Kim, Jong Sung [Dept. of Mechanical Engineering, Sunchon National University, Suncheon (Korea, Republic of); Kim, Jin Won [Dept. of Nuclear Engineering, Chosun University, Gwangju (Korea, Republic of)

2015-04-15

This paper proposes strain-based acceptance criteria for assessing plastic instability of the safety class 1 nuclear components made of ferritic steel during level D service loads. The strain-based criteria were proposed with two approaches: (1) a section average approach and (2) a critical location approach. Both approaches were based on the damage initiation point corresponding to the maximum load-carrying capability point instead of the fracture point via tensile tests and finite element analysis (FEA) for the notched specimen under uni-axial tensile loading. The two proposed criteria were reviewed from the viewpoint of design practice and philosophy to select a more appropriate criterion. As a result of the review, it was found that the section average approach is more appropriate than the critical location approach from the viewpoint of design practice and philosophy. Finally, the criterion based on the section average approach was applied to a simplified reactor pressure vessel (RPV) outlet nozzle subject to SSE loads. The application shows that the strain-based acceptance criteria can consider cumulative damages caused by the sequential loads unlike the stress-based acceptance criteria and can reduce the over conservatism of the stress-based acceptance criteria, which often occurs for level D service loads.

Multi-Canister Overpack (MCO) Combustible Gas Management Leak Test Acceptance Criteria (OCRWM)

International Nuclear Information System (INIS)

SHERRELL, D.L.

2000-01-01

The purpose of this document is to support the Spent Nuclear Fuel Project's combustible gas management strategy while avoiding the need to impose any requirements for oxygen free atmospheres within storage tubes that contain multi-canister overpacks (MCO). In order to avoid inerting requirements it is necessary to establish and confirm leak test acceptance criteria for mechanically sealed and weld sealed MCOs that are adequte to ensure that, in the unlikely event the leak test results for any MCO were to approach either of those criteria, it could still be handled and stored in stagnant air without compromising the SNF Project's overall strategy to prevent accumulation of combustible gas mixtures within MCOs or within their surroundings. To support that strategy, this document: (1) establishes combustible gas management functions and minimum functional requirements for the MCO's mechanical seals and closure weld(s); (2) establishes a maximum practical value for the minimum required initial MCO inert backfill gas pressure; and (3) based on items 1 and 2, establishes and confirms leak test acceptance criteria for the MCO's mechanical seal and final closure weld(s)

GABARAP activates ULK1 and traffics from the centrosome dependent on Golgi partners WAC and GOLGA2/GM130

OpenAIRE

Joachim, Justin; Tooze, Sharon A.

2016-01-01

ABSTRACT WAC and GOLGA2/GM130 are 2 Golgi proteins that affect autophagy; however, their mechanism of action was unknown. We have shown that WAC binding to GOLGA2 at the Golgi displaces GABARAP from GOLGA2 to allow the maintenance of a nonlipidated centrosomal GABARAP pool. Centrosomal GABARAP can traffic to autophagic structures during starvation. In addition GABARAP specifically promotes ULK1 activation and this is independent of GABARAP lipidation but likely requires a LIR-mediated GABARAP...

The use of acceptability criteria for radiological risk at AWE Aldermaston

International Nuclear Information System (INIS)

Thurston, B.B.; Tutt, K.J.; Zabierek, G.A.

1989-01-01

The limit-line approach to setting acceptable risk criteria for nuclear power plants is in general use in the United Kingdom. The Atomic Weapons Establishment (AWE) is a Ministry of Defence Establishment which contains a number of nuclear material processing facilities. Limit-line risk criteria have been used for some years to provide a framework within which identified hazards may be judged in a systematic manner, rather than on an ad hoc basis. This paper describes how this is applied to both new facilities and to changes made to existing ones including decommissioning. (author)

Acceptance criteria for deposition of low-level and intermediate-level radiation levels radioactive wastes

International Nuclear Information System (INIS)

2002-09-01

This norm establishes the criteria for acceptance low and intermediate radiation level for safe deposition in repositories, for assuring the protection of workers, population and environment against the hazardous effects of the ionizing radiations. The criteria of this norm applies to the low and intermediate radiation levels

Technical Basis For Radiological Acceptance Criteria For Uranium At The Y-12 National Security Complex

Energy Technology Data Exchange (ETDEWEB)

Veinot, K. G.

2009-07-22

The purpose of this report is to establish radiological acceptance criteria for uranium. Other factors for acceptance not considered include criticality safety concerns, contaminants to the process stream, and impacts to the Safety Basis for the affected facilities. Three types of criteria were developed in this report. They include limits on external penetrating and non-penetrating radiation and on the internal hazard associated with inhalation of the material. These criteria are intended to alleviate the need for any special controls beyond what are normally utilized for worker protection from uranium hazards. Any proposed exceptions would require case-by-case evaluations to determine cost impacts and feasibility. Since Y-12 has set rigorous ALARA goals for worker doses, the external limits are based on assumptions of work time involved in the movement of accepted material plus the desire that external doses normally received are not exceeded, and set so that no special personnel monitoring would be required. Internal hazard controls were established so that dose contributions from non-uranium nuclides would not exceed 10% of that expected from the uranium component. This was performed using a Hazard Index (HI) previously established for work in areas contaminated with non-uranium nuclides. The radiological acceptance criteria for uranium are summarized in Table 1. Note that these limits are based on the assumption that radioactive daughter products have reached equilibrium.

Managing Hanford Site solid waste through strict acceptance criteria

International Nuclear Information System (INIS)

Jasen, W.G.; Pierce, R.D.; Willis, N.P.

1993-02-01

Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA) and the Resource Conservation and Recovery Act of 1976 (RCRA) have led to the definition of a group of wastes called radioactive mixed wastes (RMW). As a result of the radioactive and hazardous properties of these wastes, strict management programs have been implemented for the management of these wastes. Solid waste management is accomplished through a systems performance approach to waste management that used best-demonstrated available technology (BDAT) and best management practices. The solid waste program at the Hanford Site strives to integrate all aspects of management relative to the treatment, storage and disposal (TSD) of solid waste. Often there are many competing and important needs. It is a difficult task to balance these needs in a manner that is both equitable and productive. Management science is used to help the process of making decisions. Tools used to support the decision making process include five-year planning, cost estimating, resource allocation, performance assessment, waste volume forecasts, input/output models, and waste acceptance criteria. The purpose of this document is to describe how one of these tools, waste acceptance criteria, has helped the Hanford Site manage solid wastes

Qualitative acceptance criteria for radioactive wastes to be disposed of in deep geological formations

International Nuclear Information System (INIS)

1990-05-01

The present Safety Guide has to be seen as a companion document to the IAEA Safety Series No. 99. It is concerned with the waste form which is an important component of the overall disposal system. Because of the broad range of waste types and conditioned forms and variations in the sites, designs and constructional approaches being considered for deep geological repositories, this report necessarily approaches the waste acceptance criteria in a general way, recognizing that the assignment of quantitative limits to these criteria has to be the responsibility of national authorities. The main objective of this Safety Guide is to set out qualitative waste acceptance criteria as a basis for specifying quantitative limits for the waste forms and packages which are intended to be disposed of in deep geological repositories. It should serve as guidance for assigning such parameter values which would fully comply with the safety assessment and performance of a waste disposal system as a whole. This document is intended to serve both national authorities and regulatory bodies involved in the development of deep underground disposal systems. The qualitative waste acceptance criteria dealt with in the present Safety Guide are primarily concerned with the disposal of high level, intermediate level and long-lived alpha bearing wastes in deep geological repositories. Although some criteria are also applicable in other waste disposal concepts, it has to be borne in mind that the set of criteria presented here shall ensure the isolation capability of a waste disposal system for periods of time much longer than for other waste streams with shorter lifetimes. 51 refs, 1 tab

GABARAP activates ULK1 and traffics from the centrosome dependent on Golgi partners WAC and GOLGA2/GM130.

Science.gov (United States)

Joachim, Justin; Tooze, Sharon A

2016-05-03

WAC and GOLGA2/GM130 are 2 Golgi proteins that affect autophagy; however, their mechanism of action was unknown. We have shown that WAC binding to GOLGA2 at the Golgi displaces GABARAP from GOLGA2 to allow the maintenance of a nonlipidated centrosomal GABARAP pool. Centrosomal GABARAP can traffic to autophagic structures during starvation. In addition GABARAP specifically promotes ULK1 activation and this is independent of GABARAP lipidation but likely requires a LIR-mediated GABARAP-ULK1 interaction.

Design loads, loading combinations and structural acceptance criteria for BWR containments in the United States

International Nuclear Information System (INIS)

Edwards, N.W.

1979-01-01

The definition of loads, loading combinations, and structural acceptance criteria used for the design and evaluation of BWR containments in the Unites States has become much more comprehensive over the past decade. The Mark I pressure suppression containment vessels were designed for a static design pressure, a design temperature, dead load and static equivalent earthquake. The current Mark III containments are being designed to accommodate many more loads such as safety relief valve discharge loads, and suppression pool hydrodynamic loadings associated with the steam condensation phenomena as well as pressure and temperature transients for a range of pipe break sizes. Consistent with the more comprehensive definition of loads and loading combinations, the ASME Code presently establishes structural acceptance criteria with different margins of safety by the definition of Service Level Assignments A, B, C and D. Acting in a responsible manner, United States utilities are currently evaluating and modifying existing containment vessels to account for the more detailed load definition and structural acceptance criteria. (orig.)

Criteria required for an acceptable point-of-care test for UTI detection: Obtaining consensus using the Delphi technique.

Science.gov (United States)

Weir, Nichola-Jane M; Pattison, Sally H; Kearney, Paddy; Stafford, Bob; Gormley, Gerard J; Crockard, Martin A; Gilpin, Deirdre F; Tunney, Michael M; Hughes, Carmel M

2018-01-01

Urinary Tract Infections (UTIs) are common bacterial infections, second only to respiratory tract infections and particularly prevalent within primary care. Conventional detection of UTIs is culture, however, return of results can take between 24 and 72 hours. The introduction of a point of care (POC) test would allow for more timely identification of UTIs, facilitating improved, targeted treatment. This study aimed to obtain consensus on the criteria required for a POC UTI test, to meet patient need within primary care. Criteria for consideration were compiled by the research team. These criteria were validated through a two-round Delphi process, utilising an expert panel of healthcare professionals from across Europe and United States of America. Using web-based questionnaires, panellists recorded their level of agreement with each criterion based on a 5-point Likert Scale, with space for comments. Using median response, interquartile range and comments provided, criteria were accepted/rejected/revised depending on pre-agreed cut-off scores. The first round questionnaire presented thirty-three criteria to the panel, of which 22 were accepted. Consensus was not achieved for the remaining 11 criteria. Following response review, one criterion was removed, while after revision, the remaining 10 criteria entered the second round. Of these, four were subsequently accepted, resulting in 26 criteria considered appropriate for a POC test to detect urinary infections. This study generated an approved set of criteria for a POC test to detect urinary infections. Criteria acceptance and comments provided by the healthcare professionals also supports the development of a multiplex point of care UTI test.

Characteristics of radioactive waste forms conditioned for storage and disposal: Guidance for the development of waste acceptance criteria

International Nuclear Information System (INIS)

1983-04-01

This report attempts to review the characteristics of the individual components of the waste package, i.e. the waste form and the container, in order to formulate, where appropriate, quidelines for the development of practical waste acceptance criteria. Primarily the criteria for disposal are considered, but if more stringent criteria are expected to be necessary for storage or transportation prior to the disposal, these will be discussed. The report will also suggest test areas which will aid the development of the final waste acceptance criteria

Characterization Results for the January 2017 H-Tank Farm 2H Evaporator Overhead Sample

Energy Technology Data Exchange (ETDEWEB)

Truong, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nicholson, J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-04-11

This report contains the radioanalytical results of the 2H evaporator overhead sample received at SRNL on January 19, 2017. Specifically, concentrations of ¹³⁷Cs, ⁹⁰Sr, and ¹²⁹I are reported and compared to the corresponding Waste Acceptance Criteria (WAC) limits of the Effluent Treatment Project (ETP) Waste Water Collection Tank (WWCT) (rev. 6). All of the radionuclide concentrations in the sample were found to be in compliance with the ETP WAC limits.

Summary of research and development activities in support of waste acceptance criteria for WIPP

International Nuclear Information System (INIS)

Hunter, T.O.

1979-11-01

The development of waste acceptance criteria for the Waste Isolation Pilot Plant (WIPP) is summarized. Specifications for acceptable waste forms are included. Nine program areas are discussed. They are: TRU characterization, HLW interactions, thermal/structural interactions, nuclide migration, permeability, brine migration, borehole plugging, operation/design support, and instrumentation development. Recommendations are included

Sample acceptance time criteria, electronic issue and alloimmunisation in thalassaemia.

Science.gov (United States)

Trompeter, S; Baxter, L; McBrearty, M; Zatkya, E; Porter, J

2015-12-01

To determine the safety of a 1-week acceptance criteria of sample receipt in laboratory to transfusion commencement in transfusion dependent thalassaemia with respect to alloimmunisation. To determine the safety of electronic issue of blood components in such a setting. Retrospective audit of alloimmunisation (1999-2012) and blood exposure in registered thalassaemia patients at a central London thalassaemia centre where the acceptance criteria for the group and save sample from arrival in the laboratory to the time of issue of blood for transfusion for someone who has been transfused in the last 28 days was 1 week, and there was electronic issue protocol for patients who have always had a negative antibody screen (other than temporary positivity in pregnant women receiving prophylactic anti-D or anti Le-a, Anti Le-b and Anti P1 that are no longer detectable). There were 133 patients with thalassemia variants regularly attending UCLH for review. A total of 105 patients had transfusion dependent thalassaemia (TDT) (7 E-beta thalassaemia, 98 beta thalassaemia major). Ten of the 84 patients who received their transfusions at UCLH were alloimmunised. Seven of them had been alloimmunised prior to arrival at UCLH. Only two patients developed antibodies at UCLH during this period. The prevalence of alloantibody formation of 2% in UCLH transfused patients, with presumptive incidence of 0.01 alloantibodies per 100 units or 0·001 immunisations per person per year compares favourably with other reported series and suggests that 1 week interval with appropriate electronic issue is acceptable practice. © 2015 British Blood Transfusion Society.

Definition of acceptance criteria for the ITER divertor plasma-facing components through systematic experimental analysis

International Nuclear Information System (INIS)

Escourbiac, F; Richou, M; Guigon, R; Durocher, A; Schlosser, J; Grosman, A; Constans, S; Merola, M; Riccardi, B

2009-01-01

Experience has shown that a critical part of the high-heat flux (HHF) plasma-facing component (PFC) is the armour to heat sink bond. An experimental study was performed in order to define acceptance criteria with regards to thermal hydraulics and fatigue performance of the International Thermonuclear Experimental Reactor (ITER) divertor PFCs. This study, which includes the manufacturing of samples with calibrated artificial defects relevant to the divertor design, is reported in this paper. In particular, it was concluded that defects detectable with non-destructive examination (NDE) techniques appeared to be acceptable during HHF experiments relevant to heat fluxes expected in the ITER divertor. On the basis of these results, a set of acceptance criteria was proposed and applied to the European vertical target medium-size qualification prototype: 98% of the inspected carbon fibre composite (CFC) monoblocks and 100% of tungsten (W) monoblock and flat tiles elements (i.e. 80% of the full units) were declared acceptable.

Definition of acceptance criteria for the ITER divertor plasma-facing components through systematic experimental analysis

Science.gov (United States)

Escourbiac, F.; Richou, M.; Guigon, R.; Constans, S.; Durocher, A.; Merola, M.; Schlosser, J.; Riccardi, B.; Grosman, A.

2009-12-01

Experience has shown that a critical part of the high-heat flux (HHF) plasma-facing component (PFC) is the armour to heat sink bond. An experimental study was performed in order to define acceptance criteria with regards to thermal hydraulics and fatigue performance of the International Thermonuclear Experimental Reactor (ITER) divertor PFCs. This study, which includes the manufacturing of samples with calibrated artificial defects relevant to the divertor design, is reported in this paper. In particular, it was concluded that defects detectable with non-destructive examination (NDE) techniques appeared to be acceptable during HHF experiments relevant to heat fluxes expected in the ITER divertor. On the basis of these results, a set of acceptance criteria was proposed and applied to the European vertical target medium-size qualification prototype: 98% of the inspected carbon fibre composite (CFC) monoblocks and 100% of tungsten (W) monoblock and flat tiles elements (i.e. 80% of the full units) were declared acceptable.

Definition of acceptance criteria for the ITER divertor plasma-facing components through systematic experimental analysis

Energy Technology Data Exchange (ETDEWEB)

Escourbiac, F; Richou, M; Guigon, R; Durocher, A; Schlosser, J; Grosman, A [CEA/IRFM, F-13108, Saint-Paul-lez-Durance (France); Constans, S [AREVA-NP, Le Creusot (France); Merola, M [ITER Organization, Cadarache (France); Riccardi, B [Fusion For Energy, Barcelona (Spain)], E-mail: frederic.escourbiac@cea.fr

2009-12-15

Experience has shown that a critical part of the high-heat flux (HHF) plasma-facing component (PFC) is the armour to heat sink bond. An experimental study was performed in order to define acceptance criteria with regards to thermal hydraulics and fatigue performance of the International Thermonuclear Experimental Reactor (ITER) divertor PFCs. This study, which includes the manufacturing of samples with calibrated artificial defects relevant to the divertor design, is reported in this paper. In particular, it was concluded that defects detectable with non-destructive examination (NDE) techniques appeared to be acceptable during HHF experiments relevant to heat fluxes expected in the ITER divertor. On the basis of these results, a set of acceptance criteria was proposed and applied to the European vertical target medium-size qualification prototype: 98% of the inspected carbon fibre composite (CFC) monoblocks and 100% of tungsten (W) monoblock and flat tiles elements (i.e. 80% of the full units) were declared acceptable.

Criteria for accepting piping thermal expansion movements during FFTF plant startup

International Nuclear Information System (INIS)

Clark, G.L.; Anderson, M.J.

1981-03-01

A deflection measurement program was conducted as a final step in the design qualification of the Fast Flux Test Facility liquid sodium piping. Measurements were obtained from the ambient empty position, through the 400 0 F (204 0 C) sodium fill, to an 800 0 F (427 0 C) maximum iso-thermal test condition. The program was designed to confirm that the pipe responded as predicted under both deadweight and thermal expansion loads. This paper describes the design of the test programs; the criteria used to select appropriate measurement locations from the approximately 4000 supports used on this pipe; and the criteria used to accept test results

Development of Waste Acceptance Criteria at 221-U Building: Initial Flow and Transport Scoping Calculations

Energy Technology Data Exchange (ETDEWEB)

Freedman, Vicky L.; Zhang, Z. F.; Keller, Jason M.; Chen, Yousu

2007-05-30

This report documents numerical flow and transport simulations performed that establish initial waste acceptance criteria for the potential waste streams that may be safely sequestered in the 221-U Building and similar canyon structures. Specifically, simulations were executed to identify the maximum loading of contaminant mass (without respect to volume) that can be emplaced within the 221-U Building with no more than 1 pCi/m2 of contaminant migrating outside the structure within a 1,000 year time period. The initial scoping simulations were executed in one dimension to assess important processes, and then two dimensions to establish waste acceptance criteria. Two monolithic conditions were assessed: (1) a grouted canyon monolith; and (2) a canyon monolith filled with sand, both assuming no cracks or fissures were present to cause preferential transport. A three-staged approach was taken to account for different processes that may impact the amount of contaminant that can be safely sequestered in canyon structure. In the first stage, flow and transport simulations established waste acceptance criteria based on a linear (Kd) isotherm approach. In the second stage, impacts on thermal loading were examined and the differences in waste acceptance criteria quantified. In the third stage of modeling, precipitation/dissolution reactions were considered on the release and transport of the contaminants, and the subsequent impact on the maximum contaminant loading. The reactive transport modeling is considered a demonstration of the reactive transport capability, and shows the importance of its use for future performance predictions once site-specific data have been obtained.

Defining waste acceptance criteria for the Hanford Replacement Cross-Site Transfer System

International Nuclear Information System (INIS)

Hudson, J.D.

1996-04-01

This document provides a methodology for defining waste acceptance criteria for the Hanford Replacement Cross-Site Transfer System (RCSTS). This methodology includes characterization, transport analysis, and control. A framework is described for each of these functions. A tool was developed for performing the calculations associated with the transport analysis. This tool, a worksheet that is available in formats acceptable for a variety of PC spreadsheet programs, enables a comparison of the pressure required to transport a given slurry at a rate that particulate suspension is maintained to the pressure drop available from the RCSTS

Special Analysis: Updated Analysis of the Effect of Wood Products on Trench Disposal Limits at the E-Area Low-Level Waste Facility

International Nuclear Information System (INIS)

Cook, J.R.

2001-01-01

This Special Analysis (SA) develops revised radionuclide inventory limits for trench disposal of low-level radioactive waste in the presence of wood products in the E-Area Low-Level Waste Facility. These limits should be used to modify the Waste Acceptance Criteria (WAC) for trench disposal. Because the work on which this SA is based employed data from tests using 100 percent wood products, the 40 percent limitation on wood products for trench (i.e., slit or engineered trench) disposal is not needed in the modified WAC

Performance-based ECCS cladding acceptance criteria: A new simulation approach

International Nuclear Information System (INIS)

Zoino, A.; Alfonsi, A.; Rabiti, C.; Szilard, R.H.; Giannetti, F.; Caruso, G.

2017-01-01

Highlights: • A new methodology to demonstrate compliance with the new ECCS acceptance criteria is described. • A wide spectrum of fuel rod initial burnup states can be analysed in the design phase. • The coupled suite PHISICS/RELAP5-3D has been used in the analyses. • A demo simulation of the equilibrium cycle, load-following and a LOCA analysis has been performed. - Abstract: The U.S. Nuclear Regulatory Commission is currently proposing rulemaking to revise the Loss Of Coolant Accident (LOCA) and therefore the Emergency Core Cooling System (ECCS) acceptance criteria, to include the effects of higher burnup on cladding performance as well as to address other technical issues. As motivated by the new rule, the need to use advanced cladding designs may be a result. A loss of operational margin may result due to the more restrictive cladding embrittlement criteria. Initial and future compliance with the rule may significantly increase vendor workload and licensee cost, as a spectrum of fuel rod initial burnup states may need to be analyzed to demonstrate compliance. Consequently, there will be an increased focus on licensee decision making related to LOCA analysis to minimize cost and impact, and to manage margin. The study here presented has been part of a big project used to investigate technical issues and approaches for future industrial applications within the Risk-Informed Safety Margin Characterization (RISMC) Pathway. Specifically, the primary aim of this study is to lay out a roadmap to demonstrate the application of the new methodology. The present analysis shows a simplified version of the methodology of an industrial application on the Core Design and the Multi-Cycle Analysis.

Preparation of acceptance tests and criteria for the Test Blanket Systems to be operated in ITER

Energy Technology Data Exchange (ETDEWEB)

Laan, J.G. van der, E-mail: JaapG.vanderLaan@iter.org [ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Cuquel, B. [AIRBUS Defence and Space S.A.S., 13115 Saint Paul Lez Durance (France); Demange, D.; Ghidersa, B.-E. [Karlsruhe Institute of Technology, Karlsruhe (Germany); Giancarli, L.M.; Iseli, M.; Jourdan, T. [ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Nevière, J.-C. [Comex-Nucleaire, 13115 Saint Paul Lez Durance (France); Pascal, R.; Ring, W. [ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex (France)

2015-10-15

Highlights: • Initial guideline for acceptance testing and acceptance criteria for Test Blanket Systems in ITER. • These tests complement those required by the applicable codes and standards, and regulations. • Completion of TBS manufacture will be followed by Factory Acceptance Testing, prior to shipment. • Next steps are “Reception Inspection Tests”, and on-site pre-installation and components tests. • This guideline allows the detailing of the TBS specific test plans and their scheduling. - Abstract: This paper describes the main acceptance criteria and required acceptance tests for the components of the six Test Blanket Systems to be installed and operated in ITER. It summarizes the guide-line toward the establishment of detailed test plans for the TBS, starting from the end-product at the ITER Members factories, and to generally define the type of tests that have to be performed on the ITER site after shipment, and/or prior to the systems final commissioning phase.

Basic considerations for the preparation of performance testing materials as related to performance evaluation acceptance criteria

International Nuclear Information System (INIS)

McCurdy, D.E.; Morton, J.S.

2001-01-01

The preparation of performance testing (PT) materials for environmental and radiobioassay applications involves the use of natural matrix materials containing the analyte of interest, the addition (spiking) of the analyte to a desired matrix (followed by blending for certain matrices) or a combination of the two. The distribution of the sample analyte concentration in a batch of PT samples will reflect the degree of heterogeneity of the analyte in the PT material and/or the reproducibility of the sample preparation process. Commercial and government implemented radioanalytical performance evaluation programs have a variety of acceptable performance criteria. The performance criteria should take into consideration many parameters related to the preparation of the PT materials including the within and between sample analyte heterogeneity, the accuracy of the quantification of an analyte in the PT material and to what 'known' value will a laboratory's result be compared. How sample preparation parameters affect the successful participation in performance evaluation (PE) programs having an acceptance criteria established as a percent difference from a 'known' value or in PE programs using other acceptance criteria, such as the guidance provided in ANSI N42.22 and N13.30 is discussed. (author)

Acceptance criteria for determining armed response force size at nuclear power plants

International Nuclear Information System (INIS)

1983-02-01

This guidance document contains acceptance criteria to be used in the NRC license review process. It consists of a scored worksheet and guidelines for interpreting the worksheet score that can be used in determining the adequacy of the armed response force size at a nuclear power reactor facility

48 CFR 15.607 - Criteria for acceptance and negotiation of an unsolicited proposal.

Science.gov (United States)

2010-10-01

... and negotiation of an unsolicited proposal. 15.607 Section 15.607 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION CONTRACTING METHODS AND CONTRACT TYPES CONTRACTING BY NEGOTIATION Unsolicited Proposals 15.607 Criteria for acceptance and negotiation of an unsolicited proposal. (a) A...

Waste characterization for the F/H Effluent Treatment Facility in support of waste certification

International Nuclear Information System (INIS)

Brown, D.F.

1994-01-01

The Waste Acceptance Criteria (WAC) procedures define the rules concerning packages of solid Low Level Waste (LLW) that are sent to the E-area vaults (EAV). The WACs tabulate the quantities of 22 radionuclides that require manifesting in waste packages destined for each type of vault. These quantities are called the Package Administrative Criteria (PAC). If a waste package exceeds the PAC for any radionuclide in a given vault, then specific permission is needed to send to that vault. To avoid reporting insignificant quantities of the 22 listed radionuclides, the WAC defines the Minimum Reportable Quantity (MRQ) of each radionuclide as 1/1000th of the PAC. If a waste package contains less than the MRQ of a particular radionuclide, then the package's manifest will list that radionuclide as zero. At least one radionuclide has to be reported, even if all are below the MRQ. The WAC requires that the waste no be ''hazardous'' as defined by SCDHEC/EPA regulations and also lists several miscellaneous physical/chemical requirements for the packages. This report evaluates the solid wastes generated within the F/H Effluent Treatment Facility (ETF) for potential impacts on waste certification

Acceptance criteria for the low enriched uranium reform amendments

International Nuclear Information System (INIS)

Emeigh, C.W.; Gundersen, G.E.; Withee, C.J.

1984-05-01

Revisions have been made to the material control and accounting requirements for NRC licensees authorized to possess and use more than one effective kilogram of special nuclear material of low strategic significance to have material control and accounting systems able to (1) confirm the presence of special nuclear material, (2) resolve indications of missing material, and (3) aid in the investigation and recovery of missing material. This document presents criteria that can be used to aid in judging the acceptability of licensee plans that would be submitted to the NRC for implementing these capabilities. General performance objectives, system capabilities, and recordkeeping are addressed

The revision of RP 91 on criteria for acceptability of radiological (including radiotherapy) and nuclear medicine installations

International Nuclear Information System (INIS)

Faulkner, K.; Malone, J. F.; Christofides, S.; Lillicrap, S.; Horton, P.

2013-01-01

In 1997 the European Commission published Radiation Protection 91: 'Criteria for acceptability of radiological (including radiotherapy) and nuclear medicine installations'(1). This document specified the minimum criteria for acceptability. It has been used to this effect in legislation, codes of practice and by individual professionals. In a single document, it defined a level of performance at which remedial action was required. The document specified a series of parameters which characterised equipment performance and acceptable levels of performance. In its time it proved to be a useful document which was applied in member states to various degrees. Since the publication of Report 91 in 1997(1), a series of weaknesses emerged over time. Development of new radiological systems and technologies, as well as improvements in traditional technologies, has created circumstances where the acceptability criteria were in need of review. These weaknesses were recognised by the European Commission and a tender for its revision was issued. The criteria were developed by a team drawn from a broad range of backgrounds including hospitals, industry, government bodies, regulators and standardisation organisations. Representatives were mainly from Europe, but individuals from the American Association of Physicists in Medicine and International Atomic Energy Agency were included in the drafting process. This study describes the process employed in developing the revised document and the consultation process involved. One of the major difficulties the revision team encountered was related to an understanding of the actual meaning of the EC Directive(2). The view taken by the revision team was that Article 8, paragraph 3 places responsibilities on both the holders of radiological equipment and competent authorities. The acceptability criteria have been produced consistent with the European Commission's Medical Exposures Directive(2), which requires that patient exposures are

48 CFR 915.607 - Criteria for acceptance and negotiation of an unsolicited proposal.

Science.gov (United States)

2010-10-01

... and negotiation of an unsolicited proposal. 915.607 Section 915.607 Federal Acquisition Regulations System DEPARTMENT OF ENERGY CONTRACTING METHODS AND CONTRACT TYPES CONTRACTING BY NEGOTIATION Unsolicited Proposals 915.607 Criteria for acceptance and negotiation of an unsolicited proposal. (c) DOE's cost...

TRU [transuranic] waste certification compliance requirements for acceptance of newly generated contact-handled wastes to be shipped to the Waste Isolation Pilot Plant: Revision 2

International Nuclear Information System (INIS)

1989-01-01

Compliance requirements are presented for certifying that unclassified, newly generated (NG), contact-handled (CH) transuranic (TRU) solid wastes from defense programs meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). Where appropriate, transportation and interim storage requirements are incorporated; however, interim storage sites may have additional requirements consistent with these requirements. All applicable Department of Energy (DOE) orders must continue to be met. The compliance requirements for stored or buried waste are not addressed in this document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste. 10 refs., 1 fig

Development of performance assessment methodology for establishment of quantitative acceptance criteria of near-surface radioactive waste disposal

Energy Technology Data Exchange (ETDEWEB)

Kim, C. R.; Lee, E. Y.; Park, J. W.; Chang, G. M.; Park, H. Y.; Yeom, Y. S. [Korea Hydro and Nuclear Power Co., Ltd., Seoul (Korea, Republic of)

2002-03-15

The contents and the scope of this study are as follows : review of state-of-the-art on the establishment of waste acceptance criteria in foreign near-surface radioactive waste disposal facilities, investigation of radiological assessment methodologies and scenarios, investigation of existing models and computer codes used in performance/safety assessment, development of a performance assessment methodology(draft) to derive quantitatively radionuclide acceptance criteria of domestic near-surface disposal facility, preliminary performance/safety assessment in accordance with the developed methodology.

References for HNF-SD-WM-TRD-007, ''System specification for the double-shell tank system: HNF-PROs, CFRs, DOE Orders, WACs''

International Nuclear Information System (INIS)

Shaw, C.P.

1998-01-01

HNF-SD-WM-TRD-O07, System Specification for the Double-Shell Tank System, (hereafter referred to as DST Specification), defines the requirements of the double-shell tank system at the Hanford Site for Phase 1 privatization. Many of the sections in this document reference other documents for design guidance and requirements. Referenced documents include Project Hanford Management Contract (PHMC) procedures (HNF-PROS), Codes of Federal Regulation (CFRs), DOE Orders, and Washington Administrative Codes (WACs). This document provides rationale for the selection and inclusion of HNF-PROS, CFRs, DOE Orders and WACs

Safety analysis, risk assessment, and risk acceptance criteria

International Nuclear Information System (INIS)

Jamali, K.

1997-01-01

This paper discusses a number of topics that relate safety analysis as documented in the Department of Energy (DOE) safety analysis reports (SARs), probabilistic risk assessments (PRA) as characterized primarily in the context of the techniques that have assumed some level of formality in commercial nuclear power plant applications, and risk acceptance criteria as an outgrowth of PRA applications. DOE SARs of interest are those that are prepared for DOE facilities under DOE Order 5480.23 and the implementing guidance in DOE STD-3009-94. It must be noted that the primary area of application for DOE STD-3009 is existing DOE facilities and that certain modifications of the STD-3009 approach are necessary in SARs for new facilities. Moreover, it is the hazard analysis (HA) and accident analysis (AA) portions of these SARs that are relevant to the present discussions. Although PRAs can be qualitative in nature, PRA as used in this paper refers more generally to all quantitative risk assessments and their underlying methods. HA as used in this paper refers more generally to all qualitative risk assessments and their underlying methods that have been in use in hazardous facilities other than nuclear power plants. This discussion includes both quantitative and qualitative risk assessment methods. PRA has been used, improved, developed, and refined since the Reactor Safety Study (WASH-1400) was published in 1975 by the Nuclear Regulatory Commission (NRC). Much debate has ensued since WASH-1400 on exactly what the role of PRA should be in plant design, reactor licensing, 'ensuring' plant and process safety, and a large number of other decisions that must be made for potentially hazardous activities. Of particular interest in this area is whether the risks quantified using PRA should be compared with numerical risk acceptance criteria (RACs) to determine whether a facility is 'safe.' Use of RACs requires quantitative estimates of consequence frequency and magnitude

Final report on a study of coherence in acceptability criteria for the technical aspects of risks associated with potentially hazardous installations

International Nuclear Information System (INIS)

Chicken, J.C.

1988-01-01

This report describes the results of the study that was made, under Contract No ECI-1390-B7221-85D, for the European Atomic Energy Community. The aim of the study was to examine and assess the feasibility of developing coherent and uniform criteria for judging the acceptability of the technical aspects of the risks associated with potentially hazardous installations. The report is arranged in five main parts. First the nature of hazardous installations is considered and this provides the basis for examination of the currently-used technical risk acceptability criteria. Next, the possible forms of criteria are explored and then universally consistent partial and overall technical risk acceptability criteria are proposed. Following this the implications of using the criteria proposed at the design, regulatory and operating levels are examined. Then, by testing the criteria against some real decisions, the practical problems of using the proposed criteria are explored. This leads to consideration of possible alternatives to the proposed criteria. Finally the conclusions that appear to be justified are summarized and the need for further work is identified

Photometric parameter maps of the Moon derived from LROC WAC images

Science.gov (United States)

Sato, H.; Robinson, M. S.; Hapke, B. W.; Denevi, B. W.; Boyd, A. K.

2013-12-01

Spatially resolved photometric parameter maps were computed from 21 months of Lunar Reconnaissance Orbiter Camera (LROC) Wide Angle Camera (WAC) images. Due to a 60° field-of-view (FOV), the WAC achieves nearly global coverage of the Moon each month with more than 50% overlap from orbit-to-orbit. From the repeat observations at various viewing and illumination geometries, we calculated Hapke bidirectional reflectance model parameters [1] for 1°x1° "tiles" from 70°N to 70°S and 0°E to 360°E. About 66,000 WAC images acquired from February 2010 to October 2011 were converted from DN to radiance factor (I/F) though radiometric calibration, partitioned into gridded tiles, and stacked in a time series (tile-by-tile method [2]). Lighting geometries (phase, incidence, emission) were computed using the WAC digital terrain model (100 m/pixel) [3]. The Hapke parameters were obtained by model fitting against I/F within each tile. Among the 9 parameters of the Hapke model, we calculated 3 free parameters (w, b, and hs) by setting constant values for 4 parameters (Bco=0, hc=1, θ, φ=0) and interpolating 2 parameters (c, Bso). In this simplification, we ignored the Coherent Backscatter Opposition Effect (CBOE) to avoid competing CBOE and Shadow Hiding Opposition Effect (SHOE). We also assumed that surface regolith porosity is uniform across the Moon. The roughness parameter (θ) was set to an averaged value from the equator (× 3°N). The Henyey-Greenstein double lobe function (H-G2) parameter (c) was given by the 'hockey stick' relation [4] (negative correlation) between b and c based on laboratory measurements. The amplitude of SHOE (Bso) was given by the correlation between w and Bso at the equator (× 3°N). Single scattering albedo (w) is strongly correlated to the photometrically normalized I/F, as expected. The c shows an inverse trend relative to b due to the 'hockey stick' relation. The parameter c is typically low for the maria (0.08×0.06) relative to the

Qualifications of and acceptance criteria for transporting special form radioactive material

International Nuclear Information System (INIS)

Hovingh, J.

1991-01-01

A special form radioactive material is a radioactive material that is in an inert, insoluble, indispersible form such that even in the event of an accident, it will not be dispersed into the environment in a way that could have an adverse impact on public health and safety. Methods of qualifying a special form radioactive material are discussed. Interpretation of acceptance criteria are proposed for the transportation of Type B quantities of a special form radioactive material. 11 refs

10 CFR 50.46a - Acceptance criteria for reactor coolant system venting systems.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Acceptance criteria for reactor coolant system venting systems. 50.46a Section 50.46a Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND... function of these systems. High point vents are not required for the tubes in U-tube steam generators...

Acceptability criteria for linear dependence in validating UV-spectrophotometric methods of quantitative determination in forensic and toxicological analysis

Directory of Open Access Journals (Sweden)

L. Yu. Klimenko

2014-08-01

Full Text Available Introduction. This article is the result of authors’ research in the field of development of the approaches to validation of quantitative determination methods for purposes of forensic and toxicological analysis and devoted to the problem of acceptability criteria formation for validation parameter «linearity/calibration model». The aim of research. The purpose of this paper is to analyse the present approaches to acceptability estimation of the calibration model chosen for method description according to the requirements of the international guidances, to form the own approaches to acceptability estimation of the linear dependence when carrying out the validation of UV-spectrophotometric methods of quantitative determination for forensic and toxicological analysis. Materials and methods. UV-spectrophotometric method of doxylamine quantitative determination in blood. Results. The approaches to acceptability estimation of calibration models when carrying out the validation of bioanalytical methods is stated in international papers, namely «Guidance for Industry: Bioanalytical method validation» (U.S. FDA, 2001, «Standard Practices for Method Validation in Forensic Toxicology» (SWGTOX, 2012, «Guidance for the Validation of Analytical Methodology and Calibration of Equipment used for Testing of Illicit Drugs in Seized Materials and Biological Specimens» (UNODC, 2009 and «Guideline on validation of bioanalytical methods» (ЕМА, 2011 have been analysed. It has been suggested to be guided by domestic developments in the field of validation of analysis methods for medicines and, particularly, by the approaches to validation methods in the variant of the calibration curve method for forming the acceptability criteria of the obtained linear dependences when carrying out the validation of UV-spectrophotometric methods of quantitative determination for forensic and toxicological analysis. The choice of the method of calibration curve is

Assessment of LANL transuranic waste management documentation

International Nuclear Information System (INIS)

Davis, K.D.; Hoevemeyer, S.S.; McCance, C.H.; Jennrich, E.A.; Lund, D.M.

1991-04-01

This report presents the findings that resulted from the evaluation of the Los Alamos National Laboratory (LANL) TRU Waste Characterization Procedures, conducted to determine their compliance with applicable DOE requirements. The driving requirements for the procedures appear to be contained in DOE Order 5820.2A; specific reference is made to Chapter II of that document. In addition, the WIPP-WAC sets forth specific waste forms and establishes the basis for LANL's TRU Waste Acceptance Criteria; any characterization plan must utilize procedures that address the requirements of the WIPP-WAC in order to ensure compliance with it. The purpose of the characterization procedures is to provide details to waste generators and/or waste certifiers regarding how the characterization plan is implemented for the gathering of analytical and/or knowledge-of-process information to allow certification of the waste. An annotated outline was developed from those criteria found in Sections 4.0 and 5.0 of the WIPP-WAC. The annotated outline of elements that should be addressed in characterization procedures is provided

An approach to societal risk acceptance criteria and risk management

International Nuclear Information System (INIS)

Okrent, D.; Whipple, C.

1977-06-01

A quantitative approach to risk acceptance criteria and risk management is proposed for activities involving risk to individuals not receiving direct benefits, such as employment, from the activity. Societal activities are divided into major facilities or technologies, all or part of which are categorized as essential, beneficial, or peripheral, and a decreasing level of acceptable risk to the most exposed individual is proposed (say, 0.0002/year for essential, 0.00001/year for beneficial, and 0.000002/year for peripheral activity). The risk would be assessed at a high confidence level (say, 90%), thereby providing an incentive to the gaining of better knowledge. Each risk-producing facility, technology, etc., would have to undergo assessment both of risk to the individual and to society. The cost of the latter would have to be internalized, probably via a tax paid to the Federal Government, which in turn would redistribute the benefit as national health insurance or reduced taxes to the individual. Risk aversion to large events would be built into the internalization of the cost of risk

Hanford Site Transuranic (TRU) Waste Certification Plan

International Nuclear Information System (INIS)

GREAGER, T.M.

2000-01-01

As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package (TRUPACT-11 SARP). In

Small bore pipe acceptance criteria for watts bar nuclear plant Tennessee Valley Authority

International Nuclear Information System (INIS)

Sun, W.S.; Lee, R.L.; Kalyanan, N.

1991-01-01

Small bore pipe (≤2 inches NPS) is traditionally analyzed by simplified techniques using Cook Book approach, which yield conservative results. However, reconciliation of these systems for as-built condition where the original criteria is observed to have been exceeded (or due to additions etc.) generally becomes a time consuming and expensive operation since a rigorous computer aided analysis or a detailed hand calculation becomes necessary. The acceptance criteria in this paper can be effectively used in such cases. The approach involves utilizing basic engineering principles and plant specific parameters (such as earthquake spectra) to estimate the system response such as pipe stress due to various loading conditions, piping frequency, support and anchor loads, valve acceleration etc

Long-Term Safety Analysis of Baldone Radioactive Waste Repository and Updating of Waste Acceptance Criteria

International Nuclear Information System (INIS)

2001-12-01

The main objective of the project was to provide advice to the Latvian authorities on the safety enhancements and waste acceptance criteria for near surface radioactive waste disposal facilities of the Baldone repository. The project included the following main activities: Analysis of the current status of the management of radioactive waste in Latvia in general and, at the Baldone repository in particular Development of the short and long-term safety analysis of the Baldone repository, including: the planned increasing of capacity for disposal and long term storage, the radiological analysis for the post-closure period Development of the Environment Impact Statement, for the new foreseen installations, considering the non radiological components Proposal of recommendations for future updating of radioactive waste acceptance criteria Proposal of recommendations for safety upgrades to the facility. The work programme has been developed in phases and main tasks as follows. Phase 0: Project inception, Phase 1: Establishment of current status, plans and practices (Legislation, regulation and standards, Radioactive waste management, Waste acceptance criteria), Phase 2: Development of future strategies for long-term safety management and recommendations for safety enhancements. The project team found the general approach use at the installation, the basic design and the operating practices appropriate to international standards. Nevertheless, a number of items subject to potential improvements were also identified. These upgrading recommendations deal with general aspects of the management (mainly storage versus disposal of long-lived sources), site and environmental surveillance, packaging (qualification of containers, waste characterization requirements), the design of an engineered cap and strategies for capping. (author)

Expanded criteria donor kidneys for younger recipients: acceptable outcomes.

Science.gov (United States)

Goplani, K R; Kute, V B; Vanikar, A V; Shah, P R; Gumber, M R; Patel, H V; Modi, P R; Trivedi, H L

2010-12-01

European senior programme (ESP) is well known for acceptable outcomes using expanded criteria donor (ECD) kidneys from donors older than 65 years for recipients older than 65 years. The incidence of end-stage renal disease (ESRD) is 229/million in India with a mean age of 45 years. We performed a retrospective analysis of transplantation of ECD versus standard criteria donor (SCD) kidneys into younger recipients. Forty-three ECD transplantations among 158 deceased donor organ transplantation (DDOT) were performed between January 2006 and December 2009. Among 43 transplantation from 30 donors, 14 were dual kidney transplantations (DKT) performed based upon biopsy evaluation. All recipients received thymoglobulin (rATG) induction followed by immunosuppression with a steroid, mycophenolate mofetil (MMF), and a calcineurin inhibitor. Statistical analysis used chi-square test and unpaired Student t test. Kaplan-Meier curves were used for survival analysis. For ECD the mean donor age was 64 ± 11 years. Cerebrovascular accidents (CVA) were the cause of death among 60% of donors, 73.13% of whom were hypertensive and 23.13% diabetic. Mean DKT donor age was 75 ± 9.17 years versus 60 ± 8.0 years for single kidney transplantation (SKT). Mean recipient age of DKT versus SKT was 44 ± 12.4 years versus 43 ± 14 years. Mean serum creatinine (SCr; mg/dL) of SKT patients was 1.64 ± 0.75 versus 1.68 ± 0.46 in DKT. Mean follow-up was 455 ± 352 days. Mean SCr of 43 ECD recipients of mean age, 43.4 ± 14.2 years was 1.61 ± 0.61 mg/dL. Among 43 recipients, 23.25% were diabetic, 41.86% displayed delayed graft function (DGF), and 23.25% experienced biopsy-proven acute rejection (BPAR). Patient survival rate was 72.09% and graft survival rate was 67.44%. For SCD transplantations (n = 115), the mean donor age was 36 ± 14 years and recipient mean age was 32.8 ± 14.07 years. Mean SCr was 1.32 ± 0.46 mg/dL with 26.95% recipients displaying DGF, whereas 20.86% had BPAR. In the SCD

Selection of a leaching test method for waste product conformity verification

Energy Technology Data Exchange (ETDEWEB)

Lopes, Isabel Sofia R.F.S.; Tello, Clédola Cássia O.; Haucz, Maria Judite A., E-mail: isabel.lopes@cdtn.br, E-mail: tellocc@cdtn.br, E-mail: hauczmj@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2017-07-01

A study on the waste acceptance criteria (WAC) for disposal in a near-surface repository is being implemented by CDTN / CNEN. The acceptance criteria are used to ensure the safety in the repository facility in order to protect the employees, the public and the environment from some possible harmful and dangerous effects of the ionizing radiation. A near-surface repository is intended to be built for disposal of the Brazilian low- and intermediate level wastes. Leaching was the criterion chosen to be studied in this research. It is extremely important for the safety assessment to evaluate the waste form in relation to the radionuclides release, to predict the repository performance in the long term. As in the Brazilian WAC the test to measure the radionuclides leaching is not defined yet, two leaching tests were selected to be performed, the ISO 6961 and the ASTM C1308. The results will be analyzed in order to verify their similarities and differences and also their advantages and disadvantages. Inactive tracers cesium and lead were used as tracers to follow the leaching in both procedures. (author)

Selection of a leaching test method for waste product conformity verification

International Nuclear Information System (INIS)

Lopes, Isabel Sofia R.F.S.; Tello, Clédola Cássia O.; Haucz, Maria Judite A.

2017-01-01

A study on the waste acceptance criteria (WAC) for disposal in a near-surface repository is being implemented by CDTN / CNEN. The acceptance criteria are used to ensure the safety in the repository facility in order to protect the employees, the public and the environment from some possible harmful and dangerous effects of the ionizing radiation. A near-surface repository is intended to be built for disposal of the Brazilian low- and intermediate level wastes. Leaching was the criterion chosen to be studied in this research. It is extremely important for the safety assessment to evaluate the waste form in relation to the radionuclides release, to predict the repository performance in the long term. As in the Brazilian WAC the test to measure the radionuclides leaching is not defined yet, two leaching tests were selected to be performed, the ISO 6961 and the ASTM C1308. The results will be analyzed in order to verify their similarities and differences and also their advantages and disadvantages. Inactive tracers cesium and lead were used as tracers to follow the leaching in both procedures. (author)

Study of waste acceptance criteria for low-level radioactive waste from medical, industrial, and research facilities (Contract research)

International Nuclear Information System (INIS)

Koibuchi, Hiroto; Dohi, Terumi; Ishiguro, Hideharu; Hayashi, Masaru; Senda, Masaki

2008-12-01

Japan Atomic Energy Agency (JAEA) is supposed to draw up the plan for the disposal program of the very low-level radioactive waste and low-level radioactive waste generated from medical, industrial and research facilities. For instance, there are these facilities in JAEA, universities, private companies, and so on. JAEA has to get to know about the waste and its acceptance of other institutions described above because it is important for us to hold the licenses for the disposal program regarding safety assessment. This report presents the basic data concerning radioactive waste of research institutes etc. except RI waste, domestic and foreign information related to acceptance criteria for disposal of the low-level radioactive waste, the current status of foreign medical waste management, waste acceptance, and such. In this report, Japan's acceptance criteria were summarized on the basis of present regulation. And, the criteria of foreign countries, United States, France, United Kingdom and Spain, were investigated by survey of each reference. In addition, it was reported that the amount of waste from laboratories etc. for near-surface disposal and their characterization in our country. The Subjects of future work: the treatment of hazardous waste, the problem of the double-regulation (the Nuclear Reactor Regulation Law and the Law Concerning Prevention from Radiation Hazards due to Radioisotopes and Others) and the possession of waste were discussed here. (author)

Using disposal criteria for choosing waste processing strategy

International Nuclear Information System (INIS)

Lindberg, Maria; Andersson, Veronica

2016-01-01

Conclusion: • Reading the WAC for the repository will give guidance not only on what is allowed and in which amount but also on what needs to be documented; • Based on a Repository WAC a strategy to achieve allowed characteristics for the waste can be developed to ensure safety during the waste processing and disposal; • Characteristics that in some way are described in the disposal WAC is worth collecting information about; • If a waste form is not present declaring it as zero will make a clear statement instead of leaving the information field blank, in particular later on in the repository lifetime; • A Waste Type Description can only be as good as the Disposal WAC allows – but collect all info that is available even if it is not asked for yet; • Small reflection – don’t try to fit all waste into one WTD – it will only create more work than you really want

Acceptance criteria for the low enriched uranium reform amendments. Revision 1

International Nuclear Information System (INIS)

Emeigh, C.W.; Gundersen, G.E.; Withee, C.J.

1985-04-01

Revisions have been made to the material control and accounting requirements for NRC licensees authorized to possess and use more than one effective kilogram of special nuclear material of low strategic significance to have MC and A systems able to (1) confirm the presence of special nuclear material, (2) resolve indications of missing material, and (3) aid in the investigation and recovery of missing material. This document presents criteria that can be used to aid in judging the acceptability of licensee plans that would be submitted to the NRC for implementing these capabilities. General performance objectives, system capabilities, and recordkeeping are addressed

Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program

International Nuclear Information System (INIS)

DOE Carlsbad Field Office

2001-01-01

The Performance Demonstration Program (PDP) for nondestructive assay (NDA) consists of a series of tests to evaluate the capability for NDA of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements obtained from NDA systems used to characterize the radiological constituents of TRU waste. The primary documents governing the conduct of the PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC; DOE 1999a) and the Quality Assurance Program Document (QAPD; DOE 1999b). The WAC requires participation in the PDP; the PDP must comply with the QAPD and the WAC. The WAC contains technical and quality requirements for acceptable NDA. This plan implements the general requirements of the QAPD and applicable requirements of the WAC for the NDA PDP. Measurement facilities demonstrate acceptable performance by the successful testing of simulated waste containers according to the criteria set by this PDP Plan. Comparison among DOE measurement groups and commercial assay services is achieved by comparing the results of measurements on similar simulated waste containers reported by the different measurement facilities. These tests are used as an independent means to assess the performance of measurement groups regarding compliance with established quality assurance objectives (QAO's). Measurement facilities must analyze the simulated waste containers using the same procedures used for normal waste characterization activities. For the drummed waste PDP, a simulated waste container consists of a 55-gallon matrix drum emplaced with radioactive standards and fabricated matrix inserts. These PDP sample components are distributed to the participating measurement facilities that have been designated and authorized by the Carlsbad Field Office (CBFO). The NDA Drum PDP materials are stored at these sites under secure conditions to

Preliminary Mark-18A (Mk-18A) Target Material Recovery Program Product Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

Robinson, Sharon M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Patton, Bradley D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2016-09-01

The Mk-18A Target Material Recovery Program (MTMRP) was established in 2015 to preserve the unique materials, e.g. ²⁴⁴Pu, in 65 previously irradiated Mk-18A targets for future use. This program utilizes existing capabilities at SRS and Savannah River National Laboratory (SRNL) to process targets, recover materials from them, and to package the recovered materials for shipping to ORNL. It also utilizes existing capabilities at ORNL to receive and store the recovered materials, and to provide any additional processing of the recovered materials or residuals required to prepare them for future beneficial use. The MTMRP is presently preparing for the processing of these valuable targets which is expected to begin in ~2019. As part of the preparations for operations, this report documents the preliminary acceptance criteria for the plutonium and heavy curium materials to be recovered from the Mk-18A targets at SRNL for transport and storage at ORNL. These acceptance criteria were developed based on preliminary concepts developed for processing, transporting, and storing the recovered Mk-18A materials. They will need to be refined as these concepts are developed in more detail.

Preliminary Mark-18A (Mk-18A) Target Material Recovery Program Product Acceptance Criteria

International Nuclear Information System (INIS)

Robinson, Sharon M.; Patton, Bradley D.

2016-01-01

The Mk-18A Target Material Recovery Program (MTMRP) was established in 2015 to preserve the unique materials, e.g. 244 Pu, in 65 previously irradiated Mk-18A targets for future use. This program utilizes existing capabilities at SRS and Savannah River National Laboratory (SRNL) to process targets, recover materials from them, and to package the recovered materials for shipping to ORNL. It also utilizes existing capabilities at ORNL to receive and store the recovered materials, and to provide any additional processing of the recovered materials or residuals required to prepare them for future beneficial use. The MTMRP is presently preparing for the processing of these valuable targets which is expected to begin in ~2019. As part of the preparations for operations, this report documents the preliminary acceptance criteria for the plutonium and heavy curium materials to be recovered from the Mk-18A targets at SRNL for transport and storage at ORNL. These acceptance criteria were developed based on preliminary concepts developed for processing, transporting, and storing the recovered Mk-18A materials. They will need to be refined as these concepts are developed in more detail.

CTOD-based acceptance criteria for heat exchanger head staybolts

International Nuclear Information System (INIS)

Lam, P.S.; Sindelar, R.L.; Barnes, D.M.; Awadalla, N.G.

1992-01-01

The primary coolant piping system of the Savannah River Site (SRS) reactors contains twelve heat exchangers to remove the waste heat from the nuclear materials production. A large break at the inlet or outlet heads of the heat exchangers would occur if the restraint members of the heads become inactive. The heat exchanger head is attached to the tubesheet by 84 staybolts. The structural integrity of the heads is demonstrated by showing the redundant capacity of the staybolts to restrain the head at design conditions and under seismic loadings. The beat exchanger head is analyzed with a three- dimensional finite element model. The restraint provided by the staybolts is evaluated for several postulated cases of inactive or missing staybolts, that is, bolts that have a flaw exceeding the ultrasonic testing (UT) threshold depth of 25% of the bolt diameter. A limit of 6 inactive staybolts is reached with a fracture criterion based on the maximum allowable local displacement at the active staybolts which corresponds to the crack tip opening displacement (CTOD) of 0.032 inches. An acceptance criteria methodology has been developed to disposition flaws reported in the staybolt inspections while ensuring adequate restraint capacity of the staybolts to maintain integrity of the heat exchanger heads against collapse. The methodology includes an approach for the baseline and periodic inspections of the staybolts. A total of up to 6 staybolts, reported as containing flaws with depths at or exceeding 25% would be acceptable in the heat exchanger

Characterization of the Old Hydrofracture Facility (OHF) waste tanks located at ORNL

International Nuclear Information System (INIS)

Keller, J.M.; Giaquinto, J.M.; Meeks, A.M.

1997-04-01

The Old Hydrofracture Facility (OHF) is located in Melton Valley within Waste Area Grouping (WAG) 5 and includes five underground storage tanks (T1, T2, T3, T4, and T9) ranging from 13,000 to 25,000 gal. capacity. During the period of 1996--97 there was a major effort to re-sample and characterize the contents of these inactive waste tanks. The characterization data summarized in this report was needed to address waste processing options, examine concerns dealing with the performance assessment (PA) data for the Waste Isolation Pilot Plant (WIPP), evaluate the waste characteristics with respect to the waste acceptance criteria (WAC) for WIPP and Nevada Test Site (NTS), address criticality concerns, and to provide the data needed to meet DOT requirements for transporting the waste. This report discusses the analytical characterization data collected on both the supernatant and sludge samples taken from three different locations in each of the OHF tanks. The isotopic data presented in this report supports the position that fissile isotopes of uranium ( 233 U and 235 U) do not satisfy the denature ratios required by the administrative controls stated in the ORNL LLLW waste acceptance criteria (WAC). The fissile isotope of plutonium ( 239 Pu and 241 Pu) are diluted with thorium far above the WAC requirements. In general, the OHF sludge was found to be hazardous (RCRA) based on total metal content and the transuranic alpha activity was well above the 100 nCi/g limit for TRU waste. The characteristics of the OHF sludge relative to the WIPP WAC limits for fissile gram equivalent, plutonium equivalent activity, and thermal power from decay heat were estimated from the data in this report and found to be far below the upper boundary for any of the remote-handled transuranic waste (RH-TRU) requirements for disposal of the waste in WIPP

Structural acceptance criteria for the evaulation of existing double-shell waste storage tanks located at the Hanford site, Richland, Washington

International Nuclear Information System (INIS)

Julyk, L.J.; Day, A.D.; Dyrness, A.D.; Moore, C.J.; Peterson, W.S.; Scott, M.A.; Shrivastava, H.P.; Sholman, J.S.; Watts, T.N.

1995-09-01

The structural acceptance criteria contained herein for the evaluation of existing underground double-shell waste storage tanks located at the Hanford Site is part of the Life Management/Aging Management Program of the Tank Waste Remediation System. The purpose of the overall life management program is to ensure that confinement of the waste is maintained over the required service life of the tanks. Characterization of the present condition of the tanks, understanding and characterization of potential degradation mechanisms, and development of tank structural acceptance criteria based on previous service and projected use are prerequisites to assessing tank integrity, to projecting the length of tank service, and to developing and applying prudent fixes or repairs. The criteria provided herein summarize the requirements for the analysis and structural qualification of the existing double-shell tanks for continued operation. Code reconciliation issues and material degradation under aging conditions are addressed. Although the criteria were developed for double-shell tanks, many of the provisions are equally applicable to single-shell tanks. However, the criteria do not apply to the evaluation of tank appurtenances and buried piping

Acceptance criteria for disposal of radioactive waste in Romania

International Nuclear Information System (INIS)

Dogaru, D.

2001-01-01

In Romania the institutional radioactive waste are managed by National Institute of R and D for Physics and Nuclear Engineering. The institutional radioactive waste are collected, treated and conditioned at the Radioactive Waste Treatment Plant then transferred and disposed to the National Repository of Radioactive Waste at Baita Bihor. National Repository for Radioactive Waste is a long term storage facility. The repository is placed in a former worked out uranium ore mine, being excavated in the Bihor peak. The repository has been sited taking into account the known geological, hydrogeoloical, seismic and meteorological and mining properties of a uranium mining site. In the absence of an updated Safety Analysis Report, the maximum radioactive content permitted by the regulatory authority in the operation license is below the values reported for other engineered repositories in mine galleries. The paper presents the acceptance criteria for disposal of radioactive waste in National Repository for Radioactive Waste at Baita Bihor. (author)

Determination of acceptable risk criteria for nuclear waste management

International Nuclear Information System (INIS)

Cohen, J.J.

1977-01-01

The initial phase of the work performed during FY 1977 consisted of performing a ''scoping'' study to define issues, determine an optimal methodology for their resolution, and compile a data base for acceptable risk criteria development. The issues, spanning technical, psychological, and ethical dimensions, were categorized in seven major areas: (1) unplanned or accidental events, (2) present vs future risks, (3) institutional controls and retrievability, (4) dose-response mechanism and uncertainty, (5) spatial distribution of exposed populations, (6) different types of nuclear wastes, and (7) public perception. The optimum methodology for developing ARC was determined to be multi-attribute decision analysis encompassing numerous specific techniques for choosing, from among several alternatives, the optimal course of action when the alternatives are constrained to meet specified attributes. The data base developed during the study comprises existing regulations and guidelines, maximum permissible dose, natural geologic hazards, nonradioactive hazardous waste practices, bioethical perspectives, and data from an opinion survey

Determination of acceptable risk criteria for nuclear waste management

Energy Technology Data Exchange (ETDEWEB)

Cohen, J.J.

1977-10-21

The initial phase of the work performed during FY 1977 consisted of performing a ''scoping'' study to define issues, determine an optimal methodology for their resolution, and compile a data base for acceptable risk criteria development. The issues, spanning technical, psychological, and ethical dimensions, were categorized in seven major areas: (1) unplanned or accidental events, (2) present vs future risks, (3) institutional controls and retrievability, (4) dose-response mechanism and uncertainty, (5) spatial distribution of exposed populations, (6) different types of nuclear wastes, and (7) public perception. The optimum methodology for developing ARC was determined to be multi-attribute decision analysis encompassing numerous specific techniques for choosing, from among several alternatives, the optimal course of action when the alternatives are constrained to meet specified attributes. The data base developed during the study comprises existing regulations and guidelines, maximum permissible dose, natural geologic hazards, nonradioactive hazardous waste practices, bioethical perspectives, and data from an opinion survey.

Criteria of acceptability relating to the approval of consumer goods containing radioactive substances

International Nuclear Information System (INIS)

Paynter, R.A.

1992-01-01

The criteria are described which the Board intends to use when considering goods containing radioactive substances for approval under the regulations that the Government intends to make with respect to such goods. Some products are deemed unacceptable in principle because there would appear to be no justification for the use of radioactive substances in them. Examples of such products are given. Other products may be approved for supply to the public depending on the doses likely to be received by individuals, principally those who use the products. A lower dose is considered acceptable from products that do not contribute to safety than from products that do. In the interim, before the regulations are made, the criteria will be used as the basis of the Board's advice to suppliers and manufacturers of goods containing radioactive substances. (Author)

Westinghouse Hanford Company plan for certifying newly generated contact -- handled transuranic waste. Revision 1

International Nuclear Information System (INIS)

Lipinski, R.M.; Backlund, E.G.

1995-09-01

All transuranic (TRU) waste generators are required by US Department of Energy (DOE) Order 5820.2A to package their TRU waste in order to comply wit the Waste Isolation Pilot Plant (WIPP) -- Waste Acceptance Criteria (WAC) or keep non-certifiable containers segregated. The Westinghouse Hanford Company (WHC) Transuranic Waste Certification Plan was developed to ensure that TRU newly generated waste at WHC meets the DOE Order 5820.2A and the WHC-WAC which includes the State of Washington Department of Ecology -- Washington Administrative Code (DOE-WAC). The metho used at WHC to package TRU waste are described in sufficient detail to meet the regulations. This document is organized to provide a brief overview of waste generation operations at WHC. The methods used to implement this plan are discussed briefly along with the responsibilities and authorities of applicable organizations. This plan describes how WHC complies with all applicable regulations and requirements set forth in the latest approved revision of WHC-EP-0063-4

Characterization of the BVEST waste tanks located at ORNL

International Nuclear Information System (INIS)

Keller, J.M.; Giaquinto, J.M.; Meeks, A.M.

1997-01-01

During the fall of 1996 there was a major effort to sample and analyze the Active Liquid Low-Level Waste (LLLW) tanks at ORNL which include the Melton Valley Storage Tanks (MVST) and the Bethel Valley Evaporator Service Tanks (BVEST). The characterization data summarized in this report was needed to address waste processing options, address concerns dealing with the performance assessment (PA) data for the Waste Isolation Pilot Plant (WIPP), evaluate the waste characteristics with respect to the waste acceptance criteria (WAC) for WIPP and Nevada Test Site (NTS), address criticality concerns, and meet DOT requirements for transporting the waste. This report discusses the analytical characterization data for the supernatant and sludge in the BVEST waste tanks W-21, W-22, and W-23. The isotopic data presented in this report supports the position that fissile isotopes of uranium and plutonium were denatured as required by the administrative controls stated in the ORNL LLLW waste acceptance criteria (WAC). In general, the BVEST sludge was found to be hazardous based on RCRA characteristics and the transuranic alpha activity was well above the 100 nCi/g limit for TRU waste. The characteristics of the BVEST sludge relative to the WIPP WAC limits for fissile gram equivalent, plutonium equivalent activity, and thermal power from decay heat were estimated from the data in this report and found to be far below the upper boundary for any of the remote-handled transuranic waste (RH-TRU) requirements for disposal of the waste in WIPP

Characterization of the C1 and C2 waste tanks located in the BVEST system at ORNL

International Nuclear Information System (INIS)

Keller, J.M.; Giaquinto, J.M.

1998-02-01

There was a major effort to sample and analyze the Active Liquid Low-Level Waste (LLLW) tanks at ORNL which include the Melton Valley Storage Tanks (MVST) and the Bethel Valley Evaporator Service Tanks (BVEST). The characterization data summarized in this report was needed to address waste processing options, address concerns dealing with the performance assessment (PA) data for the Waste Isolation Pilot Plant (WIPP), evaluate the waste characteristics with respect to the waste acceptance criteria (WAC) for WIPP and Nevada Test Site (NTS), address criticality concerns, and meet DOT requirements for transporting the waste. This report discusses the analytical characterization data for the supernatant and sludge in the BVEST waste tanks C-1 and C-2. The isotopic data presented in this report supports the position that fissile isotopes of uranium ( 233 U and 235 U) and plutonium ( 239 Pu and 241 Pu) were denatured as required by the administrative controls stated in the ORNL LLLW waste acceptance criteria (WAC). In general, the sludge in tanks C1 and C2 was found to be hazardous based on RCRA characteristics and the transuranic alpha activity was well above the 100 nCi/g limit for TRU waste. Additional characteristics of the C1 and C2 sludge inventory relative to the WIPP WAC limits for fissile gram equivalent, plutonium equivalent activity, and thermal power from decay heat were estimated from the data in this report and found to be far below the upper boundary for any of the remote-handled transuranic waste (RH-TRU) requirements for disposal of the waste in WIPP

SRNL Phase 1 Assessment Of The WAC/DQO And Unit Operations For The WTP Waste Qualification Program

International Nuclear Information System (INIS)

Peeler, D.; Adamson, D.; Bannochie, C.; Cozzi, A.; Eibling, R.; Hay, M.; Hansen, E.; Herman, D.; Martino, C.; Nash, C.; Pennebaker, F.; Poirier, M.; Reboul, S.; Stone, M.; Taylor-Pashow, K.; White, T.; Wilmarth, B.

2012-01-01

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is currently transitioning its emphasis from a design and construction phase toward start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements related to actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program to be implemented to support the WTP. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS), based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested the utilization of subject matter experts from SRNL to support a technology exchange to perform a review of the WTP waste qualification program, discuss the general qualification approach at SRS, and to identify critical lessons learned through the support of DWPF's sludge batch qualification efforts. As part of Phase 1, SRNL subject matter experts in critical technical and/or process areas reviewed specific WTP waste qualification information. The Phase 1 review was a collaborative, interactive, and iterative process between the two organizations. WTP provided specific analytical procedures, descriptions of equipment, and general documentation as baseline review material. SRNL subject matter experts reviewed the information and, as appropriate, requested follow-up information or clarification to specific areas of interest. This process resulted in multiple teleconferences with key technical contacts from both organizations resolving technical issues that lead to the results presented in this report. This report provides the results of SRNL's Phase 1 review of the WAC-DQO waste acceptance criteria and processability parameters, and the specific unit operations which are required to support WTP waste qualification efforts. The review resulted in SRNL providing concurrence, alternative methods, or gap identification

SRNL PHASE 1 ASSESSMENT OF THE WAC/DQO AND UNIT OPERATIONS FOR THE WTP WASTE QUALIFICATION PROGRAM

Energy Technology Data Exchange (ETDEWEB)

Peeler, D.; Adamson, D.; Bannochie, C.; Cozzi, A.; Eibling, R.; Hay, M.; Hansen, E.; Herman, D.; Martino, C.; Nash, C.; Pennebaker, F.; Poirier, M.; Reboul, S.; Stone, M.; Taylor-Pashow, K.; White, T.; Wilmarth, B.

2012-05-16

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is currently transitioning its emphasis from a design and construction phase toward start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements related to actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program to be implemented to support the WTP. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS), based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested the utilization of subject matter experts from SRNL to support a technology exchange to perform a review of the WTP waste qualification program, discuss the general qualification approach at SRS, and to identify critical lessons learned through the support of DWPF's sludge batch qualification efforts. As part of Phase 1, SRNL subject matter experts in critical technical and/or process areas reviewed specific WTP waste qualification information. The Phase 1 review was a collaborative, interactive, and iterative process between the two organizations. WTP provided specific analytical procedures, descriptions of equipment, and general documentation as baseline review material. SRNL subject matter experts reviewed the information and, as appropriate, requested follow-up information or clarification to specific areas of interest. This process resulted in multiple teleconferences with key technical contacts from both organizations resolving technical issues that lead to the results presented in this report. This report provides the results of SRNL's Phase 1 review of the WAC-DQO waste acceptance criteria and processability parameters, and the specific unit operations which are required to support WTP waste qualification efforts. The review resulted in SRNL providing concurrence, alternative methods, or gap

Advances in flaw evaluation procedures and acceptance criteria for reactor piping

International Nuclear Information System (INIS)

Gamble, R.M.; Zahoor, A.; Norris, D.M.

1986-01-01

During the past several years, intergranular stress corrosion cracks (IGSCC) have been detected in stainless steel piping in boiling water reactors (BWRs) and have resulted in an increased number of flaw evaluations. To reduce the outage time associated with evaluating IGSCC, various research and ASME code groups have spent significant effort to provide utility personnel with efficient means to detect, classify, and size flaws, and to determine suitability for return to service for flawed stainless steel piping. One of the several nondestructive evaluation technologies that has received considerable attention is fracture mechanics, the discipline that considers the failure of flawed material. Fracture mechanics can be used to answer two key questions concerning return to service of flawed pipe: (a) what is the largest flaw size that can be returned to service and still maintain adequate safety margins at the applied loads, and (b) how much operating time remains before the crack reaches the largest allowable size? The purpose of this paper is to provide an overview of the recently developed ASME code Section XI flaw size evaluation procedure and acceptance criteria for stainless steel piping and their application by BWR owners to efficiently determine if flaws found by nondestructive examination are acceptable for continued service

Advances in flaw evaluation procedures and acceptance criteria for reactor piping

Energy Technology Data Exchange (ETDEWEB)

Gamble, R.M.; Zahoor, A.; Norris, D.M.

1986-01-01

During the past several years, intergranular stress corrosion cracks (IGSCC) have been detected in stainless steel piping in boiling water reactors (BWRs) and have resulted in an increased number of flaw evaluations. To reduce the outage time associated with evaluating IGSCC, various research and ASME code groups have spent significant effort to provide utility personnel with efficient means to detect, classify, and size flaws, and to determine suitability for return to service for flawed stainless steel piping. One of the several nondestructive evaluation technologies that has received considerable attention is fracture mechanics, the discipline that considers the failure of flawed material. Fracture mechanics can be used to answer two key questions concerning return to service of flawed pipe: (a) what is the largest flaw size that can be returned to service and still maintain adequate safety margins at the applied loads, and (b) how much operating time remains before the crack reaches the largest allowable size. The purpose of this paper is to provide an overview of the recently developed ASME code Section XI flaw size evaluation procedure and acceptance criteria for stainless steel piping and their application by BWR owners to efficiently determine if flaws found by nondestructive examination are acceptable for continued service.

HOW TO DEAL WITH WASTE ACCEPTANCE UNCERTAINTY USING THE WASTE ACCEPTANCE CRITERIA FORECASTING AND ANALYSIS CAPABILITY SYSTEM (WACFACS)

Energy Technology Data Exchange (ETDEWEB)

Redus, K. S.; Hampshire, G. J.; Patterson, J. E.; Perkins, A. B.

2002-02-25

The Waste Acceptance Criteria Forecasting and Analysis Capability System (WACFACS) is used to plan for, evaluate, and control the supply of approximately 1.8 million yd3 of low-level radioactive, TSCA, and RCRA hazardous wastes from over 60 environmental restoration projects between FY02 through FY10 to the Oak Ridge Environmental Management Waste Management Facility (EMWMF). WACFACS is a validated decision support tool that propagates uncertainties inherent in site-related contaminant characterization data, disposition volumes during EMWMF operations, and project schedules to quantitatively determine the confidence that risk-based performance standards are met. Trade-offs in schedule, volumes of waste lots, and allowable concentrations of contaminants are performed to optimize project waste disposition, regulatory compliance, and disposal cell management.

HOW TO DEAL WITH WASTE ACCEPTANCE UNCERTAINTY USING THE WASTE ACCEPTANCE CRITERIA FORECASTING AND ANALYSIS CAPABILITY SYSTEM (WACFACS)

International Nuclear Information System (INIS)

Redus, K. S.; Hampshire, G. J.; Patterson, J. E.; Perkins, A. B.

2002-01-01

The Waste Acceptance Criteria Forecasting and Analysis Capability System (WACFACS) is used to plan for, evaluate, and control the supply of approximately 1.8 million yd3 of low-level radioactive, TSCA, and RCRA hazardous wastes from over 60 environmental restoration projects between FY02 through FY10 to the Oak Ridge Environmental Management Waste Management Facility (EMWMF). WACFACS is a validated decision support tool that propagates uncertainties inherent in site-related contaminant characterization data, disposition volumes during EMWMF operations, and project schedules to quantitatively determine the confidence that risk-based performance standards are met. Trade-offs in schedule, volumes of waste lots, and allowable concentrations of contaminants are performed to optimize project waste disposition, regulatory compliance, and disposal cell management

Performance Demonstration Program Plan for Nondestructive Assay of Boxed Wastes for the TRU Waste Characterization Program

International Nuclear Information System (INIS)

2001-01-01

The Performance Demonstration Program (PDP) for nondestructive assay (NDA) consists of a series of tests to evaluate the capability for NDA of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements obtained from NDA systems used to characterize the radiological constituents of TRU waste. The primary documents governing the conduct of the PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC; DOE 1999a) and the Quality Assurance Program Document (QAPD; DOE 1999b). The WAC requires participation in the PDP; the PDP must comply with the QAPD and the WAC. The WAC contains technical and quality requirements for acceptable NDA. This plan implements the general requirements of the QAPD and applicable requirements of the WAC for the NDA PDP for boxed waste assay systems. Measurement facilities demonstrate acceptable performance by the successful testing of simulated waste containers according to the criteria set by this PDP Plan. Comparison among DOE measurement groups and commercial assay services is achieved by comparing the results of measurements on similar simulated waste containers reported by the different measurement facilities. These tests are used as an independent means to assess the performance of measurement groups regarding compliance with established quality assurance objectives (QAO's). Measurement facilities must analyze the simulated waste containers using the same procedures used for normal waste characterization activities. For the boxed waste PDP, a simulated waste container consists of a modified standard waste box (SWB) emplaced with radioactive standards and fabricated matrix inserts. An SWB is a waste box with ends designed specifically to fit the TRUPACT-II shipping container. SWB's will be used to package a substantial volume of the TRU waste for disposal. These PDP sample components

Low-level radioactive waste management: transitioning to off-site disposal at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Dorries, Alison M.

2010-01-01

Facing the closure of nearly all on-site management and disposal capability for low-level radioactive waste (LLW), Los Alamos National Laboratory (LANL) is making ready to ship the majority of LLW off-site. In order to ship off-site, waste must meet the Treatment, Storage, and Disposal Facility's (TSDF) Waste Acceptance Criteria (WAC). In preparation, LANL's waste management organization must ensure LANL waste generators characterize and package waste compliantly and waste characterization documentation is complete and accurate. Key challenges that must be addressed to successfully make the shift to off-site disposal of LLW include improving the detail, accuracy, and quality of process knowledge (PK) and acceptable knowledge (AK) documentation, training waste generators and waste management staff on the higher standard of data quality and expectations, improved WAC compliance for off-site facilities, and enhanced quality assurance throughout the process. Certification of LANL generators will allow direct off-site shipping of LLW from their facilities.

[Professor Wacław Kuśnierczyk (1908-1997)--Pro Memoria in the century of birthday].

Science.gov (United States)

Brozek, Krzysztof; Kozakiewicz, Jacek; Kierzek, Andrzej

2009-01-01

Wacław Kuśnierczyk was born in 1908 in Sniatyń. He received the degree in medicine at Jan Kazimierz University in Lwów in 1932. He did his PhD degree under Professor Zaleski supervision in 1938 at Jan Kazimierz University. At that time he concentrated his scientific activity on research on tuberculosis. In 1953 he obtained the title of second degree specialist in ear, nose and throat diseases. He became a chief of Otolaryngology at Urban Hospital No 4 in Katowice in 1960. Since then this eminent physician was working on tumours located in upper respiratory tract and the possibility of its endoscopic diagnosis at Silesian Academy of Medicine in Katowice. As one of the first he pointed out the negative influence of smoking cigarettes on cancer of larynx. It was Wacław Kuśnierczyk who implemented new priorities for integrated programs in patient care, research, education and cancer prevention. He has published widely in peer reviewed journals and has edited or contributed to many books. He has given many major lectures and is the recipient of numerous prestigious awards for his scientific accomplishments. The achievement of Professor Kuśnierczyk were the valuable source of information for the physicians. In 1997, on the 31st of January he died in Katowice.

Nevada test site waste acceptance criteria

International Nuclear Information System (INIS)

1996-01-01

This document provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document

Nevada test site waste acceptance criteria

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-09-01

This document provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document.

Derivation of Waste Acceptance Criteria for Low and Intermediate Level Waste in Surface Disposal Facility

International Nuclear Information System (INIS)

Gagner, L.; Voinis, S.

2000-01-01

In France, low- and intermediate-level radioactive wastes are disposed in a near-surface facility, at Centre de l'Aube disposal facility. This facility, which was commissioned in 1992, has a disposal capacity of one million cubic meters, and will be operated up to about 2050. It took over the job from Centre de la Manche, which was commissioned in 1969 and shut down in 1994, after having received about 520,000 cubic meters of wastes. The Centre de l'Aube disposal facility is designed to receive a many types of waste produced by nuclear power plants, reprocessing, decommissioning, as well as by the industry, hospitals and armed forces. The limitation of radioactive transfer to man and the limitation of personnel exposure in all situations considered plausible require limiting the total activity of the waste disposed in the facility as well as the activity of each package. The paper presents how ANDRA has derived the activity-related acceptance criteria, based on the safety analysis. In the French methodology, activity is considered as end-point for deriving the concentration limits per package, whereas it is the starting point for deriving the total activity limits. For the concentration limits (called here LMA) the approach consists of five steps: the determination of radionuclides important for safety with regards to operational and long-term safety, the use of relevant safety scenarios as a tool to derive quantitative limits, the setting of dose constraint per situation associated with scenarios, the setting of contribution factor per radionuclide, and the calculation of concentration activity limits. An exhaustive survey has been performed and has shown that the totality of waste packages which should be delivered by waste generators are acceptable in terms of activity limits in the Centre de l'Aube. Examples of concentration activity limits derived from this methodology are presented. Furthermore those limits have been accepted by the French regulatory body and

Technical basis for acceptance criteria on the susceptibility of digital systems to electromagnetic interference

International Nuclear Information System (INIS)

Ewing, P.D.; Korsah, K.; Antonescu, C.

1992-01-01

This paper discusses the development of the technical basis for establishing acceptance criteria on the susceptibility of digital systems to electromagnetic interference (EMI). The effort is sponsored by the US Nuclear Regulatory Commission and stems from the safety-related issues that need to be addressed with the application of digital instrumentation and controls systems in nuclear power plants. Designers of digital circuits are incorporating increasingly higher clock frequencies and lower logic voltage levels, thereby leading to the risk of susceptibility when spurious interference is misinterpreted as legitimate logic. Development of the technical basis for acceptance criteria centers around establishing good engineering practices to ensure that sufficient levels of electromagnetic compatibility (EMC) are maintained between the nuclear power plant's electronic and electromechanical systems. First, good EMC design and installation practices are needed to control the emissions from interference sources and their impact on other nearby circuits and systems. Then, a test and evaluation program is needed to outline the EMI tests to be performed, the associated test methods to be followed, and adequate test limits to ensure that the circuit or system under test meets the recommended guidelines. Test and evaluation should be followed by periodic maintenance to assess whether the recommended EMI control practices continue to be adhered to as part of the routine operation of the nuclear power plant. By following these steps, the probability of encountering safety-related problems associated with EMI will be greatly reduced

RSE-M code progress in the field of examination evaluation and flaw acceptance criteria

International Nuclear Information System (INIS)

Barthelet, B.; Le Delliou, P.; Heliot, J.; Faidy, C.; Drubay, B.

1995-01-01

The RSE-M Code provides rules and requirements for in service inspection of light water cooled nuclear power plants. The code first edition was established by EDF and published in 1990 by AFCEN. In 1992, a second RSE-M project was launched by EDF and FRAMATOME with the objective to address a 1995 edition more completed considering the needs of owners, users, manufacturers and inspectors. This paper focuses on evaluation of examination results and presents the work done in the field of flaw acceptance criteria over the last three years. (author). 5 refs., 3 figs

Screening and comparison of remedial alternatives for the South Field and flyash piles at the Fernald site

International Nuclear Information System (INIS)

Bumb, A.C.; Jones, G.N.

1996-05-01

The South Field, the Inactive Flyash Pile, and the Active Flyash Pile are in close proximity to each other and are part of Operable Unit 2 (OU2) at the Fernald Environmental Management Project (FEMP). The baseline risk assessment indicated that the exposure pathways which pose the most significant risk are external radiation from radionuclides in surface soils and use of uranium contaminated groundwater. This paper presents screening and comparison of various remedial alternatives considered to mitigate risks from the groundwater pathway. Eight remedial alternatives were developed which consisted of consolidation and capping, excavation and off-site disposal with or without treatment, excavation and on-site disposal with or without treatment and combinations of these. Risk-based source (soil) preliminary remediation levels (PRLs) and waste acceptance criteria (WACs) were developed for consolidation and capping, excavation, and on-site disposal cell. The PRLs and WACs were developed using an integrated modeling tool consisting of an infiltration model, a surface water model, a vadose zone model, and a three-dimensional contaminant migration model in saturated media. The PRLs and WACs were then used to determine need for soil treatment, determine excavation volumes, and screen remedial alternatives. The selected remedial alternative consisted of excavation and on-site disposal with off-site disposal of the fraction exceeding the WAC

A facility design for repackaging ORNL CH-TRU legacy waste in Building 3525

International Nuclear Information System (INIS)

Huxford, T.J.; Cooper, R.H. Jr.; Davis, L.E.; Fuller, A.B.; Gabbard, W.A.; Smith, R.B.; Guay, K.P.; Smith, L.C.

1995-07-01

For the last 25 years, the Oak Ridge National Laboratory (ORNL) has conducted operations which have generated solid, contact-handled transuranic (CH-TRU) waste. At present the CH-TRU waste inventory at ORNL is about 3400 55-gal drums retrievably stored in RCRA-permitted, aboveground facilities. Of the 3400 drums, approximately 2600 drums will need to be repackaged. The current US Department of Energy (DOE) strategy for disposal of these drums is to transport them to the Waste Isolation Pilot Plant (WIPP) in New Mexico which only accepts TRU waste that meets a very specific set of criteria documented in the WIPP-WAC (waste acceptance criteria). This report describes activities that were performed from January 1994 to May 1995 associated with the design and preparation of an existing facility for repackaging and certifying some or all of the CH-TRU drums at ORNL to meet the WIPP-WAC. For this study, the Irradiated Fuel Examination Laboratory (IFEL) in Building 3525 was selected as the reference facility for modification. These design activities were terminated in May 1995 as more attractive options for CH-TRU waste repackaging were considered to be available. As a result, this document serves as a final report of those design activities

Nevada Test Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

U.S. Department of Energy, Nevada Operations Office, Waste Acceptance Criteria

1999-01-01

This document provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the Nevada Test Site

Industry Application Emergency Core Cooling System Cladding Acceptance Criteria Early Demonstration

Energy Technology Data Exchange (ETDEWEB)

Szilard, Ronaldo H. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Youngblood, Robert W. [FPoliSolutions LLC, Murrysville, PA (United States); Zhang, Hongbin [Idaho National Lab. (INL), Idaho Falls, ID (United States); Zhao, Haihua [Idaho National Lab. (INL), Idaho Falls, ID (United States); Bayless, Paul D. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rabiti, Cristian [Idaho National Lab. (INL), Idaho Falls, ID (United States); Alfonsi, Andrea [Idaho National Lab. (INL), Idaho Falls, ID (United States); Smith, Curtis L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Frepoli, Cesare [FPoliSolutions LLC, Murrysville, PA (United States); Yurko, Joseph P. [FPoliSolutions LLC, Murrysville, PA (United States); Swindlehurst, Gregg [GS Nuclear Consulting, Charlotte, NC (United States); Zoino, Angelo [Univ. of Rome Tor Vergata (Italy)

2015-09-01

The U. S. NRC is currently proposing rulemaking designated as “10 CFR 50.46c” to revise the loss-of-coolant-accident (LOCA)/emergency core cooling system (ECCS) acceptance criteria to include the effects of higher burnup on cladding performance as well as to address other technical issues. The NRC is also currently resolving the public comments with the final rule expected to be issued in April 2016. The impact of the final 50.46c rule on the industry may involve updating of fuel vendor LOCA evaluation models, NRC review and approval, and licensee submittal of new LOCA evaluations or re-analyses and associated technical specification revisions for NRC review and approval. The rule implementation process, both industry and NRC activities, is expected to take 4-6 years following the rule effective date. As motivated by the new rule, the need to use advanced cladding designs may be a result. A loss of operational margin may result due to the more restrictive cladding embrittlement criteria. Initial and future compliance with the rule may significantly increase vendor workload and licensee cost as a spectrum of fuel rod initial burnup states may need to be analyzed to demonstrate compliance. Consequently, there will be an increased focus on licensee decision making related to LOCA analysis to minimize cost and impact, and to manage margin. The proposed rule would apply to a light water reactor and to all cladding types.

TRU waste certification and TRUPACT-2 payload verification

International Nuclear Information System (INIS)

Hunter, E.K.; Johnson, J.E.

1990-01-01

The Waste Isolation Pilot Plant (WIPP) established a policy that requires each waste shipper to verify that all waste shipments meet the requirements of the Waste Acceptance Criteria (WAC) prior to being shipped. This verification provides assurance that transuranic (TRU) wastes meet the criteria while still retained in a facility where discrepancies can be immediately corrected. Each Department of Energy (DOE) TRU waste facility planning to ship waste to the Waste Isolation Pilot Plant (WIPP) is required to develop and implement a specific program including Quality Assurance (QA) provisions to verify that waste is in full compliance with WIPP's WAC. This program is audited by a composite DOE and contractor audit team prior to granting the facility permission to certify waste. During interaction with the Nuclear Regulatory Commission (NRC) on payload verification for shipping in TRUPACT-II, a similar system was established by DOE. The TRUPACT-II Safety Analysis Report (SAR) contains the technical requirements and physical and chemical limits that payloads must meet (like the WAC). All shippers must plan and implement a payload control program including independent QA provisions. A similar composite audit team will conduct preshipment audits, frequent subsequent audits, and operations inspections to verify that all TRU waste shipments in TRUPACT-II meet the requirements of the Certificate of Compliance issued by the NRC which invokes the SAR requirements. 1 fig

Acceptance criteria for the physical protection upgrade rule requirements for fixed sites. Information guide

International Nuclear Information System (INIS)

Dwyer, P.

1980-09-01

This document has been developed as a tool to assist in providing consistent evaluation of upgraded physical security plans submitted in response to the Physical Protection Upgrade Rule, effective March 25, 1980. It presents a means for assuring licensee compliance with every regulatory requirement of particular significance to the protection of the public health and safety. Acceptance criteria are included to determine the extent to which each licensee meets the regulatory requirements. The format parallels Regulatory Guide 5.52, Standard Format and Content of a Licensee Physical Protection Plan for Strategic Special Nuclear Material at Fixed Sites

TRU waste certification and TRUPACT-II payload verification

International Nuclear Information System (INIS)

Hunter, E.K.; Johnson, J.E.

1990-01-01

The Waste Isolation Pilot Plant (WIPP) established a policy (subsequently confirmed and required by DOE Order 5820.2A, Radioactive Waste Management, September 1988) that requires each waste shipper to verify that all waste shipments meet the requirements of the Waste Acceptance Criteria (WAC) prior to being shipped. This verification provides assurance that transuranic (TRU) wastes meet the criteria while still retained in a facility where discrepancies can be immediately corrected. In this manner, problems that would arise if WAC violations were discovered at the receiver, where corrective facilities are not available, are avoided. Each Department of Energy (DOE) TRU waste facility planning to ship waste to the Waste Isolation Pilot Plant (WIPP) is required to develop and implement a specific program including Quality Assurance (QA) provisions to verify that waste is in full compliance with WIPP's WAC. This program is audited by a composite DOE and contractor audit team prior to granting the facility permission to certify waste. During interaction with the Nuclear Regulatory Commission (NRC) on payload verification for shipping in TRUPACT-II, a similar system was established by DOE. The TRUPACT-II Safety Analysis Report (SAR) contains the technical requirements and physical and chemical limits that payloads must meet (like the WAC). All shippers must plan and implement a payload control program including independent QA provisions. A similar composite audit team will conduct preshipment audits, frequent subsequent audits, and operations inspections to verify that all TRU waste shipments in TRUPACT-II meet the requirements of the Certificate of Compliance (C of C) issued by the NRC which invokes the SAR requirements. 1 fig

How to Create High-Impact Writing Assignments That Enhance Learning and Development and Reinvigorate WAC/WID Programs: What Almost 72,000 Undergraduates Taught Us

Science.gov (United States)

Anderson, Paul; Anson, Chris M.; Gonyea, Robert M.; Paine, Charles

2016-01-01

This article reports on a study that suggests ways that Writing Across the Curriculum/Writing in the Disciplines (WAC/WID) programs can increase the effectiveness of their efforts, including implementation of writingintensive courses, which are one of the Association of American Colleges and Universities' High-Impact Educational Practices. The…

Flaw acceptance criteria taking into consideration the NDT: radiographic and ultrasonic testing. Analysis through the fracture mechanics methods

International Nuclear Information System (INIS)

Capurro, E.; Alicino, F.; Corvi, A.

1993-01-01

The present study compares and evaluates the flaw acceptance criteria of the non-destructive inspections meeting European Community standards, through the application of the fracture mechanics methods that were determined and verified by the previous activity. Some choices were made; these, however, do not change the general validity of the conclusions. Shaved full-penetration butt welds of Class 1 components making up the primary circuit were considered and the following parameters varied: standards: French, German, Italian (ASME III) and UK; material: AISI 316 and low alloy steel A 533; base material and weld metal; temperature: RT, 370 deg C for the austenitic and 260 deg C for the ferritic steel; ultrasonic and radiographic methods; defect position: surface and internal; stress condition: situations with different primary and secondary stresses. From a preliminary examination of this study it is evident that the large quantity of results available and the abundance of information contained therein make a simple and exhaustive synthesis difficult. In fact, different analyses are possible and we have, therefore, limited the research to activities to perform a comparison and a general evaluation of the acceptance criteria of the non-destructive testing. (authors). 57 refs., 25 figs., 11 tabs

Transmittal of the Calculation Package that Supports the Analysis of Performance of the Environmental Management Waste Management Facility Oak Ridge, Tennessee (Based 5-Cell Design Issued 8/14/09)

Energy Technology Data Exchange (ETDEWEB)

Williams M.J.

2009-09-14

This document presents the results of an assessment of the performance of a build-out of the Environmental Management Waste Management Facility (EMWMF). The EMWMF configuration that was assessed includes the as-constructed Cells 1 through 4, with a groundwater underdrain that was installed beneath Cell 3 during the winter of 2003-2004, and Cell 5, whose proposed design is an Addendum to Remedial Design Report for the Disposal of Oak Ridge Reservation Comprehensive Environmental Response, Compensation, and Liability Act of 1980 Waste, Oak Ridge, Tennessee, DOE/OR/01-1873&D2/A5/R1. The total capacity of the EMWMF with 5 cells is about 1.7 million cubic yards. This assessment was conducted to determine the conditions under which the approved Waste Acceptance Criteria (WAC) for the EMWMF found in the Attainment Plan for Risk/Toxicity-Based Waste Acceptance Criteria at the Oak Ridge Reservation, Oak Ridge, Tennessee [U.S. Department of Energy (DOE) 2001a], as revised for constituents added up to October 2008, would remain protective of public health and safety for a five-cell disposal facility. For consistency, the methods of analyses and the exposure scenario used to predict the performance of a five-cell disposal facility were identical to those used in the Remedial Investigation and Feasibility Study (RI/FS) and its addendum (DOE 1998a, DOE 1998b) to develop the approved WAC. To take advantage of new information and design changes departing from the conceptual design, the modeling domain and model calibration were upaded from those used in the RI/FS and its addendum. It should be noted that this analysis is not intended to justify or propose a change in the approved WAC.

Athabasca Chipewyan First Nation inquiry : report on WAC Bennett Dam and damage to Indian Reserve no. 201 claim

International Nuclear Information System (INIS)

1998-03-01

Aspects of a claim regarding the WAC Bennett Dam in British Columbia and damage to Indian Reserve 201 are discussed. An inquiry was held to determine whether the Crown owes an outstanding obligation to the Athabasca Chipewyan First Nation regarding damages sustained on their reserve as a result of the construction and operation of the dam. The claim alleges that the drying out of the Peace-Athabasca Delta severely affected the First Nation's treaty rights to hunt, trap and fish for food in the area. It was noted that the dam was constructed in the early 1960s before the establishment of mandatory environmental assessment procedures which are in place today to ensure that projects comply with certain safeguards and minimum standards. In 1971, the Peace-Athabasca Delta Project Group (PADPG) was established to review and to assess the environmental damage caused by the dam. The group was also advised to implement a strategy to mitigate the ongoing environmental deterioration in the Delta. It was concluded that Canada breached its statutory and fiduciary obligations to the Athabasca Chipewyan First nation by failing to take reasonable measures to prevent, to mitigate, or to seek compensation for unjustified infringement on its treaty rights and for environmental damages to IR 201. In this report the Commission recommends that the claim by the Athabasca Chipewyan First Nation be accepted for negotiation under Canada's specific claims policy. figs

2727-S Nonradioactive Dangerous Waste Storage Facility clean closure evaluation report

International Nuclear Information System (INIS)

Luke, S.N.

1994-01-01

This report presents the analytical results of 2727-S NRDWS facility closure verification soil sampling and compares these results to clean closure criteria. The results of this comparison will determine if clean closure of the unit is regulatorily achievable. This report also serves to notify regulators that concentrations of some analytes at the site exceed sitewide background threshold levels (DOE-RL 1993b) and/or the limits of quantitation (LOQ). This report also presents a Model Toxics Control Act Cleanup (MTCA) (WAC 173-340) regulation health-based closure standard under which the unit can clean close in lieu of closure to background levels or LOQ in accordance with WAC 173-303-610. The health-based clean closure standard will be closure to MTCA Method B residential cleanup levels. This report reconciles all analyte concentrations reported above background or LOQ to this health-based cleanup standard. Regulator acceptance of the findings presented in this report will qualify the TSD unit for clean closure in accordance with WAC 173-303-610 without further TSD unit soil sampling, or soil removal and/or decontamination. Nondetected analytes require no further evaluation

Westinghouse Hanford Company plan for certifying newly generated contact-handled transuranic waste for emplacement in the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Lipinski, R.M.; Sheehan, J.S.

1992-07-01

Westinghouse Hanford Company (Westinghouse Hanford) currently manages an interim storage site for Westinghouse Hanford and non-Westinghouse Hanford-generated transuranic (TRU) waste and operates TRU waste generating facilities within the Hanford Site in Washington State. Approval has been received from the Waste Acceptance Criteria Certification Committee (WACCC) and Westinghouse Hanford TRU waste generating facilities to certify newly generated contact-handled TRU (CH-TRU) solid waste to meet the Waste Acceptance Criteria (WAC). This document describes the plan for certifying newly generated CH-TRU solid waste to meet the WAC requirements for storage at the Waste Isolation Pilot Plant (WIPP) site. Attached to this document are facility-specific certification plans for the Westinghouse Hanford TRU waste generators that have received WACCC approval. The certification plans describe operations that generate CH-TRU solid waste and the specific procedures by which these wastes will be certified and segregated from uncertified wastes at the generating facilities. All newly generated CH-TRU solid waste is being transferred to the Transuranic Storage and Assay Facility (TRUSAF) and/or a controlled storage facility. These facilities will store the waste until the certified TRU waste can be sent to the WIPP site and the non-certified TRU waste can be sent to the Waste Receiving and Processing Facility. All non-certifiable TRU waste will be segregated and clearly identified

Documentation of acceptable knowledge for LANL Plutonium Facility transuranic waste streams

International Nuclear Information System (INIS)

Montoya, A.J.; Gruetzmacher, K.; Foxx, C.; Rogers, P.S.Z.

1998-01-01

Characterization of transuranic waste from the LANL Plutonium Facility for certification and transportation to WIPP includes the use of acceptable knowledge as specified in the WIPP Quality Assurance Program Plan. In accordance with a site-specific procedure, documentation of acceptable knowledge for retrievably stored and currently generated transuranic waste streams is in progress at LANL. A summary overview of the transuranic waste inventory is complete and documented in the Sampling Plan. This document also includes projected waste generation, facility missions, waste generation processes, flow diagrams, times, and material inputs. The second part of acceptable knowledge documentation consists of assembling more detailed acceptable knowledge information into auditable records and is expected to require several years to complete. These records for each waste stream must support final assignment of waste matrix parameters, EPA hazardous waste numbers, and radionuclide characterization. They must also include a determination whether waste streams are defense waste streams for compliance with the WIPP Land Withdrawal Act. The LANL Plutonium Facility's mission is primarily plutonium processing in basic special nuclear material (SNM) research activities to support national defense and energy programs. It currently has about 100 processes ranging from SNM recovery from residues to development of plutonium 238 heat sources for space applications. Its challenge is to characterize and certify waste streams from such diverse and dynamic operations using acceptable knowledge. This paper reports the progress on the certification of the first of these waste streams to the WIPP WAC

Towards the development of workable acceptance criteria for the divertor CFC monoblock armour

Energy Technology Data Exchange (ETDEWEB)

D' Agata, E. [ITER International Team, ITER Joint Work Site, Boltzmannstr. 2, D-85748 Garching (Germany)]. E-mail: dagatae@itereu.de; Tivey, R. [ITER International Team, ITER Joint Work Site, Boltzmannstr. 2, D-85748 Garching (Germany)

2005-11-15

The plasma-facing components (PFCs) of the ITER divertor will be subjected to high heat flux (HHF). Carbon-fibre composite (CFC) is selected as the armour for the region of highest heat flux where the scrape-off layer of the plasma intercepts the vertical targets (VT). Failure of the armour to heat sink joints will compromise the performance of the divertor and could ultimately result in its failure and the shut down of the ITER machine. There are tens of thousands of CFCs to CuCrZr joints. The aim of the PFC design is to ensure that the divertor can continue to function even with the failure of a few joints. In preparation for writing the procurement specification for the ITER vertical target PFCs, a programme of work is underway with the objective of defining workable acceptance criteria for the PFC armour joints.

Towards the development of workable acceptance criteria for the divertor CFC monoblock armour

International Nuclear Information System (INIS)

D'Agata, E.; Tivey, R.

2005-01-01

The plasma-facing components (PFCs) of the ITER divertor will be subjected to high heat flux (HHF). Carbon-fibre composite (CFC) is selected as the armour for the region of highest heat flux where the scrape-off layer of the plasma intercepts the vertical targets (VT). Failure of the armour to heat sink joints will compromise the performance of the divertor and could ultimately result in its failure and the shut down of the ITER machine. There are tens of thousands of CFCs to CuCrZr joints. The aim of the PFC design is to ensure that the divertor can continue to function even with the failure of a few joints. In preparation for writing the procurement specification for the ITER vertical target PFCs, a programme of work is underway with the objective of defining workable acceptance criteria for the PFC armour joints

Selecting the Acceptance Criteria of Medicines in the Reimbursement List of Public Health Insurance of Iran, Using the "Borda" Method: a Pilot Study.

Science.gov (United States)

Viyanchi, Amir; Rasekh, Hamid Reza; Rajabzadeh Ghatari, Ali; SafiKhani, Hamid Reza

2015-01-01

Decision-making for medicines to be accepted in Iran's public health insurance reimbursement list is a complex process and involves factors, which should be considered in applying a coverage for medicine costs. These processes and factors are not wholly assessed, while assessment of these factors is an essential need for getting a transparent and evidence-based approach toward medicine reimbursement in Iran. This paper aims to show an evidence-based approach toward medicine selection criteria to inform the medical reimbursement decision makers in Iranian health insurance organizations. To explore an adaptable decision-making framework while incorporating a method called "Borda" in medicine reimbursement assessment, we used the help of an expert group including decision makers and clinical researchers who are also policy makers to appraise the five chief criteria that have three sub criteria (Precision, Interpretability, and Cost). Also software "Math-lab"7, "SPSS" 17 and Excel 2007 were used in this study. "Borda" estimates the amount of perceived values from different criteria and creates a range from one to five while providing a comprehensive measurement of a large spectrum of criteria. Participants reported that the framework provided an efficient approach to systematic consideration in a pragmatic format consisting of many parts to guide decision-makings, including criteria and value (a model with the core of Borda) and evidences (medicine reimbursement based on criteria). The most important criterion for medicine acceptance in health insurance companies, in Iran, is the "life-threatening" factor and "evidence quality" is accounted as the fifth important factor. This pilot study showed the usefulness of incorporating Borda in medicine reimbursement decisions to support a transparent and systematic appraisal of health insurance companies' deeds. Further research is needed to advance Borda-based approaches that are effective on health insurance decision making.

TRU Waste Sampling Program: Volume I. Waste characterization

International Nuclear Information System (INIS)

Clements, T.L. Jr.; Kudera, D.E.

1985-09-01

Volume I of the TRU Waste Sampling Program report presents the waste characterization information obtained from sampling and characterizing various aged transuranic waste retrieved from storage at the Idaho National Engineering Laboratory and the Los Alamos National Laboratory. The data contained in this report include the results of gas sampling and gas generation, radiographic examinations, waste visual examination results, and waste compliance with the Waste Isolation Pilot Plant-Waste Acceptance Criteria (WIPP-WAC). A separate report, Volume II, contains data from the gas generation studies

Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal. Results of a Coordinated Research Project

International Nuclear Information System (INIS)

2016-05-01

Graphite is widely used in the nuclear industry and in research facilities and this has led to increasing amounts of irradiated graphite residing in temporary storage facilities pending disposal. This publication arises from a coordinated research project (CRP) on the processing of irradiated graphite to meet acceptance criteria for waste disposal. It presents the findings of the CRP, the general conclusions and recommendations. The topics covered include, graphite management issues, characterization of irradiated graphite, processing and treatment, immobilization and disposal. Included on the attached CD-ROM are formal reports from the participants

Nevada Test Site waste acceptance criteria [Revision 1

Energy Technology Data Exchange (ETDEWEB)

None

1997-08-01

Revision one updates the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document.

Nevada Test Site waste acceptance criteria [Revision 1

International Nuclear Information System (INIS)

None

1997-01-01

Revision one updates the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document

Data Quality Objectives Process for Designation of K-Basins Debris

International Nuclear Information System (INIS)

WESTCOTT, J.L.

2000-01-01

The U.S. Department of Energy has developed a schedule and approach for the removal of spent fuels, sludge, and debris from the K East (KE) and K West (KW) Basins, located in the 100 Area at the Hanford Site. The project that is the subject of this data quality objective (DQO) process is focused on the removal of debris from the K Basins and onsite disposal of the debris at the Environmental Restoration Disposal Facility (ERDF). This material previously has been dispositioned at the Hanford Low-Level Burial Grounds (LLBGs) or Central Waste Complex (CWC). The goal of this DQO process and the resulting Sampling and Analysis Plan (SAP) is to provide the strategy for characterizing and designating the K-Basin debris to determine if it meets the Environmental Restoration Disposal Facility Waste Acceptance Criteria (WAC), Revision 3 (BHI 1998). A critical part of the DQO process is to agree on regulatory and WAC interpretation, to support preparation of the DQO workbook and SAP

Mixed waste certification plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility. Revision 1

International Nuclear Information System (INIS)

1995-01-01

The purpose of this plan is to describe the organization and methodology for the certification of mixed waste handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan is composed to meet the requirements found in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and follows the suggested outline provided by WHC in the letter of April 26, 1990, to Dr. R.H. Thomas, Occupational Health Division, LBL. Mixed waste is to be transferred to the WHC Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington

Waste certification program plan for Oak Ridge National Laboratory. Revision 2

International Nuclear Information System (INIS)

1997-09-01

This document defines the waste certification program (WCP) developed for implementation at Oak Ridge National Laboratory (ORNL). The document describes the program structure, logic, and methodology for certification of ORNL wastes. The purpose of the WCP is to provide assurance that wastes are properly characterized and that the Waste Acceptance Criteria (WAC) for receiving facilities are met. The program meets the waste certification requirements for mixed (both radioactive and hazardous) and hazardous ncluding polychlorinated biphenyls (PCB) waste. Program activities will be conducted according to ORNL Level 1 document requirements

Special Analysis for the Disposal of the Neutron Products Incorporated Sealed Source Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

Energy Technology Data Exchange (ETDEWEB)

None, None

2014-08-31

The purpose of this special analysis (SA) is to determine if the Neutron Products Incorporated (NPI) Sealed Sources waste stream (DRTK000000056, Revision 0) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The NPI Sealed Sources waste stream consists of 850 60Co sealed sources (Duratek [DRTK] 2013). The NPI Sealed Sources waste stream requires a special analysis (SA) because the waste stream 60Co activity concentration exceeds the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

Functional design criteria for FY 1993-2000 groundwater monitoring wells

International Nuclear Information System (INIS)

Williams, B.A.

1996-01-01

The purpose of this revision is to update the Line Item Project, 93-L-GFW-152 Functional Design Criteria (FDC) to reflect changes approved in change control M-24-91-6, Engineering Change Notices (ECNs), and expand the scope to include subsurface investigations along with the borehole drilling. This revision improves the ability and effectiveness of maintaining RCRA and Operational groundwater compliance by combining borehole and well drilling with subsurface data gathering objectives. The total projected number of wells to be installed under this project has decreased from 200 and the scope has been broadened to include additional subsurface investigation activities that usually occur simultaneously with most traditional borehole drilling and monitoring well installations. This includes borehole hydrogeologic characterization activities, and vadose monitoring. These activities are required under RCRA 40 CFR 264 and 265 and WAC 173-303 for site characterization, groundwater and vadose assessment and well placement

Derivation of quantitative acceptance criteria for disposal of radioactive waste to near surface facilities: Development and implementation of an approach for the post-closure phase

International Nuclear Information System (INIS)

Torres, C.

2000-01-01

The International Atomic Energy Agency has established a project to develop and illustrate, through practical examples, an approach that allows the derivation of quantitative waste acceptance criteria for near surface disposal of radioactive waste. The first phase focussed on the derivation of example post-closure safety waste acceptance criteria through the use of a safety assessment approach that allows for the derivation of values in a clear and well documented manner. The approach consists of five steps: the specification of the assessment context; the description of the disposal system; the development and justification of scenarios; the formulation and implementation of models; and the calculation and derivation of example values. The approach has been successfully used to derive activity values for the disposal of radioactive waste to illustrative near surface facilities. (author)

Acceptance criteria considerations for miscellaneous wastes

International Nuclear Information System (INIS)

Irvine, A.R.; Forsberg, C.W.

1987-01-01

EPA standards set forth limitations regarding releases to the accessible environment adjacent to a geologic repository. The NRC criteria pertaining to waste form and engineered barrier performance place certain restrictions on the physical and chemical nature of the waste form and require substantially complete confinement of radioactivity until the high-heat-production period is past. After this period, the annual release of radionuclides from the waste package is normally limited to 1 part in 100,000 of the amounts calculated to be present at 1000-y decay. The regulation permits deviation from these criteria in exceptional circumstances. One such circumstance might be the absence of a significant perturbation in temperature around the stored waste. The lack of significant heat release will eliminate the hydrologic driving force for dispersal of radionuclides. Exceptional circumstances which potentially could justify a less stringent long-term release criterion are: small quantity of radioactivity, the nature of the radioactive species, and the nature of the geology in which the waste is to be emplaced. Because the MW after a suitable decay period have low heat release rates per unit volume, they apparently could be so emplaced in a repository that there would be no compelling need, according to the reasoning presented in 10 CFR 60, for a 1000-y container. Regarding attainment of the specified long-term release rate criterion, neither the solubility limits for the various waste forms nor the conductance of potential migration barriers are currently adequately characterized. The relatively small total heat generation rate for the MW in combination with the usual low volumetric heat generation rate apparently will allow application of migration barriers in a low temperature environment where barrier performance would be expected to be unchanged with time

Documentation of acceptable knowledge for Los Alamos National Laboratory Plutonium Facility TRU waste stream

International Nuclear Information System (INIS)

Montoya, A.J.; Gruetzmacher, K.M.; Foxx, C.L.; Rogers, P.Z.

1998-03-01

Characterization of transuranic waste from the LANL Plutonium Facility for certification and transportation to WIPP includes the use of acceptable knowledge as specified in the WIPP Quality Assurance Program Plan. In accordance with a site specific procedure, documentation of acceptable knowledge for retrievably stored and currently generated transuranic waste streams is in progress at LANL. A summary overview of the TRU waste inventory is complete and documented in the Sampling Plan. This document also includes projected waste generation, facility missions, waste generation processes, flow diagrams, times, and material inputs. The second part of acceptable knowledge documentation consists of assembling more detailed acceptable knowledge information into auditable records and is expected to require several years to complete. These records for each waste stream must support final assignment of waste matrix parameters, EPA hazardous waste numbers, and radionuclide characterization. They must also include a determination whether waste streams are defense waste streams for compliance with the WIPP Land Withdrawal Act. The LANL Plutonium Facility's mission is primarily plutonium processing in basic special nuclear material (SNM) research activities to support national defense and energy programs. It currently has about 100 processes ranging from SNM recovery from residues to development of plutonium 238 heat sources for space applications. Its challenge is to characterize and certify waste streams from such diverse and dynamic operations using acceptable knowledge. This paper reports the progress on the certification of the first of these waste streams to the WIPP WAC

Recommendations for Glass Durability Test Criteria

International Nuclear Information System (INIS)

Strachan, D.M.

1999-01-01

The objective of this short report is to define a set of activities that should lead to a specification for a test that can be used as one of the acceptance criteria and as an indicator of acceptable long-term behavior in contact with water. Since the glass composition is not yet defined and is likely to change as the composition of the waste changes, a strategy for developing criteria for what is acceptable involves a series of tests and modeling activities. The results of these activities lead to a criterion for an acceptable product and the data that are needed to reliably determine the behavior of the glass in the storage environment

DOE natural phenomenal hazards design and evaluation criteria

International Nuclear Information System (INIS)

Murray, R.C.; Nelson, T.A.; Short, S.A.; Kennedy, R.P.; Chander, H.; Hill, J.R.; Kimball, J.K.

1994-10-01

It is the policy of the Department of Energy (DOE) to design, construct, and operate DOE facilities so that workers, the general public, and the environment are protected from the impacts of natural phenomena hazards (NPH). Furthermore, DOE has established explicit goals of acceptable risk for NPH performance. As a result, natural phenomena hazard (earthquake, extreme wind, and flood) design and evaluation criteria for DOE facilities have been developed based on target probabilistic performance goals. These criteria include selection of design/evaluation NPH input from probabilistic hazard curves combined with commonly practiced deterministic response evaluation methods and acceptance criteria with controlled levels of conservatism. For earthquake considerations, conservatism is intentionally introduced in specification of material strengths and capacities, in the allowance of limited inelastic behavior, and by a seismic scale factor. Criteria have been developed following a graded approach for several performance goals ranging from that appropriate for normal-use facilities to that appropriate for facilities involving hazardous or critical operations. Performance goals are comprised of qualitative expressions of acceptable behavior and of target quantitative probabilities that acceptable limits of behavior are maintained. The criteria are simple procedures but have a rigorous basis. This paper addresses DOE seismic design and evaluation criteria

Acceptance criteria for non-destructive examination of double-shell tanks

International Nuclear Information System (INIS)

Jensen, C.E.

1995-09-01

This supporting document provides requirements for acceptance of relevant indications found during non-destructive examination of double-shell tanks (DSTs) at Hanford 200 areas. Requirements for evaluation of relevant indications are provided to determine acceptability of continued safe operation of the DSTs. Areas of the DSTs considered include the tank wall vapor space, liquid-vapor interface, wetted tank wall, sludge-liquid interface, and the knuckle region

Ammunition Peculiar Equipment (APE) 1995, NIR Propellant Analyzer, to MIL-STD-398, Military Standard Shields, Operational for Ammunition Operations, Criteria for Design of and Tests for Acceptance

National Research Council Canada - National Science Library

2003-01-01

... (SJMAC-DEM) to test the Ammunition Peculiar Equipment (APE) 1995 NIR Propellant Analyzer, to MIL-STD-398, "Military Standard Shields, Operational for Ammunition Operations, Criteria for Design of and Tests for Acceptance...

Acceptance Probability (P a) Analysis for Process Validation Lifecycle Stages.

Science.gov (United States)

Alsmeyer, Daniel; Pazhayattil, Ajay; Chen, Shu; Munaretto, Francesco; Hye, Maksuda; Sanghvi, Pradeep

2016-04-01

This paper introduces an innovative statistical approach towards understanding how variation impacts the acceptance criteria of quality attributes. Because of more complex stage-wise acceptance criteria, traditional process capability measures are inadequate for general application in the pharmaceutical industry. The probability of acceptance concept provides a clear measure, derived from specific acceptance criteria for each quality attribute. In line with the 2011 FDA Guidance, this approach systematically evaluates data and scientifically establishes evidence that a process is capable of consistently delivering quality product. The probability of acceptance provides a direct and readily understandable indication of product risk. As with traditional capability indices, the acceptance probability approach assumes that underlying data distributions are normal. The computational solutions for dosage uniformity and dissolution acceptance criteria are readily applicable. For dosage uniformity, the expected AV range may be determined using the s lo and s hi values along with the worst case estimates of the mean. This approach permits a risk-based assessment of future batch performance of the critical quality attributes. The concept is also readily applicable to sterile/non sterile liquid dose products. Quality attributes such as deliverable volume and assay per spray have stage-wise acceptance that can be converted into an acceptance probability. Accepted statistical guidelines indicate processes with C pk > 1.33 as performing well within statistical control and those with C pk  1.33 is associated with a centered process that will statistically produce less than 63 defective units per million. This is equivalent to an acceptance probability of >99.99%.

Low-level waste certification plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility. Revision 1

International Nuclear Information System (INIS)

1995-01-01

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan is composed to meet the requirements found in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and follows the suggested outline provided by WHC in the letter of April 26, 1990, to Dr. R.H. Thomas, Occupational Health Division, LBL. LLW is to be transferred to the WHC Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington

Low-level waste certification plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility. Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-10

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan is composed to meet the requirements found in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and follows the suggested outline provided by WHC in the letter of April 26, 1990, to Dr. R.H. Thomas, Occupational Health Division, LBL. LLW is to be transferred to the WHC Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington.

Development of comprehensive waste acceptance criteria for commercial nuclear waste

International Nuclear Information System (INIS)

O'Hara, F.A.; Miller, N.E.; Ausmus, B.S.; Yates, K.R.; Means, J.L.; Christensen, R.N.; Kulacki, F.A.

1979-01-01

A detailed methodology is presented for the identification of the characteristics of commercial nuclear waste which may require criteria. This methodology is analyzed as a six-step process which begins with identification of waste operations and proceeds until the waste characteristics affecting the potential release of radionuclides are determined. All waste types and operations were analyzed using the methodology presented. Several illustrative example are included. It is found that thirty-three characteristics can be identified as possibly requiring criteria

Are regulation-driven performance criteria still acceptable? - The German point of view.

Science.gov (United States)

Orth, Matthias

2015-05-01

Performance criteria should be a challenge for the laboratories to improve their quality. In countries with mandatory proficiency testing, the definition of performance criteria is a particular issue. If the definition of performance criteria is mandated from the regulatory bodies to medico-scientific institutions, scientific approaches (i.e., based on biological variation), the state-of-the-art approach (i.e., based on technical feasibility) as well as medical needs can be used to set up performance criteria such as the Richtlinie der Bundesärztekammer (RiliBÄK; Guideline of the German Medical Association on Quality Assurance in Medical Laboratory Examinations) in Germany. The experiences with RiliBÄK show that these performance criteria have to be revised on an ongoing basis.

Sustainability and acceptance - new challenges for nuclear energy

International Nuclear Information System (INIS)

Lensa, W. von

2001-01-01

This paper discusses the concept of sustainability in relation to acceptance of nuclear energy. Acceptance is viewed in terms of public acceptance, industrial acceptance, and internal acceptance/consensus within the nuclear community. It addresses sustainability criteria, the need for innovation, and the different levels of acceptability. The mechanisms of risk perception are discussed along with the technological consequences from risk perception mechanisms leading to specific objections against nuclear energy. (author)

Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal. Results of a Coordinated Research Project. Companion CD-ROM

International Nuclear Information System (INIS)

2016-05-01

Graphite is widely used in the nuclear industry and in research facilities and this has led to increasing amounts of irradiated graphite residing in temporary storage facilities pending disposal. This publication arises from a coordinated research project (CRP) on the processing of irradiated graphite to meet acceptance criteria for waste disposal. It presents the findings of the CRP, the general conclusions and recommendations. The topics covered include, graphite management issues, characterization of irradiated graphite, processing and treatment, immobilization and disposal. Included on the attached CD-ROM are formal reports from the participants

Electricity supply between acceptance, acceptability and social compatibility; Energieversorgung zwischen Akzeptanz, Akzeptabilitaet und Sozialvertraeglichkeit

Energy Technology Data Exchange (ETDEWEB)

Schubert, Katharina; Koch, Marco K. [Bochum Univ. (Germany). Lehrstuhl Energiesysteme und Energiewirtschaft (LEE)

2012-11-01

Acceptance promotion is supposed to be an indispensable premise for a successful realization of an energy concept. The contribution identifies deficiencies of the energy policy, including intransparency, complexity of decision procedures, for instance in case of the so called energy transmission line extension acceleration law, that has caused irritation and anger in the public. The justification of acceptance promotion is questioned in connection with the German nuclear policy reversal following the Fukushima accident. A research program ''public acceptance of large-scale power plants for electricity generation'' is presented. The issues criteria and limits of acceptability are of main importance for this discussion.

From waste packages acceptance criteria to waste packages acceptance process at the Centre de l'Aube disposal facility

International Nuclear Information System (INIS)

Dutzer, M.

2003-01-01

The Centre de l'Aube disposal facility has now been operated for 10 years. At the end of 2001, about 124,000 m3 of low and intermediate level short lived waste packages, representing 180,000 packages, have been disposed, for a total capacity of 1,000,000 m3. The flow of waste packages is now between 12 and 15,000 m3 per year, that is one third of the flow that was taken into account for the design of the repository. It confirms the efforts by waste generators to minimise waste production. This flow represents 25 to 30,000 packages, 50% are conditioned into the compaction facility of the repository, so that 17,000 packages are disposed per year. 54 disposal vaults have been closed. In 1996-1999, the safety assessment of the repository have been reviewed, taking into account the experience of operation. This assessment was investigated by the regulatory body and, subsequently, a so-called 'definitive license' to operate was granted to ANDRA on September 2, 1999 with updated licensing requirements. Another review will be performed in 2004. To ensure a better consistency with the safety assessment of the facility, Andra issued new technical requirements for waste packages at the end of 2000. Discussions with waste generators also showed that the waste package acceptance process should be improved to provide a more precise definition of operational criteria to comply with in waste conditioning facilities. Consequently, a new approach has been implemented since 2000. (orig.)

Safety criteria for nuclear chemical plants

International Nuclear Information System (INIS)

Ball, P.W.; Curtis, L.M.

1983-01-01

Safety measures have always been required to limit the hazards due to accidental release of radioactive substances from nuclear power plants and chemical plants. The risk associated with the discharge of radioactive substances during normal operation has also to be kept acceptably low. BNFL (British Nuclear Fuels Ltd.) are developing risk criteria as targets for safe plant design and operation. The numerical values derived are compared with these criteria to see if plants are 'acceptably safe'. However, the criteria are not mandatory and may be exceeded if this can be justified. The risk assessments are subject to independent review and audit. The Nuclear Installations Inspectorate also has to pass the plants as safe. The assessment principles it uses are stated. The development of risk criteria for a multiplant site (nuclear chemical plants tend to be sited with many others which are related functionally) is discussed. This covers individual members of the general public, societal risks, risks to the workforce and external hazards. (U.K.)

Acceptance test procedure for Project W-280

International Nuclear Information System (INIS)

Stites, C.G.

1994-01-01

This Document is the Acceptance Test Procedure for 200 Area C and SY Tank Farm Lighting Upgrade. This Acceptance Test Procedure has been prepared to demonstrate that the Tank Farm Lighting Systems function correctly as required by project criteria and as intended by design

Simplified probabilistic approach to determine safety factors in deterministic flaw acceptance criteria

International Nuclear Information System (INIS)

Barthelet, B.; Ardillon, E.

1997-01-01

The flaw acceptance rules in nuclear components rely on deterministic criteria supposed to ensure the safe operating of plants. The interest of having a reliable method of evaluating the safety margins and the integrity of components led Electricite de France to launch a study to link safety factors with requested reliability. A simplified analytical probabilistic approach is developed to analyse the failure risk in Fracture Mechanics. Assuming lognormal distributions of the main random variables, it is possible considering a simple Linear Elastic Fracture Mechanics model, to determine the failure probability as a function of mean values and logarithmic standard deviations. The 'design' failure point can be analytically calculated. Partial safety factors on the main variables (stress, crack size, material toughness) are obtained in relation with reliability target values. The approach is generalized to elastic plastic Fracture Mechanics (piping) by fitting J as a power law function of stress, crack size and yield strength. The simplified approach is validated by detailed probabilistic computations with PROBAN computer program. Assuming reasonable coefficients of variations (logarithmic standard deviations), the method helps to calibrate safety factors for different components taking into account reliability target values in normal, emergency and faulted conditions. Statistical data for the mechanical properties of the main basic materials complement the study. The work involves laboratory results and manufacture data. The results of this study are discussed within a working group of the French in service inspection code RSE-M. (authors)

Proposed radiological protection criteria for waste disposal options

International Nuclear Information System (INIS)

Hill, M.D.

1981-01-01

Criteria which are based solely on the consequences of releases of radionuclides, that is doses to man, are inappropriate for decisions on the acceptability of many of the disposal options for solid wastes. The risks associated with disposal options in which the intention is to isolate wastes from the biosphere for any length of time have two major components: the probability that a release of radionuclides will occur and the probability that subsequent radiation doses will give rise to deleterious effects. It is therefore necessary to develop criteria which embody the basic radiological principle of keeping risks to acceptable levels and take account of both components of risk. In this paper proposed criteria are described and some of the implications of adopting these criteria are discussed. (author)

The use of economic criteria in providing a basis for safe reactor operation

International Nuclear Information System (INIS)

Graham, J.

1989-01-01

Probabilistic criteria based upon an acceptance measure of protection for owner investment can complete the range of design probabilistic criteria between those set by acceptance public safety and those set by acceptable reliability in plant operation. Criteria which address the protection of owner investment have the benefit of lowering risk in adjacent risk regions by providing greater reliability in operation as well as less risk to the safety of the public and the environment. Such investment protection criteria are currently being used to extend plant life but they could also be used very beneficially as part of the initial design process. In this paper trial criteria are suggested which address the risk of extended plant shutdown with the resultant necessity to purchase replacement power, and the risk of replacement of expensive plant components. Additional financial assessment is required to ensure that there is a proper correlation between acceptable measures of owner-investment protection and the levels of probabilistic defence suggested, but the trial criteria proposed can be used as important practical design criteria

NWTS program criteria for mined geologic disposal of nuclear waste: program objectives, functional requirements, and system performance criteria

International Nuclear Information System (INIS)

1981-04-01

At the present time, final repository criteria have not been issued by the responsible agencies. This document describes general objectives, requirements, and criteria that the DOE intends to apply in the interim to the National Waste Terminal Storage (NWTS) Program. These objectives, requirements, and criteria have been developed on the basis of DOE's analysis of what is needed to achieve the National objective of safe waste disposal in an environmentally acceptable and economic manner and are expected to be consistent with anticipated regulatory standards. The qualitative statements in this document address the broad issues of public and occupational health and safety, institutional acceptability, engineering feasibility, and economic considerations. A comprehensive set of criteria, general and project specific, of which these are a part, will constitute a portion of the technical basis for preparation and submittal by the DOE of formal documents to support future license applications for nuclear waste repositories

NWTS program criteria for mined geologic disposal of nuclear waste: program objectives, functional requirements, and system performance criteria

Energy Technology Data Exchange (ETDEWEB)

None

1981-04-01

At the present time, final repository criteria have not been issued by the responsible agencies. This document describes general objectives, requirements, and criteria that the DOE intends to apply in the interim to the National Waste Terminal Storage (NWTS) Program. These objectives, requirements, and criteria have been developed on the basis of DOE's analysis of what is needed to achieve the National objective of safe waste disposal in an environmentally acceptable and economic manner and are expected to be consistent with anticipated regulatory standards. The qualitative statements in this document address the broad issues of public and occupational health and safety, institutional acceptability, engineering feasibility, and economic considerations. A comprehensive set of criteria, general and project specific, of which these are a part, will constitute a portion of the technical basis for preparation and submittal by the DOE of formal documents to support future license applications for nuclear waste repositories.

Top-level regulatory criteria for the standard MHTGR

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-10-15

The Licensing Plan for the Standard MHTGR (Ref. 1) describes a program to support a U.S. Nuclear Regulatory Commission (NRC) design review and approval. The Plan calls for the submittal of Top-Level Regulatory Criteria to the NRC for concurrence with their completeness and acceptability for the MHTGR program. The Top-Level Regulatory Criteria are defined as the standards for judging licensability that directly specify acceptable limits for protection of the public health and safety and the environment. The criteria proposed herein are for normal plant operation and a broad spectrum of anticipated events, including accidents. The approach taken is to define a set of criteria which are general as opposed to being design specific. Specifically, it is recommended that criteria be met which: 1. Are less prescriptive than current regulation, thereby encouraging maximum flexibility in design approaches. 2. Are measurable. 3. Are not more strict than the criteria for current power plants.

Present state of the design and realization of regional radioactive waste depositories and waste acceptance criteria for disposal

International Nuclear Information System (INIS)

Kortus, J.

1988-01-01

Surface type regional depositories for radioactive wastes from nuclear power plants are described in detail. The depository of the Mochovce nuclear power plant is located near the plant, that of the Dukovany nuclear power plant is directly on the premises of the plant. Particular attention is paid to the design of the monolithic reinforced concrete pits, draining of rainwater from their surface, draining of seeping rainwater from the pit environment by means of a double drainage system, and insulation of the pits against water. The construction of the Mochovce depository started in 1987; some experience gained from this activity is presented. The radioactive waste acceptance criteria for depositories of this kind, based on safety analysis, are given. (author). 2 figs

Idaho National Engineering Laboratory code assessment of the Rocky Flats transuranic waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

This report is an assessment of the content codes associated with transuranic waste shipped from the Rocky Flats Plant in Golden, Colorado, to INEL. The primary objective of this document is to characterize and describe the transuranic wastes shipped to INEL from Rocky Flats by item description code (IDC). This information will aid INEL in determining if the waste meets the waste acceptance criteria (WAC) of the Waste Isolation Pilot Plant (WIPP). The waste covered by this content code assessment was shipped from Rocky Flats between 1985 and 1989. These years coincide with the dates for information available in the Rocky Flats Solid Waste Information Management System (SWIMS). The majority of waste shipped during this time was certified to the existing WIPP WAC. This waste is referred to as precertified waste. Reassessment of these precertified waste containers is necessary because of changes in the WIPP WAC. To accomplish this assessment, the analytical and process knowledge available on the various IDCs used at Rocky Flats were evaluated. Rocky Flats sources for this information include employee interviews, SWIMS, Transuranic Waste Certification Program, Transuranic Waste Inspection Procedure, Backlog Waste Baseline Books, WIPP Experimental Waste Characterization Program (headspace analysis), and other related documents, procedures, and programs. Summaries are provided of: (a) certification information, (b) waste description, (c) generation source, (d) recovery method, (e) waste packaging and handling information, (f) container preparation information, (g) assay information, (h) inspection information, (i) analytical data, and (j) RCRA characterization.

HEU Holdup Measurements on 321-M A-Lathe

International Nuclear Information System (INIS)

Dewberry, R.A.

2002-01-01

The Analytical Development Section of SRTC was requested by the Facilities Disposition Division (FDD) of the Savannah River Site to determine the holdup of enriched uranium in the 321-M facility as part of an overall deactivation project of the facility. The 321-M facility was used to fabricate enriched uranium fuel assemblies, lithium-aluminum target tubes, neptunium assemblies, and miscellaneous components for the production reactors. The results of the holdup assays are essential for determining compliance with the solid waste Waste Acceptance Criteria, Material Control and Accountability, and to meet criticality safety controls. Three measurement systems were used to determine highly enriched uranium (HEU) holdup. This report covers holdup measurements on the A-Lathe that was used to machine uranium-aluminum-alloy (U-Al). Our results indicated that the lathe contained more than the limits stated in the Waste Acceptance Criteria (WAC) for the solid waste E-Area Vaults. Thus the lathe was decontaminated three times and assayed four times in order to bring the amounts of uranium to an acceptable content. This report will discuss the methodology, Non-Destructive Assay (NDA) measurements, and results of the U-235 holdup on the lathe

Modeling Carbon Turnover in Five Terrestrial Ecosystems in the Boreal Zone Using Multiple Criteria of Acceptance

International Nuclear Information System (INIS)

Karlberg, Louise; Gustafsson, David; Jansson, Per-Erik

2006-01-01

Estimates of carbon fluxes and turnover in ecosystems are key elements in the understanding of climate change and in predicting the accumulation of trace elements in the biosphere. In this paper we present estimates of carbon fluxes and turnover times for five terrestrial ecosystems using a modeling approach. Multiple criteria of acceptance were used to parameterize the model, thus incorporating large amounts of multi-faceted empirical data in the simulations in a standardized manner. Mean turnover times of carbon were found to be rather similar between systems with a few exceptions, even though the size of both the pools and the fluxes varied substantially. Depending on the route of the carbon through the ecosystem, turnover times varied from less than one year to more than one hundred, which may be of importance when considering trace element transport and retention. The parameterization method was useful both in the estimation of unknown parameters, and to identify variability in carbon turnover in the selected ecosystems

Sediment quality criteria: A review with recommendations for developing criteria for the Hanford Site

Energy Technology Data Exchange (ETDEWEB)

Driver, C.J.

1994-05-01

Criteria for determining the quality of liver sediment are necessary to ensure that concentrations of contaminants in aquatic systems are within acceptable limits for the protection of aquatic and human life. Such criteria should facilitate decision-making about remediation, handling, and disposal of contaminants. Several approaches to the development of sediment quality criteria (SQC) have been described and include both descriptive and numerical methods. However, no single method measures all impacts at all times to all organisms (U.S. EPA 1992b). The U.S. EPA`s interest is primarily in establishing chemically based, numerical SQC that are applicable nation-wide (Shea 1988). Of the approaches proposed for SQC development, only three are being considered for numerical SQC on a national level. These approaches include an Equilibrium Partitioning Approach, a site-specific method using bioassays (the Apparent Effects Threshold Approach), and an approach similar to EPA`s water quality criteria (Pavlou and Weston 1984). Although national (or even regional) criteria address a number of political, litigative, and engineering needs, some researchers feel that protection of benthic communities require site-specific, biologically based criteria (Baudo et al. 1990). This is particularly true for areas where complex mixtures of contaminants are present in sediments. Other scientifically valid and accepted procedures for freshwater SQC include a background concentration approach, methods using field or spiked bioassays, a screening level concentration approach, the Apparent Effects Threshold Approach, the Sediment Quality Triad, the International Joint Commission Sediment Assessment Strategy, and the National Status and Trends Program Approach. The various sediment assessment approaches are evaluated for application to the Hanford Reach and recommendations for Hanford Site sediment quality criteria are discussed.

Early Site Permit Demonstration Program: Regulatory criteria evaluation report

International Nuclear Information System (INIS)

1993-03-01

The primary objective of the Early Site Plan Demonstration Program (ESPDP) is to demonstrate successfully the use of 10CFR52 to obtain ESPs for one or more US sites for one (or more) ALWR nuclear power plants. It is anticipated that preparation of the ESP application and interaction with NRC during the application review process will result not only in an ESP for the applicant(s) but also in the development of criteria and definition of processes, setting the precedent that facilitates ESPs for subsequent ESP applications. Because siting regulatory processes and acceptance criteria are contained in over 100 separate documents, comprehensive licensing and technical reviews were performed to establish whether the requirements and documentation are self-consistent, whether the acceptance criteria are sufficiently well-defined and clear, and whether the licensing process leading to the issuance of an ESP is unambiguously specified. This document provides appendices A and B of this report. Appendix A contains a list of regulations, regulatory guidance, and acceptance criteria; Appendix B contains a cross-reference index of siting-related documentation

Crew Transportation Technical Standards and Design Evaluation Criteria

Science.gov (United States)

Lueders, Kathryn L.; Thomas, Rayelle E. (Compiler)

2015-01-01

Crew Transportation Technical Standards and Design Evaluation Criteria contains descriptions of technical, safety, and crew health medical processes and specifications, and the criteria which will be used to evaluate the acceptability of the Commercial Providers' proposed processes and specifications.

Risk based seismic design criteria

International Nuclear Information System (INIS)

Kennedy, R.P.

1999-01-01

In order to develop a risk based seismic design criteria the following four issues must be addressed: (1) What target annual probability of seismic induced unacceptable performance is acceptable? (2) What minimum seismic margin is acceptable? (3) Given the decisions made under Issues 1 and 2, at what annual frequency of exceedance should the safe-shutdown-earthquake (SSE) ground motion be defined? (4) What seismic design criteria should be established to reasonably achieve the seismic margin defined under Issue 2? The first issue is purely a policy decision and is not addressed in this paper. Each of the other three issues are addressed. Issues 2 and 3 are integrally tied together so that a very large number of possible combinations of responses to these two issues can be used to achieve the target goal defined under Issue 1. Section 2 lays out a combined approach to these two issues and presents three potentially attractive combined resolutions of these two issues which reasonably achieves the target goal. The remainder of the paper discusses an approach which can be used to develop seismic design criteria aimed at achieving the desired seismic margin defined in resolution of Issue 2. Suggestions for revising existing seismic design criteria to more consistently achieve the desired seismic margin are presented. (orig.)

Experimental activity on the definition of acceptance criteria for the ITER divertor plasma facing components

International Nuclear Information System (INIS)

Escourbiac, F.; Constans, S.; Vignal, N.; Cantone, V.; Richou, M.; Durocher, A.; Riccardi, B.; Bobin, I.; Jouvelot, J.L.; Merola, M.

2009-01-01

Tens of thousands of armor/heat sink joints will be produced by the industry during the manufacturing of ITER divertor PFC, statistically, there is a probability that joints with defects be delivered. The purpose of this paper is to study the detection and evolution during operation of calibrated defects artificially implemented on samples, as an experimental basis for the definition of acceptance criteria for the bond armor/heat sink in the frame of industrial manufacturing conditions.It was found that current CFC monoblock design option was compatible with the heat loads specified at the lower part of the vertical target (up to 20 MW/m 2 ), including the presence of armor/heat sink defects (up to 50 deg. extension for a location at 0 deg. or 45 deg.) detectable with NDE techniques developed in Europe (US, SATIR). The current W monoblock design appeared suitable for the upper part of the vertical target with defects extension up to 50 deg. but is not adapted for heat flux of 20 MW/m 2 . The studied W flat tile design proved to be compatible with fluxes of 5 MW/m 2 but unable to sustain cycling fluxes of 10 MW/m 2 .

Probabilistic relationships in acceptable risk studies

International Nuclear Information System (INIS)

Benjamin, J.R.

1977-01-01

Acceptable risk studies involve uncertainties in future events; consequences and associated values, the acceptability levels, and the future decision environment. Probabilistic procedures afford the basic analytical tool to study the influence of each of these parameters on the acceptable risk decision, including their interrelationships, and combinations. A series of examples are presented in the paper in increasing complexity to illustrate the principles involved and to quantify the relationships to the acceptable risk decision. The basic objective of such studies is to broaden the scientific basis of acceptable risk decision making. It is shown that rationality and consistency in decision making is facilitated by such studies and that rather simple relationships exist in many situations of interest. The variation in criteria associated with an increase in the state of knowledge or change in the level of acceptability is also discussed. (Auth.)

Probabilistic relationships in acceptable risk studies

International Nuclear Information System (INIS)

Benjamin, J.R.

1977-01-01

Acceptable risk studies involve uncertainties in future events: consequences and associated values, the acceptability levels, and the future decision environment. Probabilistic procedures afford the basic analytical tool to study the influence of each of these parameters on the acceptable risk decision, including their interrelationships, and combinations. A series of examples are presented in the paper in increasing complexity to illustrate the principles involved and to quantify the relationships to the acceptable risk decision. The basic objective of such studies is to broaden the scientific basis of acceptable risk decision making. It is shown that rationality and consistency in decision making is facilitated by such studies and that rather simple relationships exist in many situations of interest. The variation in criteria associated with an increase in the state of knowledge or change in the level of acceptability is also discussed

Feasibility and acceptability of electronic symptom surveillance with clinician feedback using the Patient-Reported Outcomes version of Common Terminology Criteria for Adverse Events (PRO-CTCAE) in Danish prostate cancer patients

DEFF Research Database (Denmark)

Baeksted, Christina; Pappot, Helle; Nissen, Aase

2017-01-01

Background: The aim was to examine the feasibility, acceptability and clinical utility of electronic symptom surveillance with clinician feedback using a subset of items drawn from the Patient-Reported Outcomes version of Common Terminology Criteria for Adverse Events (PRO-CTCAE) in a cancer...

Safety criteria from the public viewpoint

International Nuclear Information System (INIS)

Renn, O.

1994-01-01

The paper attempts to outline the scope and limits of a consensus for the evaluation of energy systems, particularly nuclear energy. It is divided into four sections. The first section deals with factual acceptance of technology, while the second inquires into the specific acceptance of nuclear energy, i.e., public perception and valuation of nuclear energy today. The third section discusses criteria of acceptability. In the fourth section, finally, the author deals with questions concerning an energy consensus and presents his own model for approaching this issue. (orig.) [de

Waste certification program plan for Oak Ridge National Laboratory. Revision 1

International Nuclear Information System (INIS)

Orrin, R.C.

1997-05-01

This document defines the waste certification program developed for implementation at Oak Ridge National Laboratory (ORNL). The document describes the program structure, logic, and methodology for certification of ORNL wastes. The purpose of the waste certification program is to provide assurance that wastes are properly characterized and that the Waste Acceptance Criteria (WAC) for receiving facilities are met. The program meets the waste certification requirements outlined in US Department of Energy (DOE) Order 5820.2A, Radioactive Waste Management, and ensures that 40 CFR documentation requirements for waste characterization are met for mixed (both radioactive and hazardous) and hazardous (including polychlorinated biphenyls) waste. Program activities will be conducted according to ORNL Level 1 document requirements

Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program

International Nuclear Information System (INIS)

2009-01-01

Each testing and analytical facility performing waste characterization activities for the Waste Isolation Pilot Plant (WIPP) participates in the Performance Demonstration Program (PDP) to comply with the Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC) (DOE/WIPP-02-3122) and the Quality Assurance Program Document (QAPD) (CBFO-94-1012). The PDP serves as a quality control check for data generated in the characterization of waste destined for WIPP. Single blind audit samples are prepared and distributed to each of the facilities participating in the PDP. The PDP evaluates analyses of simulated headspace gases, constituents of the Resource Conservation and Recovery Act (RCRA), and transuranic (TRU) radionuclides using nondestructive assay (NDA) techniques.

Permeability of Consolidated Incinerator Facility Wastes Stabilized with Portland Cement

International Nuclear Information System (INIS)

Walker, B.W.

1999-01-01

The Consolidated Incinerator Facility (CIF) at the Savannah River Site (SRS) burns low-level radioactive wastes and mixed wastes as method of treatment and volume reduction. The CIF generates secondary waste, which consists of ash and off-gas scrubber solution. Currently the ash is stabilized/solidified in the Ashcrete process. The scrubber solution (blowdown) is sent to the SRS Effluent Treatment Facility (ETF) for treatment as waste water. In the past, the scrubber solution was also stabilized/solidified in the Ashcrete process as blowcrete and will continue to be treated this way for listed waste burns and scrubber solution that do not meet the Effluent Treatment Facility (ETF) Waste Acceptance Criteria (WAC)

Waste certification program plan for Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Kornegay, F.C.

1996-09-01

This document defines the waste certification program being developed for implementation at Oak Ridge National Laboratory (ORNL). The document describes the program structure, logic, and methodology for certification of ORNL wastes. The purpose of the waste certification program is to provide assurance that wastes are properly characterized and that the Waste Acceptance Criteria (WAC) for receiving facilities are met. The program meets the waste certification requirements outlined in U.S. Department of Energy (DOE) Order 5820.2A, Radioactive Waste Management, and ensures that 40 CFR documentation requirements for waste characterization are met for mixed (both radioactive and hazardous) and hazardous (including polychlorinated biphenyls) waste. Program activities will be conducted according to ORNL Level 1 document requirements

Technical considerations associated with spent fuel acceptance. Final report

International Nuclear Information System (INIS)

Supko, E.M.

1996-06-01

This study was initiated by the Electric Power Research Institute (EPRI) to identify technical considerations associated with spent fuel acceptance and implementation of a waste management system that includes the use of transportable storage systems, and to serve as an opening dialogue among Standard Contract Holders and the department of Energy's Office of Civilian Radioactive Waste management (OCRWM) prior to the development of waste acceptance criteria or issuance of a Notice of Proposed Rulemaking by OCRWM to amend the Standard Contract. The original purpose of the Notice of Proposed Rulemaking was to address changes to the Standard Contract to implement a multi-purpose canister based system and to address other issues that were not adequately addressed in the standard contract. Even if DOE does not develop a multi-purpose canister based system for waste acceptance, it will still be necessary to develop waste acceptance criteria in order to accept spent fuel in transportable storage systems that are being deployed for at-reactor storage. In this study, technical issues associated with spent fuel acceptance will be defined and potential options and alternatives for resolution of technical considerations will be explored

Cone penetrometer moisture probe acceptance test report

International Nuclear Information System (INIS)

Barnes, G.A.

1996-01-01

This Acceptance Test Report (ATR) documents the results of WHC-SD-WM-ATP-146 (Prototype Cone Penetrometer Moisture Probe Acceptance Test Procedure) and WHC-SD-WM-ATP-145 (Cone Penetrometer Moisture Probe Acceptance Test Procedure). The master copy of WHC-SD-WM-ATP-145 can be found in Appendix A and the master copy of WHC-SD-WM-ATP-146 can be found in Appendix B. Also included with this report is a matrix showing design criteria of the cone penetrometer moisture probe and the verification method used (Appendix C)

Heat exchanger, head and shell acceptance criteria

International Nuclear Information System (INIS)

Lam, P.S.; Sindelar, R.L.

1992-09-01

Instability of postulated flaws in the head component of the heat exchanger could not produce a large break, equivalent to a DEGB in the PWS piping, due to the configuration of the head and restraint provided by the staybolts. Rather, leakage from throughwall flaws in the head would increase with flaw length with finite leakage areas that are bounded by a post-instability flaw configuration. Postulated flaws at instability in the shell of the heat exchanger or in the cooling water nozzles could produce a large break in the Cooling Water System (CWS) pressure boundary. An initial analysis of flaw stability for postulated flaws in the heat exchanger head was performed in January 1992. This present report updates that analysis and, additionally, provides acceptable flaw configurations to maintain defined structural or safety margins against flaw instability of the external pressure boundary components of the heat exchanger, namely the head, shell, and cooling water nozzles. Structural and flaw stability analyses of the heat exchanger tubes, the internal pressure boundary of the heat exchangers or interface boundary between the PWS and CWS, were previously completed in February 1992 as part of the heat exchanger restart evaluation and are not covered in this report

Safety and reliability criteria

International Nuclear Information System (INIS)

O'Neil, R.

1978-01-01

Nuclear power plants and, in particular, reactor pressure boundary components have unique reliability requirements, in that usually no significant redundancy is possible, and a single failure can give rise to possible widespread core damage and fission product release. Reliability may be required for availability or safety reasons, but in the case of the pressure boundary and certain other systems safety may dominate. Possible Safety and Reliability (S and R) criteria are proposed which would produce acceptable reactor design. Without some S and R requirement the designer has no way of knowing how far he must go in analysing his system or component, or whether his proposed solution is likely to gain acceptance. The paper shows how reliability targets for given components and systems can be individually considered against the derived S and R criteria at the design and construction stage. Since in the case of nuclear pressure boundary components there is often very little direct experience on which to base reliability studies, relevant non-nuclear experience is examined. (author)

A systematic review of patient acceptance of consumer health information technology.

Science.gov (United States)

Or, Calvin K L; Karsh, Ben-Tzion

2009-01-01

A systematic literature review was performed to identify variables promoting consumer health information technology (CHIT) acceptance among patients. The electronic bibliographic databases Web of Science, Business Source Elite, CINAHL, Communication and Mass Media Complete, MEDLINE, PsycArticles, and PsycInfo were searched. A cited reference search of articles meeting the inclusion criteria was also conducted to reduce misses. Fifty-two articles met the selection criteria. Among them, 94 different variables were tested for associations with acceptance. Most of those tested (71%) were patient factors, including sociodemographic characteristics, health- and treatment-related variables, and prior experience or exposure to computer/health technology. Only ten variables were related to human-technology interaction; 16 were organizational factors; and one was related to the environment. In total, 62 (66%) were found to predict acceptance in at least one study. Existing literature focused largely on patient-related factors. No studies examined the impact of social and task factors on acceptance, and few tested the effects of organizational or environmental factors on acceptance. Future research guided by technology acceptance theories should fill those gaps to improve our understanding of patient CHIT acceptance, which in turn could lead to better CHIT design and implementation.

Los Alamos National Laboratory transuranic waste quality assurance project plan. Revision 1

International Nuclear Information System (INIS)

1997-01-01

This Transuranic (TRU) Waste Quality Assurance Project Plan (QAPjP) serves as the quality management plan for the characterization of transuranic waste in preparation for certification and transportation. The Transuranic Waste Characterization/Certification Program (TWCP) consists of personnel who sample and analyze waste, validate and report data; and provide project management, quality assurance, audit and assessment, and records management support, all in accordance with established requirements for disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP) facility. This QAPjP addresses how the TWCP meets the quality requirements of the Carlsbad Area Office (CAO) Quality Assurance Program Description (QAPD) and the technical requirements of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP). The TWCP characterizes and certifies retrievably stored and newly generated TRU waste using the waste selection, testing, sampling, and analytical techniques and data quality objectives (DQOs) described in the QAPP, the Los Alamos National Laboratory Transuranic Waste Certification Plan (Certification Plan), and the CST Waste Management Facilities Waste Acceptance Criteria and Certification [Los Alamos National Laboratory (LANL) Waste Acceptance Criteria (WAC)]. At the present, the TWCP does not address remote-handled (RH) waste

A comparison between criteria for diagnosing atopic eczema in infants

DEFF Research Database (Denmark)

Jøhnke, H; Vach, W; Norberg, L A

2005-01-01

Research Centre (DARC) criteria developed for this study and doctor-diagnosed visible eczema with typical morphology and atopic distribution. Additionally, the U.K. diagnostic criteria based on a questionnaire were used at 1 year of age. Agreement between the four criteria was analysed at each time point...... the four criteria demonstrated that cumulative incidences showed better agreement than point prevalence values. CONCLUSIONS: Agreement between different criteria for diagnosing AE was acceptable, but the mild cases constituted a diagnostic problem, although they were in the minority. Repeated examinations...

W-087 Acceptance test procedure. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Joshi, A.W.

1997-06-10

This Acceptance Test Procedure/Operational Test Procedure (ATP/OTP) has been prepared to demonstrate that the Electrical/Instrumentation and Mechanical systems function as required by project criteria and to verify proper operation of the integrated system including the interlocks.

W-087 Acceptance test procedure. Revision 1

International Nuclear Information System (INIS)

Joshi, A.W.

1997-01-01

This Acceptance Test Procedure/Operational Test Procedure (ATP/OTP) has been prepared to demonstrate that the Electrical/Instrumentation and Mechanical systems function as required by project criteria and to verify proper operation of the integrated system including the interlocks

Special Analysis for the Disposal of the Idaho National Laboratory Unirradiated Light Water Breeder Reactor Rods and Pellets Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

Energy Technology Data Exchange (ETDEWEB)

None

2014-08-31

The purpose of this special analysis (SA) is to determine if the Idaho National Laboratory (INL) Unirradiated Light Water Breeder Reactor (LWBR) Rods and Pellets waste stream (INEL103597TR2, Revision 2) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The INL Unirradiated LWBR Rods and Pellets waste stream consists of 24 containers with unirradiated fabricated rods and pellets composed of uranium oxide (UO2) and thorium oxide (ThO2) fuel in zirconium cladding. The INL Unirradiated LWBR Rods and Pellets waste stream requires an SA because the 229Th, 230Th, 232U, 233U, and 234U activity concentrations exceed the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

An evaluation and acceptance of COTS software for FPGA-based controllers in NPPS

International Nuclear Information System (INIS)

Jung, Sejin; Kim, Eui-Sub; Yoo, Junbeom; Kim, Jang-Yeol; Choi, Jong Gyun

2016-01-01

Highlights: • All direct/indirect COTS SW should be dedicated. • FPGA synthesis tools are important for the safety of new digital I&Cs. • No standards/reports are yet available to deal with the indirect SW – FPGA synthesis tools. • This paper proposes a new evaluation/acceptance process and criteria for indirect SW. - Abstract: FPGA (Field-Programmable Gate Array) has received much attention from nuclear industry as an alternative platform of PLC (Programmable Logic Controller)-based digital I&C (Instrumentation & Control). Software aspect of FPGA development encompasses several commercial tools such as logic synthesis and P&R (Place & Route), which should be first dedicated in accordance with domestic standards based on EPRI NP-5652. Even if a state-of-the-art supplementary EPRI TR-1025243 makes an effort, the dedication of indirect COTS (Commercial Off-The-Shelf) SW such as FPGA logic synthesis tools has still caused a dispute. This paper proposes an acceptance process and evaluation criteria, specific to COTS SW, not commercial-grade direct items. It specifically incorporates indirect COTS SW and also provides categorized evaluation criteria for acceptance. It provides an explicit linkage between acceptance methods (Verification and Validation techniques) and evaluation criteria, too. We tried to perform the evaluation and acceptance process upon a commercial FPGA logic synthesis tool being used to develop a new FPGA-based digital I&C in Korea, and could confirm its applicability.

Manufacturing and testing of reference samples for the definition of acceptance criteria for the ITER divertor

International Nuclear Information System (INIS)

Visca, Eliseo; Cacciotti, E.; Libera, S.; Mancini, A.; Pizzuto, A.; Roccella, S.; Riccardi, B.; Escourbiac, F.; Sanguinetti, G.P.

2010-01-01

The most critical part of a high heat flux (HHF) plasma facing component (PFC) is the armour to heat sink joint. An experimental study was launched by EFDA in order to define the acceptance criteria to be used for the procurements of the ITER Divertor PFCs. ENEA is involved in the European International Thermonuclear Experimental Reactor (ITER) R and D activities and together with Ansaldo Ricerche S.p.A. has manufactured several PFCs mock-ups using the Hot Radial Pressing and Pre-Brazed Casting technologies. According to the technical specifications issued by EFDA, ENEA and Ansaldo have collaborated to manufacture half of the samples with calibrated artificial defects required for this experimental study. After manufacturing, the samples were examined by ultrasonic and SATIR non-destructive examination (NDE) methods in order to confirm the size and position of the artificial defects. In particular, it was concluded that defects are detectable with these NDE techniques and they finally gave indication about the threshold of propagation during high heat flux experiments relevant with heat fluxes expected in ITER Divertor. This paper reports the manufacturing procedure used to obtain the required calibrated artificial defects in the CFC and W armoured samples as well as the NDE results and the thermal high heat flux results.

Manufacturing and testing of reference samples for the definition of acceptance criteria for the ITER divertor

Energy Technology Data Exchange (ETDEWEB)

Visca, Eliseo, E-mail: visca@frascati.enea.i [Associazione EURATOM-ENEA sulla Fusione, Frascati (Italy); Cacciotti, E.; Libera, S.; Mancini, A.; Pizzuto, A.; Roccella, S. [Associazione EURATOM-ENEA sulla Fusione, Frascati (Italy); Riccardi, B., E-mail: Bruno.Riccardi@f4e.europa.e [Fusion For Energy, Barcelona (Spain); Escourbiac, F., E-mail: frederic.escourbiac@iter.or [ITER Organization, Cadarache (France); Sanguinetti, G.P., E-mail: gianpaolo.sanguinetti@aen.ansaldo.i [Ansaldo Energia S.p.A., Genova (Italy)

2010-12-15

The most critical part of a high heat flux (HHF) plasma facing component (PFC) is the armour to heat sink joint. An experimental study was launched by EFDA in order to define the acceptance criteria to be used for the procurements of the ITER Divertor PFCs. ENEA is involved in the European International Thermonuclear Experimental Reactor (ITER) R and D activities and together with Ansaldo Ricerche S.p.A. has manufactured several PFCs mock-ups using the Hot Radial Pressing and Pre-Brazed Casting technologies. According to the technical specifications issued by EFDA, ENEA and Ansaldo have collaborated to manufacture half of the samples with calibrated artificial defects required for this experimental study. After manufacturing, the samples were examined by ultrasonic and SATIR non-destructive examination (NDE) methods in order to confirm the size and position of the artificial defects. In particular, it was concluded that defects are detectable with these NDE techniques and they finally gave indication about the threshold of propagation during high heat flux experiments relevant with heat fluxes expected in ITER Divertor. This paper reports the manufacturing procedure used to obtain the required calibrated artificial defects in the CFC and W armoured samples as well as the NDE results and the thermal high heat flux results.

The development of criteria for radioactive waste disposal

International Nuclear Information System (INIS)

Wagstaff, K.P.

1985-02-01

Radiation protection criteria are needed in Canada for judging the acceptability of radioactive waste disposal options for which there are potential long-term radiological impacts. This paper discusses the difficulties encountered in applying the ICRP system of dose limitation to the long term and the alternative approaches to criteria being developed and adopted by various other international and national bodies. Finally, the present situation in Canada is reviewed and conclusions are drawn on the general direction in which national criteria are being formulated and expressed

Air pollution control residues from waste incineration: current UK situation and assessment of alternative technologies.

Science.gov (United States)

Rani, D Amutha; Boccaccini, A R; Deegan, D; Cheeseman, C R

2008-11-01

Current disposal options for APC residues in the UK and alternative treatment technologies developed world-wide have been reviewed. APC residues are currently landfilled in the UK where they undergo in situ solidification, although the future acceptability of this option is uncertain because the EU waste acceptance criteria (WAC) introduce strict limits on leaching that are difficult to achieve. Other APC residue treatment processes have been developed which are reported to reduce leaching to below relevant regulatory limits. The Ferrox process, the VKI process, the WES-PHix process, stabilisation/solidification using cementitious binders and a range of thermal treatment processes are reviewed. Thermal treatment technologies convert APC residues combined with other wastes into inert glass or glass-ceramics that encapsulate heavy metals. The waste management industry will inevitably use the cheapest available option for treating APC residues and strict interpretation and enforcement of waste legislation is required if new, potentially more sustainable technologies are to become commercially viable.

Air pollution control residues from waste incineration: Current UK situation and assessment of alternative technologies

International Nuclear Information System (INIS)

Amutha Rani, D.; Boccaccini, A.R.; Deegan, D.; Cheeseman, C.R.

2008-01-01

Current disposal options for APC residues in the UK and alternative treatment technologies developed world-wide have been reviewed. APC residues are currently landfilled in the UK where they undergo in situ solidification, although the future acceptability of this option is uncertain because the EU waste acceptance criteria (WAC) introduce strict limits on leaching that are difficult to achieve. Other APC residue treatment processes have been developed which are reported to reduce leaching to below relevant regulatory limits. The Ferrox process, the VKI process, the WES-PHix process, stabilisation/solidification using cementitious binders and a range of thermal treatment processes are reviewed. Thermal treatment technologies convert APC residues combined with other wastes into inert glass or glass-ceramics that encapsulate heavy metals. The waste management industry will inevitably use the cheapest available option for treating APC residues and strict interpretation and enforcement of waste legislation is required if new, potentially more sustainable technologies are to become commercially viable

Mixed waste characterization and certification at the Nevada Test Site

International Nuclear Information System (INIS)

Kawamura, T.A.; Dodge, R.L.; Fitzsimmons, P.K.

1988-01-01

The Radioactive Waste Management Project (RWMP) at the Nevada Test Site (NTS) was recently granted interim status by the state of Nevada to receive mixed waste (MW). The RCRA Part B permit application has been revised and submitted to the state. Preliminary indications are that the permit will be granted. In conjunction with revision of the Part B Permit application, pertinent DOE guidelines governing waste acceptance criteria (WAC) and waste characterization were also revised. The guidelines balance the need for full characterization of hazardous constituents with as low as reasonably achievable (ALARA) precepts. Because it is not always feasible to obtain a full chemical analysis without undue or unnecessary radiological exposure of personnel, process knowledge is considered an acceptable method of waste characterization. A balance of administrative controls and verification procedures, as well as careful documentation and high standards of quality assurance, are essential to the characterization and certification program developed for the NTS

A research for Class II defect Bored Pile’s Accept Criteria: A case of Penang Second Marine bridge

Science.gov (United States)

Huang, Kang

2018-03-01

The aim of this preliminary research is to study the accept criteria of class II bored pile with subtle defect. According to a detailed comparison of the existed different standards, Chinese ones are more applicable especially for the large diameter bored piles. Through the concrete coring at pile No P25-03 of this case and the comparison to the actual calculation, the Class II pile’s defects were very minor. Comparison was also made for the effects on pile structural capacities before and after repair of the defects. the feasible repair proposal may bring forward to more defects to the piles. The Class II piles don’t need any further repairation when piles have typical of similar character and sonic logging test result with P25-03‘s one. For other Class II piles with some differences in characters, verification is needed through further concrete coring on the pile. The recommendation of this research could be adopted for the similar huge marine structures which installed large diameter bored piles.

Scientific opinion on the evaluation of substances as acceptable previous cargoes for edible fats and oils

DEFF Research Database (Denmark)

Petersen, Annette

Shipping of edible fats and oils into Europe is permitted in bulk tanks, provided that the previous cargo is included in a positive list. The European Commission requested EFSA to evaluate the acceptability as previous cargoes for fats and oils the substances calcium lignosulphonate, methyl acetate...... the criteria for acceptability as previous cargoes. Due to uncertainties, mainly with regard to the composition and toxicity of the low molecular mass fraction, and the fact that the toxicological database is limited to the 40–65 grade and does not cover all grades of calcium lignosulphonate shipped...... as previous cargoes, the EFSA Panel on Contaminants in the Food Chain (CONTAM Panel) concluded that calcium lignosulphonate does not meet the criteria for acceptability as a previous cargo. Only food-grade ammonium sulphate meets the criteria for acceptability as a previous cargo due to uncertainties about...

A STATISTICAL APPROACH FOR DERIVING KEY NFC EVALUATION CRITERIA

Directory of Open Access Journals (Sweden)

S.K. KIM

2014-02-01

As a result of analyzing the weight of evaluation criteria with the sample of nuclear power experts and the general public, both sides recognized safety as the most important evaluation criterion, and the social factors such as public acceptance appeared to be ranked as more important evaluation criteria by the nuclear energy experts than the general public.

Extended BRS algebra and color confinement criteria

International Nuclear Information System (INIS)

Shintani, Meiun.

1983-09-01

We examine the color-confinement criteria proposed by Kugo and Ojima. With the use of the extended BRS symmetry and the Nakanishi's theorem, we look for the representations of the BRS algebra compatible with the first condition of their criteria (the K-O condition) and then ask whether or not they are physically acceptable. As a result, the quartet mechanism does not work, and the K-O condition is not regarded as a confinement condition. (author)

Criteria for decommissioning

International Nuclear Information System (INIS)

Ricci, P.F.

1988-01-01

In this paper the authors describe three risk acceptability criteria as parts of a strategy to clean up decommissioned facilities, related to both the status quo and to a variety of alternative technical clean-up options. The acceptability of risk is a consideration that must enter into any decision to establish when a site is properly decommissioned. To do so, both the corporate and public aspects of the acceptability issue must be considered. The reasons for discussion the acceptability of risk are to: Legitimize the process for making cleanup decisions; Determine who is at risk, who benefits, and who bears the costs of site cleanup, for each specific cleanup option, including the do nothing option; Establish those factors that, taken as a whole, determine measures of acceptability; Determine chemical-specific aggregate and individual risk levels; and Establish levels for cleanup. The choice of these reasons is pragmatic. The method consistent with these factors is risk-risk-effectiveness: the level of cleanup must be consistent with the foreseeable use of the site and budget constraints. Natural background contamination is the level below which further cleanup is generally inefficient. Case-by-case departures from natural background are to be considered depending on demonstrated risk. For example, a hot spot is obviously a prima facie exception, but should be rebuttable. Rebuttability means that, through consensus, the ''hot spot'' is shown not to be associated with exposure

Hanford Site Transuranic (TRU) Waste Certification Plan

Energy Technology Data Exchange (ETDEWEB)

GREAGER, T.M.

1999-09-09

The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria within which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP.

Environmental risk assessment: its contribution to criteria development for HLW disposal

International Nuclear Information System (INIS)

Smith, G.M.; Little, R.H.; Watkins, B.M.

1999-01-01

Principles for radioactive waste management have been provided by the International Atomic Energy Agency in Safety Series No.111-F, which was published in 1995. This has been a major step forward in the process of achieving acceptance for proposals for disposal of radioactive waste, for example, for High Level Waste disposal in deep repositories. However, these principles have still to be interpreted and developed into practical radiation protection criteria. Without prejudicing final judgements on the acceptability of waste proposals, an important aspect is that practical demonstration of compliance (or the opposite) with these criteria must be possible. One of the IAEA principles requires that radioactive waste shall be managed in such a way as to provide an acceptable level of protection of the environment. There has been and continues to be considerable debate as to how to demonstrate compliance with such a principle. This paper briefly reviews the current status and considers how experience in other areas of environmental protection could contribute to criteria development for HLW disposal

Plugging criteria for WWER SG tubes

Energy Technology Data Exchange (ETDEWEB)

Papp, L.; Wilam, M. [Vitkovice NPP Services (Switzerland); Herman, M. [Vuje, Trnava (Slovakia)

1997-12-31

At operated Czech and Slovak nuclear power plants the 80 % criteria for crack or other bulk defect depth is used for steam generator heat exchanging tubes plugging. This criteria was accepted as the recommendation of designer of WWER steam generators. Verification of this criteria was the objective of experimental program performed by Vitkovice, J.S.C., UJV Rez, J.S.C. and Vuje Trnava, J.S.C .. Within this program the following factors were studied: (1) Influence of secondary water chemistry on defects initiation and propagation, (2) Statistical evaluation of corrosion defects progression at operated SG, and (3) Determination of critical pressure for tube rupture as a function of eddy current indications. In this presentation items (2) and (3) are considered.

Plugging criteria for WWER SG tubes

Energy Technology Data Exchange (ETDEWEB)

Papp, L; Wilam, M [Vitkovice NPP Services (Switzerland); Herman, M [Vuje, Trnava (Slovakia)

1998-12-31

At operated Czech and Slovak nuclear power plants the 80 % criteria for crack or other bulk defect depth is used for steam generator heat exchanging tubes plugging. This criteria was accepted as the recommendation of designer of WWER steam generators. Verification of this criteria was the objective of experimental program performed by Vitkovice, J.S.C., UJV Rez, J.S.C. and Vuje Trnava, J.S.C .. Within this program the following factors were studied: (1) Influence of secondary water chemistry on defects initiation and propagation, (2) Statistical evaluation of corrosion defects progression at operated SG, and (3) Determination of critical pressure for tube rupture as a function of eddy current indications. In this presentation items (2) and (3) are considered.

Hanford Site Transuranic (TRU) Waste Certification Plan

International Nuclear Information System (INIS)

GREAGER, T.M.

1999-01-01

The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria with in which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP

Acceptance of spent fuel of varying characteristics

International Nuclear Information System (INIS)

Short, S.M.

1990-03-01

This paper is a preliminary overview of a study with the primary objective of establishing a set of acceptance selection criteria and corresponding spent fuel characteristics to be incorporated as a component of requirements for the Federal Waste Management System (FWMS). A number of alternative acceptance allocations and selection rules were analyzed to determine the operational sensitivity of each element of the FWMS to the resultant spent fuel characteristics. Preliminary recommendations of the study include three different sets of selection rules to be included in the FWMS design basis. 2 refs., 4 figs., 4 tabs

[Organization of socially acceptable working hours in nursing].

Science.gov (United States)

Büssing, A; Glaser, J

1994-05-01

Three dimensions in the structure of the working hour system of nurses, rendering them socially acceptable, are becoming important: duration of the working day, the time of day which is being worked and the distribution of working hours. The latter two are of particular importance because flexible shift is becoming the dominant pattern in nursing. Six indicators are discussed as criteria for social acceptability: security of employment which includes access to the labour-market, level of income, health, opportunity for social relationships, social participation, and autonomy. Responses of 297 nurses in one General Hospital taking part in a study, were analysed to examine empirically the concept of 'socially acceptable structure of the working hours'. Ideal and factual patterns are considered first. Secondly aspects of autonomy are considered and the way this depends on time, thirdly the criteria used to define 'social acceptability' are examined for validity. Results show firstly the cross contrast between the hospital's expectation and the nurses' wishes with regard to working hours. Furthermore, inspite of the demand for flexibility, staff have very little choice and there is little sign of joint decision making. Thirdly results show that health, interpersonal and social aspects are of special importance and that, correspondingly, in the view of nurses, financial and practical problems are of lesser importance in their every day life.

Selection criteria of residents for residency programs in Kuwait.

Science.gov (United States)

Marwan, Yousef; Ayed, Adel

2013-01-19

In Kuwait, 21 residency training programs were offered in the year 2011; however, no data is available regarding the criteria of selecting residents for these programs. This study aims to provide information about the importance of these criteria. A self-administered questionnaire was used to collect data from members (e.g. chairmen, directors, assistants …etc.) of residency programs in Kuwait. A total of 108 members were invited to participate. They were asked to rate the importance level (scale from 1 to 5) of criteria that may affect the acceptance of an applicant to their residency programs. Average scores were calculated for each criterion. Of the 108 members invited to participate, only 12 (11.1%) declined to participate. Interview performance was ranked as the most important criteria for selecting residents (average score: 4.63/5.00), followed by grade point average (average score: 3.78/5.00) and honors during medical school (average score: 3.67/5.00). On the other hand, receiving disciplinary action during medical school and failure in a required clerkship were considered as the most concerning among other criteria used to reject applicants (average scores: 3.83/5.00 and 3.54/5.00 respectively). Minor differences regarding the importance level of each criterion were noted across different programs. This study provided general information about the criteria that are used to accept/reject applicants to residency programs in Kuwait. Future studies should be conducted to investigate each criterion individually, and to assess if these criteria are related to residents' success during their training.

Project W-049H Collection System Acceptance Test

International Nuclear Information System (INIS)

Buckles, D.I.

1994-01-01

The Acceptance Test Procedure (ATP) Program for Project W-049H covers the following activities: Disposal system, Collection system, Instrumentation and control system. Each activity has its own ATP. The purpose of the ATPs is to verify that the systems have been constructed in accordance with the construction documents and to demonstrate that the systems function as required by the Project criteria. This ATP has been prepared to demonstrate that the Collection System Instrumentation functions as required by project criteria

Multi criteria analysis in the renewable energy industry

CERN Document Server

San Cristóbal Mateo, José Ramón

2012-01-01

Decision makers in the Renewable Energy sector face an increasingly complex social, economic, technological, and environmental scenario in their decision process. Different groups of decision-makers become involved in the process, each group bringing along different criteria therefore, policy formulation for fossil fuel substitution by Renewable Energies must be addressed in a multi-criteria context. Multi Criteria Analysis in the Renewable Energy Industry is a direct response to the increasing interest in the Renewable Energy industry which can be seen as an important remedy to many environmental problems that the world faces today. The multiplicity of criteria and the increasingly complex social, economic, technological, and environmental scenario makes multi-criteria analysis a valuable tool in the decision-making process for fossil fuel substitution. The detailed chapters explore the use of the Multi-criteria decision-making methods and how they provide valuable assistance in reaching equitable and accept...

Criteria for safety-related operator actions

International Nuclear Information System (INIS)

Gray, L.H.; Haas, P.M.

1983-01-01

The Safety-Related Operator Actions (SROA) Program was designed to provide information and data for use by NRC in assessing the performance of nuclear power plant (NPP) control room operators in responding to abnormal/emergency events. The primary effort involved collection and assessment of data from simulator training exercises and from historical records of abnormal/emergency events that have occurred in operating plants (field data). These data can be used to develop criteria for acceptability of the use of manual operator action for safety-related functions. Development of criteria for safety-related operator actions are considered

Characterizing cemented TRU waste for RCRA hazardous constituents

International Nuclear Information System (INIS)

Yeamans, D.R.; Betts, S.E.; Bodenstein, S.A.

1996-01-01

Los Alamos National Laboratory (LANL) has characterized drums of solidified transuranic (TRU) waste from four major waste streams. The data will help the State of New Mexico determine whether or not to issue a no-migration variance of the Waste Isolation Pilot Plant (WIPP) so that WIPP can receive and dispose of waste. The need to characterize TRU waste stored at LANL is driven by two additional factors: (1) the LANL RCRA Waste Analysis Plan for EPA compliant safe storage of hazardous waste; (2) the WIPP Waste Acceptance Criteria (WAC) The LANL characterization program includes headspace gas analysis, radioassay and radiography for all drums and solids sampling on a random selection of drums from each waste stream. Data are presented showing that the only identified non-metal RCRA hazardous component of the waste is methanol

Preliminary Disposal Analysis for Selected Accelerator Production of Tritium Waste Streams

International Nuclear Information System (INIS)

Ades, M.J.; England, J.L.

1998-06-01

A preliminary analysis was performed for two selected Accelerator Production of Tritium (APT) generated mixed and low-level waste streams to determine if one mixed low-level waste (MLLW) stream that includes the Mixed Waste Lead (MWL) can be disposed of at the Nevada Test Site (NTS) and at the Hanford Site and if one low-level radioactive waste (LLW) stream, that includes the Tungsten waste stream (TWS) generated by the Tungsten Neutron Source modules and used in the Target/Blanket cavity vessel, can be disposed of in the LLW Vaults at the Savannah River Plant (SRP). The preliminary disposal analysis that the radionuclide concentrations of the two selected APT waste streams are not in full compliance with the Waste Acceptance Criteria (WAC) and the Performance Assessment (PA) radionuclide limits of the disposal sites considered

The second iteration of the Systems Prioritization Method: A systems prioritization and decision-aiding tool for the Waste Isolation Pilot Plant: Volume 1, Synopsis of method and results

International Nuclear Information System (INIS)

Prindle, N.H.; Mendenhall, F.T.; Boak, D.M.

1996-05-01

In March 1994, the US Department of Energy Carlsbad Area Office (DOE/CAO) embarked on an effort to design and implement a performance- based decision-aiding tool to provide an analytical basis for planning, prioritizing, and selecting programmatic options for the Waste Isolation Pilot Plant (WIPP). This tool, called Systems Prioritization Method (SPM) defines the most viable combinations of scientific investigations, engineered alternatives (EAs), and waste acceptance criteria (WAC) for supporting the final WIPP compliance application. The scope of SPM is restricted to selected portions of applicable Environmental Protection Agency (EPA) long-term performance regulations. SPM calculates the probabilities of certain sets of activities demonstrating compliance with various regulations. SPM provides results in the form of a decision matrix to identify cost-effective programmatic paths with a high probability of successfully demonstrating compliance

The second iteration of the Systems Prioritization Method: A systems prioritization and decision-aiding tool for the Waste Isolation Pilot Plant: Volume 1, Synopsis of method and results

Energy Technology Data Exchange (ETDEWEB)

Prindle, N.H.; Mendenhall, F.T.; Boak, D.M. [and others

1996-05-01

In March 1994, the US Department of Energy Carlsbad Area Office (DOE/CAO) embarked on an effort to design and implement a performance- based decision-aiding tool to provide an analytical basis for planning, prioritizing, and selecting programmatic options for the Waste Isolation Pilot Plant (WIPP). This tool, called Systems Prioritization Method (SPM) defines the most viable combinations of scientific investigations, engineered alternatives (EAs), and waste acceptance criteria (WAC) for supporting the final WIPP compliance application. The scope of SPM is restricted to selected portions of applicable Environmental Protection Agency (EPA) long-term performance regulations. SPM calculates the probabilities of certain sets of activities demonstrating compliance with various regulations. SPM provides results in the form of a decision matrix to identify cost-effective programmatic paths with a high probability of successfully demonstrating compliance.

Characterization of Samples from Old Solvent Tanks S1 through S22

Energy Technology Data Exchange (ETDEWEB)

Leyba, J.D.

1999-03-25

The Old Radioactive Waste Burial Ground (ORWBG, 643-E) contains 22 old solvent tanks (S1 - S22) which were used to receive and store spent PUREX solvent from F- and H-Canyons. The tanks are cylindrical, carbon-steel, single-wall vessels buried at varying depths. A detailed description of the tanks and their history can be found in Reference 1. A Sampling and Analysis Plan for the characterization of the material contained in the old solvent tanks was developed by the Analytical Development Section (ADS) in October of 19972. The Sampling and Analysis Plan identified several potential disposal facilities for the organic and aqueous phases present in the old solvent tanks which included the Solvent Storage Tank Facility (SSTF), the Mixed Waste Storage Facilities (MWSF), Transuranic (TRU) Pad, and/or the Consolidated Incineration Facility (CIF). In addition, the 241-F/H Tank Farms, TRU Pads, and/or the MWSF were identified as potential disposal facilities for the sludge phases present in the tanks. The purpose of this sampling and characterization was to obtain sufficient data on the material present in the old solvent tanks so that a viable path forward could be established for the closure of the tanks. Therefore, the parameters chosen for the characterization of the various materials present in the tanks were based upon the Waste Acceptance Criteria (WAC) of the SSTF3, TRU Pads4, MWSF5, CIF6, and/or 241-F/H Tank Farms7. Several of the WAC's have been revised, canceled, or replaced by new procedures since October of 1997 and hence where required, the results of this characterization program were compared against the latest revision of the appropriate WAC.

The leak before break criteria, requirements and implications

International Nuclear Information System (INIS)

Martinez M, E.

1992-05-01

Inside this work a general balance is made on the Leak before break approach (LBB), like they are the history and licensing, those limitations, the acceptance criteria of the LBB, the current state of the regulatory development and the current state of it application in countries like E.U.A, Germany, Canada, Italy and France. Everything it with the purpose of evaluating the opportunities that offers the LBB criteria for it possible application in Mexico. (Author)

Technical evaluation of draft ANSI Standard N13.30, ''performance criteria for radiobioassay''

International Nuclear Information System (INIS)

MacLellan, J.A.; Traub, R.J.

1986-03-01

The Pacific Northwest Laboratory (PNL) is conducting a research program to evaluate the appropriateness of criteria in the ANSI draft Standard N13.30, ''Performance Criteria for Radiobioassay.'' The evaluation has progressed parallel with the preparation of the Standard by evaluating the performance of existing bioassay laboratories against the criteria specified. Recommendations for revision of the Standard and implementation of a testing/accreditation program have been formulated based on study results. The current performance testing program includes both in-vivo counting and in-vitro sample measurements. Test criteria specified in the Standard include relative bias, relative precision, and acceptable minimum detectable activity (AMDA). Results to date have indicated that the acceptance criteria in the Standard are appropriate for the existing state of the industry and are achievable by a majority of the participating laboratories. Specific conclusions are that the AMDA criteria are most difficult for the laboratories to achieve; the relative bias criterion is second in difficulty, and the precision criterion presents no problem for the laboratories; most of the participating laboratories can meet the Standard; and failure rates may decrease as the laboratories become more knowledgeable of the performance criteria. 3 refs., 11 figs., 6 tabs

[Revision of McDonald's new diagnostic criteria for multiple sclerosis].

Science.gov (United States)

Wiendl, H; Kieseier, B C; Gold, R; Hohlfeld, R; Bendszus, M; Hartung, H-P

2006-10-01

In 2001, an international panel suggested new diagnostic criteria for multiple sclerosis (MS). These criteria integrate clinical, imaging (MRI), and paraclinical results in order to facilitate diagnosis. Since then, these so-called McDonald criteria have been broadly accepted and widely propagated. In the meantime a number of publications have dealt with the sensitivity and specificity for MS diagnosis and with implementing these new criteria in clinical practice. Based on these empirical values and newer data on MS, an international expert group recently proposed a revision of the criteria. Substantial changes affect (1) MRI criteria for the dissemination of lesions over time, (2) the role of spinal cord lesions in the MRI and (3) diagnosis of primary progressive MS. In this article we present recent experiences with the McDonald and revised criteria.

Final characterization report for the 104-B-1 Tritium Vault and 104-B-2 Tritium Laboratory

International Nuclear Information System (INIS)

Encke, D.B.; Harris, R.A.

1996-11-01

This report is a compilation of the characterization data collected from the 104-B-1 Tritium Vault and the 104-B-2 Trillium Laboratory. The characterization activities were organized and implemented to evaluate the radiological status and identify any hazardous materials. The data contained in this report reflects the current conditions and status of the 104-B-1 Tritium Vault and 104-B-2 Tritium Laboratory. This information is intended to be utilized in support of future building decontamination and demolition, to allow for proper disposal of the demolition debris as required by the Washington Administrative Code, WAC 173-303, the Hanford Site Solid Waste Acceptance Criteria, WHC-EP-0063, and the Environmental Restoration Disposal Facility Waste Acceptance Criteria, BHI-00139. Based on the historical information and facility inspections, the only hazardous materials sampling and analysis activities necessary were to identify lead paint and asbestos containing materials (ACM) in the 104-B-1 Tritium Vault and the 104-B-2 Tritium Laboratory. Asbestos samples were obtained from the outer boundary of the roof areas to confirm the presence and type of asbestos containing fibers. Lead paint samples were obtained to confirm the presence and quantity of lead paint on the roof trim, doors and vents

Characterization of the MVST waste tanks located at ORNL

Energy Technology Data Exchange (ETDEWEB)

Keller, J.M.; Giaquinto, J.M.; Meeks, A.M.

1996-12-01

During the fall of 1996 there was a major effort to sample and analyze the Active Liquid Low-Level Waste (LLLW) tanks at ORNL which include the Melton Valley Storage Tanks (MVST) and the Bethel Valley Evaporator Service Tanks (BVEST). The characterization data summarized in this report was needed to address waste processing options, address concerns of the performance assessment (PA) data for the Waste Isolation Pilot Plant (WIPP), evaluate the characteristics with respect to the waste acceptance criteria (WAC) for WIPP and Nevada Test Site (NTS), address criticality concerns, and meet DOT requirements for transporting the waste. This report only discusses the analytical characterization data for the MVST waste tanks. The isotopic data presented in this report support the position that fissile isotopes of uranium and plutonium were ``denatured`` as required by administrative controls. In general, MVST sludge was found to be both hazardous by RCRA characteristics and the transuranic alpha activity was well about the limit for TRU waste. The characteristics of the MVST sludge relative to the WIPP WAC limits for fissile gram equivalent, plutonium equivalent activity, and thermal power from decay heat, were estimated from the data in this report and found to be far below the upper boundary for any of the remote-handled transuranic waste requirements for disposal of the waste in WIPP.

Characterization of the MVST waste tanks located at ORNL

International Nuclear Information System (INIS)

Keller, J.M.; Giaquinto, J.M.; Meeks, A.M.

1996-12-01

During the fall of 1996 there was a major effort to sample and analyze the Active Liquid Low-Level Waste (LLLW) tanks at ORNL which include the Melton Valley Storage Tanks (MVST) and the Bethel Valley Evaporator Service Tanks (BVEST). The characterization data summarized in this report was needed to address waste processing options, address concerns of the performance assessment (PA) data for the Waste Isolation Pilot Plant (WIPP), evaluate the characteristics with respect to the waste acceptance criteria (WAC) for WIPP and Nevada Test Site (NTS), address criticality concerns, and meet DOT requirements for transporting the waste. This report only discusses the analytical characterization data for the MVST waste tanks. The isotopic data presented in this report support the position that fissile isotopes of uranium and plutonium were ''denatured'' as required by administrative controls. In general, MVST sludge was found to be both hazardous by RCRA characteristics and the transuranic alpha activity was well about the limit for TRU waste. The characteristics of the MVST sludge relative to the WIPP WAC limits for fissile gram equivalent, plutonium equivalent activity, and thermal power from decay heat, were estimated from the data in this report and found to be far below the upper boundary for any of the remote-handled transuranic waste requirements for disposal of the waste in WIPP

Acceptance test procedure for High Pressure Water Jet System

International Nuclear Information System (INIS)

Crystal, J.B.

1995-01-01

The overall objective of the acceptance test is to demonstrate a combined system. This includes associated tools and equipment necessary to perform cleaning in the 105 K East Basin (KE) for achieving optimum reduction in the level of contamination/dose rate on canisters prior to removal from the KE Basin and subsequent packaging for disposal. Acceptance tests shall include necessary hardware to achieve acceptance of the cleaning phase of canisters. This acceptance test procedure will define the acceptance testing criteria of the high pressure water jet cleaning fixture. The focus of this procedure will be to provide guidelines and instructions to control, evaluate and document the acceptance testing for cleaning effectiveness and method(s) of removing the contaminated surface layer from the canister presently identified in KE Basin. Additionally, the desired result of the acceptance test will be to deliver to K Basins a thoroughly tested and proven system for underwater decontamination and dose reduction. This report discusses the acceptance test procedure for the High Pressure Water Jet

Retrospective analysis of 'gamma distribution' based IMRT QA criteria

International Nuclear Information System (INIS)

Wen, C.; Chappell, R.A.

2010-01-01

Full text: IMRT has been implemented into clinical practice at Royal Hobart Hospital (RHH) since mid 2006 for treating patients with Head and Neck (H and N) or prostate tumours. A local quality assurance (QA) acceptance criteria based on 'gamma distribution' for approving IMRT plan was developed and implemented in early 2007. A retrospective analysis of such criteria over 194 clinical cases will be presented. The RHH IMRT criteria was established with assumption that gamma distribution obtained through inter-comparison of 2 D dose maps between planned and delivered was governed by a positive-hail' normal distribution. A commercial system-MapCheck was used for 2 D dose map comparison with a built-in gamma analysis tool. Gamma distribution histogram was generated and recorded for all cases. By retrospectively analysing those distributions using curve fitting technique, a statistical gamma distribution can be obtained and evaluated. This analytical result can be used for future IMRT planing and treatment delivery. The analyses indicate that gamma distribution obtained through MapCheckTM is well under the normal distribution, particularly for prostate cases. The applied pass/fail criteria is not overly sensitive to identify 'false fails' but can be further tighten-up for smaller field while for larger field found in both H and N and prostate cases, the criteria was correctly applied. Non-uniform distribution of detectors in MapCheck and experience level of planners are two major factors to variation in gamma distribution among clinical cases. This criteria derived from clinical statistics is superior and more accurate than single-valued criteria for lMRT QA acceptance procedure. (author)

Acceptable Knowledge Summary Report for Waste Stream: SR-T001-221F-HET/Drums

International Nuclear Information System (INIS)

Lunsford, G.F.

1999-01-01

This report is fully responsive to the requirements of Section 4.0 ''Acceptable Knowledge'' from the WIPP Transuranic Waste Characterization Quality Assurance Plan, CAO-94-1010, and provides a sound, (and auditable) characterization that satisfies the WIPP criteria for Acceptable Knowledge

Mark II containment lead plant program load evaluation and acceptance criteria

International Nuclear Information System (INIS)

1978-10-01

The report, prepared by the Office of Nuclear Reactor Regulation, addresses the portion of the Mark II owner's program that provides a generic methodology for establishing design basis LOCA and safety relief valve loads for the lead Mark II facilities (Zimmer, Shoreham, and LaSalle), i.e., the lead plant program. The report includes an evaluation of the Mark II owner's load methodology, a description of load methodologies that we find acceptable for use in the individual plant unique assessments, and the basis for the stated conclusions

Early Site Permit Demonstration Program: Regulatory criteria evaluation report

International Nuclear Information System (INIS)

1993-03-01

The primary objective of the Early Site Plan Demonstration Program (ESPDP) is to demonstrate successfully the use of 10CFR52 to obtain ESPs for one or more US sites for one (or more) ALWR nuclear power plants. It is anticipated that preparation of the ESP application and interaction with NRC during the application review process will result not only in an ESP for the applicant(s) but also in the development of criteria and definition of processes, setting the precedent that facilitates ESPs for subsequent ESP applications. Because siting regulatory processes and acceptance criteria are contained in over 100 separate documents, comprehensive licensing and technical reviews were performed to establish whether the requirements and documentation are self-consistent, whether the acceptance criteria are sufficiently well-defined and clear, and whether the licensing process leading to the issuance of an ESP is unambiguously specified. This document provides appendices C and D of this report. Appendix C contains data from the licensing and technical reviews; Appendix D contains technology toolkit data sheets

Waste acceptance product specifications for vitrified high-level waste forms

International Nuclear Information System (INIS)

Applewhite-Ramsey, A.; Sproull, J.F.

1994-01-01

The Department of Energy (DOE) Office of Environmental Restoration and Waste Management (EM) has developed Waste Acceptance Product Specifications (EM-WAPS). The EM-WAPS will be the basis for defining product acceptance criteria compatible with the requirements of the Civilian Radioactive Waste Management System (CRWMS). The relationship between the EM-WAPS and the CRWMS Systems Requirements document (WA-SRD) will be discussed. The impact of the EM-WAPS on the Savannah River Sit (SRS) Defense Waste Processing Facility's (DWPF) Waste Acceptance Program, Waste Qualification Run planning, and startup schedule will also be reported. 14 refs., 2 tabs

Considerations for developing seismic design criteria for nuclear waste storage repositories

International Nuclear Information System (INIS)

Owen, G.N.; Yanev, P.I.; Scholl, R.E.

1980-04-01

The function of seismic design criteria is to reduce the potential for hazards that may arise during various stages of the repository life. During the operational phase, the major concern is with the possible effects of earthquakes on surface facilities, underground facilities, and equipment. During the decommissioned phase, the major concern is with the potential effects of earthquakes on the geologic formation, which may result in a reduction in isolation capacity. Existing standards and guides or criteria used for the static and seismic design of licensed nuclear facilities were reviewed and evaluated for their applicability to repository design. This report is directed mainly toward the development of seismic design criteria for the underground structures of repositories. An initial step in the development of seismic design criteria for the underground structures of repositories is the development of performance criteria, or minimum standards of acceptable behavior. A number of possible damage modes are identified for the operating phase of the repository; however, no damage modes are foreseen that would perturb the long-term function of the repository, except for the possibility of increased permeability within the rock mass. Subsequent steps in formulating acceptable seismic design criteria for the underground structures involve the quantification of the design process. The report discusses the necessity of specifying the form of ground motion that would be needed for seismic analysis and the procedures that may be used for making ground motion predictions. Further discussions outline what is needed for analysis, including rock properties, failure criteria, modeling techniques, seismic hardening criteria for the host rock mass, and probabilistic considerations

FFTBM and primary pressure acceptance criterion

International Nuclear Information System (INIS)

Prosek, A.

2004-01-01

When thermalhydraulic computer codes are used for simulation in the area of nuclear engineering the question is how to conduct an objective comparison between the code calculation and measured data. To answer this the fast Fourier transform based method (FFTBM) was developed. When the FFTBM method was developed the acceptance criteria for primary pressure and total accuracy were set. In the recent study the FFTBM method was used for accuracy quantification of RD-14M large LOCA test B9401 calculations. The blind accuracy analysis indicated good total accuracy while the primary pressure criterion was not fulfilled. The objective of the study was therefore to investigate the reasons for not fulfilling the primary pressure acceptance criterion and the applicability of the criterion to experimental facilities simulating heavy water reactor. The results of the open quantitative analysis showed that sensitivity analysis for influence parameters provide sufficient information to judge in which calculation the accuracy of primary pressure is acceptable. (author)

Qualification criteria to certify a package for air transport of plutonium

International Nuclear Information System (INIS)

1977-12-01

The document describes qualification criteria developed by the U.S. Nuclear Regulatory Commission to certify a package for air transport of plutonium. Included in the document is a discussion of aircraft accident conditions and a summary of the technical basis for the qualification criteria. The criteria require prototype packages to be subjected to various individual and sequential tests that simulate the conditions produced in severe aircraft accidents. Specific post-test acceptance standards are prescribed for each of the three safety functions of a package. The qualification criteria also prescribe certain operational controls to be exercised during transport

Preliminary estimates of the impacts of alternative spent fuel acceptance rates

International Nuclear Information System (INIS)

Clark, L.L.; McKee, R.W.; Short, S.M.

1986-02-01

The rate at which spent fuel is accepted by the federal waste management system is an important interface between the private nuclear power sector and the federal government, which will assume responsibility for spent fuel disposal. An analysis of alternative rates based on minimum age criteria indicates substantial incentives to limit acceptance rates so as to result in minimum 10 to 15 year fuel ages for repository acceptance [1500 to 2500 metric tons of uranium (MTU) per year]. These incentives include lower heat generation rates and systems costs

A Statistical Approach for Deriving Key NFC Evaluation Criteria

Energy Technology Data Exchange (ETDEWEB)

Kim, S. K; Kang, G. B.; Ko, W. I [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Young, S. R.; Gao, R. X. [Univ. of Science and Technology, Daejeon (Korea, Republic of)

2014-02-15

This study suggests 5 evaluation criteria (safety and technology, environmental impact, economic feasibility, social factors, and institutional factors) and 24 evaluation indicators for a NFC (nuclear fuel cycle) derived using factor analysis. To do so, a survey using 1 on 1 interview was given to nuclear energy experts and local residents who live near nuclear power plants. In addition, by conducting a factor analysis, homogeneous evaluation indicators were grouped with the same evaluation criteria, and unnecessary evaluation criteria and evaluation indicators were dropped out. As a result of analyzing the weight of evaluation criteria with the sample of nuclear power experts and the general public, both sides recognized safety as the most important evaluation criterion, and the social factors such as public acceptance appeared to be ranked as more important evaluation criteria by the nuclear energy experts than the general public.

A Statistical Approach for Deriving Key NFC Evaluation Criteria

International Nuclear Information System (INIS)

Kim, S. K; Kang, G. B.; Ko, W. I; Young, S. R.; Gao, R. X.

2014-01-01

This study suggests 5 evaluation criteria (safety and technology, environmental impact, economic feasibility, social factors, and institutional factors) and 24 evaluation indicators for a NFC (nuclear fuel cycle) derived using factor analysis. To do so, a survey using 1 on 1 interview was given to nuclear energy experts and local residents who live near nuclear power plants. In addition, by conducting a factor analysis, homogeneous evaluation indicators were grouped with the same evaluation criteria, and unnecessary evaluation criteria and evaluation indicators were dropped out. As a result of analyzing the weight of evaluation criteria with the sample of nuclear power experts and the general public, both sides recognized safety as the most important evaluation criterion, and the social factors such as public acceptance appeared to be ranked as more important evaluation criteria by the nuclear energy experts than the general public

Preliminary waste acceptance requirements for the planned Konrad repository

International Nuclear Information System (INIS)

Warnecke, E.; Brennecke, P.

1987-01-01

The Physikalisch-Technische Bundesanstalt (PTB) has established Preliminary Waste Acceptance Requirements for the planned Konrad repository. These requirements were developed, in accordance with the Safety Criteria of the Reactor Safety Commission, with the help of a site specific safety assessment; they are under the reservation of the plan approval procedure, which is still in progress. In developing waste acceptance requirements, the PTB fulfills one of its duties as the institute responsible for waste disposal and gives guidelines for waste conditioning to waste producers and conditioners. (orig.) [de

Preliminary Systems Design Study assessment report

International Nuclear Information System (INIS)

Mayberry, J.L.; Feizollahi, F.; Del Signore, J.C.

1992-01-01

The System Design Study (SDS), part of the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examined techniques for the remediation of hazardous and transuranic waste stored at Radioactive Waste Management Complex's Subsurface Disposal Area at the INEL. Using specific technologies, system concepts for treating the buried waste and the surrounding contaminated soil were evaluated. Evaluation included implementability, effectiveness, and cost. The SDS resulted in the development of technology requirements including demonstration, testing, and evaluation activities needed for implementing each concept. This volume contains introduction section containing a brief SDS background and lists the general assumptions and considerations used during the development of the system concepts. The introduction section is followed by sections describing two system concepts that produce a waste form in compliance with the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC) and transportation package (TRAMPAC) requirements. This system concept category is referred to as Waste Form 4, ''WIPP and TRAMPAC Acceptable.'' The following two system concepts are under this category: Sort, Treat, and Repackage System (4-BE-2); Volume Reduction and Packaging System (4-BE-4)

A Systematic Review of Patient Acceptance of Consumer Health Information Technology

OpenAIRE

Karsh, BT; Or, CKL

2009-01-01

A systematic literature review was performed to identify variables promoting consumer health information technology (CHIT) acceptance among patients. The electronic bibliographic databases Web of Science, Business Source Elite, CINAHL, Communication and Mass Media Complete, MEDLINE, PsycArticles, and PsycInfo were searched. A cited reference search of articles meeting the inclusion criteria was also conducted to reduce misses. Fifty-two articles met the selection criteria. Among them, 94 diff...

SLUDGE BATCH 5 ACCEPTANCE EVALUATION RADIONUCLIDE CONCENTRATIONS IN TANK 51 SB5 QUALIFICATION SAMPLE PREPARED AT SRNL

International Nuclear Information System (INIS)

Bannochie, C; Ned Bibler, N; David Diprete, D

2008-01-01

Presented in this report are radionuclide concentrations required as part of the program of qualifying Sludge Batch Five (SB5) for processing in the Defense Waste Processing Facility (DWPF). Part of this SB5 material is currently in Tank 51 being washed and prepared for transfer to Tank 40. The acceptance evaluation needs to be completed prior to the transfer of the material in Tank 51 to Tank 40 to complete the formation of SB5. The sludge slurry in Tank 40 has already been qualified for DWPF and is currently being processed as SB4. The radionuclide concentrations were measured or estimated in the Tank 51 SB5 Qualification Sample prepared at Savannah River National Laboratory (SRNL). This sample was prepared from the three liter sample of Tank 51 sludge slurry taken on March 21, 2008. The sample was delivered to SRNL where it was initially characterized in the Shielded Cells. Under direction of the Liquid Waste Organization it was then modified by five washes, six decants, an addition of Pu/Be from Canyon Tank 16.4, and an addition of NaNO2. This final slurry now has a composition expected to be similar to that of the slurry in Tank 51 after final preparations have been made for transfer of that slurry to Ta Determining the radionuclide concentrations in this Tank 51 SB5 Qualification Sample is part of the work requested in Technical Task Request (TTR) No. HLW-DWPF-TTR-2008-0010. The work with this qualification sample is covered by a Task Technical and Quality Assurance Plan and an Analytical Study Plan. The radionuclides included in this report are needed for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria (TSR/WAC) Evaluation, and the DWPF Solid Waste Characterization Program (TTR Task 2). Radionuclides required to meet the Waste Acceptance Product Specifications (TTR Task 5) will be measured at a later date after the slurry from Tank 51 has been transferred to Tank 40. Then a sample of the as-processed SB5 will be taken and

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.

Early Site Permit Demonstration Program: Regulatory criteria evaluation report

Energy Technology Data Exchange (ETDEWEB)

1993-03-01

The primary objective of the ESPDP is to demonstrate successfully the use of 10CFR52 to obtain ESPs for one or more US sites for one (or more) ALWR nuclear power plants. It is anticipated that preparation of the ESP application and interaction with NRC during the application review process will result not only in an ESP for the applicant(s) but also in the development of criteria and definition of processes, setting the precedent that facilitates ESPs for subsequent ESP applications. Because siting regulatory processes and acceptance criteria are contained in over 100 separate documents, comprehensive licensing and technical reviews were performed to establish whether the requirements and documentation are self-consistent, whether the acceptance criteria are sufficiently well-defined and clear, and whether the licensing process leading to the issuance of an ESP is unambiguously specified. The results of the technical and licensing evaluations are presented in this report. The purpose, background, and organization of the ESPDP is delineated in Section 1. Section 11 contains flowcharts defining siting application requirements, environmental report requirements, and emergency planning/preparedness requirements for ALWRS. The licensing and technical review results are presented in Section III.

Early Site Permit Demonstration Program: Regulatory criteria evaluation report

International Nuclear Information System (INIS)

1993-03-01

The primary objective of the ESPDP is to demonstrate successfully the use of 10CFR52 to obtain ESPs for one or more US sites for one (or more) ALWR nuclear power plants. It is anticipated that preparation of the ESP application and interaction with NRC during the application review process will result not only in an ESP for the applicant(s) but also in the development of criteria and definition of processes, setting the precedent that facilitates ESPs for subsequent ESP applications. Because siting regulatory processes and acceptance criteria are contained in over 100 separate documents, comprehensive licensing and technical reviews were performed to establish whether the requirements and documentation are self-consistent, whether the acceptance criteria are sufficiently well-defined and clear, and whether the licensing process leading to the issuance of an ESP is unambiguously specified. The results of the technical and licensing evaluations are presented in this report. The purpose, background, and organization of the ESPDP is delineated in Section 1. Section 11 contains flowcharts defining siting application requirements, environmental report requirements, and emergency planning/preparedness requirements for ALWRS. The licensing and technical review results are presented in Section III

Acceptance test report for the Westinghouse 100 ton hydraulic trailer

International Nuclear Information System (INIS)

Barrett, R.A.

1995-01-01

The SY-101 Equipment Removal System 100 Ton Hydraulic Trailer was designed and built by KAMP Systems, Inc. Performance of the Acceptance Test Procedure at KAMP's facility in Ontario, California (termed Phase 1 in this report) was interrupted by discrepancies noted with the main hydraulic cylinder. The main cylinder was removed and sent to REMCO for repair while the trailer was sent to Lampson's facility in Pasco, Washington. The Acceptance Test Procedure was modified and performance resumed at Lampson (termed Phase 2 in this report) after receipt of the repaired cylinder. At the successful conclusion of Phase 2 testing the trailer was accepted as meeting all the performance criteria specified

The role of natural analogues in safety assessment and acceptability

International Nuclear Information System (INIS)

Papp, Toenis

1987-01-01

The safety assessment must evaluate the level of safety for a repository, the confidence that can be placed on the assessment and how well the repository can meet the acceptance criteria of the society. Many of the processes and phenomena that govern the long term performance of a deep geologic repository for radioactive waste also take place in nature. To investigate these natural analogues and try to validate the models on which the safety assessment are based is a main task in the effort to build of confidence in the safety assessments. The assessment of the safety of a repository can, however, not only be based on good models. The possible role of natural analogues or natural evidence in other parts of the safety assessment is discussed. Specially with regard to - the need to demonstrate that all relevant processes have been taken into account, and that the important ones have been validated to an acceptable level for relevant parameters spans, -the definition and analysis of external scenarios for the safety assessment and for the claim that all reasonable scenarios have been addressed, - the public confidence in the long-term relevance of the acceptance criteria. (author)

Seismic design criteria for the system 80+ advanced light water reactor

International Nuclear Information System (INIS)

Manrique, M.A.; Dermitzakis, S.N.; Gerdes, L.D.; Kennedy, R.P.; Idriss, I.M.; Cassidy, J.R.

1991-01-01

This paper presents the development of seismic design criteria in support of design certification by the Nuclear Regulatory Commission (NRC) of the ABB-Combustion Engineering's System 80+ Standard Design. The design certification effort is sponsored by the US Department of Energy (DOE). The development of the design criteria included: (a) development of the seismic control motion, (b) development of generic soil profiles for anticipated sites, (c) generation of in-structure response spectra and design loads for structures and equipment through soil-structure interaction (SSI) analyses, and (d) acceptance criteria for future construction sites

Feasibility and acceptability of electronic symptom surveillance with clinician feedback using the Patient-Reported Outcomes version of Common Terminology Criteria for Adverse Events (PRO-CTCAE) in Danish prostate cancer patients

DEFF Research Database (Denmark)

Bæksted, Christina; Pappot, Helle; Nissen, Aase

2017-01-01

-CTCAE questionnaire on tablet computers using AmbuFlex software at each treatment visit in the outpatient clinic. In total, 22 symptomatic toxicities (41 PRO-CTCAE items), corresponding to the symptomatic adverse-events profile associated with the regimens commonly used for prostate cancer treatment (Docetaxel......Background: The aim was to examine the feasibility, acceptability and clinical utility of electronic symptom surveillance with clinician feedback using a subset of items drawn from the Patient-Reported Outcomes version of Common Terminology Criteria for Adverse Events (PRO-CTCAE) in a cancer...

Variability amongst radiographers in the categorization of clinical acceptability for digital trauma radiography

Science.gov (United States)

Decoster, Robin; Toomey, Rachel; Smits, Dirk; Mol, Harrie; Verhelle, Filip; Butler, Marie-Louise

2016-03-01

Introduction: Radiographers evaluate anatomical structures to judge clinical acceptability of a radiograph. Whether a radiograph is deemed acceptable for diagnosis or not depends on the individual decision of the radiographer. Individual decisions cause variation in the accepted image quality. To minimise these variations definitions of acceptability, such as in RadLex, were developed. On which criteria radiographers attribute a RadLex categories to radiographs is unknown. Insight into these criteria helps to further optimise definitions and reduce variability in acceptance between radiographers. Therefore, this work aims the evaluation of the correlation between the RadLex classification and the evaluation of anatomical structures, using a Visual Grading Analysis (VGA) Methods: Four radiographers evaluated the visibility of five anatomical structures of 25 lateral cervical spine radiographs on a secondary class display with a VGA. They judged clinical acceptability of each radiograph using RadLex. Relations between VGAS and RadLex category were analysed with Kendall's Tau correlation and Nagelkerke pseudo-R². Results: The overall VGA score (VGAS) and the RadLex score correlate (rτ= 0.62, pscore. The reproduction of spinous processes (rτ=0.67, pscore. Conclusion: RadLex scores and VGAS correlate positively, strongly and significantly. The predictive value of bony structures may support the use of these in the judgement of clinical acceptability. Considerable inter-observer variations in the VGAS within a certain RadLex category, suggest that observers use of observer specific cut-off values.

Acceptance criteria for reprocessed AcuNav catheters: comparison between functionality testing and clinical image assessment.

Science.gov (United States)

Bank, Alan J; Berry, James M; Wilson, Robert F; Lester, Bruce R

2009-03-01

The AcuNav-catheter is a vector-phased array ultrasound catheter that has shown great utility for both diagnosis and electrophysiological interventions. To test the feasibility of limited catheter reuse and to ensure that reprocessed catheters would produce acceptable clinical images, the present study compared the 2-D and Doppler image quality, as determined by clinical assessment, with the catheter's functional status as determined by the FirstCall 2000 transducer tester. Reprocessed catheters from four functional categories, two acceptable and two unacceptable, were used to collect images, 2-D and Doppler, from a porcine heart. The images were blinded and then rated by clinical evaluation. The study found that catheter images from all functional categories were found to be clinically acceptable except for those from the lowest unacceptable category. In addition, examination of tip deflection characteristics showed no significant difference between new and reprocessed catheters. We conclude that reprocessed AcuNav catheters that pass functional tests are able to produce clinical images, 2-D and Doppler, which are equivalent to their new counterparts.

Dysplastic naevus: histological criteria and their inter-observer reproducibility.

Science.gov (United States)

Hastrup, N; Clemmensen, O J; Spaun, E; Søndergaard, K

1994-06-01

Forty melanocytic lesions were examined in a pilot study, which was followed by a final series of 100 consecutive melanocytic lesions, in order to evaluate the inter-observer reproducibility of the histological criteria proposed for the dysplastic naevus. The specimens were examined in a blind fashion by four observers. Analysis by kappa statistics showed poor reproducibility of nuclear features, while reproducibility of architectural features was acceptable, improving in the final series. Consequently, we cannot apply the combined criteria of cytological and architectural features with any confidence in the diagnosis of dysplastic naevus, and, until further studies have documented that architectural criteria alone will suffice in the diagnosis of dysplastic naevus, we, as pathologists, shall avoid this term.

Spent nuclear fuel project-criteria document Cold Vacuum Drying Facility phase 2 safety analysis report

International Nuclear Information System (INIS)

Garvin, L.J.

1998-01-01

The criteria document provides the criteria and guidance for developing the SNF CVDF Phase 2 SAR. This SAR will support the US Department of Energy, Richland Operations Office decision to authorize the procurement, installation, and installation acceptance testing of the CVDF systems

Acceptance test report, plutonium finishing plant life safety upgrade

International Nuclear Information System (INIS)

Hodge, S.G.

1994-01-01

This acceptance Test Procedure (ATP) has been prepared to demonstrate that modifications to the Fir Protection systems function as required by project criteria. The ATP will test the Fire Alarm Control Panels, Flow Alarm Pressure Switch, Heat Detectors, Smoke Detectors, Flow Switches, Manual Pull Stations, and Gong/Door By Pass Switches

Acceptance test report for the Westinghouse 100 ton hydraulic trailer

Energy Technology Data Exchange (ETDEWEB)

Barrett, R.A.

1995-03-06

The SY-101 Equipment Removal System 100 Ton Hydraulic Trailer was designed and built by KAMP Systems, Inc. Performance of the Acceptance Test Procedure at KAMP`s facility in Ontario, California (termed Phase 1 in this report) was interrupted by discrepancies noted with the main hydraulic cylinder. The main cylinder was removed and sent to REMCO for repair while the trailer was sent to Lampson`s facility in Pasco, Washington. The Acceptance Test Procedure was modified and performance resumed at Lampson (termed Phase 2 in this report) after receipt of the repaired cylinder. At the successful conclusion of Phase 2 testing the trailer was accepted as meeting all the performance criteria specified.

Development of flaw evaluation and acceptance procedures for flaw indications in the cooling water system at the Savannah River site K reactor

International Nuclear Information System (INIS)

Tandon, S.; Bamford, W.H.; Cowfer, C.D.; Ostrowski, R.

1993-01-01

This paper describes the methodology used in determining the criteria for acceptance of inspection indications in the K-Reactor Cooling Water System at the Savannah River Plant. These criteria have been developed in a manner consistent with the development of similar criteria in the ASME Code Section XI for commercial light water reactors, but with a realistic treatment of the operating conditions in the cooling water system. The technical basis for the development of these criteria called ''Acceptance Standards'' is contained in this paper. A second portion of this paper contains the methodology used in the construction of flaw evaluation charts which have been developed for each specific line size in the cooling water system. The charts provide the results of detailed fracture mechanics calculations which have been completed to determine the largest flaw which can be accepted in the cooling water system without repair. These charts are designed for use in conjunction with in-service inspections of the cooling water system, and only require inspection results to determine acceptability

Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program

International Nuclear Information System (INIS)

2005-01-01

The Performance Demonstration Program (PDP) for Nondestructive Assay (NDA) is a test program designed to yield data on measurement system capability to characterize drummed transuranic (TRU) waste generated throughout the Department of Energy (DOE) complex. The tests are conducted periodically and provide a mechanism for the independent and objective assessment of NDA system performance and capability relative to the radiological characterization objectives and criteria of the Office of Characterization and Transportation (OCT). The primary documents requiring an NDA PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC), which requires annual characterization facility participation in the PDP, and the Quality Assurance Program Document (QAPD). This NDA PDP implements the general requirements of the QAPD and applicable requirements of the WAC. Measurement facilities must demonstrate acceptable radiological characterization performance through measurement of test samples comprised of pre-specified PDP matrix drum/radioactive source configurations. Measurement facilities are required to analyze the NDA PDP drum samples using the same procedures approved and implemented for routine operational waste characterization activities. The test samples provide an independent means to assess NDA measurement system performance and compliance per criteria delineated in the NDA PDP Plan. General inter-comparison of NDA measurement system performance among DOE measurement facilities and commercial NDA services can also be evaluated using measurement results on similar NDA PDP test samples. A PDP test sample consists of a 55-gallon matrix drum containing a waste matrix type representative of a particular category of the DOE waste inventory and nuclear material standards of known radionuclide and isotopic composition typical of DOE radioactive material. The PDP sample components are made available to participating measurement facilities as designated by the

New contact boiling experiments to evaluate Calandria tube strain acceptance criteria

Energy Technology Data Exchange (ETDEWEB)

El-Hawary, M.; Szymanski, J.; Tanase, A.; Delja, A.; Oussoren, A., E-mail: Magdy.El-Hawary@cnsc-ccsn.gc.ca [Canadian Nuclear Safety Comission, Ottawa, ON (Canada); Neal, P. [Canadian Nuclear Laboratories, Chalk River, ON (Canada)

2015-07-01

The Canadian Nuclear Safety Commission(CNSC) has contracted the Canadian Nuclear Laboratories(CNL) to conduct additional Contact Boiling (CB) experiments with the main objective of evaluating the acceptance criterion of CalandriaTube (CT) strain limit of 2%, proposed by the industry for fuel channel integrity assessments. The test conditions are selected using analytical tools and guidance from existing CANDU Owners Group (COG) test results, so as to lead to CT strain close to this value. The experiments will also be used to evaluate the CT quench temperature correlation proposed. This paper presents conditions selected for the first three experiments, their most important results and their preliminary analysis, with a focus on the test which produced CT strain in excess of 2%. (author)

Upgraded acceptance criteria from transient thermography control for the W7-X divertor target elements

Energy Technology Data Exchange (ETDEWEB)

Missirlian, M. [CEA, IRFM, F-13108 Saint-Paul-Lez-Durance (France)], E-mail: marc.missirlian@cea.fr; Boscary, J. [Max-Planck-Institut fuer Plasmaphysik, Euratom Association, Boltzmannstr. 2, D-85748 Garching (Germany); Guigon, R.; Schlosser, J.; Durocher, A. [CEA, IRFM, F-13108 Saint-Paul-Lez-Durance (France); Greuner, H. [Max-Planck-Institut fuer Plasmaphysik, Euratom Association, Boltzmannstr. 2, D-85748 Garching (Germany)

2009-06-15

The commissioning of plasma-facing component fields needs advanced non-destructive methods to detect in a reliable way the defects, which can impair the component performances and/or integrity during operation. Within this framework, CEA developed a dedicated non-destructive examination method based on active infrared thermography (SATIR facility) to inspect the bonding between armour material and metallic heat sink. Used with successful in the commissioning of the toroidal pump limiter of Tore Supra, this technique was applied in the frame of the pre-series activities of the Wendelstein 7-X high heat flux divertor elements to assess the bonding quality of the delivered components. This paper presents the methodology adopted to define an acceptance criterion based on SATIR test bed possibly applied for a serial inspection of the Wendelstein 7-X elements. Using the well-tried acceptance test based on the DTref{sub m}ax parameter, the new method includes advanced data post-processing techniques from thermo-signal SATIR and a data merging method to help the decision-making and to optimise the reliability of the binary response expected for a final decision in terms of acceptance test.

Upgraded acceptance criteria from transient thermography control for the W7-X divertor target elements

International Nuclear Information System (INIS)

Missirlian, M.; Boscary, J.; Guigon, R.; Schlosser, J.; Durocher, A.; Greuner, H.

2009-01-01

The commissioning of plasma-facing component fields needs advanced non-destructive methods to detect in a reliable way the defects, which can impair the component performances and/or integrity during operation. Within this framework, CEA developed a dedicated non-destructive examination method based on active infrared thermography (SATIR facility) to inspect the bonding between armour material and metallic heat sink. Used with successful in the commissioning of the toroidal pump limiter of Tore Supra, this technique was applied in the frame of the pre-series activities of the Wendelstein 7-X high heat flux divertor elements to assess the bonding quality of the delivered components. This paper presents the methodology adopted to define an acceptance criterion based on SATIR test bed possibly applied for a serial inspection of the Wendelstein 7-X elements. Using the well-tried acceptance test based on the DTref m ax parameter, the new method includes advanced data post-processing techniques from thermo-signal SATIR and a data merging method to help the decision-making and to optimise the reliability of the binary response expected for a final decision in terms of acceptance test.

Data quality objectives summary report for the 107-N Basin recirculation building liquid/sediment

International Nuclear Information System (INIS)

Nossardi, O.A.; Miller, M.S.; Carlson, D.

1997-01-01

The scope of the 107-N Basin Recirculation Facility Liquid/Sediment Data Quality Objectives (DQO) exclusively involves the determination of sampling and analytical requirements during the deactivation period. The sampling requirements are primarily directed at sample characterization for comparison to decontamination and decommissioning (D and D) endpoint acceptance criteria in preparation for turnover of the facilities (listed below) to D and D organization. If determined to be waste, the sample characterization is also used for comparison with the waste acceptance criteria (WAC) of the receiving facilities for selection of the appropriate disposition. Additionally, the data generated from the characterization will be used to support the selection of available disposition options. The primary media within the scope of this DQO includes the following: Accumulated liquids and sediment contained in tanks, vessels, pump wells, sumps, associated piping, and valve pit floors; and Limited solid debris (anticipated to be discovered). Although the title of this report refers only to the 107-N Basin Recirculation Building, this DQO encompasses the following four 100-N Buildings/areas: 1310-N valve pit area inside the Radioactive Chemical Waste Treatment Pump House (silo); 1314-N Waste Pump (Overflow) Tank at the Liquid Waste Disposal Station; 105-N Lift Station pump well and valve pit areas inside the 105-N Reactor Building; and 107-N Basin Recirculation Building

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

Design criteria for the structural analysis of shipping cask containment vessels

International Nuclear Information System (INIS)

Anon.

1979-01-01

10 CFR Part 71, Sections 71.35 and 71.36, require that packages used to transport radioactive materials meet specified normal and hypothetical accident conditions. Acceptable design criteria are presented for use in the structural analysis of the containment vessels of Type B packages used to transport irradiated nuclear fuel. Alternative design criteria meeting the structural requirements of 10 CFR Part 71, Section 71.35 and 71.36, may also be used

Independent review of Oak Ridge HCTW test program and development of seismic evaluation criteria

International Nuclear Information System (INIS)

1995-05-01

Many of the existing buildings at the Oak Ridge Y-12 Plant are steel frame construction with unreinforced hollow clay tile infill walls (HCTW). The HCTW infill provides some lateral seismic resistance to the design/evaluation basis earthquake; however acceptance criteria for this construction must be developed. The basis for the development of seismic criteria is the Oak Ridge HCTW testing and analysis program and the target performance goals of DOE 5480.28 and DOE-STD-1020-94. This report documents and independent review of the testing and analysis program and development of recommended acceptance criteria for Oak Ridge HCTW construction. The HCTW test program included ''macro'' wall in-plane and out-of-plane tests, full-scale wall in-plane and out-of-plane tests, in-situ out-of-plane test, shake table tests, and masonry component tests

Acceptance criteria for the evaluation of Category 1 fuel cycle facility physical security plans

Energy Technology Data Exchange (ETDEWEB)

Dwyer, P.A.

1991-10-01

This NUREG document presents criteria developed from US Nuclear Regulatory Commission regulations for the evaluation of physical security plans submitted by Category 1 fuel facility licensees. Category 1 refers to those licensees who use or possess a formula quantity of strategic special nuclear material.

Acceptance criteria for the evaluation of Category 1 fuel cycle facility physical security plans

International Nuclear Information System (INIS)

Dwyer, P.A.

1991-10-01

This NUREG document presents criteria developed from US Nuclear Regulatory Commission regulations for the evaluation of physical security plans submitted by Category 1 fuel facility licensees. Category 1 refers to those licensees who use or possess a formula quantity of strategic special nuclear material

Analysis of existing work-zone devices with MASH safety performance criteria.

Science.gov (United States)

2009-02-01

Crashworthy, work-zone, portable sign support systems accepted under NCHRP Report No. 350 were analyzed to : predict their safety peformance according to the TL-3 MASH evaluation criteria. An analysis was conducted to determine : which hardware param...

International comparison of safety criteria applied to radwaste repositories. Safety aspects of the post-operational phase

International Nuclear Information System (INIS)

Baltes, B.

1994-01-01

There is a generally accepted system of framework safety conditions governing the construction, operation, and post-operational monitoring of radwaste repositories. Although the development of these framework conditions may vary from country to country, the resulting criteria are based on the commonly accepted system of priciples and purposes established for ultimate radioactive waste disposal. The experience accumulated by GRS in the course of the plan approval procedure for the Konrad mine site and the safety-relevant studies performed for the planned Morsleben repository clearly show demand for further development of the safety criteria. In Germany, it is especially the safety criteria and detailed requirements filling the framework safety conditions that need revision and in-depth definition, as well as comparison and harmonisation with internationally applied criteria. These activities will particularly consider the international convention on radioactive waste management currently in preparation under the auspieces of the IAEA. (orig.) [de

Development of small reactor safety criteria in Canada

International Nuclear Information System (INIS)

Ernst, P.C.; French, P.M.; Axford, D.J.; Snell, V.G.

1990-01-01

A number of new small reactor designs have been proposed in Canada over the last several years and some have reached the stage where licensing discussions have been initiated with the Atomic Energy Control Board (AECB). An inter-organizational Small Reactor Criteria (SRC) working group was formed in 1988 to propose safety and licensing criteria for these small reactors. Two levels of criteria are proposed. The first level forms a safety philosophy and the second is a set of criteria for specific reactor applications. The safety philosophy consists of three basic safety objectives together with evaluation criteria, and fourteen fundamental principles measured by specific criteria, which must be implemented to meet the safety objectives. Two of the fourteen principles are prime: defence in depth, and safety culture; the other twelve principles can be seen as deriving from them. A benefit of this approach is that the concepts of defence in depth and safety culture become well-defined. The objectives and principles are presented in the paper and their criteria are summarized. The second level of criteria, under development, will form a safety application set and will provide small reactor criteria in a number of general areas, such as regulatory process and safety assessment, as well as for specific reactor life-cycle activities, from siting through to decommissioning. The criteria are largely deterministic. However, the frequencies and consequences of postulated accidents are assessed against numerical criteria to assist in judging the acceptability of plant design, operation, and proposed siting. All criteria proposed are designed to be testable in some evidentiary fashion, readily enabling an assessment of compliance for a given proposal

Criteria for candidate species for aquaculture

Energy Technology Data Exchange (ETDEWEB)

Webber, H H; Riordan, P F

1976-01-01

The nature of the animal taxa that are the most probable candidates for an intensive, commercial aquatic animal husbandry industry is considered. A characterization is presented of those biological criteria that lend the species the necessary physiological and genetic malleability to be adapted and molded into a domesticated race. The animal cultivated must be amenable to intensive management in high-density confinements such as those now being engineered for high-yield aquaculture. Attributes considered are discussed in the context of the various aquacultural ecosystems in which the specific biotype is expected to achieve satisfactory growth and survival. Correlative with bionomic criteria, economic requirements are posed and evaluated in an effort to define a socially and financially profitable agribusiness system. Investment requirements and operating costs are considered in terms of expected returns. However, since production alone is insufficient to sustain an enterprise - i.e., the product must be sold - production costs must be judged against market values. Therefore, ultimate use or consumer acceptance criteria are incorporated into the list of essential requirements for a candidate species for aquafarming.

Waste Receiving and Processing (WRAP) facility engineering study

International Nuclear Information System (INIS)

Christie, M.A.; Cammann, J.W.; McBeath, R.S.; Rode, H.H.

1985-01-01

A new Hanford waste management facility, the Waste Receiving and Processing (WRAP) facility (planned to be operational by FY 1994) will receive, inspect, process, and repackage contact-handled transuranic (CH-TRU) contaminated solid wastes. The wastes will be certified according to the waste acceptance criteria for disposal at the Waste Isolation Pilot Plant (WIPP) geologic repository in southeast New Mexico. Three alternatives which could cost effectively be applied to certify Hanford CH-TRU waste to the WIPP Waste Acceptance Criteria (WIPP-WAC) have been examined in this updated engineering study. The alternatives differed primarily in the reference processing systems used to transform nonconforming waste into an acceptable, certified waste form. It is recommended to include the alternative of shredding and immobilizing nonconforming wastes in cement (shred/grout processing) in the WRAP facility. Preliminary capital costs for WRAP in mid-point-of-construction (FY 1991) dollars were estimated at $45 million for new construction and $37 million for modification and installation in an existing Hanford surplus facility (231-Z Building). Operating, shipping, and decommissioning costs in FY 1986 dollars were estimated at $126 million, based on a 23-y WRAP life cycle (1994 to 2017). During this period, the WRAP facility will receive an estimated 38,000 m 3 (1.3 million ft 3 ) of solid CH-TRU waste. The study recommends pilot-scale testing and evaluation of the processing systems planned for WRAP and advises further investigation of the 231-Z Building as an alternative to new facility construction

Criteria for cesium capsules to be shipped as special form radioactive material

International Nuclear Information System (INIS)

Lundeen, J.E.

1994-01-01

The purpose of this report is to compile all the documentation which defines the criteria for Waste Encapsulation and Storage Facility (WESF) cesium capsules at the IOTECH facility and Applied Radiant Energy Corporation (ARECO) to be shipped as special form radioactive material in the Beneficial Uses Shipping System (BUSS) Cask. The capsules were originally approved as special form in 1975, but in 1988 the integrity of the capsules came into question. WHC developed the Pre-shipment Acceptance Test Criteria for capsules to meet in order to be shipped as special form material. The Department of Energy approved the criteria and directed WHC to ship the capsules at IOTECH and ARECO meeting this criteria to WHC as special form material

The acceptability of the female and male condom: a randomized crossover trial.

Science.gov (United States)

Kulczycki, Andrzej; Kim, Dhong-Jin; Duerr, Ann; Jamieson, Denise J; Macaluso, Maurizio

2004-01-01

Although studies have assessed the acceptability of male and female condoms, comparative trial data are lacking. A sample of 108 women in stable relationships recruited from an urban, reproductive health clinic were randomly assigned to use 10 male or female condoms, followed by use of 10 of the other type. A nurse provided instruction in correct method use. Demographic information was collected in a baseline questionnaire; acceptability data were collected in follow-up and exit questionnaires and coital logs. Nonparametric and chi-square statistics were used to analyze measures of the methods' relative acceptability. Bowker's test of symmetry was adapted to test the null hypothesis of no difference in acceptability between condom types. Participants used 678 female and 700 male condoms. Although neither method scored high on user satisfaction measures, the 63 women completing the study protocol preferred the male condom to the female condom for ease of application or insertion, ease of removal, general fit, feel of the condom during intercourse and ease of penetration. Participants reported that their partner also favored the male condom, although women generally appeared to like this method more than their partner did. In a direct comparison between the methods at the end of the study, women generally judged male condoms superior on specified preference criteria. Across a range of criteria, the female condom was less acceptable than the male condom to most women and their partners. Although both types had low acceptability, they are needed and valid methods of pregnancy and disease prevention. That neither rated high on user satisfaction measures underscores the need for more barrier methods that women and men can use.

Reportable Nuclide Criteria for ORNL Radioactive Waste Management Activities - 13005

International Nuclear Information System (INIS)

McDowell, Kip; Forrester, Tim; Saunders, Mark

2013-01-01

The U.S. Department of Energy's Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee generates numerous radioactive waste streams. Many of those streams contain a large number of radionuclides with an extremely broad range of concentrations. To feasibly manage the radionuclide information, ORNL developed reportable nuclide criteria to distinguish between those nuclides in a waste stream that require waste tracking versus those nuclides of such minimal activity that do not require tracking. The criteria include tracking thresholds drawn from ORNL onsite management requirements, transportation requirements, and relevant treatment and disposal facility acceptance criteria. As a management practice, ORNL maintains waste tracking on a nuclide in a specific waste stream if it exceeds any of the reportable nuclide criteria. Nuclides in a specific waste stream that screen out as non-reportable under all these criteria may be dropped from ORNL waste tracking. The benefit of these criteria is to ensure that nuclides in a waste stream with activities which meaningfully affect safety and compliance are tracked, while documenting the basis for removing certain isotopes from further consideration. (authors)

General criteria for radioactive waste disposal

International Nuclear Information System (INIS)

Maxey, M.N.; Musgrave, B.C.; Watkins, G.B.

1979-01-01

Techniques are being developed for conversion of radioactive wastes to solids and their placement into repositories. Criteria for such disposal are needed to assure protection of the biosphere. The ALARA (as low as reasonably achievable) principle should be applicable at all times during the disposal period. Radioactive wastes can be categorized into three classes, depending on the activity. Three approaches were developed for judging the adequacy of disposal concepts: acceptable risk, ore body comparison, and three-stage ore body comparison

Emotional and Spiritual Quotient Approach Improve Biology Education Students’ Acceptance of Evolution Theory

Science.gov (United States)

Darussyamsu, R.; Fadilah, M.; Putri, D. H.

2018-04-01

Emotional and spiritual aspect is one of main factors that influence students’ acceptance of a theory. This study aim to measure university students’ acceptance of evolution by learns evolution using emotional and spiritual quotient (ESQ) approach. This is a quasi-experimental research using one shot case study design with the subject 36 biology educational students at Biology Department, Faculty of Mathematics and Natural Science, Universitas Negeri Padang. Data collected using the MATE instrument by Rutledge and Warden (2000) after the students learn evolution for eight meetings since January until March 2017. The result showed that by learning evolution theory combine with ESQ aspects increase students acceptance from very low become moderate acceptance. It concluded that ESQ aspects can improve students’ acceptance of evolution. Any criteria depend on it are discussed.

The use of fracture mechanics for the evaluation of NDE flaw acceptance standards

Energy Technology Data Exchange (ETDEWEB)

Alicino, A; Capurro, E; Ansaldo, Sp; Corvi, A [Ansaldo SpA, Genoa (Italy)

1988-12-31

This document deals with the use of fracture mechanics criteria to evaluate the Non Destructive Examination (NDE) flaw acceptance standards. The communication discusses the general schemes and the guidelines of the activity carried out. (TEC).

AAPT Diagnostic Criteria for Chronic Cancer Pain Conditions

OpenAIRE

Paice, Judith A.; Mulvey, Matt; Bennett, Michael; Dougherty, Patrick M.; Farrar, John T.; Mantyh, Patrick W.; Miaskowski, Christine; Schmidt, Brian; Smith, Thomas J.

2016-01-01

Chronic cancer pain is a serious complication of malignancy or its treatment. Currently, no comprehensive, universally accepted cancer pain classification system exists. Clarity in classification of common cancer pain syndromes would improve clinical assessment and management. Moreover, an evidence-based taxonomy would enhance cancer pain research efforts by providing consistent diagnostic criteria, ensuring comparability across clinical trials. As part of a collaborative effort between the A...

Liquid Effluent Monitoring Program at the Pacific Northwest Laboratory

International Nuclear Information System (INIS)

Ballinger, M.Y.

1995-05-01

Pacific Northwest Laboratory (PNL) is conducting a program to monitor the waste water from PNL-operated research and development facilities on the Hanford Site. The purpose of the program is to collect data to assess administrative controls and to determine whether discharges to the process sewer meet sewer criteria. Samples have been collected on a regular basis from the major PNL facilities on the Hanford Site since March 1994. A broad range of analyses has been performed to determine the primary constituents in the liquid effluent. The sampling program is briefly summarized in the paper. Continuous monitoring of pH, conductivity, and flow also provides data on the liquid effluent streams. In addition to sampling and monitoring, the program is evaluating the dynamics of the waste stream with dye studies and is evaluating the use of newer technologies for potential deployment in future sampling/monitoring efforts. Information collected to date has been valuable in determining sources of constituents that may be higher than the Waste Acceptance Criteria (WAC) for the Treated Effluent Disposal Facility (TEDF). This facility treats the waste streams before discharge to the Columbia River

Bayesian predictive risk modeling of microbial criteria for Campylobacter in broilers

DEFF Research Database (Denmark)

Nauta, Maarten; Ranta, J.; Mikkelä, A.

Microbial Criteria define the acceptability of food products, based on the presence or detected number of microorganisms in samples. The criteria are applied at the level of defined food lots. Generally, these are interpreted as statistical batches representing the production [1]. The batches...... be assessed by computing posterior distribution of the parameters - a Bayesian evidence synthesis. The outcome of a defined Microbial Criterion (MC) for a batch provides additional evidence concerning the batch. Posterior predictive consumer risk (probability of illness) was computed for such batch...

Quality criteria for landscape visualisation

International Nuclear Information System (INIS)

Waldi, H.-P.; Witt, U. de

1996-01-01

The rapid expansion of wind energy utilisation in Western Europe can strain the limits of social acceptance with citizens living in wind development areas. One of the problems wind farm engineers and local authorities face is the visual impact of wind turbines. To determine the influence on the landscape visualisations of wind farms photorealistic compositions are used. In many cases it is part of the planning procedure. The quality of this visualization can strongly influence the success of the permission procedure. We will give criteria which can give help to reduce the possibility of unwanted manipulations. (author)

Frequency limitations on reactor release derived from radiological criteria

International Nuclear Information System (INIS)

Clarke, R.H.

1976-05-01

Acceptable frequencies are suggested with which a number of defined individual and collective dose criteria are met. This has enabled a relationship to be proposed between the frequency and any event leading to release of radioactive material and the dose commitment to the hypothetical individual at the site boundary. The philosphy developed is generally applicable, but in this instance it has been demonstrated for an SGHW Reactor located at Sizewell. The results are derived on the basis of an acceptable level of risk of fatality to the most exposed individual and the application of the methodology to other reactor types and sites is demonstrated. (author)

Draft principles, policy, and acceptance criteria for decommissioning of U.S. Department of Energy contaminated surplus facilities and summary of international decommissioning programs

International Nuclear Information System (INIS)

Singh, B.K.

1994-12-01

Decommissioning activities enable the DOE to reuse all or part of a facility for future activities and reduce hazards to the general public and any future work force. The DOE Office of Environment, Health and Safety has prepared this document, which consists of decommissioning principles and acceptance criteria, in an attempt to establish a policy that is in agreement with the NRC policy. The purpose of this document is to assist individuals involved with decommissioning activities in determining their specific responsibilities as identified in Draft DOE Order 5820.DDD, ''Decommissioning of US Department of Energy Contaminated Surplus Facilities'' (Appendix A). This document is not intended to provide specific decommissioning methodology. The policies and principles of several international decommissioning programs are also summarized. These programs are from the IAEA, the NRC, and several foreign countries expecting to decommission nuclear facilities. They are included here to demonstrate the different policies that are to be followed throughout the world and to allow the reader to become familiar with the state of the art for environment, safety, and health (ES and H) aspects of nuclear decommissioning

Risk analysis and risk acceptance criteria in the planning processes of hazardous facilities-A case of an LNG plant in an urban area

International Nuclear Information System (INIS)

Vinnem, Jan Erik

2010-01-01

Planning of hazardous facilities is usually carried out on the basis of a risk-informed decision-making and planning process making use of risk analysis. This practice is well established in Norway under petroleum legislation but less so for onshore facilities under non-petroleum legislation. The present paper focuses on the use of risk analysis studies for risk evaluation against risk acceptance criteria, risk communication and derivation of technical and operational requirements in these circumstances. This is demonstrated through reference to a case study involving an LNG plant currently under construction in an urban area in Norway. The main finding is that risk-informed legislation is a fragile legislative system which is dependent on conscientious and open-minded use by the industrial developer. In the opposite case, the authorities may well be unable to correct the situation and the legislation may fail to protect the neighbourhood from unreasonable exposure to risk. Reference is also made to the international perspective where authorities define what is deemed tolerable risk, which would appear to be a more robust and defensible approach.

Screening Criteria and Considerations of Offshore Enhanced Oil Recovery

Directory of Open Access Journals (Sweden)

Pan-Sang Kang

2016-01-01

Full Text Available The application of enhanced oil recovery (EOR in offshore oil fields has received significant attention due to the potentially enormous amount of recoverable oil. However, EOR application offshore is in its very early stage due to conditions that are more complex than onshore oil fields, owing to the unique parameters present offshore. Therefore, successful EOR applications in offshore oil fields require different screening criteria than those for conventional onshore applications. A comprehensive database for onshore applications of EOR processes together with a limited offshore EOR application database are analyzed in this paper, and the important parameters for successful offshore application are incorporated into the new EOR screening criteria. In this paper, screening criteria to determine acceptable EOR processes for offshore fields, including hydrocarbon gas miscible, CO2 miscible, and polymer processes, are presented. Suggested screening criteria for these EOR processes comprise quantitative boundaries and qualitative considerations. Quantitative screening criteria are predominantly based on quantifiable data, such as oil and reservoir properties. Qualitative screening considerations mainly focus on the operational issues present offshore, including platform space constraints, limited disposal options, injectant availability, and flow assurance matters (including hydrate formation and difficulties in emulsion separation.

Criteria impacting shipments of Rocky Flats Plant radioactive mixed wastes

International Nuclear Information System (INIS)

Clawson, R.L.; Eide, J.H.

1992-05-01

Westinghouse Hanford Company, Transportation and Packaging Division, under contract for the Los Alamos Technology Office-Rocky Flats Plant, has developed this synopsis report to be used as a reference in the development of the Rocky Flats Plant Comprehensive Treatment and Management Plan and the Rocky Flats Plant Residue Elimination Plan. This report represents the criteria for packaging, shipping, and transporting Rocky Flats Plant radioactive mixed wastes. It is a compilation of state and federal regulations, US Department of Energy orders, and acceptance criteria specific to US Department of Energy radioactive mixed waste treatment, storage and disposal facilities

Seismic design and evaluation criteria based on target performance goals

International Nuclear Information System (INIS)

Murray, R.C.; Nelson, T.A.; Kennedy, R.P.; Short, S.A.

1994-04-01

The Department of Energy utilizes deterministic seismic design/evaluation criteria developed to achieve probabilistic performance goals. These seismic design and evaluation criteria are intended to apply equally to the design of new facilities and to the evaluation of existing facilities. In addition, the criteria are intended to cover design and evaluation of buildings, equipment, piping, and other structures. Four separate sets of seismic design/evaluation criteria have been presented each with a different performance goal. In all these criteria, earthquake loading is selected from seismic hazard curves on a probabilistic basis but seismic response evaluation methods and acceptable behavior limits are deterministic approaches with which design engineers are familiar. For analytical evaluations, conservatism has been introduced through the use of conservative inelastic demand-capacity ratios combined with ductile detailing requirements, through the use of minimum specified material strengths and conservative code capacity equations, and through the use of a seismic scale factor. For evaluation by testing or by experience data, conservatism has been introduced through the use of an increase scale factor which is applied to the prescribed design/evaluation input motion

Some problems in the acceptability of implementing radiation protection programs

International Nuclear Information System (INIS)

Neill, R.H.

1997-01-01

The three fundamentals that radiation protection programs are based upon are; 1) establishing a quantitative correlation between radiation exposure and biological effects in people; 2) determining a level of acceptable risk of exposure; and 3) establishing systems to measure the radiation dose to insure compliance with the regulations or criteria. The paper discusses the interrelationship of these fundamentals, difficulties in obtaining a consensus of acceptable risk and gives some examples of problems in identifying the most critical population-at-risk and in measuring dose. Despite such problems, it is recommended that we proceed with the existing conservative structure of radiation protection programs based upon a linear no threshold model for low radiation doses to insure public acceptability of various potential radiation risks. Voluntary compliance as well as regulatory requirements should continue to be pursued to maintain minimal exposure to ionizing radiation. (author)

Study on Influencing Factor Analysis and Application of Consumer Mobile Commerce Acceptance

Science.gov (United States)

Li, Gaoguang; Lv, Tingjie

Mobile commerce (MC) refers to e-commerce activities carried out using a mobile device such as a phone or PDA. With new technology, MC will be rapidly growing in the near future. At the present time, what factors making consumer accept MC and what MC applications are acceptable by consumers are two of hot issues both for MC providers and f or MC researchers. This study presents a proposed MC acceptance model that integrates perceived playfulness, perceived risk and cost into the TAM to study which factors affect consumer MC acceptance. The proposed model includes five variables, namely perceived risk, cost, perceived usefulness, perceived playfulness, perceived ease of use, perceived playfulness. Then, using analytic hierarchy process (AHP) to calculate weight of criteria involved in proposed model. Finally, the study utilizes fuzzy comprehensive evaluation method to evaluate MC applications accepted possibility, and then a MC application is empirically tested using data collected from a survey of MC consumers.

Preliminary waste acceptance criteria for the ICPP spent fuel and waste management technology development program

International Nuclear Information System (INIS)

Taylor, L.L.; Shikashio, R.

1993-09-01

The purpose of this document is to identify requirements to be met by the Producer/Shipper of Spent Nuclear Fuel/High-LeveL Waste SNF/HLW in order for DOE to be able to accept the packaged materials. This includes defining both standard and nonstandard waste forms

A proposed acceptance process for commercial off-the-shelf (COTS) software in reactor applications

International Nuclear Information System (INIS)

Preckshot, G.G.; Scott, J.A.

1996-03-01

This paper proposes a process for acceptance of commercial off-the-shelf (COTS) software products for use in reactor systems important to safety. An initial set of four criteria establishes COTS software product identification and its safety category. Based on safety category, three sets of additional criteria, graded in rigor, are applied to approve/disapprove the product. These criteria fall roughly into three areas: product assurance, verification of safety function and safety impact, and examination of usage experience of the COTS product in circumstances similar to the proposed application. A report addressing the testing of existing software is included as an appendix

Seismic design and evaluation criteria for DOE facilities (DOE-STD-1020-XX)

International Nuclear Information System (INIS)

Short, S.A.; Kennedy, R.P.; Murray, R.C.

1993-01-01

Seismic design and evaluation criteria for DOE facilities are provided in DOE-STD-1020-XX. The criteria include selection of design/evaluation seismic input from probabilistic seismic hazard curves combined with commonly practiced deterministic response evaluation methods and acceptance criteria with controlled levels of conservatism. Conservatism is intentionally introduced in specification of material strengths and capacities, in the allowance of limited inelastic behavior and by a seismic load factor. These criteria are based on the performance or risk goals specified in DOE 5480.28. Criteria have been developed following a graded approach for several performance goals ranging from that appropriate for normal-use facilities to that appropriate for facilities involving hazardous or critical operations. Performance goals are comprised of desired behavior and of the probability of not achieving that behavior. Following the seismic design/evaluation criteria of DOE-STD-1020-XX is sufficient to demonstrate that the probabilistic performance or risk goals are achieved. The criteria are simple procedures but with a sound, rigorous basis for the achievement of goals

An open trial of Acceptance-based Separated Family Treatment (ASFT) for adolescents with anorexia nervosa.

Science.gov (United States)

Timko, C Alix; Zucker, Nancy L; Herbert, James D; Rodriguez, Daniel; Merwin, Rhonda M

2015-06-01

Family based-treatments have the most empirical support in the treatment of adolescent anorexia nervosa; yet, a significant percentage of adolescents and their families do not respond to manualized family based treatment (FBT). The aim of this open trial was to conduct a preliminary evaluation of an innovative family-based approach to the treatment of anorexia: Acceptance-based Separated Family Treatment (ASFT). Treatment was grounded in Acceptance and Commitment Therapy (ACT), delivered in a separated format, and included an ACT-informed skills program. Adolescents (ages 12-18) with anorexia or sub-threshold anorexia and their families received 20 treatment sessions over 24 weeks. Outcome indices included eating disorder symptomatology reported by the parent and adolescent, percentage of expected body weight achieved, and changes in psychological acceptance/avoidance. Half of the adolescents (48.0%) met criteria for full remission at the end of treatment, 29.8% met criteria for partial remission, and 21.3% did not improve. Overall, adolescents had a significant reduction in eating disorder symptoms and reached expected body weight. Treatment resulted in changes in psychological acceptance in the expected direction for both parents and adolescents. This open trial provides preliminary evidence for the feasibility, acceptability, and efficacy of ASFT for adolescents with anorexia. Directions for future research are discussed. Copyright © 2015 Elsevier Ltd. All rights reserved.

Certification Plan, Radioactive Mixed Waste Hazardous Waste Handling Facility

International Nuclear Information System (INIS)

Albert, R.

1992-01-01

The purpose of this plan is to describe the organization and methodology for the certification of radioactive mixed waste (RMW) handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). RMW is low-level radioactive waste (LLW) or transuranic (TRU) waste that is co-contaminated with dangerous waste as defined in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and the Washington State Dangerous Waste Regulations, 173-303-040 (18). This waste is to be transferred to the Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington. This plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF (Section 4); and a list of the current and planned implementing procedures used in waste certification

The citon contribution on the improvement of technologies to radioactive waste facilities, a responsible and ethic activity

International Nuclear Information System (INIS)

Sociu, F.; Barariu, G.

2015-01-01

The main objective of this work is to presents information about the effort of CITON's specialists involved in nuclear activity, in order to reduce the radioactive impact on biosphere by improvement of the radwaste management strategy. The National Repository for Radwaste Baita - Bihor (DNDR) is designed for the disposal of institutional waste. According to the recommendations from the Safety Analysis performed in the frame of the PHARE project, DNDR needs to be improved. This activity is performed by CITON in the frame of a National project. The National Strategy for disposal of the radwaste from Fuel Cycle has as objective the commissioning of the Saligny Repository. Wastes arising from the Cernavoda NPP must be treated in order to be disposed to Saligny Repository. The main requirement for the Radwaste Treatment Plant (RWTP) consists in achieving the treatment of radwaste, as to ensure the compliance with the Waste Acceptance Criteria (WAC) of the Saligny Repository. (authors)

Free Moisture in GT-73 Resin Waste Generated from the Effluent Treatment Facility

International Nuclear Information System (INIS)

Kaplan, D.I.

2002-01-01

Solid Waste Division is presently evaluating whether to transfer spent resin generated from the Effluent Treatment Facility (ETF) to the Nevada Test Site (NTS). One of the criteria for the waste to be accepted at the NTS is that the waste must not contain more than 1 vol-percent free liquid. This criterion reduces the amount of liquid, a primary vector for subsurface contaminant migration (along with colloids), introduced into the repository. This criterion also serves to reduce the chance of an accidental spill during transport of the waste to the NTS. On December 15, 1997, a shipment from Fernald to the NTS leaked some liquid waste onto a highway in Kingman, Arizona, resulting in a Type B Accident Investigation. The direct cause of the leak was attributed to broken welds related to the use of substandard containers. The overall objective of this study was to provide guidance as to whether the spent GT-73 resin would meet the free moisture WAC set by the NTS

Quality Assistance Objectives for Nondestructive Assay at the Waste Receiving and Processing (WRAP) Facility

International Nuclear Information System (INIS)

CANTALOUB, M.G.

2000-01-01

The Waste Receiving and Processing (WRAP) facility, located on the Word Site in southeast Washington, is a key link in the certification of transuranic (TRU) waste for shipment to the Waste Isolation Pilot Plant (WIPP). Waste characterization is one of the vital functions performed at WRAP, and nondestructive assay (NDA) measurements of TRU waste containers is one of two required methods used for waste characterization. The Waste Acceptance Criteria for the Waste Isolation Pilot Plant, DOE/WIPP-069 (WIPP-WAC) delineates the quality assurance objectives which have been established for NDA measurement systems. Sites must demonstrate that the quality assurance objectives can be achieved for each radioassay system over the applicable ranges of measurement. This report summarizes the validation of the WRAP NDA systems against the radioassay quality assurance objectives or QAOs. A brief description of the each test and significant conclusions are included. Variables that may have affected test outcomes and system response are also addressed

Los Alamos National Laboratory TRU waste sampling projects

International Nuclear Information System (INIS)

Yeamans, D.; Rogers, P.; Mroz, E.

1997-01-01

The Los Alamos National Laboratory (LANL) has begun characterizing transuranic (TRU) waste in order to comply with New Mexico regulations, and to prepare the waste for shipment and disposal at the Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico. Sampling consists of removing some head space gas from each drum, removing a core from a few drums of each homogeneous waste stream, and visually characterizing a few drums from each heterogeneous waste stream. The gases are analyzed by GC/MS, and the cores are analyzed for VOC's and SVOC's by GC/MS and for metals by AA or AE spectroscopy. The sampling and examination projects are conducted in accordance with the ''DOE TRU Waste Quality Assurance Program Plan'' (QAPP) and the ''LANL TRU Waste Quality Assurance Project Plan,'' (QAPjP), guaranteeing that the data meet the needs of both the Carlsbad Area Office (CAO) of DOE and the ''WIPP Waste Acceptance Criteria, Rev. 5,'' (WAC)

Sodium-Bearing Waste Treatment Alternatives Implementation Study

Energy Technology Data Exchange (ETDEWEB)

Charles M. Barnes; James B. Bosley; Clifford W. Olsen

2004-07-01

The purpose of this document is to discuss issues related to the implementation of each of the five down-selected INEEL/INTEC radioactive liquid waste (sodium-bearing waste - SBW) treatment alternatives and summarize information in three main areas of concern: process/technical, environmental permitting, and schedule. Major implementation options for each treatment alternative are also identified and briefly discussed. This report may touch upon, but purposely does not address in detail, issues that are programmatic in nature. Examples of these include how the SBW will be classified with respect to the Nuclear Waste Policy Act (NWPA), status of Waste Isolation Pilot Plant (WIPP) permits and waste storage availability, available funding for implementation, stakeholder issues, and State of Idaho Settlement Agreement milestones. It is assumed in this report that the SBW would be classified as a transuranic (TRU) waste suitable for disposal at WIPP, located in New Mexico, after appropriate treatment to meet transportation requirements and waste acceptance criteria (WAC).

The Predictive Value of Selection Criteria in an Urban Magnet School

Science.gov (United States)

Lohmeier, Jill Hendrickson; Raad, Jennifer

2012-01-01

The predictive value of selection criteria on outcome data from two cohorts of students (Total N = 525) accepted to an urban magnet high school were evaluated. Regression analyses of typical screening variables (suspensions, absences, metropolitan achievement tests, middle school grade point averages [GPAs], Matrix Analogies test scores, and…

Idaho National Engineering Laboratory release criteria for decontamination and decommissioning

International Nuclear Information System (INIS)

Dolenc, M.R.; Case, M.J.

1986-01-01

Criteria have been developed for release of Idaho National Engineering Laboratory (INEL) facilities and land areas following decontamination and decommissioning (D and D). Decommissioning release criteria in the form of dose guidelines were proposed by the US Nuclear Regulatory Commission as early as 1980. These criteria were used on an interim basis for INEL D and D projects. However, dose guidelines alone do not adequately cover the criteria necessary to release sites for unrestricted use. In actual practice, other parameters such as pathways analyses, sampling and instrumentation techniques, and implementation procedures are required to develop the basis for unrestricted release of a site. Thus, a rigorous approach for evaluating these other parameters is needed to develop acceptable D and D release criteria. Because of the complex and sensitive nature of the dose and pathways analyses work, a thorough review by experts in those respective fields was desired. Input and support in preparing or reviewing each part of the criteria development task was solicited from several DOE field offices. Experts were identified and contracted to assist in preparing portions of the release criteria, or to serve on a peer-review committee. Thus, the entire release criteria development task was thoroughly reviewed by recognized experts from each DOE field office, to validate technical content of the INEL site-specific document

Extending the foreign spent fuel acceptance program: Policy and implementation issues

International Nuclear Information System (INIS)

Lyman, Edwin S.

2005-01-01

The May 2006 expiration date of the Foreign Research Reactor Spent Nuclear Fuel (FRR SNF) Acceptance Program is fast approaching. In April 2004, Energy Secretary Spencer Abraham instructed the Energy Department to 'initiate actions necessary to extend .... the fuel acceptance deadline'. However, extending the deadline may not be a simple task. The limits on the original program resulted from a delicate negotiation among many stakeholders. Any proposal to increase the duration and scope of the program will have to be considered in the context of DOE's failure since 1996 to develop viable treatment, packaging and long-term disposal options for FRR SNF. It is also unclear whether accepting additional low-enriched uranium FRR SNF can be justified on security grounds. This paper will propose criteria for acceptance of spent fuel under an extension that are intended to minimize controversy and ensure consistency with a threat-based prioritization of homeland security expenditures. (author)

Establishing endangered species recovery criteria using predictive simulation modeling

Science.gov (United States)

McGowan, Conor P.; Catlin, Daniel H.; Shaffer, Terry L.; Gratto-Trevor, Cheri L.; Aron, Carol

2014-01-01

Listing a species under the Endangered Species Act (ESA) and developing a recovery plan requires U.S. Fish and Wildlife Service to establish specific and measurable criteria for delisting. Generally, species are listed because they face (or are perceived to face) elevated risk of extinction due to issues such as habitat loss, invasive species, or other factors. Recovery plans identify recovery criteria that reduce extinction risk to an acceptable level. It logically follows that the recovery criteria, the defined conditions for removing a species from ESA protections, need to be closely related to extinction risk. Extinction probability is a population parameter estimated with a model that uses current demographic information to project the population into the future over a number of replicates, calculating the proportion of replicated populations that go extinct. We simulated extinction probabilities of piping plovers in the Great Plains and estimated the relationship between extinction probability and various demographic parameters. We tested the fit of regression models linking initial abundance, productivity, or population growth rate to extinction risk, and then, using the regression parameter estimates, determined the conditions required to reduce extinction probability to some pre-defined acceptable threshold. Binomial regression models with mean population growth rate and the natural log of initial abundance were the best predictors of extinction probability 50 years into the future. For example, based on our regression models, an initial abundance of approximately 2400 females with an expected mean population growth rate of 1.0 will limit extinction risk for piping plovers in the Great Plains to less than 0.048. Our method provides a straightforward way of developing specific and measurable recovery criteria linked directly to the core issue of extinction risk. Published by Elsevier Ltd.

International Political Actorness of the European Union: Evaluation Criteria

Directory of Open Access Journals (Sweden)

GNATYUK N.N.

2014-06-01

Full Text Available The European Union is a completely new international entity which is hard to evaluate using traditional criteria of political actorness. Its active international presence stimulates the modeling of international actor features beyond the scope of “state-international organization” scheme. The concept of international actorness serves as a starting point for the development of appropriate analytical model. Unlike the traditional state-centered approaches which define an international actor through its affiliation witch the international system, this concept operates at the internal level of international entity and at the international structure level. Furthermore, both of these levels are treated as ontologically neutral and mutually constitutive. This basic theoretical scheme is used for elaboration of evaluation criteria of political actorness. The proposed system of criteria is based on drawing, synthesizing and developing the main writings on “new international actors” since the times of classic work by Carol A. Cosgrove and Kenneth J. Twitchett. The key elements of actorness assessed in this article include defining of capacity to act on the global scene as well as the acceptance by other actors and by international system as a whole. At the internal level, the EU’s actor capacity is measured by assessing its core elements ranging from core aspects, such as autonomy, authority, actor capability, coherence and cohesion to identity aspects. On the external level, the decisive criteria are recognition and acceptance by others which reflect expectations and perceptions of the EU. The proposed approach of evaluating the international actorness enables us to consider the political activity of the EU on the basis of coordinated system of interaction between the variables of international and domestic levels of the analysis. Furthermore, this contributes to the development of cumulative, coherent, and comprehensive theory of international

MULTIPLE CRITERIA DECISION MAKING IN STRATEGIC PLANNING OF TABLE EGG PRODUCTION

Directory of Open Access Journals (Sweden)

Ana Crnčan

2016-06-01

Full Text Available The main research objective was to analyze and evaluate different systems of table egg production by using the multiple criteria analysis, the method of Analytic Hierarchy Process (AHP in decision making within strategic planning of production. The survey involved 79 producers of table eggs registered in the Records on laying hens’ farms in the Republic of Croatia. In the first stage, the research defined the criteria and sub-criteria for system evaluation which were compared in pairs in order to determine the weight or importance for each of them. Alternatives were evaluation based on definition of priorities of examinees and the extent to which they meet each of the defined criteria and sub-criteria. Intensity of examinees’ preferences were entered into the Expert Choice software in order to evaluate ranking results of egg production systems. Defined model consisted of a quantitative criterion of economic indicators, and the other two referred to qualitative criteria, market indicators and technical-technological factors. Each criterion had its corresponding sub-criteria that were evenly distributed in numerical order. Based on individual assessments of the examinees, overall cumulative evaluation was obtained for the table egg production systems. Accordingly, the most acceptable alternative to egg production is the indoor keeping system (priority 0.301. It is followed by the free-range system of keeping laying hens (priority 0.253. The third-ranked alternative is egg production by hens kept in conventional cages (priority 0.226, while the fourth-ranked least acceptable alternative, as of the total evaluation, is the ecological system of egg production (priority 0.220. Taking into account the obtained results of multiple criteria evaluation as well as EU and world trends in changing consumers’ habits including food safety and quality as well as customers’ preferences towards local market and local products, it is recommended that eggs

Advances in seismic criteria to qualify structures, systems and components in operating reactors

International Nuclear Information System (INIS)

Manrique, M.A.; Bak, W.R.

1989-01-01

This paper describes improved seismic evaluation criteria and analysis methodologies used as part of the seismic reevaluation of San Onofre Nuclear Generating Station, Unit 1. The plant had originally been designed for 0.25 g ground acceleration and was required to be upgraded to a 0.67 g ground acceleration as part of the plant's Long Term Service Seismic Reevaluation Program. The application of the criteria and methods described in this paper to demonstrate the seismic capability of the plant resulted in efficient plant modifications with considerable cost savings to the plant owner. The NRC accepted these criteria and methods based on favorable results of reviews, audits and independent verification of the theories, bases and implementation procedures of the proposed criteria and analysis methods

Nuclear reactor philosophy and criteria

International Nuclear Information System (INIS)

Atchison, R.J.

1979-07-01

Nuclear power plant safety criteria and principles developed in Canada are directed towards minimizing the chance of failure of the fuel and preventing or reducing to an acceptably low level the escape of fission products should fuel failure occur. Safety criteria and practices are set forth in the Reactor Siting Guide, which is based upon the concept of defence in depth. The Guide specifies that design and construction shall follow the best applicable code, standard or practice; the total of all serious process system failures shall not exceed one in three years; special safety systems are to be physically and functionally separate from process systems and each other; and safety systems shall be testable, with unavailability less than 10 - 3 . Doses to the most exposed member of the public due to normal operation, serious process failures, and dual failures are specified. Licensees are also required to consider the effects of extreme conditions due to airplane crashes, explosions, turbine disintegration, pipe burst, and natural disasters. Safety requirements are changing as nuclear power plant designs evolve and in response to social and economic pressures

Most Scottish neurologists do not apply the 2010 McDonald criteria when diagnosing multiple sclerosis.

Science.gov (United States)

Lumley, R; Davenport, R; Williams, A

2015-03-01

The diagnostic criteria for multiple sclerosis have evolved over time and currently the 2010 McDonald criteria are the most widely accepted. These criteria allow the diagnosis of multiple sclerosis to be made at the clinically isolated syndrome stage provided certain criteria are met on a single magnetic resonance brain scan. Our hypothesis was that neurologists in Scotland did not use these criteria routinely. We sent a SurveyMonkey questionnaire to all Scottish neurologists (consultants and trainees) regarding the diagnosis of multiple sclerosis. Our questionnaire response rate was 65/99 (66%). Most Scottish neurologists were aware of the criteria and 31/58 (53%) felt that they were using these routinely. However, in a clinical vignette designed to test the application of these criteria, only 5/57 (9%) of neurologists appeared to use them. Scottish neurologists' use of the 2010 McDonald criteria for diagnosis of multiple sclerosis varies from practitioners' perception of their use of these criteria.

Acceptance-criteria for the bedrock for deep geologic disposal of spent nuclear fuel. Proceedings from a seminar at Gothenburg University

International Nuclear Information System (INIS)

1995-11-01

The seminar was directed to Nordic participants, and discussed disposal in the Nordic crystalline bedrock. Criteria for the bedrock should include: It should give durable mechanical protection for the engineered barriers; give a stable and favorable chemical environment for these barriers; have a low turnover of ground water in the near field; be easy to characterize; give favorable recipient-conditions; not have valuable minerals in workable quantities. These general criteria raise several questions coupled to the safety analysis: e.g. the need for geological, hydrological and geochemical parameters. Which data are missing, which are most difficult to find? What should the site characterization program look like to focus on factors that are of the highest importance according to the safety analysis. The demands on the conditions at a site need to be translated into quantitative criteria, which should be expressed as values that can be measured at the site or deduced from such measurements. These questions were discussed at the seminar, and 21 contributions from Finnish, Norwegian and Swedish participants are reported in these proceedings under the chapters: Coupling to the safety analysis; Methodology and criteria for site selection in a regional geoscientific perspective; Rock as a building material - prognosis and result; Geoscientific criteria for the bedrock at the repository - Mechanical protection; Geoscientific criteria for the bedrock at the repository - Low ground water turnover, chemically favorable and stable environment in the near field; Geoscientific criteria for the bedrock at the repository - Demands on the bedrock concerning the migration of radionuclides

Proposed approach to derivation of acceptance criteria for disposal of disused sealed sources mixed with other accepted wastes in near-surface repository

International Nuclear Information System (INIS)

Salzer, P.; Stefula, V.; Homola, J.

2003-01-01

The Mochovce repository is described in the report. It is vault type near surface repository with 80 concrete vaults (2x2x20), 90 FRC containers (3.1 m 3 ) in one vault (3x10x3), compacted clay bath-tub around double row. 300 years of institutional control are envisioned.The following scenarios are examined: Normal evolution scenario; Alternative evolution scenarios (perforated clay barrier; well in close proximity); Intruder scenarios (construction of simple dwelling; construction of multi-storey building; construction of road; residence scenario). It is being proposed that the DSSs are disposed of in the containers together with normal operational waste. Long-lived alpha emitters - excluded a priori (e.g. 226 Ra); Short-lived (T 1/2 = 10 2 days) radionuclides - interim stored until decayed down to clearance level 60 Co - no activity limit, with due consideration of operational safety. The DSSs disposal issue is thus reduced to the disposal of 137 Cs. No limit has been imposed on total activity. Existing limits for operational waste: 3.13.10 13 Bq / container in the upper layer; 3.41.10 13 Bq / container in the bottom or intermediate layer. The acceptance criteria are assessed according to the risk. Two are models set up in MicroShield ver. 5.0. Homogenous source of 137 Cs in cubic concrete container and point source (hot spot) of the same activity. The result is - dose from the point source is 16.6 times higher than the one from the cube. As a result the following new restrictions arise for disposal of the 137 Cs spent industrial sources: disposal of DSSs is forbidden in the upper layer of the containers; maximum activity of the 137 Cs disused industrial source emplaced into the FRC container is 3.41x10 13 / 16.6 = 2.05x10 12 Bq in case of FRC filling by non-radioactive cement mortar; if the cemented radioactive waste is to be used for filling of FRC, decrease of the limit for the disused sealed source is equivalent to the radioactivity of the cement mixture

Containment design, performance criteria and research needs for advanced reactor designs

International Nuclear Information System (INIS)

Bagdi, G.; Ali, S.; Costello, J

2004-01-01

This paper points out some important shifts in the basic expectations in the performance requirements for containment structures and discusses the areas where the containment structure design requirements and acceptance criteria can be integrated with ultimate test based insights. Although there has not been any new reactor construction in the United States for over thirty years, several designs of evolutionary and advanced reactors have already been certified. Performance requirements for containment structures under design basis and severe accident conditions and explicit consideration of seismic margins have been used in the design certification process. In the United States, the containment structure design code is the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NE-Class MC for the steel containment and Section III, Division 2 for reinforced and prestressed concrete reactor vessels and containments. This containment design code was based on the early concept of applying design basis internal pressure and associated load combinations that included the operating basis and safe shutdown earthquake ground motion. These early design criteria served the nuclear industry and the regulatory authorities in maintaining public health and safety. However, these early design criteria do not incorporate the performance criteria related to containment function in an integrated fashion. Research in large scale model testing of containment structures to failure from over pressurization and shake table testing using simulated ground motion, have produced insights related to failure modes and material behavior at failure. The results of this research provide the opportunity to integrate these observations into design and acceptance criteria. This integration process would identify 'gaps' in the present knowledge and future research needs. This knowledge base is important for gleaning risk-informed insights into

Predicting nurses' use of healthcare technology using the technology acceptance model: an integrative review.

Science.gov (United States)

Strudwick, Gillian

2015-05-01

The benefits of healthcare technologies can only be attained if nurses accept and intend to fully use them. One of the most common models utilized to understand user acceptance of technology is the Technology Acceptance Model. This model and modified versions of it have only recently been applied in the healthcare literature among nurse participants. An integrative literature review was conducted on this topic. Ovid/MEDLINE, PubMed, Google Scholar, and CINAHL were searched yielding a total of 982 references. Upon eliminating duplicates and applying the inclusion and exclusion criteria, the review included a total of four dissertations, three symposium proceedings, and 13 peer-reviewed journal articles. These documents were appraised and reviewed. The results show that a modified Technology Acceptance Model with added variables could provide a better explanation of nurses' acceptance of healthcare technology. These added variables to modified versions of the Technology Acceptance Model are discussed, and the studies' methodologies are critiqued. Limitations of the studies included in the integrative review are also examined.

105 K East isolation barrier acceptance analysis report

International Nuclear Information System (INIS)

McCracken, K.J.; Irwin, J.J.

1995-01-01

The objective of this document is to report and interpret the findings of the isolation barrier acceptance tests performed in 105KE/100K. The tests were performed in accordance with the test plan (McCracken 1995c) and acceptance test procedure (McCracken 1995a). The test report (McCracken 1995b) contains the test data. This document compares the test data (McCracken 1995b) against the criteria (McCracken 1995a, c). A discussion of the leak rate analytical characterization (Irwin 1995) describes how the flow characteristics and the flow rate will be determined using the test data from the test report (McCracken 1995b). The barriers must adequately control the leakage from the main basin to the discharge chute to less than the 1,500 gph (5,680 lph) Safety Analysis Report (SAR 1994) limit

Design requirements, criteria and methods for seismic qualification of CANDU power plants

International Nuclear Information System (INIS)

Singh, N.; Duff, C.G.

1979-10-01

This report describes the requirements and criteria for the seismic design and qualification of systems and equipment in CANDU nuclear power plants. Acceptable methods and techniques for seismic qualification of CANDU nuclear power plants to mitigate the effects or the consequences of earthquakes are also described. (auth)

Criteria and principles for environmental assessment of disposal of radioactive wastes

International Nuclear Information System (INIS)

Hill, M.D.

1989-01-01

This paper describes the criteria which are used in judging whether methods for the disposal of radioactive wastes are acceptable, from a radiological protection point of view, and the principles used in assessing the radiological impact of waste disposal methods. Gaseous, liquid and solid wastes are considered, and the discussion is relevant to wastes arising from the nuclear power industry, and from medical practices, general industry and research. Throughout the paper, emphasis is given to the general criteria and principles recommended by international organizations rather than to the detailed legislative and regulatory requirements in particular countries

Protection criteria from the non-ionizing radiations

International Nuclear Information System (INIS)

Touzet, Rodolfo E.

2004-01-01

The first objective of the protection philosophy is to determinate the relation reason-effect in order to establish the exposition thresholds to acceptable values. To establish the radioprotection criteria is important to considerate the following: a-) The damage and effects of the non-ionizing radiation; b-) The physical aspects of the fields exposition; and c-) The dosimetry of the involucrate tissues. The non-ionizing radiation includes the optics radiations (ultraviolet, visible, infrared and laser), and the electromagnetic radiations (microwave, radars, magnetic and electrostatics fields)

Ecological radiation protection criteria for nuclear power

International Nuclear Information System (INIS)

Kryshev, I.I.

1993-01-01

By now a large quantity of radioactive hazards of all sizes and shapes has accumulated in Russia. They include RBMK, VVER, and BN (fast-neutron) nuclear power plants, nuclear fuel processing plants, radioactive waste dumps, ships with nuclear power units, etc. In order to evaluate the radioecological situation correctly, the characteristics of the radioactive contamination must be compiled in these areas with some system of criteria which will provide an acceptable level of ecological safety. Currently health criteria for radiation protection are, which are oriented to man's radiation protection, predominate. Here the concept of a thresholdless linear dose-response dependence, which has been confirmed experimentally only at rather high doses (above 1 Gy), is taken as the theoretical basis for evaluating and normalizing radiation effects. According to one opinion, protecting people against radiation is sufficient to protect other types of organisms, although they are not necessarily of the same species. However, from the viewpoint of ecology, this approach is incorrect, because it does not consider radiation dose differences between man and other living organisms. The article discusses dose-response dependences for various organisms, biological effects of ionizing radiation, and appropriate radiation protection criteria

Protocol for the verification of minimum criteria

International Nuclear Information System (INIS)

Gaggiano, M.; Spiccia, P.; Gaetano Arnetta, P.

2014-01-01

This Protocol has been prepared with reference to the provisions of article 8 of the Legislative Decree of May 26, 2000 No. 187. Quality controls of radiological equipment fit within the larger 'quality assurance Program' and are intended to ensure the correct operation of the same and the maintenance of that State. The pursuit of this objective guarantees that the radiological equipment subjected to those controls also meets the minimum criteria of acceptability set out in annex V of the aforementioned legislative decree establishing the conditions necessary to allow the functions to which each radiological equipment was designed, built and for which it is used. The Protocol is established for the purpose of quality control of radiological equipment of Cone Beam Computer Tomography type and reference document, in the sense that compliance with stated tolerances also ensures the subsistence minimum acceptability requirements, where applicable.

Radioactive waste management: review on clearance levels and acceptance criteria legislation, requirements and standards.

Science.gov (United States)

Maringer, F J; Suráň, J; Kovář, P; Chauvenet, B; Peyres, V; García-Toraño, E; Cozzella, M L; De Felice, P; Vodenik, B; Hult, M; Rosengård, U; Merimaa, M; Szücs, L; Jeffery, C; Dean, J C J; Tymiński, Z; Arnold, D; Hinca, R; Mirescu, G

2013-11-01

In 2011 the joint research project Metrology for Radioactive Waste Management (MetroRWM)(1) of the European Metrology Research Programme (EMRP) started with a total duration of three years. Within this project, new metrological resources for the assessment of radioactive waste, including their calibration with new reference materials traceable to national standards will be developed. This paper gives a review on national, European and international strategies as basis for science-based metrological requirements in clearance and acceptance of radioactive waste. © 2013 Elsevier Ltd. All rights reserved.

Engineering study of generic site criteria for selected DOE plutonium facilities

International Nuclear Information System (INIS)

Kingsbury, R.J.; Greenwood, J.M.; Sandoval, M.D.

1980-09-01

The objectives of this study were to identify criteria that would be applied to selection of a site for plutonium facilities such as those at the Rocky Flats Plant, to establish the relative importance of these criteria, and to identify suitable areas within the United States for location of plutonium facilities with respect to these criteria. Sources of the site criteria identified include federal laws, federal agency regulations, state laws and regulations, and requirements associated with operations to be performed at the site. The criteria identified during the study were organized into 14 major categories. The relative importnace of each category and each criterion within the categories were established using group decision-making techniques. The major criteria categories, their assigned weight on a scale of 1 to 10, and their relative priority ranks are as follows: geology/seismicity; public safety; environmental impact; meteorology; hydrology; topography; transportation; utilities; personnel; safeguards/security; land area and availability; land use compatibility; and, public acceptance. A suitability analysis of the continental United States was performed using only those criteria that could be mapped at a national scale. Suitability was assessed with respect to each of these criteria, and individual suitability maps were prepared. A composite suitability map was generated using computerized overlay techniques. This map provides a starting point for identifying specific candidate sites if an actual site selection were to be conducted

Suggested non-proliferation criteria for commercial nuclear fuel cycles

International Nuclear Information System (INIS)

Laney, R.V.; Heubotter, P.R.

1978-01-01

Based on the Administration's policy to prevent nuclear weapons proliferation through diversion of fuel from commercial reactor fuel cycles, a ''benchmark'' set of nonproliferation criteria was prepared for the commercial nuclear fuel cycle. These criteria should eliminate incremental risks of proliferation beyond those inherent in the present generation of low-enriched-uranium-fueled reactors operating in a once-through mode, with internationally safeguarded storage of spent fuel. They focus on the balanced application of technical constraints consistent with the state of the technology, with minimal requirements for institutional constraints, to provide a basis for assessing the proliferation resistance of proposed fission power systems. The paper contains: (1) our perception of the nuclear energy policy and of the baseline proliferation risk accepted under this policy; (2) objectives for a reactor and fuel cycle strategy which address the technical, political, and institutional aspects of diversion and proliferation and, at the same time, satisfy the Nation's needs for efficient, timely, and economical utilization of nuclear fuel resources; (3) criteria which are responsive to these objectives and can therefore be used to screen proposed reactor and fuel cycle strategies; and (4) a rationale for these criteria

105K West Isolation Barrier Acceptance Test results

International Nuclear Information System (INIS)

McCracken, K.J.; Irwin, J.J.

1995-01-01

The objective of this document is to report and interpret the findings of the isolation barrier acceptance tests performed in 105KW/100K. The tests were performed in accordance with the test plan and acceptance test procedure. The test report contains the test data. This document compares the test data against the criteria. A discussion of the leak rate analytical characterization describes how the flow characteristics flow rate will be determined using the test data from the test report. Two modes of water loss were considered; basin and/or discharge chute leakage, and evaporation. An initial test established baseline leakage data and instrumentation performance. Test 2 evaluated the sealing performance of the isolation barrier by inducing an 11 in. (27.9 cm) level differential across the barrier. The leak rate at this 11 in. (27.9 cm) level is extrapolated to the 16 ft. (4.9 m) level differential postulated in the DBE post seismic event. If the leak rate, adjusted for evaporation and basin leakage (determined from Test 1), is less than the SAR limit of 1,500 gph (5,680 lph) at a 16 ft (4.9 m) level differential, the barriers pass the acceptance test

Quality of laboratory studies assessing effects of Bt-proteins on non-target organisms: minimal criteria for acceptability.

Science.gov (United States)

De Schrijver, Adinda; Devos, Yann; De Clercq, Patrick; Gathmann, Achim; Romeis, Jörg

2016-08-01

The potential risks that genetically modified plants may pose to non-target organisms and the ecosystem services they contribute to are assessed as part of pre-market risk assessments. This paper reviews the early tier studies testing the hypothesis whether exposure to plant-produced Cry34/35Ab1 proteins as a result of cultivation of maize 59122 is harmful to valued non-target organisms, in particular Arthropoda and Annelida. The available studies were assessed for their scientific quality by considering a set of criteria determining their relevance and reliability. As a case-study, this exercise revealed that when not all quality criteria are met, weighing the robustness of the study and its relevance for risk assessment is not obvious. Applying a worst-case expected environmental concentration of bioactive toxins equivalent to that present in the transgenic crop, confirming exposure of the test species to the test substance, and the use of a negative control were identified as minimum criteria to be met to guarantee sufficiently reliable data. This exercise stresses the importance of conducting studies meeting certain quality standards as this minimises the probability of erroneous or inconclusive results and increases confidence in the results and adds certainty to the conclusions drawn.

IMPORTANCE OF MULTIPLE CRITERIA FOR PRIORITY SETTING OF HIV/AIDS INTERVENTIONS.

Science.gov (United States)

Tromp, Noor; Prawiranegara, Rozar; Siregar, Adiatma; Sunjaya, Deni; Baltussen, Rob

2015-01-01

This study describes the views of various stakeholders on the importance of different criteria for priority setting of HIV/AIDS interventions in Indonesia. Based on a general list of criteria and a focus group discussion with stakeholders (n = 6), a list was developed of thirty-two criteria that play a role in priority setting in HIV/AIDS control in West-Java province. Criteria were categorized according to the World Health Organization's health system goals and building block frameworks. People living with HIV/AIDS (n = 49), healthcare workers (HCW) (n = 41), the general population (n = 43), and policy makers (n = 22) rated the importance of thirty-two criteria on a 5-point Likert-scale. Thereafter, respondents ranked the highest rated criteria to express more detailed preferences. Stakeholders valued the following criteria as most important for the priority setting of HIV/AIDS interventions: an intervention's impact on the HIV/AIDS epidemic, reduction of stigma, quality of care, effectiveness on individual level, and feasibility in terms of current capacity of the health system (i.e., HCW, product, information, and service requirements), financial sustainability, and acceptance by donors. Overall, stakeholders' preferences for the importance of criteria are similar. Our study design outlines an approach for other settings to identify which criteria are important for priority setting of health interventions. For Indonesia, these study results may be used in priority setting processes for HIV/AIDS control and may contribute to more transparent and systematic allocation of resources.

40 CFR 80.584 - What are the precision and accuracy criteria for approval of test methods for determining the...

Science.gov (United States)

2010-07-01

... criteria for approval of test methods for determining the sulfur content of motor vehicle diesel fuel, NRLM....584 What are the precision and accuracy criteria for approval of test methods for determining the... available gravimetric sulfur standard in the range of 1-10 ppm sulfur shall not differ from the accepted...

Working draft regulatory guide on release criteria for decommissioning: NRC staff's draft for comment

International Nuclear Information System (INIS)

Daily, M.C.; Huffert, A.; Cardile, F.; Malaro, J.C.

1994-08-01

The Nuclear Regulatory Commission's (NRC) regulations in 10 CFR 20 are being amended to include radiological criteria for decommissioning of lands and structures at nuclear facilities. 10 CFR Part 20, Subpart E establishes criteria for the remediation of contaminated sites or facilities that will allow their release for future use with or without restrictions. The criteria include a Total Effective Dose Equivalent (TEDE) limit of 15 mrem/year (0.15 mSv/y) that should not be exceeded by an average individual among those who could potentially receive the greatest exposure from any residual activity within a facility or on a site. The criteria also require a licensee to reduce any residual radioactivity to as-low-as-reasonably-achievable (ALARA) levels. This staff draft guide describes acceptable procedures for determining the predicted dose level (PDL) from any residual radioactivity at the site. It describes the basic features of the calculational models and the associated default assumptions and parameter values the NRC staff would find acceptable in calculating PDLs. Appendices A, B, and C provide numerical values that can be used to estimate the dose from residual radioactivity remaining at a site. Since 10 CFR Part 20, Subpart E introduces several new concepts, definitions and discussions are included in a regulatory position concepts section of the guide to assist licensees in understanding some of the philosophy underlying the rule

Criteria for permission of radiosterilized products to application in medicine; Zasady dopuszczania wyrobow sterylizowanych radiacyjnie do stosowania w medycynie

Energy Technology Data Exchange (ETDEWEB)

Achmatowicz, T [Instytut Lekow, Warsaw (Poland)

1997-10-01

The criteria being used in Poland for permission of radiosterilized medical materials to commercial application result from regulations being in force. The international regulations are also taken into account. The all criteria and procedure needed for any product become accepted for radiosterilization and commercial medical use have been presented and discussed. 1 tab.

Key acceptability attributes of orodispersible films.

Science.gov (United States)

Scarpa, Mariagiovanna; Paudel, Amrit; Kloprogge, Frank; Hsiao, Wen Kai; Bresciani, Massimo; Gaisford, Simon; Orlu, Mine

2018-04-01

The features rendering orodispersible films (ODFs) patient-centric formulations are widely discussed in the scientific literature. However there is a lack of research studies exploring ODF characteristics with a potential impact on end-user acceptability. The aim of this study was to identify the key ODF characteristics affecting end-user acceptability by developing in vitro test methods for the prediction of ODFs acceptability and correlate these formulation characteristics with the data obtained from a human panel study. Four drug-free single-polymer films were prepared by solvent casting. Solutions of poly(vinyl) alcohol (PVOH) 39 KDa (P1), PVOH 197 KDa (P2), carboxymethylcellulose (CMC) 395 KDa (C1), and CMC 725 KDa (C2) were prepared. Texture analysis and Dynamic Mechanical Analysis (DMA) were used to assess film tack. Petri dish and drop methods were used to assess disintegration time. A human panel of 24 healthy young adults was employed to identify end-user acceptability criteria of the four study film samples. Texture analysis data of ODF tack were not found to be in agreement with the in vivo perceived stickiness in the mouth. However, measurement of the area under the adhesive force curve obtained by DMA correlated with in vivo perceived stickiness data for all samples. The disintegration times obtained by drop method were more comparable to human panel data than the petri dish method. Hence DMA and drop methods proved to be promising methodologies for the prediction of the end-user acceptability. The type and molecular weight of the film-forming polymer had a strong influence on stickiness perception, whereas only polymeric molecular weight influenced perceived disintegration time. The human panel study showed that Participant Reported Outcomes (PROs) for the perceived stickiness in the mouth and disintegration time of test films received significantly different scores between samples, and thus were identified as the key attributes with the

Application fuzzy multi-attribute decision analysis method to prioritize project success criteria

Science.gov (United States)

Phong, Nguyen Thanh; Quyen, Nguyen Le Hoang Thuy To

2017-11-01

Project success is a foundation for project owner to manage and control not only for the current project but also for future potential projects in construction companies. However, identifying the key success criteria for evaluating a particular project in real practice is a challenging task. Normally, it depends on a lot of factors, such as the expectation of the project owner and stakeholders, triple constraints of the project (cost, time, quality), and company's mission, vision, and objectives. Traditional decision-making methods for measuring the project success are usually based on subjective opinions of panel experts, resulting in irrational and inappropriate decisions. Therefore, this paper introduces a multi-attribute decision analysis method (MADAM) for weighting project success criteria by using fuzzy Analytical Hierarchy Process approach. It is found that this method is useful when dealing with imprecise and uncertain human judgments in evaluating project success criteria. Moreover, this research also suggests that although cost, time, and quality are three project success criteria projects, the satisfaction of project owner and acceptance of project stakeholders with the completed project criteria is the most important criteria for project success evaluation in Vietnam.

Microbiological criteria for good manufacturing practice (GMP)

Energy Technology Data Exchange (ETDEWEB)

Farkas, J [Inst. of Preservation and Livestock Products Technology, Univ. of Horticulture and Food Industry, Budapest (Hungary); Zukal, E [Inst. of Preservation and Livestock Products Technology, Univ. of Horticulture and Food Industry, Budapest (Hungary)

1992-01-01

Good manufacturing practice (GMP) consist of an effective manufacturing operation and an effective application of food control. GMP is best supported by the Hazard Analysis Critical Control Point system (HACCP) of the preventive quality assurance, which requires that food irradiation as any food processing technology should be used only with foods of an acceptable quality and adequate handling and storage procedures should precede and follow the processing. The paper concentrates on the first element of the HACCP system for an irradiation plant: the incoming product control, i.e. whether GMP of foods to be irradiated can be assessed by establishing microbiological criteria for their previous good manufacturing practice. In this regard, it summarizes considerations and findings of a ''Consultation on Microbiological Criteria for Foods to be Further Processed Including by Irradiation'' held in 1989 by the International Consultative Group on Food irradiation at the Headquarters of the World Health Organization, Geneva. Difficulties in establishing reference values and defining good manufacturing practices will be pointed out. (orig.)

The Success Criteria of Scientific Pedagogic Activities

Directory of Open Access Journals (Sweden)

M. V. Ovchinnikov

2013-01-01

Full Text Available The paper considers the problem of scientific pedagogic activity assessment of the higher school academic staff. The existing options of quality estimation are listed along with their deficiencies; the most acceptable in the authors’ opinion being the systematic approach. The latter allows considering almost every aspect of scientific-pedagogic activity. On that ground, the authors recommend the following success estimation criteria: gnostic, projecting, communicative, informational, and organizational. The criteria of work satisfaction and its results are taken into consideration as additional ones. The indicators of each criterion are given demonstrating that the as- sessment can be both internal (subjective and external (objective, denoted in the normative acts. The problem of complex and just quality assessment of scientific- pedagogic activity is quite relevant as it affects the academic staff motivation. The authors believe that the research findings can improve the objectivity of teachers’ work assessment and give way to differentiated approaches to their motivation and stimulation. 

Microbiological criteria for good manufacturing practice (GMP)

International Nuclear Information System (INIS)

Farkas, J.; Zukal, E.

1992-01-01

Good manufacturing practice (GMP) consist of an effective manufacturing operation and an effective application of food control. GMP is best supported by the Hazard Analysis Critical Control Point system (HACCP) of the preventive quality assurance, which requires that food irradiation as any food processing technology should be used only with foods of an acceptable quality and adequate handling and storage procedures should precede and follow the processing. The paper concentrates on the first element of the HACCP system for an irradiation plant: the incoming product control, i.e. whether GMP of foods to be irradiated can be assessed by establishing microbiological criteria for their previous good manufacturing practice. In this regard, it summarizes considerations and findings of a ''Consultation on Microbiological Criteria for Foods to be Further Processed Including by Irradiation'' held in 1989 by the International Consultative Group on Food irradiation at the Headquarters of the World Health Organization, Geneva. Difficulties in establishing reference values and defining good manufacturing practices will be pointed out. (orig.) [de

Definition of criteria related to occupational exposure for use in multi-criteria decision making process for nuclear accidents in Brazil

International Nuclear Information System (INIS)

Silva, Diogo N.G.; Guimaraes, Jean R.D.; Rochedo, Elaine R.R.

2013-01-01

After the occurrence of nuclear or radiological accidents, the selection of strategies for remediation of contaminated areas and of protective measures for members of public should be based on previously established criteria. Hence, it becomes possible to reduce the stress of population and to prevent the exposure of workers, especially if an implemented measure is not effective in reducing doses for each particular situation. When an accident with radioactive material causes environmental contamination, decisions about remediation of affected areas are complex because there are many factors associated with decontamination processes. Such complexity is related to technical procedures, public acceptance, the feasibility of implementing the measure, costs and legal aspects. This work is part of a project which aims to develop a multi-criteria tool to provide support for decision making processes in cases of nuclear or radiological accidents in Brazil. Primarily, a database containing information about protective and remediation measures for contaminated areas which can be applied nationally was created. Some criteria have already been defined for the classification of these measures regarding aspects of relevance of pathways to public exposure and of the infrastructure necessary to implement the measure. In this paper, the issues related to the exposure of the workforce are assessed and compared to the dose averted to members of the public resulting from the implementation of each remediation procedure. The procedures described in the database are then ranked according to selected criteria. In the next step, these ratings will be incorporated by the multi-criteria tool. (author)

Definition of criteria related to occupational exposure for use in multi-criteria decision making process for nuclear accidents in Brazil

Energy Technology Data Exchange (ETDEWEB)

Silva, Diogo N.G.; Guimaraes, Jean R.D., E-mail: dneves@biof.ufrj.br, E-mail: jeanrdg@biof.ufrj.br [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Instituto de Biofisica Carlos Chagas Filho; Rochedo, Elaine R.R., E-mail: elainerochedo@gmail.com [Instituto Militar de Engenharia (IME), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

2013-07-01

After the occurrence of nuclear or radiological accidents, the selection of strategies for remediation of contaminated areas and of protective measures for members of public should be based on previously established criteria. Hence, it becomes possible to reduce the stress of population and to prevent the exposure of workers, especially if an implemented measure is not effective in reducing doses for each particular situation. When an accident with radioactive material causes environmental contamination, decisions about remediation of affected areas are complex because there are many factors associated with decontamination processes. Such complexity is related to technical procedures, public acceptance, the feasibility of implementing the measure, costs and legal aspects. This work is part of a project which aims to develop a multi-criteria tool to provide support for decision making processes in cases of nuclear or radiological accidents in Brazil. Primarily, a database containing information about protective and remediation measures for contaminated areas which can be applied nationally was created. Some criteria have already been defined for the classification of these measures regarding aspects of relevance of pathways to public exposure and of the infrastructure necessary to implement the measure. In this paper, the issues related to the exposure of the workforce are assessed and compared to the dose averted to members of the public resulting from the implementation of each remediation procedure. The procedures described in the database are then ranked according to selected criteria. In the next step, these ratings will be incorporated by the multi-criteria tool. (author)

Geomembrane selection criteria for uranium tailings ponds

International Nuclear Information System (INIS)

Mitchell, D.H.; Cuello, R.

1986-09-01

The selection criteria, particularly those involving chemical compatibility, of geomembranes to be used in ponds at uranium mill operations are discussed. The principal functional criteria which a geomembrane must meet for this application are: (1) a specified service life and (2) low permeability. Chemical compatibility with the waste is essential in meeting these functional criteria. In two different types of aging tests using simulated acidic uranium mill waste, degradation of chemical and physical properties were examined in geomembranes of high-density polyethylene, polyvinyl chloride, and chlorosulfonated polyethylene. Compatibility tests according to the National Sanitation Foundation procedures are recommended to ascertain the stability of certain physical properties of the proposed geomembrane. Actual experience with a specific geomembrane in an identical application is probably the best method to assure compatibility; however, this experience is frequently not available. Experience with a geomembrane in similar applications is valuable in the selection process, however, small differences in either the geomembrane formulation or the waste composition may result in large differences in performance of the geomembrane. It is likely that many geomembranes have acceptable chemical stability for typical uranium mill applications, therefore, additional factors in the selection processes will include seaming characteristics, mechanical properties, site characteristics, and costs

Final waste forms project: Performance criteria for phase I treatability studies

International Nuclear Information System (INIS)

Gilliam, T.M.; Hutchins, D.A.; Chodak, P. III

1994-06-01

This document defines the product performance criteria to be used in Phase I of the Final Waste Forms Project. In Phase I, treatability studies will be performed to provide open-quotes proof-of-principleclose quotes data to establish the viability of stabilization/solidification (S/S) technologies. This information is required by March 1995. In Phase II, further treatability studies, some at the pilot scale, will be performed to provide sufficient data to allow treatment alternatives identified in Phase I to be more fully developed and evaluated, as well as to reduce performance uncertainties for those methods chosen to treat a specific waste. Three main factors influence the development and selection of an optimum waste form formulation and hence affect selection of performance criteria. These factors are regulatory, process-specific, and site-specific waste form standards or requirements. Clearly, the optimum waste form formulation will require consideration of performance criteria constraints from each of the three categories. Phase I will focus only on the regulatory criteria. These criteria may be considered the minimum criteria for an acceptable waste form. In other words, a S/S technology is considered viable only if it meet applicable regulatory criteria. The criteria to be utilized in the Phase I treatability studies were primarily taken from Environmental Protection Agency regulations addressed in 40 CFR 260 through 265 and 268; and Nuclear Regulatory Commission regulations addressed in 10 CFR 61. Thus the majority of the identified criteria are independent of waste form matrix composition (i.e., applicable to cement, glass, organic binders etc.)

Imaging and diagnostic criteria for multiple sclerosis: are we there yet?

International Nuclear Information System (INIS)

Josey, Lawrence; Curley, Michael; Mousavi, Foroogh Jafari; Taylor, Bruce V.; Lucas, Robyn; Coulthard, Alan

2012-01-01

Excluding post traumatic injury, Multiple Sclerosis (MS) is the most common disabling neurological disorder of young adults. Although the effect on mortality is limited, the association of a young demographic and significant morbidity combine to make MS a devastating disease. Since MS was given its first detailed description in 1868, diagnostic criteria continue to evolve. Recently, there has been an international commitment to combine both clinical and paraclinical tests to arrive at an earlier diagnosis. Widespread acceptance of the use of MRI in diagnosis, monitoring and research has made the role of the radiologist more critical than ever in this disease. The primary diagnostic criteria for MS are the International Panel criteria, commonly referred to as the McDonald criteria and it is essential that the radiology community is aware of the work preceding these criteria, so that they are understood in the correct context and the importance acknowledged. Literature review utilising key word search to obtain the historical and current context of magnetic resonance imaging in the diagnosis of MS. A succinct description of the evolution of criteria for the diagnosis of MS. Radiologists must recognise that there are specific diagnostic criteria for MS that continue to evolve as a result of new research, improved technology and clinical experience and it is crucial that these criteria be applied in daily practice. It should be evident that diagnostic imaging criteria for MS will be most effective when combined with standardised MRI protocols such as those published by the international Consortium of Multiple Sclerosis Centres.

Final waste forms project: Performance criteria for phase I treatability studies

Energy Technology Data Exchange (ETDEWEB)

Gilliam, T.M. [Oak Ridge National Lab., TN (United States); Hutchins, D.A. [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States); Chodak, P. III [Massachusetts Institute of Technology (United States)

1994-06-01

This document defines the product performance criteria to be used in Phase I of the Final Waste Forms Project. In Phase I, treatability studies will be performed to provide {open_quotes}proof-of-principle{close_quotes} data to establish the viability of stabilization/solidification (S/S) technologies. This information is required by March 1995. In Phase II, further treatability studies, some at the pilot scale, will be performed to provide sufficient data to allow treatment alternatives identified in Phase I to be more fully developed and evaluated, as well as to reduce performance uncertainties for those methods chosen to treat a specific waste. Three main factors influence the development and selection of an optimum waste form formulation and hence affect selection of performance criteria. These factors are regulatory, process-specific, and site-specific waste form standards or requirements. Clearly, the optimum waste form formulation will require consideration of performance criteria constraints from each of the three categories. Phase I will focus only on the regulatory criteria. These criteria may be considered the minimum criteria for an acceptable waste form. In other words, a S/S technology is considered viable only if it meet applicable regulatory criteria. The criteria to be utilized in the Phase I treatability studies were primarily taken from Environmental Protection Agency regulations addressed in 40 CFR 260 through 265 and 268; and Nuclear Regulatory Commission regulations addressed in 10 CFR 61. Thus the majority of the identified criteria are independent of waste form matrix composition (i.e., applicable to cement, glass, organic binders etc.).

Acceptance and Avoidance Processes at Different Levels of Psychological Recovery from Enduring Mental Illness.

Science.gov (United States)

Siqueira, Vinicius R; Oades, Lindsay G

2015-01-01

Objective. This study examined the use of psychological acceptance and experiential avoidance, two key concepts of Acceptance and Commitment Therapy (ACT), in the psychological recovery process of people with enduring mental illness. Method. Sixty-seven participants were recruited from the metropolitan, regional, and rural areas of New South Wales, Australia. They all presented some form of chronic mental illness (at least 12 months) as reflected in DSM-IV Axis I diagnostic criteria. The Acceptance and Action Questionnaire (AAQ-19) was used to measure the presence of psychological acceptance and experiential avoidance; the Recovery Assessment Scale (RAS) was used to examine the levels of psychological recovery; and the Scales of Psychological Well-Being was used to observe if there are benefits in utilizing psychological acceptance and experiential avoidance in the recovery process. Results. An analysis of objectively quantifiable measures found no clear correlation between the use of psychological acceptance and recovery in mental illness as measured by the RAS. The data, however, showed a relationship between psychological acceptance and some components of recovery, thereby demonstrating its possible value in the recovery process. Conclusion. The major contribution of this research was the emerging correlation that was observed between psychological acceptance and positive levels of psychological well-being among individuals with mental illness.

Attitudes of belgian students of medicine, philosophy, and law toward euthanasia and the conditions for its acceptance.

Science.gov (United States)

Roelands, Marc; Van den Block, Lieve; Geurts, Sylvie; Deliens, Luc; Cohen, Joachim

2015-01-01

Euthanasia is legal in Belgium if due care criteria are met, which is judged by committees including physicians, ethicists, and jurists. We examined whether students in these disciplines differ in how they judge euthanasia as an acceptable act. A cross-sectional, anonymous e-mail survey revealed that they have similar attitudes and accept its legalization. Therefore, joint decision-making of physicians, ethicists, and lawyers regarding euthanasia seems to have a common attitudinal base in Belgium. However, they differ to some extent regarding the conditions they put forward for euthanasia being acceptable. Philosophy of life (religion) was an independent predictor of these attitudes.

A generic approach for containment success criteria under severe accident loads

International Nuclear Information System (INIS)

Sammataro, R.F.; Solonick, W.R.; Edwards, N.W.

1992-01-01

The U.S. Department of Energy (DOE), Office of New Production Reactors (NP), has identified safety as the foremost design criterion for the Heavy Water New Production Reactor (NPR-HWR). The DOE-NP has issued the Deterministic Severe Accident Criteria (DSACs) to guide the design of the NPR-HWR containment for resistance to severe accidents. The DSAC concept provides for a generic approach for success criteria to predict the threshold of containment failure under severe accident loads. This concept consists of two parts: (1) Problem Statements that are qualitative and quantitative bases for calculating associated loadings and containment response to those loadings, and (2) Success Criteria that specify acceptable containment response measures and limits for each problem statement. This paper is limited to a discussion of a generic approach for containment success criteria. The main elements of these success criteria are expressed in terms of elastic stresses and inelastic strains. Containment performance is based on the best estimate of failure as predicted by either stress or strain, buckling, displacements, or ability to withstand missile perforation. Since these limits are best estimates of failure, no conservatism exists in these success criteria. Rather, conservatism is to be provided in the problem statements, i.e., the quantified severe accident loads. These success criteria are presented on a multi-tiered basis for static pressure and temperature loadings, dynamic loadings, and missiles. Within the static pressure and temperature loadings and the dynamic loadings, the criteria are separated into elastic analysis success criteria and inelastic analysis success criteria. Each of these areas, in turn, defines limits on either the stress or strain measures as well as on measures for buckling and displacements

Radiological design criteria for fusion power test facilities

International Nuclear Information System (INIS)

Singh, M.S.; Campbell, G.W.

1982-01-01

The quest for fusion power and understanding of plasma physics has resulted in planning, design, and construction of several major fusion power test facilities, based largely on magnetic and inertial confinement concepts. We have considered radiological design aspects of the Joint European Torus (JET), Livermore Mirror and Inertial Fusion projects, and Princeton Tokamak. Our analyses on radiological design criteria cover acceptable exposure levels at the site boundary, man-rem doses for plant personnel and population at large, based upon experience gained for the fission reactors, and on considerations of cost-benefit analyses

The effect of discounting, different mortality reduction schemes and predictive cohort life tables on risk acceptability criteria

International Nuclear Information System (INIS)

Rackwitz, Ruediger

2006-01-01

Technical facilities should be optimal with respect to benefits and cost. Optimization of technical facilities involving risks for human life and limb require an acceptability criterion and suitable discount rates both for the public and the operator depending on for whom the optimization is carried out. The life quality index is presented and embedded into modem socio-economic concepts. A general risk acceptability criterion is derived. The societal life saving cost to be used in optimization as life saving or compensation cost and the societal willingness-to-pay based on the societal value of a statistical life or on the societal life quality index are developed. Different mortality reduction schemes are studied. Also, predictive cohort life tables are derived and applied. Discount rates γ must be long-term averages in view of the time horizon of some 20 to more than 100 years for the facilities of interest and net of inflation and taxes. While the operator may use long-term averages from the financial market for his cost-benefit analysis the assessment of interest rates for investments of the public into risk reduction is more difficult. The classical Ramsey model decomposes the real interest rate (=output growth rate) into the rate of time preference of consumption and the rate of economical growth multiplied by the elasticity of marginal utility of consumption. It is proposed to use a relatively small interest rate of 3% implying a rate of time preference of consumption of about 1%. This appears intergenerationally acceptable from an ethical point of view. Risk-consequence curves are derived for an example

Consideration of Criteria for a Conceptual Near Surface Radioactive Waste disposal Facility in Kenya

Energy Technology Data Exchange (ETDEWEB)

Nderitu, Stanley Werugia; Kim, Changlak [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2014-05-15

The purpose of the criteria is to limit the consequences of events which could lead to radiation exposures. This study will present an approach for establishing radiological waste acceptance criteria using a safety assessment methodology and illustrate some of its application in establishing limits on the total activity and the activity concentrations of radioactive waste to be disposed in a conceptual near surface disposal facility in Kenya. The approach will make use of accepted methods and computational schemes currently used in assessing the safety of near surface disposal facilities. The study will mainly focus on post-closure periods. The study will employ some specific inadvertent human intrusion scenarios in the development of example concentration ranges for the disposal of near-surface wastes. The overall goal of the example calculations is to illustrate the application of the scenarios in a performance assessment to assure that people in the future cannot receive a dose greater than an established limit. The specific performance assessments will use modified scenarios and data to establish acceptable disposal concentrations for specific disposal sites and conditions. Safety and environmental impacts assessments is required in the post-closure phase to support particular decisions in development, operation, and closure of a near surface repository.

Proposed limiting values for performance criteria in acceptance testing of diagnostic X-ray equipment in the Federal Republic of Germany

International Nuclear Information System (INIS)

Baeuml, A.

1989-01-01

In the Federal Republic of Germany a new X-ray ordinance came into force in 1988 containing a specific paragraph on quality assurance for all medical X-ray units stipulating acceptance tests, regular checks and supervision by medical bodies and the competent authorities. Acceptance testing is to be performed by engineers from equipment suppliers of manufacturers in new and existing installations. It is expected that the service engineers will adjust the equipment in such a way as to obtain optimal performance before measurements are made, the results of which are to be stated in a certificate describing quality status of the equipment. A working group has developed guidelines for these acceptance tests. Items to be measured are reported and proposed limiting values and their tolerances are discussed. (author)

Proposed limiting values for performance criteria in acceptance testing of diagnostic X-ray equipment in the Federal Republic of Germany

International Nuclear Information System (INIS)

Baeuml, A.

1989-01-01

In the Federal Republic of Germany a new X-ray ordinance came into force in 1988 containing a specific paragraph on quality assurance for all medical X-ray units stipulating acceptance tests, regular checks and supervision by medical bodies and the competent authorities. Acceptance testing is to be performed by engineers from the equipment suppliers or manufacturers in new and also existing installations. It is expected that the service engineers will adjust the equipment in such a way as to obtain optimal performance before measurements are made, the results of which are to be stated in a certificate describing the quality status of the equipment. A working group has developed guidelines for these acceptance tests. The items to be measured are reported and the proposed limiting values and their tolerances are discussed. (author)

Creating a common Danish list of railway timetable evaluation criteria and revising the timetabling process accordingly

DEFF Research Database (Denmark)

Schittenhelm, Bernd; Landex, Alex

2012-01-01

criteria: capacity consumption on line sections and systematic timetable. Rank 2 criteria: robustness of the timetable and societal acceptance of the timetable and rank 3 criteria: travel time of trains and attractive transfer options. With this new tool a revised timetabling process at Rail Net Denmark...... is proposed. The very basic structure of the process cannot be changed due to EU legislation and Rail Net Europe guidelines. Key performance indicators derived from the identified timetabling criteria are introduced. As is a more iterative approach to the timetabling process due to the assumption of major...... improvements within timetable planning systems. This new iterative timetabling process using key performance indicators will result in improved future timetables and in lower levels of disagreement between timetable stakeholders....

Acceptance test report, 241-SY-101 Flexible Receiver System, Phase 1 testing

International Nuclear Information System (INIS)

Ritter, G.A.

1995-01-01

This document summarizes the results of the Phase 1 acceptance test of the 241-SY-101 Flexible Receiver System (FRS). This acceptance test consisted of a pressure-decay/leak test of the containment bag to verify that the seams along the length of the bag had been adequately sealed. The sealing integrity of the FRS must be verified to ensure that the release of waste and aerosols will be minimized during the removal of the test mixer pump from Tank 241-SY-101. The FRS is one of six major components of the Equipment Removal System, which has been designed to retrieve, transport, and store the mixer pump. This acceptance test was performed at Lancs Industries in Kirkland, Washington on January 17, 1995. The bag temperature-compensated pressure loss of 575 Pa was below the acceptance criteria of 625 Pa and the test results were therefore found to be acceptable. The bag manufacturer estimates that 80--90% of the pressure loss is attributed to leakage around the bag inflation valve where the pressure gage was connected. A leak detector was applied over the entire bag during the pre-tests and no leakage was found. Furthermore, the leak rate corresponding to this pressure loss is very small when compared to the acceptable leak rate of the completely assembled FRS. The sealing integrity of the assembled FRS is verified in Phase 3 testing

UO3 deactivation end point criteria

International Nuclear Information System (INIS)

Stefanski, L.D.

1994-01-01

The UO 3 Deactivation End Point Criteria are necessary to facilitate the transfer of the UO 3 Facility from the Office of Facility Transition and Management (EM-60) to the office of Environmental Restoration (EM-40). The criteria were derived from a logical process for determining end points for the systems and spaces at the UO 3 , Facility based on the objectives, tasks, and expected future uses pertinent to that system or space. Furthermore, the established criteria meets the intent and supports the draft guidance for acceptance criteria prepared by EM-40, open-quotes U.S. Department of Energy office of Environmental Restoration (EM-40) Decontamination and Decommissioning Guidance Document (Draft).close quotes For the UO 3 Facility, the overall objective of deactivation is to achieve a safe, stable and environmentally sound condition, suitable for an extended period, as quickly and economically as possible. Once deactivated, the facility is kept in its stable condition by means of a methodical surveillance and maintenance (S ampersand M) program, pending ultimate decontamination and decommissioning (D ampersand D). Deactivation work involves a range of tasks, such as removal of hazardous material, elimination or shielding of radiation fields, partial decontamination to permit access for inspection, installation of monitors and alarms, etc. it is important that the end point of each of these tasks be established clearly and in advance, for the following reasons: (1) End points must be such that the central element of the deactivation objective - to achieve stability - is unquestionably achieved. (2) Much of the deactivation work involves worker exposure to radiation or dangerous materials. This can be minimized by avoiding unnecessary work. (3) Each task is, in effect, competing for resources with other deactivation tasks and other facilities. By assuring that each task is appropriately bounded, DOE's overall resources can be used most fully and effectively

Criteria for high-level waste disposal

International Nuclear Information System (INIS)

Sousselier, Y.

1981-01-01

Disposal of radioactive wastes is storage without the intention of retrieval. But in such storage, it may be useful and in some cases necessary to have the possibility of retrieval at least for a certain period of time. In order to propose some criteria for HLW disposal, one has to examine how this basic concept is to be applied. HLW is waste separated as a raffinate in the first cycle of solvent extraction in reprocessing. Such waste contains the bulk of fission products which have long half lives, therefore the safety of a disposal site, at least after a certain period of time, must be intrinsic, i.e. not based on human intervention. There is a consensus that such a disposal is feasible in a suitable geological formation in which the integrity of the container will be reinforced by several additional barriers. Criteria for disposal can be proposed for all aspects of the question. The author discusses the aims of the safety analysis, particularly the length of time for this analysis, and the acceptable dose commitments resulting from the release of radionuclides, the number and role of each barrier, and a holistic analysis of safety external factors. (Auth.)

Decision modeling and acceptance criteria

DEFF Research Database (Denmark)

Ditlevsen, Ove Dalager

2003-01-01

compensation value of a human life and a public money equivalent of a human life, where the last value usually is considerably larger than the first value, it is possible from the decision analysis to determine an upper limit that the public should impose on the ratio of the owner´s expected loss rate......) that combines wealth in terms of Gross Domestic Product per person, life expectancy at birth, and yearly work time into a single number. The philosophy behind the published evaluations is that the prevention of a loss of a life is counteracted by a cost such that the LQI remains unchanged (Skjong R, Ronold K......; Decision Analysis; Life quality index; Random interest rate; Risk aversion; Socio-economic value; Uncertainty aversion...

Bayesian risk-based acceptance criteria

International Nuclear Information System (INIS)

Martz, H.F.; Abramson, L.R.; Johnson, J.W.

1996-04-01

Mechanistic (or deterministic) analysis is traditionally performed in the process of designing a new nuclear reactor or reactor core and also as part of the safety analysis of existing reactors or reload cores. Mechanistic accident analysis is characterized by the specification of an initial operating condition, an initiating event, and subsequent system faults. These subsequent faults are often chosen, through such mechanisms as the worst single failure criterion, so as to maximize the consequences of the accident. Thus, the behavior of all reactor system hardware is prescribed before this analysis begins. Mechanistic analysis then attempts to predict the dynamic response of the system and usually involves detailed reactor physics and thermal-hydraulic predictions of the system behavior, including such parameters as power distributions in the reactor core, coolant temperatures and flow rates, and fuel clad temperature distributions. The objective of this analysis has typically been to establish and verify reactor operating limits and technical specifications, so that severe core damage (SCD) is prevented for a wide variety of reactor accidents

Bridging the Gap between Social Acceptance and Ethical Acceptability.

Science.gov (United States)

Taebi, Behnam

2017-10-01

New technology brings great benefits, but it can also create new and significant risks. When evaluating those risks in policymaking, there is a tendency to focus on social acceptance. By solely focusing on social acceptance, we could, however, overlook important ethical aspects of technological risk, particularly when we evaluate technologies with transnational and intergenerational risks. I argue that good governance of risky technology requires analyzing both social acceptance and ethical acceptability. Conceptually, these two notions are mostly complementary. Social acceptance studies are not capable of sufficiently capturing all the morally relevant features of risky technologies; ethical analyses do not typically include stakeholders' opinions, and they therefore lack the relevant empirical input for a thorough ethical evaluation. Only when carried out in conjunction are these two types of analysis relevant to national and international governance of risky technology. I discuss the Rawlsian wide reflective equilibrium as a method for marrying social acceptance and ethical acceptability. Although the rationale of my argument is broadly applicable, I will examine the case of multinational nuclear waste repositories in particular. This example will show how ethical issues may be overlooked if we focus only on social acceptance, and will provide a test case for demonstrating how the wide reflective equilibrium can help to bridge the proverbial acceptance-acceptability gap. © 2016 The Authors Risk Analysis published by Wiley Periodicals, Inc. on behalf of Society for Risk Analysis.

A generic approach for steel containment vessel success criteria for severe accident loads

International Nuclear Information System (INIS)

Sammataro, R.F.; Solonick, W.R.; Edwards, N.W.

1993-01-01

Safety has been defined as the foremost design criterion for the Heavy Water New Production Reactor (NPR-HWR) by the U.S. DOE, Office of New Production Reactors (NP). The DOE-NP issued the Deterministic Severe Accident Criteria (DSAC) concept to guide the design of the NPR-HWR containment for resistance to severe accidents. The DSAC concept provides for a generic approach for containment vessel success criteria to predict the threshold of containment failure under severe accident loads. This concept consists of two parts: (1) Problem Statements and (2) Success Criteria. The paper is limited to a discussion of a success criteria. These criteria define acceptable containment response measures and limits for each problem statement. The criteria are based on the 'best estimate' of failure with no conservatism. Rather, conservatism, if required, is to be provided in the problem statements prepared by the designer and/or the regulatory authorities. The success criteria are presented on a multi-tiered basis for static pressure and temperature loadings, dynamic loadings, and missiles that may impact the containment. Within the static pressure and temperature loadings and the dynamic loadings, the criteria are separated into elastic analysis success criteria and inelastic analysis success criteria. Each of these areas, in turn, defines limits on either the stress or strain measures as well as on measures for buckling and displacements. The rationale upon which these criteria are based is contained in referenced documents. Rigorous validation of the criteria by comparison with results from analytical or experimental programs and application of the criteria to a containment design remain as future tasks. (orig./HP)

Speciation of methylmercury and ethylmercury by gas chromatography cold vapor atomic fluresence spectroscopy

Energy Technology Data Exchange (ETDEWEB)

Boggess, A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-09-28

Existing models and simulants of tank disposition media at SRS have presumed the presence of high concentrations of inorganic mercury. However, recent quarterly tank analyses show that mercury is present as organomercurial species at concentrations that may present challenges to remediation and disposition and may exceed the Saltstone Waste Acceptance Criteria (WAC). To-date, methylmercury analysis for Savannah River Remediation (SRR) has been performed off-site by Eurofins Scientific (Lancaster, PA). A series of optimization and validation experiments has been performed at SRNL, which has resulted in the development of on-site organomercury speciation capabilities using purge and trap gas chromatography coupled with thermal desorption cold vapor atomic fluorescence spectroscopy (P&T GC/CVAFS). Speciation has been achieved for methylmercury, with a method reporting limit (MRL) values of 1.42 pg for methylmercury. Results obtained by SRNL from the analysis of past quarterly samples from tanks 21, 40, and 50 have demonstrated statistically indistinguishable concentration values compared with the concentration data obtained from Eurofins, while the data from SRNL has demonstrated significantly improved precision and processing time.

Decommissioning of nuclear facilities using current criteria

International Nuclear Information System (INIS)

Shum, E.Y.; Swift, J.J.; Malaro, J.C.

1991-01-01

When a licensed nuclear facility ceases operation, the US Nuclear Regulatory Commission (NRC) is responsible for ensuring that the facility and its site are decontaminated to an acceptable level so that it is safe to release that facility and site for unrestricted public use. Currently, the NRC is developing decommissioning criteria based on reducing public doses from residual contamination in soils and structures at sites released for unrestricted use to as low as is reasonably achievable (ALARA). Plans are to quantify ALARA in terms of an annual total effective dose equivalent (TEDE) to an average member of the most highly exposed population group. The NRC is working on a regulatory guidance document to provide a technical basis for translating residual contamination levels to annual dose levels. Another regulatory guide is being developed to provide guidance to the licensee on how to conduct radiological surveys to demonstration compliance with the NRC decommissioning criteria. The methods and approaches used in these regulatory guides on the decommissioning of a nuclear facility are discussed in the paper

Microbiological criteria for good manufacturing practice (GMP)

Energy Technology Data Exchange (ETDEWEB)

Farkas, J. (Inst. of Preservation and Livestock Products Technology, Univ. of Horticulture and Food Industry, Budapest (Hungary)); Zukal, E. (Inst. of Preservation and Livestock Products Technology, Univ. of Horticulture and Food Industry, Budapest (Hungary))

1992-01-01

Good manufacturing practice (GMP) consist of an effective manufacturing operation and an effective application of food control. GMP is best supported by the Hazard Analysis Critical Control Point system (HACCP) of the preventive quality assurance, which requires that food irradiation as any food processing technology should be used only with foods of an acceptable quality and adequate handling and storage procedures should precede and follow the processing. The paper concentrates on the first element of the HACCP system for an irradiation plant: the incoming product control, i.e. whether GMP of foods to be irradiated can be assessed by establishing microbiological criteria for their previous good manufacturing practice. In this regard, it summarizes considerations and findings of a ''Consultation on Microbiological Criteria for Foods to be Further Processed Including by Irradiation'' held in 1989 by the International Consultative Group on Food irradiation at the Headquarters of the World Health Organization, Geneva. Difficulties in establishing reference values and defining good manufacturing practices will be pointed out. (orig.)

Toward optimizing patient-specific IMRT QA techniques in the accurate detection of dosimetrically acceptable and unacceptable patient plans.

Science.gov (United States)

McKenzie, Elizabeth M; Balter, Peter A; Stingo, Francesco C; Jones, Jimmy; Followill, David S; Kry, Stephen F

2014-12-01

The authors investigated the performance of several patient-specific intensity-modulated radiation therapy (IMRT) quality assurance (QA) dosimeters in terms of their ability to correctly identify dosimetrically acceptable and unacceptable IMRT patient plans, as determined by an in-house-designed multiple ion chamber phantom used as the gold standard. A further goal was to examine optimal threshold criteria that were consistent and based on the same criteria among the various dosimeters. The authors used receiver operating characteristic (ROC) curves to determine the sensitivity and specificity of (1) a 2D diode array undergoing anterior irradiation with field-by-field evaluation, (2) a 2D diode array undergoing anterior irradiation with composite evaluation, (3) a 2D diode array using planned irradiation angles with composite evaluation, (4) a helical diode array, (5) radiographic film, and (6) an ion chamber. This was done with a variety of evaluation criteria for a set of 15 dosimetrically unacceptable and 9 acceptable clinical IMRT patient plans, where acceptability was defined on the basis of multiple ion chamber measurements using independent ion chambers and a phantom. The area under the curve (AUC) on the ROC curves was used to compare dosimeter performance across all thresholds. Optimal threshold values were obtained from the ROC curves while incorporating considerations for cost and prevalence of unacceptable plans. Using common clinical acceptance thresholds, most devices performed very poorly in terms of identifying unacceptable plans. Grouping the detector performance based on AUC showed two significantly different groups. The ion chamber, radiographic film, helical diode array, and anterior-delivered composite 2D diode array were in the better-performing group, whereas the anterior-delivered field-by-field and planned gantry angle delivery using the 2D diode array performed less well. Additionally, based on the AUCs, there was no significant difference

[Early diagnosis of HIV in Primary Care in Spain. Results of a pilot study based on targeted screening based on indicator conditions, behavioral criteria and region of origin].

Science.gov (United States)

Agustí, Cristina; Martín-Rabadán, María; Zarco, José; Aguado, Cristina; Carrillo, Ricard; Codinachs, Roger; Carmona, Jose Manuel; Casabona, Jordi

2018-03-01

To estimate the prevalence of HIV infection in patients diagnosed with an indicator condition (IC) for HIV and/or risk behavior for their acquisition and/or coming from high prevalence countries. To determine the acceptability and feasibility of offering HIV testing based on IC and behavioral and origin criteria in Primary Care (PC). Cross-sectional study in a convenience sample. Six PC centers in Spain. The inclusion criteria were: patients between 16 and 65years old who presented at least one of the proposed ICs and/or at least one of the proposed behavioral and/or origin criteria. A total of 388 patients participated. HIV serology was offered to all patients who met the inclusion criteria. Description of IC frequency, behavioral and origin criteria. Prevalence of HIV infection. Level of acceptability and feasibility of the HIV screening based on IC and behavioral and origin criteria. A total of 174 patients had an IC (44.84%). The most common behavioral criterion was: having unprotected sex at some time in life with people who did not know their HIV status (298; 76.8%). Four HIV+ patients (1.03%) were diagnosed. All had an IC and were men who had sex with men. The level of acceptability in PC was high. Offering HIV testing to patients with IC and behavioral criteria is feasible and effective in PC. Copyright © 2017 Elsevier España, S.L.U. All rights reserved.

Acceptability of HIV self-testing: a systematic literature review.

Science.gov (United States)

Krause, Janne; Subklew-Sehume, Friederike; Kenyon, Chris; Colebunders, Robert

2013-08-08

The uptake of HIV testing and counselling services remains low in risk groups around the world. Fear of stigmatisation, discrimination and breach of confidentiality results in low service usage among risk groups. HIV self-testing (HST) is a confidential HIV testing option that enables people to find out their status in the privacy of their homes. We evaluated the acceptability of HST and the benefits and challenges linked to the introduction of HST. A literature review was conducted on the acceptability of HST in projects in which HST was offered to study participants. Besides acceptability rates of HST, accuracy rates of self-testing, referral rates of HIV-positive individuals into medical care, disclosure rates and rates of first-time testers were assessed. In addition, the utilisation rate of a telephone hotline for counselling issues and clients` attitudes towards HST were extracted. Eleven studies met the inclusion criteria (HST had been offered effectively to study participants and had been administered by participants themselves) and demonstrated universally high acceptability of HST among study populations. Studies included populations from resource poor settings (Kenya and Malawi) and from high-income countries (USA, Spain and Singapore). The majority of study participants were able to perform HST accurately with no or little support from trained staff. Participants appreciated the confidentiality and privacy but felt that the provision of adequate counselling services was inadequate. The review demonstrates that HST is an acceptable testing alternative for risk groups and can be performed accurately by the majority of self-testers. Clients especially value the privacy and confidentiality of HST. Linkage to counselling as well as to treatment and care services remain major challenges.

The Relationship between Treatment Integrity and Acceptability of Reading Interventions for Children with Attention-Deficit/Hyperactivity Disorder

Science.gov (United States)

Mautone, Jennifer A.; DuPaul, George J.; Jitendra, Asha K.; Tresco, Katy E.; Junod, Rosemary Vile; Volpe, Robert J.

2009-01-01

This study examined the relationship between treatment integrity and acceptability for reading interventions across two consultation models, intensive data-based academic intervention (IDAI) and traditional data-based academic intervention (TDAI). Participants included 83 first- through fourth-grade students who met research criteria for…

Conference on wind power development in the face of landscape and local project acceptability challenges

International Nuclear Information System (INIS)

Victoire Lejzerzon; Sauron, Claire; Villot, Marie; Ratzbor, Guenter; Tausch, Christian; Cagneaux, Bertrand; Jouneau, Agathe; Stemmer, Boris; Huebner, Gundula; Orozco-Souel, Paola; Lhermitte, Charles; Ferus, Elisabeth; Benezech, Philippe; Gunzelmann, Thomas

2015-01-01

The French-German office for Renewable energies (OFAEnR) organised a conference on n wind power development in the face of landscape and local project acceptability challenges. In the framework of this French-German exchange of experience, participants addressed the following points: the conciliation between landscape protection and wind power development, the definition of landscape environmental quality criteria, the needs and usages of the departments in charge of the treatment of landscape studies in France, the socio-psychological approach of the local acceptability of wind farm projects, the re-powering tool for the improvement of the wind farm integration in the landscape, and the conciliation between the monuments maintenance and wind power development. This document brings together the available presentations (slides) made during this event: 1 - Conciliating landscape protection and wind power development goals in France (Marie Villot); 2 - Wind turbines: Conflicts between development goals, landscape and acceptance - Perception and criteria (Guenter Ratzbor); 3 - Bayern's wind power atlas: a planning tool which takes into account the landscape aspects (Christian Tausch); 4 - Landscape assessment in wind farms projects: what and how to do in French administrative procedures? (Bertrand Cagneaux); 5 - Methods for evaluation of landscape for wind farms projects - A French project developer's feedback (Agathe Jouneau); 6 - Landscape Assessment: Methods from German Landscape Practice (Boris Stemmer); 7 - Acceptance of Wind Turbines - Social Psychological Research (Gundula Huebner); 8 - Local consultation: who to involve, when and how? (Paola Orozco-Souel); 9 - Local acceptability: what dialogue concepts and strategies, and how to manage wind energy objection (Charles Lhermitte); 10 - Re-powering and landscape: chances and limits (Elisabeth Ferus); 11 - Wind power and cultural heritage: consultation and dialogue to succeed (Philippe Benezech); 12

Power Distribution System Planning Evaluation by a Fuzzy Multi-Criteria Group Decision Support System

Directory of Open Access Journals (Sweden)

Tiefeng Zhang

2010-10-01

Full Text Available The evaluation of solutions is an important phase in power distribution system planning (PDSP which allows issues such as quality of supply, cost, social service and environmental implications to be considered and usually involves the judgments of a group of experts. The planning problem is thus suitable for the multi-criteria group decision-making (MCGDM method. The evaluation process and evaluation criteria often involve uncertainties incorporated in quantitative analysis with crisp values and qualitative judgments with linguistic terms; therefore, fuzzy sets techniques are applied in this study. This paper proposes a fuzzy multi-criteria group decision-making (FMCGDM method for PDSP evaluation and applies a fuzzy multi-criteria group decision support system (FMCGDSS to support the evaluation task. We introduce a PDSP evaluation model, which has evaluation criteria within three levels, based on the characteristics of a power distribution system. A case-based example is performed on a test distribution network and demonstrates how all the problems in a PDSP evaluation are addressed using FMCGDSS. The results are acceptable to expert evaluators.

Feasibility Study on the Development of Index that Shows Social and Cultural Acceptance of Nuclear Power

Energy Technology Data Exchange (ETDEWEB)

Cho, SeongKyung [Bangmok College of General Education at Myongji Univ., Yongin (Korea, Republic of); Choi, Seungho; Yoon, Hana; Song, Jiyeon [Domo Brodeur, Seoul (Korea, Republic of)

2015-05-15

In this context, it is necessary to manage and develop an index that can measure the level of public acceptance by establishing the terms of social/cultural public acceptance of nuclear power in a practical manner and by identifying influential factors of public acceptance. Developing an index itself is not intended to increase the public acceptance of nuclear power. This study intends to contribute to determining energy policy acceptable to the public by estimating the level of potential social conflicts related to nuclear power policies with eligible evaluation criteria on social/cultural acceptance and by reducing relevant social costs. Key conclusions and proposal of this research are as follows. First, the influential factors of acceptance are reliability of nuclear safety, risk perception of nuclear power and beneficial perception of nuclear power. Among them, reliability of nuclear safety appears to have the most influence. In addition, benefit perception of nuclear power at the social level is significantly higher than that at the individual level. However, in relation to risk perception, a gap between experts and the public is found as nuclear industry premises that accident does not occur while the public premises that accident may occur.

Feasibility Study on the Development of Index that Shows Social and Cultural Acceptance of Nuclear Power

International Nuclear Information System (INIS)

Cho, SeongKyung; Choi, Seungho; Yoon, Hana; Song, Jiyeon

2015-01-01

In this context, it is necessary to manage and develop an index that can measure the level of public acceptance by establishing the terms of social/cultural public acceptance of nuclear power in a practical manner and by identifying influential factors of public acceptance. Developing an index itself is not intended to increase the public acceptance of nuclear power. This study intends to contribute to determining energy policy acceptable to the public by estimating the level of potential social conflicts related to nuclear power policies with eligible evaluation criteria on social/cultural acceptance and by reducing relevant social costs. Key conclusions and proposal of this research are as follows. First, the influential factors of acceptance are reliability of nuclear safety, risk perception of nuclear power and beneficial perception of nuclear power. Among them, reliability of nuclear safety appears to have the most influence. In addition, benefit perception of nuclear power at the social level is significantly higher than that at the individual level. However, in relation to risk perception, a gap between experts and the public is found as nuclear industry premises that accident does not occur while the public premises that accident may occur

Evaluation criteria for dialogue processes: key findings from RISCOM II

International Nuclear Information System (INIS)

Atherton, Elizabeth

2003-01-01

As part of Work Package 4 (undertaken by a consortium of partners from the United Kingdom) in the joint European project RISCOM II, work was undertaken on evaluation criteria for determining the success of dialogue processes; this note outlines its key findings as, in order to continue the development of dialogue processes, it is important to evaluate and learn from the experience of engaging with stakeholders. Criteria can be developed to evaluate how successful a process has been, these can range from very practical criteria relating to how well the process worked or be linked to more subjective criteria developed from the aims of the dialogue process itself. Some criteria are particularly relevant to dialogue processes that aim to encourage deliberation and the development of stakeholders' views through participation in the dialogue process: transparency, legitimacy, equality of access, 'being able to speak', a deliberative environment, openness of framing, developing insight into range of issues (new meanings are generated), inclusive and 'best' knowledge elicited, producing acceptable/tolerable and usable outcomes/decisions, improvement of trust and understanding between participants, developing a sense of shared responsibility and common good. Evaluation will incur a cost in terms of time and money, but will help practitioners to be able to develop processes that meet the needs of those who participate and improve the way that we try to engage people in the debate

Discussion on the environmental protection acceptance method and the critical issues of the completion of projects about radiation usage in the hospitals

International Nuclear Information System (INIS)

Wang Wei

2014-01-01

It is widely used in the world that the hospitals take advantages of radiation technology. Practically it is involved radioactive isotope, sealed source and the usage of ray device. Based on the environmental protection acceptance of the finished projects, this article is aimed at the actual characteristics of the medical practice and differentiating the major factors of environmental effects, choosing the monitoring criteria and method of environmental protection acceptance and exploring the critical issues in the course of acceptance. Finally this essay is intended to provide theory evidence and technical support in the acceptance of the above projects. (author)

Acceptance test report for portable exhauster POR-007/Skid E

International Nuclear Information System (INIS)

Kriskovich, J.R.

1998-01-01

This document describes Acceptance Testing performed on Portable Exhauster POR-007/Skid E. It includes measurements of bearing vibration levels, pressure decay testing, programmable logic controller interlocks, high vacuum, flow and pressure control functional testing. The purpose of Acceptance testing documented by this report was to demonstrate compliance of the exhausters with the performance criteria established within HNF-0490, Rev. 1 following a repair and upgrade effort at Hanford. In addition, data obtained during this testing is required for the resolution of outstanding Non-conformance Reports (NCR), and finally, to demonstrate the functionality of the associated software for the pressure control and high vacuum exhauster operating modes provided for by W-320. Additional testing not required by the ATP was also performed to assist in the disposition and close out of receiving inspection report and for application design information (system curve). Results of this testing are also captured within this document

Five criteria for using a surrogate endpoint to predict treatment effect based on data from multiple previous trials.

Science.gov (United States)

Baker, Stuart G

2018-02-20

A surrogate endpoint in a randomized clinical trial is an endpoint that occurs after randomization and before the true, clinically meaningful, endpoint that yields conclusions about the effect of treatment on true endpoint. A surrogate endpoint can accelerate the evaluation of new treatments but at the risk of misleading conclusions. Therefore, criteria are needed for deciding whether to use a surrogate endpoint in a new trial. For the meta-analytic setting of multiple previous trials, each with the same pair of surrogate and true endpoints, this article formulates 5 criteria for using a surrogate endpoint in a new trial to predict the effect of treatment on the true endpoint in the new trial. The first 2 criteria, which are easily computed from a zero-intercept linear random effects model, involve statistical considerations: an acceptable sample size multiplier and an acceptable prediction separation score. The remaining 3 criteria involve clinical and biological considerations: similarity of biological mechanisms of treatments between the new trial and previous trials, similarity of secondary treatments following the surrogate endpoint between the new trial and previous trials, and a negligible risk of harmful side effects arising after the observation of the surrogate endpoint in the new trial. These 5 criteria constitute an appropriately high bar for using a surrogate endpoint to make a definitive treatment recommendation. Published 2017. This article is a U.S. Government work and is in the public domain in the USA.

Quality assurance requirements and methods for high level waste package acceptability

International Nuclear Information System (INIS)

1992-12-01

This document should serve as guidance for assigning the necessary items to control the conditioning process in such a way that waste packages are produced in compliance with the waste acceptance requirements. It is also provided to promote the exchange of information on quality assurance requirements and on the application of quality assurance methods associated with the production of high level waste packages, to ensure that these waste packages comply with the requirements for transportation, interim storage and waste disposal in deep geological formations. The document is intended to assist both the operators of conditioning facilities and repositories as well as national authorities and regulatory bodies, involved in the licensing of the conditioning of high level radioactive wastes or in the development of deep underground disposal systems. The document recommends the quality assurance requirements and methods which are necessary to generate data for these parameters identified in IAEA-TECDOC-560 on qualitative acceptance criteria, and indicates where and when the control methods can be applied, e.g. in the operation or commissioning of a process or in the development of a waste package design. Emphasis is on the control of the process and little reliance is placed on non-destructive or destructive testing. Qualitative criteria, relevant to disposal of high level waste, are repository dependent and are not addressed here. 37 refs, 3 figs, 2 tabs

Radiological control criteria for materials considered for recycle and reuse

International Nuclear Information System (INIS)

Kennedy, W.E. Jr.; Hill, R.L.; Aaberg, R.L.; Wallo, A. III

1994-11-01

Pacific Northwest Laboratory (PNL) is conducting technical analyses to support the US Department of Energy (DOE), Office of Environmental Guidance, Air, Water, and Radiation Division (DOE/EH-232) in developing radiological control criteria for recycling or reuse of metals or equipment containing residual radioactive contamination from DOE operations. The criteria, framed as acceptable concentrations for release of materials for recycling or reuse, are risk-based and were developed through analysis of generic radiation exposure scenarios and pathways. The analysis includes evaluation of relevant radionuclides, potential mechanisms of exposure, and non-health-related impacts of residual radioactivity on electronics and film. The analysis considers 42 key radionuclides that DOE operations are known to generate and that may be contained in recycled or reused metals or equipment. Preliminary results are compared with similar results reported by the International Atomic Energy Agency, by radionuclide grouping

Public acceptance of renewable energies. Results from case studies in Germany

Energy Technology Data Exchange (ETDEWEB)

Zoellner, Jan; Schweizer-Ries, Petra; Wemheuer, Christin [Department of Psychology, Otto-von-Guericke-University Magdeburg, Universitaetsplatz 2, 39106 Magdeburg (Germany)

2008-11-15

This article addresses the public acceptance of certain renewable energies (grid-connected larger PV ground-installed systems, biomass plants and wind turbines) from a socio-scientific perspective. Using an environmental-psychological approach to investigate the social factors relevant to the formation of public acceptance towards renewable energies in four different regions, recommendations for the further implementation of renewable energy systems were to be derived. The present study has been conducted in a multi-modal research design combining a standardised questionnaire and qualitative interviews and focused on the residents' views and perceptions. Especially within the quantitative analyses, the results indicate that economic consideration of the respective renewable energy system, understood as a positive cost-benefit calculation made by the individual, is the strongest predictor for a reported acceptance. Furthermore, the importance of landscape evaluation and a strong connection between procedural justice criteria, such as transparency, early and accurate information as well as possibilities to participate during the planning and installation process, and a reported public acceptance became evident. Qualitative data were analysed in reference to the grounded theory and showed the relevance of the operating company's commitment on the local level, participation of the general public and the choice of the location for the plant were among the relevant aspects for acceptance in the implementation process. This survey is part of a 3-year project funded by the Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU). (author)

Public acceptance of renewable energies: Results from case studies in Germany

Energy Technology Data Exchange (ETDEWEB)

Zoellner, Jan [Department of Psychology, Otto-von-Guericke-University Magdeburg, Universitaetsplatz 2, 39106 Magdeburg (Germany)], E-mail: jan.zoellner@ovgu.de; Schweizer-Ries, Petra; Wemheuer, Christin [Department of Psychology, Otto-von-Guericke-University Magdeburg, Universitaetsplatz 2, 39106 Magdeburg (Germany)

2008-11-15

This article addresses the public acceptance of certain renewable energies (grid-connected larger PV ground-installed systems, biomass plants and wind turbines) from a socio-scientific perspective. Using an environmental-psychological approach to investigate the social factors relevant to the formation of public acceptance towards renewable energies in four different regions, recommendations for the further implementation of renewable energy systems were to be derived. The present study has been conducted in a multi-modal research design combining a standardised questionnaire and qualitative interviews and focused on the residents' views and perceptions. Especially within the quantitative analyses, the results indicate that economic consideration of the respective renewable energy system, understood as a positive cost-benefit calculation made by the individual, is the strongest predictor for a reported acceptance. Furthermore, the importance of landscape evaluation and a strong connection between procedural justice criteria, such as transparency, early and accurate information as well as possibilities to participate during the planning and installation process, and a reported public acceptance became evident. Qualitative data were analysed in reference to the grounded theory and showed the relevance of the operating company's commitment on the local level, participation of the general public and the choice of the location for the plant were among the relevant aspects for acceptance in the implementation process. This survey is part of a 3-year project funded by the Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU)

Public acceptance of renewable energies: Results from case studies in Germany

International Nuclear Information System (INIS)

Zoellner, Jan; Schweizer-Ries, Petra; Wemheuer, Christin

2008-01-01

This article addresses the public acceptance of certain renewable energies (grid-connected larger PV ground-installed systems, biomass plants and wind turbines) from a socio-scientific perspective. Using an environmental-psychological approach to investigate the social factors relevant to the formation of public acceptance towards renewable energies in four different regions, recommendations for the further implementation of renewable energy systems were to be derived. The present study has been conducted in a multi-modal research design combining a standardised questionnaire and qualitative interviews and focused on the residents' views and perceptions. Especially within the quantitative analyses, the results indicate that economic consideration of the respective renewable energy system, understood as a positive cost-benefit calculation made by the individual, is the strongest predictor for a reported acceptance. Furthermore, the importance of landscape evaluation and a strong connection between procedural justice criteria, such as transparency, early and accurate information as well as possibilities to participate during the planning and installation process, and a reported public acceptance became evident. Qualitative data were analysed in reference to the grounded theory and showed the relevance of the operating company's commitment on the local level, participation of the general public and the choice of the location for the plant were among the relevant aspects for acceptance in the implementation process. This survey is part of a 3-year project funded by the Federal Ministry for the Environment, Nature Conservation and Nuclear Safety (BMU)

A Preliminary Investigation of Acceptance and Commitment Therapy as a Treatment for Marijuana Dependence in Adults

Science.gov (United States)

Twohig, Michael P.; Shoenberger, Deacon; Hayes, Steven C.

2007-01-01

In this investigation, 3 adults who met criteria for marijuana dependence were treated using an abbreviated version of acceptance and commitment therapy (ACT). The treatment was delivered in eight weekly 90-min individual sessions. The effects of the intervention were assessed using a nonconcurrent multiple baseline across participants design.…

The leak before break criteria, requirements and implications; El criterio de fuga antes de ruptura, requerimientos e implicaciones

Energy Technology Data Exchange (ETDEWEB)

Martinez M, E

1992-05-15

Inside this work a general balance is made on the Leak before break approach (LBB), like they are the history and licensing, those limitations, the acceptance criteria of the LBB, the current state of the regulatory development and the current state of it application in countries like E.U.A, Germany, Canada, Italy and France. Everything it with the purpose of evaluating the opportunities that offers the LBB criteria for it possible application in Mexico. (Author)

Preparing to Accept Research Data: Creating Guidelines for Librarians

Directory of Open Access Journals (Sweden)

Laura B. Palumbo

2015-11-01

Full Text Available Rutgers University Libraries have recognized the need to expand their current research data services into a well-documented and well-supported service available to the Rutgers research community. In 2005, Rutgers University Libraries created RUcore, Rutgers University Community Repository, which has served as the University’s formal repository for institutional scholarship, special collections, and Electronic Theses & Dissertations. With the impetus of the 2010 NSF directive for research data sharing and preservation, RUcore development was extended to accept research data content. Ingest of pilot data projects began in 2010 via a librarian-mediated process. In order to provide a better defined workflow and mission for research data services, in July 2014, the Rutgers University Librarian organized a Task Force to investigate the evaluation process for technical, legal, and confidential issues involved in research data acceptance, and to establish an administrative and evaluation framework for the deposit of research data. After a review of 35 repositories using 34 criteria, the Task Force drafted a plan for research data acceptance which proposes wide-spread acceptance of mediated data projects, and prepares for future self-deposit in an online interface. This paper will discuss the issues addressed by the Task Force; acknowledging ownership of data through an institutional data policy, preventing exposure of confidential or sensitive data, establishing a reconfigured data team, requirements for storage capacity and funding, creating a workflow which includes collaboration with research offices, and offering guidance for both researchers and librarians working with research data.

Present state of the design and realization of regional radioactive waste depositories and waste acceptance criteria for disposal. Soucasny stav reseni a realizace regionalnich ulozist RA odpadu a kriteria prijatelnosti techto odpadu k ukladani

Energy Technology Data Exchange (ETDEWEB)

Kortus, J [Chemoprojekt, Prague (Czechoslovakia)

1988-06-01

Surface type regional depositories for radioactive wastes from nuclear power plants are described in detail. The depository of the Mochovce nuclear power plant is located near the plant, that of the Dukovany nuclear power plant is directly on the premises of the plant. Particular attention is paid to the design of the monolithic reinforced concrete pits, draining of rainwater from their surface, draining of seeping rainwater from the pit environment by means of a double drainage system, and insulation of the pits against water. The construction of the Mochovce depository started in 1987; some experience gained from this activity is presented. The radioactive waste acceptance criteria for depositories of this kind, based on safety analysis, are given. (author). 2 figs.

The arterial circle of Willis of the mouse helps to decipher secrets of cerebral vascular accidents in the human.

Science.gov (United States)

Okuyama, Shinichi; Okuyama, Jun; Okuyama, Junko; Tamatsu, Yuichi; Shimada, Kazuyuki; Hoshi, Hajime; Iwai, Junichi

2004-01-01

The human brain represents an elaborate product of hominizing evolution. Likewise, its supporting vasculature may also embody evolutionary consequences. Thus, it is conceivable that the human tendency to develop cerebral vascular accidents (CVAs) might represent a disease of hominization. In a search for hominizing changes on the arterial circle of Willis (hWAC), we attempted an anatomical comparison of the hWAC with that of the mouse (mWAC) by injecting aliquots of resin into the vasculature of the mouse and then creating vascular endocasts of the mWAC. The internal carotid artery of the mouse (mICA) unites with the mWAC midway between the middle cerebral artery (mMCA) and posterior cerebral artery (mPCA). The mWAC does not complete a circle: the mWAC nourishes the anterior portion of the circle which branches out to the olfactory artery (OlfA) and mPCA, along with the mMCA, and the basilar artery (mBA) does not connect to the mPCA. The OlfA is thicker than the mMCA. The relative brain weight of the mouse was 74 g on average for a 60 kg male and 86 g for a 60 kg female, respectively, as compared with 1424 g for a 60 kg man. These findings are consistent with the mouse being a nocturnal carnivore that lives on olfactory information in contrast to the human that lives diurnally and depends on visual and auditory information. In man, the human ICA (hICA) unites with the hWAC at a point where the human middle cerebral artery (hMCA) branches out, and thus, blood from the hICA does not flow through the hWAC but drains into the hMCA directly. The hMCA is thicker than the anterior cerebral artery. The hPCA receives blood from the hBA rather than from the hICA, and thus, the entire hWAC forms a closed circuit. Since the hICA drains directly into the hMCA without flowing a distance through the hWAC, the capacitor and equalizer functions of the WAC will be mitigated so much that the resultant hemodynamic changes would render the hMCA more likely to contribute to CVAs. Thus

Official criteria for diagnostics of diabetes mellitus, normoglycemia and glycemic self-control

Directory of Open Access Journals (Sweden)

O.V. Kaminskiy

2017-04-01

Full Text Available The paper considers the questions of diagnostics of diabetes mellitus (DM and early violations of carbohydrate metabolism. Venous plasma was underlined to be the only commonly accepted standard for blood glucose determination for prediabetes and diabetes mellitus diagnosis. In the third world countries (including Ukraine peripheral (capillary plasma of blood can be used for self-control and diagnostics of prediabetes and DM as their fasting values correspond to those of venous plasma and do not require revaluation. While using portable glucometers for carbohydrate violations diagnostics postprandial glucose value and after meal should be estimated in conversion. Normoglycemia is glucose concentration in venous plasma from 3.9 mmol/l (ADA criteria to 6.0 mmol/l (WHO criteria.

US Department of Energy acceptance of commercial transuranic waste

International Nuclear Information System (INIS)

Taboas, A.L.; Bennett, W.S.; Brown, C.M.

1980-02-01

Contaminated transuranic wastes generated as a result of non-defense activities have been disposed of by shallow land burial at a commercially operated (NECO) facility located on the Hanford federal reservation, which is licensed by the State of Washington and by the NRC. About 15,000 ft 3 of commercial TRU waste have been generated each year, but generation for the next three years could triple due to decontamination and decommissioning scheduled to start in 1980. Disposal at other commercial burial sites has been precluded due to sites closing or prohibitions on acceptance of transuranic wastes. The State of Washington recently modified the NECO-Hanford operating license, effective February 29, 1980, to provide that radioactive wastes contaminated with transuranics in excess of 10 nCi/g will not be accepted for disposal. Consistent with the state policy, the NRC amended the NECO special nuclear material license so that Pu in excess of 10n Ci/g cannot be accepted after February 29, 1980. As a result, NRC requested DOE to examine the feasibility of accepting these wastes at a DOE operated site. TRU wastes accepted by the DOE would be placed in retrievable storage in accordance with DOE policy which requires retrievable storage of transuranic wastes pending final disposition in a geologic repository. DOE transuranic wastes are stored at six major DOE sites: INEL, Hanford, LASL, NTS, ORNL, and SRP. A specific site for receiving commercial TRU waste has not yet been selected. Shipments to DOE-Hanford would cause the least disruption to past practices. Commercial TRU wastes would be subject to waste form and packaging criteria established by the DOE. The waste generators would be expected to incur all applicable costs for DOE to take ownership of the waste, and provide storage, processing, and repository disposal. The 1980 charge to generators for DOE acceptance of commercial TRU waste is $147 per cubic foot

Some considerations for establishing seismic design criteria for nuclear plant piping

International Nuclear Information System (INIS)

Chen, W.P.; Chokshi, N.C.

1997-01-01

The Energy Technology Engineering Center (ETEC) is providing assistance to the U.S. NRC in developing regulatory positions on the seismic analysis of piping. As part of this effort, ETEC previously performed reviews of the ASME Code, Section III piping seismic design criteria as revised by the 1994 Addenda. These revised criteria were based on evaluations by the ASME Special Task Group on Integrated Piping Criteria (STGIPC) and the Technical Core Group (TCG) of the Advanced Reactor Corporation (ARC) of the earlier joint Electric Power Research Institute (EPRI)/NRC Piping ampersand Fitting Dynamic Reliability (PFDR) program. Previous ETEC evaluations reported at the 23rd WRSM of seismic margins associated with the revised criteria are reviewed. These evaluations had concluded, in part, that although margins for the timed PFDR tests appeared acceptable (>2), margins in detuned tests could be unacceptable (<1). This conclusion was based primarily on margin reduction factors (MRFs) developed by the ASME STGIPC and ARC/TCG from realistic analyses of PFDR test 36. This paper reports more recent results including: (1) an approach developed for establishing appropriate seismic margins based on PRA considerations, (2) independent assessments of frequency effects on margins, (3) the development of margins based on failure mode considerations, and (4) the implications of Code Section III rules for Section XI

Design criteria for piping and nozzles program

International Nuclear Information System (INIS)

Moore, S.E.; Bryson, J.W.

1977-01-01

This report reviews the activities and accomplishments of the Design Criteria for Piping and Nozzles program being conducted by the Oak Ridge National Laboratory for the period July 1, 1975, to September 30, 1976. The objectives of the program are to conduct integrated experimental and analytical stress analysis studies of piping system components and isolated and closely-spaced pressure vessel nozzles in order to confirm and/or improve the adequacy of structural design criteria and analytical methods used to assure the safe design of nuclear power plants. Activities this year included the development of a finite-element program for analyzing two closely spaced nozzles in a cylindrical pressure vessel; a limited-parameter study of vessels with isolated nozzles, finite-element studies of piping elbows, a fatigue test of an out-of-round elbow, summary and evaluation of experimental studies on the elastic-response and fatigue failure of tees, parameter studies on the behavior of flanged joints, publication of fifteen topical reports and papers on various experimental and analytical studies; and the development and acceptance of a number of design rules changes to the ASME Code. 2 figures, 2 tables

Use of DOE site selection criteria for screening low-level waste disposal sites on the Oak Ridge Reservation

International Nuclear Information System (INIS)

Lee, D.W.; Ketelle, R.H.; Stinton, L.H.

1983-09-01

The proposed Department of Energy (DOE) site selection criteria were applied to the Oak Ridge Reservation, and the application was evaluated to determine the criteria's usefulness in the selection of a low-level waste disposal site. The application of the criteria required the development of a methodology to provide a framework for evaluation. The methodology is composed of site screening and site characterization stages. The site screening stage relies on reconnaissance data to identify a preferred site capable of satisfying the site selection criteria. The site characterization stage relies on a detailed site investigation to determine site acceptability. The site selection criteria were applied to the DOE Oak Ridge Reservation through the site screening stage. Results of this application were similar to those of a previous siting study on the Oak Ridge Reservation. The DOE site selection criteria when coupled with the methodology that was developed were easily applied and would be adaptable to any region of interest

Neutron absorber qualification and acceptance testing from the designer's perspective

International Nuclear Information System (INIS)

Bracey, W.; Chiocca, R.

2004-01-01

Starting in the mid 1990's, the USNRC began to require less than 100% credit for the 10B present in fixed neutron absorbers spent fuel transport packages. The current practice in the US is to use only 75% of the specified 10B in criticality safety calculations unless extensive acceptance testing demonstrates both the presence of the 10B and uniformity of its distribution. In practice, the NRC has accepted no more than 90% credit for 10B in recent years, while other national competent authorities continue to accept 100%. More recently, with the introduction of new neutron absorber materials, particularly aluminum / boron carbide metal matrix composites, the NRC has also expressed expectations for qualification testing, based in large part on Transnuclear's successful application to use a new composite material in the TN-68 storage / transport cask. The difficulty is that adding more boron than is really necessary to a metal has some negative effects on the material, reducing the ductility and the thermal conductivity, and increasing the cost. Excessive testing requirements can have the undesired effect of keeping superior materials out of spent fuel package designs, without a corresponding justification based on public safety. In European countries and especially in France, 100% credit has been accepted up to now with materials controls specified in the Safety Analysis Report (SAR): Manufacturing process approved by qualification testing Materials manufacturing controlled under a Quality Assurance system. During fabrication, acceptance testing directly on products or on representative samples. Acceptance criteria taking into account a statistical uncertainty corresponding to 3σ. The original and current bases for the reduced 10 B credit, the design requirements for neutron absorber materials, and the experience of Transnuclear and Cogema Logistics with neutron absorber testing are examined. Guidelines for qualification and acceptance testing and process controls

Mixed Waste Focus Area - Waste form initiative

International Nuclear Information System (INIS)

Nakaoka, R.; Waters, R.; Pohl, P.; Roach, J.

1998-01-01

The mission of the US Department of Energy's (DOE) Mixed Waste Focus Area (MWFA) is to provide acceptable technologies that enable implementation of mixed waste treatment systems which are developed in partnership with end-users, stakeholders, tribal governments, and regulators. To accomplish this mission, a technical baseline was established in 1996 and revised in 1997. The technical baseline forms the basis for determining which technology development activities will be supported by the MWFA. The primary attribute of the technical baseline is a set of prioritized technical deficiencies or roadblocks related to implementation of mixed waste treatment systems. The Waste Form Initiative (WFI) was established to address an identified technical deficiency related to waste form performance. The primary goal of the WFI was to ensure that the mixed low-level waste (MLLW) treatment technologies being developed, currently used, or planned for use by DOE would produce final waste forms that meet the waste acceptance criteria (WAC) of the existing and/or planned MLLW disposal facilities. The WFI was limited to an evaluation of the disposal requirements for the radioactive component of MLLW. Disposal requirements for the hazardous component are dictated by the Resource Conservation and Recovery Act (RCRA), and were not addressed. This paper summarizes the technical basis, strategy, and results of the activities performed as part of the WFI

Test Results for CSTR Test 3

International Nuclear Information System (INIS)