Radiological/toxicological sabotage assessments at the Savannah River Site

International Nuclear Information System (INIS)

Johnson, H.D.; Pascal, M.D.; Richardson, D.L.

1995-01-01

This paper describes the methods being employed by Westinghouse Savannah River Company (WSRC) to perform graded assessments of radiological and toxicological sabotage vulnerability at Savannah River Site (SRS) facilities. These assessments are conducted to ensure that effective measures are in place to prevent, mitigate, and respond to a potential sabotage event which may cause an airborne release of radiological/toxicological material, causing an adverse effect on the health and safety of employees, the public, and the environment. Department of Energy (DOE) Notice 5630.3A, open-quotes Protection of Departmental Facilities Against Radiological and Toxicological Sabotage,close quotes and the associated April 1993 DOE-Headquarters guidance provide the requirements and outline an eight-step process for hazardous material evaluation. The process requires the integration of information from a variety of disciplines, including safety, safeguards and security, and emergency preparedness. This paper summarizes WSRC's approach towards implementation of the DOE requirements, and explains the inter-relationships between the Radiological and Toxicological Assessments developed using this process, and facility Hazard Assessment Reports (HAs), Safety Analysis Reports (SARs), and Facility Vulnerability Assessments (VAs)

"Set Up to Fail": Institutional Racism and the Sabotage of School Improvement

Science.gov (United States)

Taylor, Dianne L.; Clark, Menthia P.

2009-01-01

Data from two previous studies are reanalyzed using the lens of institutional racism to examine district decisions that undermined, or sabotaged, improvement efforts at schools attended by students of color. Opportunities to rectify the sabotage were available but not pursued. A model portrays the interaction between decision-maker intent,…

SPTH3: subroutine for finding shortest sabotage paths

International Nuclear Information System (INIS)

Hulme, B.L.; Holdridge, D.B.

1977-07-01

This document explains how to construct a sabotage graph which models any fixed-site facility and how to use the subroutine SPTH3 to find shortest paths in the graph. The shortest sabotage paths represent physical routes through the site which would allow an adversary to take advantage of the greatest weaknesses in the system of barriers and alarms. The subroutine SPTH3 is a tool with which safeguards designers and analysts can study the relative effects of design changes on the adversary routing problem. In addition to showing how to use SPTH3, this report discusses the methods used to find shortest paths and several implementation details which cause SPTH3 to be extremely efficient

A Study on Developing a Framework for Sabotage Protection of Nuclear Facilities

International Nuclear Information System (INIS)

Kim, Kilyoo; Jung, WooSik

2007-01-01

A methodology related to physical protection of nuclear facilities against sabotage is preparing by IAEA. However, the framework of IAEA is somewhat superficial and it seems not to reflect the risk concept since IAEA prefers a proven technology. In this paper, a framework for sabotage protection of nuclear facilities using risk assessment is described

A standardized approach for determining radiological sabotage targets

International Nuclear Information System (INIS)

Gardner, B.H.; Snell, M.K.

1993-01-01

The US Department of Energy has required radiological sabotage vulnerability assessments to be conducted for years. However, the exact methodology to be used in this type of analysis still remains somewhat elusive. Therefore, there is tremendous variation in the methodologies and assumptions used to determine release levels and doses potentially affecting the health and safety of the public. In some cases, there are three orders of magnitude difference in results for dispersal of similar materials under similar meteorological conditions. To address this issue, the authors have developed an approach to standardizing radiological sabotage target analysis that starts by addressing basic assumptions and then directs the user to some recommended computerized analytical tools. Results from different dispersal codes are also compared in this analysis

The DOE policy for protection against radiological and toxicological sabotage

International Nuclear Information System (INIS)

Hassell, C. Jr.; Callahan, S.; Myers, D.

1995-01-01

In response to a Department of Energy Office of Security Evaluations study on radiological and toxicological sabotage, the Under Secretary of Energy has directed that all departmental elements initiate analyses to determine the extent of radiological and toxicological sabotage threats within the department. To accomplish this, a plan was adopted whereby radioactive and other hazardous materials at DOE sites would be assessed by an interdisciplinary team as to quantities, ranked according to their hazards, subjected to a vulnerability assessment, and appropriate upgrades selected and monitored. This paper is a discussion of those efforts

Sabotage Operations of the Prewar Anti-Facist League - Poland

National Research Council Canada - National Science Library

Szubanski, Rajmund

1960-01-01

The following article is a translation and deals with sabotage operations of the prewar Anti-Fascist League that was connected to the Communist Party, the International Seaman's and Dockers' Unions...

Summary report of workshop on sabotage protection in nuclear power plant design

International Nuclear Information System (INIS)

1977-02-01

During the Summer of 1976, Sandia Laboratories hosted a workshop on Sabotage Protection in Nuclear Power Plant Design in which 11 consultants from the nuclear power industry participated. Each consultant is highly qualified and experienced in nuclear power plant design. The objective of the workshop was to identify practicable design measures which could be employed in future nuclear power plants to provide increased protection against sabotage. The report summarizes the conclusions and recommendations of the workshop

Discussion of sabotage vulnerabilities: consequences of airborne releases

International Nuclear Information System (INIS)

Lu, M.S.; Epel, L.G.

1985-01-01

A simplified mathematical model has been developed to provide conservative estimates of radioactive and/or chemical dispersal consequences. The model is useful in assessing physical security protection needs and determining classification levels for information on DOE facilities. Sabotage scenarios for dispersals were developed based on public information, such as safety analysis reports and environmental impact statements for facilities of interest. The dispersal mechanisms considered included criticality incidents, explosive methods, pyrotechnics, lofting, etc. The technical knowledge required by a malevolent group intent upon causing dispersal includes the attack objective information, (target, source-consequences correlation and propagation characteristics) as well attack capability information (physical security, disperal know-how and engineered safety and protection features). Physical protection measures, which could protect materials via deterrence, detection, delay and apprehension, were suggested, along with classification techniques which could protect against dispersal by denying access to information critical to the success of sabotage. 9 refs., 6 figs

The Faustian bargain-hazards of theft and sabotage: Nuclear proliferation

International Nuclear Information System (INIS)

Anon.

1975-01-01

It is argued that the fissionable material in nuclear reactors, fuel reprocessing plants, waste storage facilities and that contained in the shipments of radioactive waste are vulnerable to sabotage and theft. (R.L.)

Getting even for customer mistreatment: the role of moral identity in the relationship between customer interpersonal injustice and employee sabotage.

Science.gov (United States)

Skarlicki, Daniel P; van Jaarsveld, Danielle D; Walker, David D

2008-11-01

Research on the "dark side" of organizational behavior has determined that employee sabotage is most often a reaction by disgruntled employees to perceived mistreatment. To date, however, most studies on employee retaliation have focused on intra-organizational sources of (in)justice. Results from this field study of customer service representatives (N = 358) showed that interpersonal injustice from customers relates positively to customer-directed sabotage over and above intra-organizational sources of fairness. Moreover, the association between unjust treatment and sabotage was moderated by 2 dimensions of moral identity (symbolization and internalization) in the form of a 3-way interaction. The relationship between injustice and sabotage was more pronounced for employees high (vs. low) in symbolization, but this moderation effect was weaker among employees who were high (vs. low) in internalization. Last, employee sabotage was negatively related to job performance ratings.

Projected Source Terms for Potential Sabotage Events Related to Spent Fuel Shipments

International Nuclear Information System (INIS)

Luna, R.E.; Neuhauser, K.S.; Vigil, M.G.

1999-01-01

Two major studies, one sponsored by the U.S. Department of Energy and the other by the U.S. Nuclear Regulatory Commission, were conducted in the late 1970s and early 1980s to provide information and source terms for an optimally successful act of sabotage on spent fuel casks typical of those available for use. This report applies the results of those studies and additional analysis to derive potential source terms for certain classes of sabotage events on spent fuel casks and spent fuel typical of those which could be shipped in the early decades of the 21st century. In addition to updating the cask and spent fuel characteristics used in the analysis, two release mechanisms not included in the earlier works were identified and evaluated. As would be expected, inclusion of these additional release mechanisms resulted in a somewhat higher total release from the postulated sabotage events. Although health effects from estimated releases were addressed in the earlier study conducted for U.S. Department of Energy, they have not been addressed in this report. The results from this report maybe used to estimate health effects

Protection of new and innovative NPPs against sabotage

International Nuclear Information System (INIS)

Guerpinar, Aybars

2005-01-01

The design of a nuclear installation requires the consideration of a multitude of aspects that also includes safety and protection against sabotage. Nuclear safety is a very important aspect of new reactor designs and new approaches to safety is a topic that has attracted international attention in recent years. The results of many IAEA Engineering Safety Reviews to nuclear installations have demonstrated that the way nuclear safety is considered in relation to external events has not been fully satisfactory for a majority of these. The main reasons for this involve the following: importing of different methods and criteria depending on the discipline involved related to the hazard in question (methods and criteria used in hydrology versus seismology for example), incorporation of design against external events too late in the process of design of the installation and appending the considerations for external events in assessment tools (both deterministic and probabilistic) as a separate item. By their nature, sabotage events may affect nuclear facilities as extreme loads not very differently from accidental external events and therefore face similar problems in the process of integration with the design of the installation at an early stage. (author)

Plague and Paideia: Sabotage in Devising Theatre with Young People

Science.gov (United States)

Wessels, Anne

2012-01-01

This ethnography, completed by the classroom teacher in a publicly funded secondary school in Mississauga, Canada, explores issues of conflict and sabotage that affected a devising project with suburban young people. The processes of devising generated ethnographic data that included a play script and videotaped rehearsals and performances. As…

Large fire scenarios in relation to sabotage of nuclear installations

International Nuclear Information System (INIS)

Contri, P.; Guerpinar, A.; ); Schneider, U.

2005-01-01

The analyses of sabotage scenarios carried out in recent years identified two major damaging mechanisms associated with such scenarios, namely: the mechanical interaction of solid bodies or pressure waves with the installations and the fire-related effects from burning substances. While the former effect may be addressed by available analytical tools developed for accidental scenarios, the latter deserves a new, specific engineering effort. In fact, all nuclear facilities are designed in relation to accidental fires; even so, they need to be assessed in relation to sabotage induced fire scenarios due to the special characteristics of such scenarios, not addressed by the current engineering practice for the design of nuclear installations. Conventional fire hazard analysis is based on the hypothesis of the presence of combustible materials in the buildings and limited number of contemporaneous sources of fire. In addition, conventional fire safety assessment relies upon the presence of mitigation measures and fire related operational procedures. In a sabotage event the validity of all these assumptions need to be checked and if the assumptions cannot be supported, then the analysis should be revised and other alternatives of protection should be developed. Also the implementation of emergency planning should be reviewed to take account of this concern. This paper collects state-of-the-art experience from some Countries, which represents the background information for the development of new IAEA documents in this field. The paper reviews how the current design practice for nuclear installations can cope with large fire scenarios caused by malevolent actions and provides recommendations to designers and operators on how to address these issues in a reasonable framework. (authors)

Conceptual Framework for Physical Protection Against Sabotage Considering Plant-specific Radiological Consequences

International Nuclear Information System (INIS)

Lee, Joung Hoon; Yu, Dong Han

2010-01-01

According to the Generation IV (Gen IV) Technology Roadmap, Gen IV nuclear energy systems (NESs) should highlight proliferation resistance and physical protection (PR and PP) as one of the four goals along with sustainability, safety and reliability, and economics. Especially, physical protection (PP) is the typical important characteristic of an NES that impedes the theft of materials suitable for nuclear explosives or radiation dispersal devices (RDD) and the sabotage of facilities and transportation by subnation entities and other non-Host State adversaries. These two subjects have been studied separately. Proliferation is commonly considered as an international concern and the past work on the PR assessments can be found. On the other hands, PP is regarded as a State security concern, much of which is classified and facility-dependent. Recently, more concern has been focused on the PP design and regulation because of rapid environment changes including radiological consequences by internal sabotage and nuclear terrorism by RDDs. The current PP Regulation has been applied intensively to the existing nuclear facilities and could be a possible guidance for the future GEN-IV NESs. This paper first reviews the IAEA guide document, INFCIRC/225, which was accepted as the standard international guideline in the physical protection area. It has been updated several times up to now, and is undergoing another revision. The paper introduces current substantial changes in the document regarding PP including the national nuclear security and sabotage in the nuclear facilities. Then, it presents a conceptual framework for physical protection against sabotage considering plant-specific radiological consequence after malicious acts within certain vital areas. The framework combines the newly developed method of vital area identification, the current PSA level 2 works, and physical protection concepts. This would help to improve a design concept of new physical protection

Conceptual Framework for Physical Protection Against Sabotage Considering Plant-specific Radiological Consequences

Energy Technology Data Exchange (ETDEWEB)

Lee, Joung Hoon; Yu, Dong Han [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2010-10-15

According to the Generation IV (Gen IV) Technology Roadmap, Gen IV nuclear energy systems (NESs) should highlight proliferation resistance and physical protection (PR and PP) as one of the four goals along with sustainability, safety and reliability, and economics. Especially, physical protection (PP) is the typical important characteristic of an NES that impedes the theft of materials suitable for nuclear explosives or radiation dispersal devices (RDD) and the sabotage of facilities and transportation by subnation entities and other non-Host State adversaries. These two subjects have been studied separately. Proliferation is commonly considered as an international concern and the past work on the PR assessments can be found. On the other hands, PP is regarded as a State security concern, much of which is classified and facility-dependent. Recently, more concern has been focused on the PP design and regulation because of rapid environment changes including radiological consequences by internal sabotage and nuclear terrorism by RDDs. The current PP Regulation has been applied intensively to the existing nuclear facilities and could be a possible guidance for the future GEN-IV NESs. This paper first reviews the IAEA guide document, INFCIRC/225, which was accepted as the standard international guideline in the physical protection area. It has been updated several times up to now, and is undergoing another revision. The paper introduces current substantial changes in the document regarding PP including the national nuclear security and sabotage in the nuclear facilities. Then, it presents a conceptual framework for physical protection against sabotage considering plant-specific radiological consequence after malicious acts within certain vital areas. The framework combines the newly developed method of vital area identification, the current PSA level 2 works, and physical protection concepts. This would help to improve a design concept of new physical protection

Are you being sabotaged by your coworkers?

Science.gov (United States)

Ferrara-Love, R

1998-10-01

Men and women are both guilty of sabotaging coworkers, but men and women do it differently and for different reasons. Men tend to do it more overtly and for more work-related reasons. However, women are more covert; their reasons are motivated more by jealousy of another's success or their own insecurity. Once women are betrayed by another, they take it more personally than their male counterparts. Men confront the betrayer and move on; that is business. Women do not confront the betrayer and see betrayal in the workplace as being let down by their friends. Women need to treat business relationships and situations as business, not as friendships.

A Study on Establishment of Unacceptable Radiological Consequence (URC) for Physical Protection against Sabotage

Energy Technology Data Exchange (ETDEWEB)

Jung, Myungtak; Koh, Moonsung; Lee, Youngwook; Jo, Kwang Ho [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2014-05-15

The international community has recommended that a graded approach should be applied to the establishment of the domestic regime for physical protection in accordance with fundamental principle H of the amended Convention on Physical Protection of Nuclear Material (CPPNM) and INFCIRC/225/rev.5. In Korea, Currently, the graded approach to unauthorized removal of nuclear material is divided into three categories (Category Ι, Category ΙΙ, Category ΙΙΙ) based on the IAEA INFCIRC/225/rev.5. Moreover, depending on the categorization of nuclear material, physical protection measures against unauthorized removal are also clearly categorized. But in the case of physical protection against sabotage, the graded approach to the physical protection measures is not applied since Unacceptable Radiological Consequence (URC) for identifying sabotage target and level is not determined. URC can be established based on either dose limit or design limit. The report by Sandia National Lab. in USA specifies that core damage is used for URC. Calculation of an exact dose is based on various assumptions and processes and subsequently increases uncertainty. Therefore, using design limit for decreasing uncertainty is more effective than using dose limit. In order to apply the graded approach to physical protection against sabotage, we have taken into Fundamental principle H : Physical protection requirements should be based on a graded approach, taking into account the current evaluation of the threat, the relative attractiveness, the nature of the material and potential consequences associated with the unauthorized removal of nuclear material and with the sabotage against nuclear material of nuclear facilities consideration legal and institutional standards on domestic and international radiological consequences and intended to provide a reference for the URC establishment by the State. The study on various standards led to the conclusion that each value has advantages and

Semiochemical sabotage: behavioral chemicals for protection of western conifers from bark beetles

Science.gov (United States)

Nancy. E. Gillette; A. Steve Munson

2009-01-01

The discovery and elucidation of volatile behavioral chemicals used by bark beetles to locate hosts and mates has revealed a rich potential for humans to sabotage beetle host-finding and reproduction. Here, we present a description of currently available semiochemical methods for use in monitoring and controlling bark beetle pests in western conifer forests. Delivery...

Pathfinding in graph-theoretic sabotage models. I. Simultaneous attack by several teams

International Nuclear Information System (INIS)

Hulme, B.L.

1976-07-01

Graph models are developed for fixed-site safeguards systems. The problem of finding optimal routes for several sabotage teams is cast as a problem of finding shortest paths in a graph. The motivation, rationale, and interpretation of the mathematical models are discussed in detail, and an algorithm for efficiently solving the associated path problem is described

Reducing the threat of nuclear theft and sabotage

International Nuclear Information System (INIS)

Bunn, Matthew; Bunn, George

2001-01-01

The appalling events of September II, 2001 make clear that the threat of well-organized global terrorist groups bent on causing mass destruction is not hypothetical but real. There is evidence that Osama bin Laden's Al Quaida organization is seeking weapons of mass destruction, and has attempted to purchase stolen nuclear material from the former Soviet Union for use in nuclear explosives. Ensuring that the technologies and materials of weapons of mass destruction - especially weapons-usable nuclear materials, do not fall into the hands of terrorist groups or hostile states must therefore be a central element of the coming global battle to prevent mass-destruction terrorism. At the same time, nuclear facilities and radioactive materials - along with a wide range of other especially hazardous facilities and materials - must be protected from mass-consequence sabotage. Limited access to fissile materials, the essential ingredients of nuclear weapons, is the principal technical barrier to nuclear proliferation in the world today. The international community has an overwhelming interest in seeing that all such material is secure and accounted for. These events highlight the urgent need to: Dramatically expand international cooperation to upgrade security and accounting for weapons- usable nuclear material, in the former Soviet Union and worldwide, with the goal of ensuring that all such material is protected to stringent standards within a few years; Ensure that all nuclear facilities and materials (and other particularly hazardous facilities) are secure from mass-consequence sabotage; Strengthen national and international standards for security of nuclear materials and facilities; Greatly expand international efforts to interdict nuclear smuggling, including the difficult but essential task of strengthening efforts to share intelligence in this critical area; Reduce the number of sites where significant quantities of weapons-usable nuclear material exist, and the size

Risk and resilience in the Nigerian oil sector: The economic effects of pipeline sabotage and theft

International Nuclear Information System (INIS)

Yeeles, Adam; Akporiaye, Alero

2016-01-01

Political unrest in the Niger Delta has long been viewed as a hurdle for extracting maximum value from Nigeria's oil resources. Recently, investors and policymakers have laid blame for sector under-performance on pipeline sabotage and theft, and sounded the alarm for an impending ‘oil crisis’. However, our understanding of the economic effects of social action against oil companies is incomplete. Rigorous analysis has not heretofore been offered as evidence for such dire futures. Despite the obvious risk of pipeline interdiction, price dynamics and aggregate production respond minimally to pipeline interdiction. Based on quantitative analysis of the relationship among price, production and pipeline interdiction from multiple data sources covering different time intervals (monthly data from 2005 to 2014 and annual data from 1999 to 2013), we find no evidence of significant effects of pipeline interdiction on production and a weak relationship between pipeline interdiction and Bonny light crude prices. Reported losses in product are substantial, but there is no evidence of statistically significant impacts on price or production in the aggregate. Explanations for this counterintuitive result are cast in terms of sector resilience. The implications of this finding for producer risk and the likelihood of an impending ‘oil crisis’ are discussed. - Highlights: • We examine the impact of pipeline sabotage and theft on the Nigerian oil economy. • Econometric analysis of production, price and pipeline interdiction over different time intervals. • Aggregate price and production are impacted minimally by pipeline interdiction. • Oil sector business risk is high, but production is resilient to interruptions from social and political unrest.

Safeguards and security by design (SSBD) for the domestic threat. Theft and sabotage

International Nuclear Information System (INIS)

DeMuth, Scott; Mullen, Mark; Pan, Paul

2011-01-01

In recent years, the Safeguards by Design (SBD) concept has received significant interest with respect to international (IAEA) safeguards objectives. However, less attention has been focused on the equally important topic of domestic (or national) Safeguards and Security by Design (SSBD), which addresses domestic requirements for material control and accounting (MC and A) and for physical protection, such as those of the Nuclear Regulatory Commission (NRC) in the United States. While international safeguards are concerned with detecting State diversion of nuclear material from peaceful uses to nuclear explosives purposes, domestic material control and accounting (MC and A) and physical protection are focused on non-State theft and sabotage. The International Atomic Energy Agency (IAEA) has described the Safeguards by Design (SBD) concept as an approach in which 'international safeguards are fully integrated into the design process of a new nuclear facility from the initial planning through design, construction, operation, and decommissioning.' This same concept is equally applicable to SSBD for domestic requirements. The United States Department of Energy (DOE) has initiated a project through its Office of Nuclear Energy (NE), and more specifically its Materials Protection, Accounting, and Control Technologies (MPACT) program, to develop a domestic SSBD discipline and methodology in parallel with similar efforts for international safeguards sponsored by the DOE Next Generation Safeguards Initiative (NGSI) and the IAEA. This paper identifies the key domestic safeguards and security requirements (i.e., MC and A and physical protection) and explains how and why Safeguards and Security by Design (SSBD) is important and beneficial for the design of future US nuclear energy systems. (author)

Safeguards and security by design (SSBD) for the domestic threat - theft and sabotage

International Nuclear Information System (INIS)

Demuth, Scott F.; Mullen, Mark

2011-01-01

Safeguards by Design (SBD) is receiving significant interest with respect to international safeguards objectives. However, less attention has been focused on the equally important topic of domestic Safeguards and Security by Design (SSBD), which addresses requirements such as those of the Nuclear Regulatory Commission (NRC) in the United States. While international safeguards are concerned with detecting State diversion of nuclear material from peaceful to nuclear explosives purposes, domestic Material Protection, Control and Accounting measures (MPC and A) are focused on non-State theft and sabotage. The International Atomic Energy Agency (IAEA) has described the Safeguards by Design (SBD) concept as an approach in which 'international safeguards are fully integrated into the design process of a new nuclear facility from the initial planning through design, construction, operation, and decommissioning.' This same concept is equally applicable to SSBD for domestic requirements. The United States Department of Energy (DOE) has initiated a project through its Office of Nuclear Energy (NE) and more specifically its Fuel Cycle Research and Development (FCRD) program, to develop a domestic SSBD discipline and methodology in parallel with similar efforts sponsored by the DOE Next Generation Safeguards Initiative (NGSI) and the IAEA for international safeguards. This activity includes the participation of industry (through DOE-sponsored contracts) and DOE National Laboratories. This paper will identify the key domestic safeguards and security requirements (i.e. MC and A and physical protection) and explain how and why Safeguards and Security by Design (SSBD) is important and beneficial for the design of future US nuclear energy systems.

The land of black gold, corruption, poverty and sabotage: Overcoming the Niger Delta’s problems through the establishment of a Nigerian Non-Renewable Revenue Special Fund (NNRSF

Directory of Open Access Journals (Sweden)

Adrian Gonzalez

2016-12-01

Full Text Available Through statistics published by the Shell Petroleum Development Company (SPDC, the paper explores why oilfield sabotage from 2009 to 2015 remains a problem in the Niger Delta, despite the 2009 amnesty programme. It explains why some of these incidents are a direct result of the failure to implement socio-economic development in successive state agencies due to corruption, a consequence of the natural resource curse. The article then explores why and how a Nigerian Non-Renewable Revenue Special Fund overseen by the United Nations Development Programme should be established which would not only manage a portion of oil revenue funds from the Niger Delta but also initiate valid social and economic projects in order to help reduce the prevalence of sabotage and instability in the region.

FRAUD/SABOTAGE Killing Nuclear-Reactors!!! ``Super"alloys GENERIC ENDEMIC Wigner's-Disease IN-stability!!!

Science.gov (United States)

Asphahani, Aziz; Siegel, Sidney; Siegel, Edward

2010-03-01

Siegel [[J.Mag.Mag.Mtls.7,312(78); PSS(a)11,45(72); Semis.& Insuls.5(79)] (at: ORNL, ANS, Westin``KL"ouse, PSEG, IAEA, ABB) warning of old/new nuclear-reactors/spent-fuel-casks/refineries/ jet/missile/rocket-engines austenitic/FCC Ni/Fe-based (so MIS- called)``super"alloys(182/82;Hastelloy-X; 600;304/304L-SSs; 690 !!!) GENERIC ENDEMIC EXTANT detrimental(synonyms): Wigner's- diseas(WD)[J.Appl.Phys.17,857(46)]; Ostwald-ripening; spinodal- decomposition; overageing-embrittlement; thermomechanical- INstability: Mayo[Google: ``If Leaks Could Kill"; at flickr.com search on ``Giant-Magnotoresistance"; find: [SiegelPolitics(79)]; Hoffman[animatedsoftware.com],...what DOE/NRC MISlabels as ``butt-welds" ``stress-corrosion cracking" endpoint's ROOT-CAUSE ULTIMATE-ORIGIN is WD overageing-embrit- tlement caused brittle-fracture cracking from early/ongoing AEC/DOE-n``u''tional-la``v''atories sabotage!!!

Relay test program

International Nuclear Information System (INIS)

Bandyopadhyay, K.K.; Kunkel, C.; Shteyngart, S.

1994-02-01

This report presents the results of a relay test program conducted by Brookhaven National Laboratory (BNL) under the sponsorship of the US Nuclear Regulatory Commission (NRC). The program is a continuation of an earlier test program the results of which were published in NUREG/CR-4867. The current program was carried out in two phases: electrical testing and vibration testing. The objective was primarily to focus on the electrical discontinuity or continuity of relays and circuit breaker tripping mechanisms subjected to electrical pulses and vibration loads. The electrical testing was conducted by KEMA-Powertest Company and the vibration testing was performed at Wyle Laboratories, Huntsville, Alabama. This report discusses the test procedures, presents the test data, includes an analysis of the data and provides recommendations regarding reliable relay testing

Details of Nazis' A-Bomb program surface

CERN Multimedia

Glanz, J

2002-01-01

Werner Heisenberg, leader of the Nazi atomic bomb program, revealed the projects existence to Niels Bohr in a meeting in Copenhagen in 1941. But contrary to several historical accounts of the meeting, Heisenberg never expressed moral qualms about building a bomb for Hitler nor hinted that he might be willing to sabotage the project, according to secret documents cited in a London newspaper yesterday (2 pages).

Use of fault and decision tree analyses to protect against industrial sabotage

International Nuclear Information System (INIS)

Fullwood, R.R.; Erdmann, R.C.

1975-01-01

Fault tree and decision tree analyses provide systematic bases for evaluation of safety systems and procedures. Heuristically, this paper shows applications of these methods for industrial sabotage analysis at a reprocessing plant. Fault trees constructed by ''leak path'' analysis for completeness through path inventory. The escape fault tree is readily developed by this method and using the reciprocal character of the trees, the attack fault tree is constructed. After construction, the events on the fault tree are corrected for their nonreciprocal character. The fault trees are algebraically solved and the protection that is afforded is ranked by the number of barriers that must be penetrated. No attempt is made to assess the barrier penetration probabilities or penetration time duration. Event trees are useful for dynamic plant protection analysis through their time-sequencing character. To illustrate their usefulness, a simple attack scenario is devised and event-tree analyzed. Two saboteur success paths and 21 failure paths are found. This example clearly shows the event tree usefulness for concisely presenting the time sequencing of key decision points. However, event trees have the disadvantage of being scenario dependent, therefore requiring a separate event tree for each scenario

FRAUD/SABOTAGE Killing Nuclear-Reactors Need Modeling!!!: "Super"alloys GENERIC ENDEMIC Wigner's-Disease/.../IN-stability: Ethics? SHMETHICS!!!

Science.gov (United States)

Asphahani, Aziz; Siegel, Sidney; Siegel, Edward

2010-03-01

Carbides solid-state chemistry domination of old/new nuclear- reactors/spent-fuel-casks/refineries/jet/missile/rocket-engines in austenitic/FCC Ni/Fe-based(so miscalled)``super"alloys(182/82; Hastelloy-X,600,304/304L-SSs,...,690!!!) GENERIC ENDEMIC EXTANT detrimental(synonyms): Wigner's-diseas(WD)[J.Appl.Phys.17,857 (1946)]/Ostwald-ripening/spinodal-decomposition/overageing- embrittlement/thermal-leading-to-mechanical(TLTM)-INstability: Mayo[Google:``If Leaks Could Kill"; at flickr.com search on ``Giant-Magnotoresistance"; find: Siegel[J.Mag.Mag.Mtls.7,312 (1978)]Politics(1979)]-Hoffman[animatedsoftware.com], what DOE/NRC MISlabels as ``butt-welds" ``stress-corrosion cracking" endpoint's ROOT-CAUSE ULTIMATE-ORIGIN is WD overageing-embritt- lement caused brittle-fracture cracking from early/ongoing AEC/ DOE-n"u"tional-la"v"atories sabotage!!!

Pseudomonas aeruginosa sabotages the generation of host proresolving lipid mediators

Energy Technology Data Exchange (ETDEWEB)

Flitter, Becca A.; Hvorecny, Kelli L.; Ono, Emiko; Eddens, Taylor; Yang, Jun; Kwak, Daniel H.; Bahl, Christopher D.; Hampton, Thomas H.; Morisseau, Christophe; Hammock, Bruce D.; Liu, Xinyu; Lee, Janet S.; Kolls, Jay K.; Levy, Bruce D.; Madden, Dean R.; Bomberger, Jennifer M.

2016-12-15

Recurrent Pseudomonas aeruginosa infections coupled with robust, damaging neutrophilic inflammation characterize the chronic lung disease cystic fibrosis (CF). The proresolving lipid mediator, 15-epi lipoxin A4 (15-epi LXA4), plays a critical role in limiting neutrophil activation and tissue inflammation, thus promoting the return to tissue homeostasis. Here, we show that a secreted P. aeruginosa epoxide hydrolase, cystic fibrosis transmembrane conductance regulator inhibitory factor (Cif), can disrupt 15-epi LXA4 transcellular biosynthesis and function. In the airway, 15-epi LXA4 production is stimulated by the epithelial-derived eicosanoid 14,15-epoxyeicosatrienoic acid (14,15-EET). Cif sabotages the production of 15-epi LXA4 by rapidly hydrolyzing 14,15-EET into its cognate diol, eliminating a proresolving signal that potently suppresses IL-8–driven neutrophil transepithelial migration in vitro. Retrospective analyses of samples from patients with CF supported the translational relevance of these preclinical findings. Elevated levels of Cif in bronchoalveolar lavage fluid were correlated with lower levels of 15-epi LXA4, increased IL-8 concentrations, and impaired lung function. Together, these findings provide structural, biochemical, and immunological evidence that the bacterial epoxide hydrolase Cif disrupts resolution pathways during bacterial lung infections. The data also suggest that Cif contributes to sustained pulmonary inflammation and associated loss of lung function in patients with CF.

An innovative approach for testing bioinformatics programs using metamorphic testing

Directory of Open Access Journals (Sweden)

Liu Huai

2009-01-01

Full Text Available Abstract Background Recent advances in experimental and computational technologies have fueled the development of many sophisticated bioinformatics programs. The correctness of such programs is crucial as incorrectly computed results may lead to wrong biological conclusion or misguide downstream experimentation. Common software testing procedures involve executing the target program with a set of test inputs and then verifying the correctness of the test outputs. However, due to the complexity of many bioinformatics programs, it is often difficult to verify the correctness of the test outputs. Therefore our ability to perform systematic software testing is greatly hindered. Results We propose to use a novel software testing technique, metamorphic testing (MT, to test a range of bioinformatics programs. Instead of requiring a mechanism to verify whether an individual test output is correct, the MT technique verifies whether a pair of test outputs conform to a set of domain specific properties, called metamorphic relations (MRs, thus greatly increases the number and variety of test cases that can be applied. To demonstrate how MT is used in practice, we applied MT to test two open-source bioinformatics programs, namely GNLab and SeqMap. In particular we show that MT is simple to implement, and is effective in detecting faults in a real-life program and some artificially fault-seeded programs. Further, we discuss how MT can be applied to test programs from various domains of bioinformatics. Conclusion This paper describes the application of a simple, effective and automated technique to systematically test a range of bioinformatics programs. We show how MT can be implemented in practice through two real-life case studies. Since many bioinformatics programs, particularly those for large scale simulation and data analysis, are hard to test systematically, their developers may benefit from using MT as part of the testing strategy. Therefore our work

Underground Nuclear Testing Program, Nevada Test Site

International Nuclear Information System (INIS)

1975-09-01

The Energy Research and Development Administration (ERDA) continues to conduct an underground nuclear testing program which includes tests for nuclear weapons development and other tests for development of nuclear explosives and methods for their application for peaceful uses. ERDA also continues to provide nuclear explosive and test site support for nuclear effects tests sponsored by the Department of Defense. This Supplement extends the Environmental Statement (WASH-1526) to cover all underground nuclear tests and preparations for tests of one megaton (1 MT) or less at the Nevada Test Site (NTS) during Fiscal Year 1976. The test activities covered include numerous continuing programs, both nuclear and non-nuclear, which can best be conducted in a remote area. However, if nuclear excavation tests or tests of yields above 1 MT or tests away from NTS should be planned, these will be covered by separate environmental statements

Test of user- and system programs coded in real time languages - requirements on program language and testing tool

International Nuclear Information System (INIS)

Hertlin, J.; Mackert, M.

1979-01-01

In the present paper the functions are presented, which should be part of a test system for user programs in a higher treat time programming language, taking into account time sequences and competitive processes. As can be shown by the problem of testing, use of higher level real time programming languages renders the task of program development essentially easier, however performance of test procedures without appropriate test systems is very difficult. After the presentation of notions and methods for the testing of programs, general requirements on testing tools are described and the test system functions for a program test, beeing uncritical with respect to time, are placed together. Thereby, for every individual function, the interface between the test system, the program under test, and the residual program-generation system (compiler, binder, operating system, delay-time system, and loader) is given too. For the time-critical test, a series of desirable functions are described, which can be implemented with acceptable expense. (orig.) [de

Improving nuclear safety at international research reactors: The Integrated Research Reactor Safety Enhancement Program (IRRSEP)

International Nuclear Information System (INIS)

Huizenga, David; Newton, Douglas; Connery, Joyce

2002-01-01

Nuclear energy continues to play a major role in the world's energy economy. Research and test reactors are an important component of a nation's nuclear power infrastructure as they provide training, experiments and operating experience vital to developing and sustaining the industry. Indeed, nations with aspirations for nuclear power development usually begin their programs with a research reactor program. Research reactors also are vital to international science and technology development. It is important to keep them safe from both accident and sabotage, not only because of our obligation to prevent human and environmental consequence but also to prevent corresponding damage to science and industry. For example, an incident at a research reactor could cause a political and public backlash that would do irreparable harm to national nuclear programs. Following the accidents at Three Mile Island and Chernobyl, considerable efforts and resources were committed to improving the safety posture of the world's nuclear power plants. Unsafe operation of research reactors will have an amplifying effect throughout a country or region's entire nuclear programs due to political, economic and nuclear infrastructure consequences. (author)

Social support for healthy behaviors: Scale psychometrics and prediction of weight loss among women in a behavioral program

Science.gov (United States)

Kiernan, Michaela; Moore, Susan D.; Schoffman, Danielle E.; Lee, Katherine; King, Abby C.; Taylor, C. Barr; Kiernan, Nancy Ellen; Perri, Michael G.

2015-01-01

Social support could be a powerful weight-loss treatment moderator or mediator but is rarely assessed. We assessed the psychometric properties, initial levels, and predictive validity of a measure of perceived social support and sabotage from friends and family for healthy eating and physical activity (eight subscales). Overweight/obese women randomized to one of two 6-month, group-based behavioral weight-loss programs (N=267; mean BMI 32.1±3.5; 66.3% White) completed subscales at baseline, and weight loss was assessed at 6 months. Internal consistency, discriminant validity, and content validity were excellent for support subscales and adequate for sabotage subscales; qualitative responses revealed novel deliberate instances not reflected in current sabotage items. Most women (>75%) “never” or “rarely” experienced support from friends or family. Using non-parametric classification methods, we identified two subscales—support from friends for healthy eating and support from family for physical activity—that predicted three clinically meaningful subgroups who ranged in likelihood of losing ≥5% of initial weight at 6 months. Women who “never” experienced family support were least likely to lose weight (45.7% lost weight) whereas women who experienced both frequent friend and family support were more likely to lose weight (71.6% lost weight). Paradoxically, women who “never” experienced friend support were most likely to lose weight (80.0% lost weight), perhaps because the group-based programs provided support lacking from friendships. Psychometrics for support subscales were excellent; initial support was rare; and the differential roles of friend versus family support could inform future targeted weight-loss interventions to subgroups at risk. PMID:21996661

In-situ thermal testing program strategy

International Nuclear Information System (INIS)

1995-06-01

In the past year the Yucca Mountain Site Characterization Project has implemented a new Program Approach to the licensing process. The Program Approach suggests a step-wise approach to licensing in which the early phases will require less site information than previously planned and necessitate a lesser degree of confidence in the longer-term performance of the repository. Under the Program Approach, the thermal test program is divided into two principal phases: (1) short-term in situ tests (in the 1996 to 2000 time period) and laboratory thermal tests to obtain preclosure information, parameters, and data along with bounding information for postclosure performance; and (2) longer-term in situ tests to obtain additional data regarding postclosure performance. This effort necessitates a rethinking of the testing program because the amount of information needed for the initial licensing phase is less than previously planned. This document proposes a revised and consolidated in situ thermal test program (including supporting laboratory tests) that is structured to meet the needs of the Program Approach. A customer-supplier model is used to define the Project data needs. These data needs, along with other requirements, were then used to define a set of conceptual experiments that will provide the required data within the constraints of the Program Approach schedule. The conceptual thermal tests presented in this document represent a consolidation and update of previously defined tests that should result in a more efficient use of Project resources. This document focuses on defining the requirements and tests needed to satisfy the goal of a successful license application in 2001, should the site be found suitable

Nuclear theft and sabotage. Priorities for reducing new threats

International Nuclear Information System (INIS)

Bunn, Matthew; Bunn, George

2001-01-01

The appalling attacks of 11 September 2001 in the United States make clear that the threat of large, well-organized global terrorist groups bent on causing mass destruction is not hypothetical but real. The attackers achieved horrifying destruction with box-cutters. The results could have been even more horrific if the attackers would have had access to, and used, weapons of mass destruction. Ensuring that technologies and materials for weapons of mass destruction - especially weapons-usable nuclear materials, whose acquisition is the most difficult part of making a nuclear bomb - do not fall into the hands of terrorist groups or hostile States must be a central element of the coming global effort to prevent catastrophic terrorism. At the same time, nuclear facilities and materials - along with a wide range of other especially hazardous facilities and materials must be protected from mass-consequence sabotage. Securing these materials and facilities must be a top priority on the international agenda - pursued at every opportunity, at every level of authority, until the job is done. At the same time, the threats against which we must defend have to be fundamentally reconsidered. On 11 September, the threat revealed itself to be bigger, smarter, better organized, and more deadly than the threats most of the world's security systems were designed to defend against. We must ensure that our defensive response is every bit as intelligent and capable as the September attackers. And we may have to rethink some of the approaches to nuclear energy that the world has been pursuing or contemplating. Every reasonable effort must be made to ensure that nuclear materials and facilities are effectively secured. In the past, many scenarios with enormously high consequences were dismissed as too unlikely to contribute much to overall risk - but now many of these probability estimates will have to be revised. A far-reaching new effort is needed to strengthen security for nuclear

Accelerated leach test development program

International Nuclear Information System (INIS)

Fuhrmann, M.; Pietrzak, R.F.; Heiser, J.; Franz, E.M.; Colombo, P.

1990-11-01

In FY 1989, a draft accelerated leach test for solidified waste was written. Combined test conditions that accelerate leaching were validated through experimental and modeling efforts. A computer program was developed that calculates test results and models leaching mechanisms. This program allows the user to determine if diffusion controls leaching and, if this is the case, to make projections of releases. Leaching mechanisms other than diffusion (diffusion plus source term partitioning and solubility limited leaching) are included in the program is indicators of other processes that may control leaching. Leach test data are presented and modeling results are discussed for laboratory scale waste forms composed of portland cement containing sodium sulfate salt, portland cement containing incinerator ash, and vinyl ester-styrene containing sodium sulfate. 16 refs., 38 figs., 5 tabs

Physical Protection Study of the Radio metallurgy Installation Using SAVIComputer Program

International Nuclear Information System (INIS)

Pinitoyo, Andreas

2000-01-01

Based on IAEA Recommendation on INFCIR/225/Rev.3 (The Physical Protectionof Nuclear Material), a nuclear installation shall have physical protectionsystem for protection or being secure on sabotage activities in theinstallation and thieve of nuclear materials. The recommendation states therequirements for physical protection of nuclear materials usage, transit andstorage. Radio metallurgy Installation of the Fuel Element and ReprocessingDevelopment Center (BATAN) at Serpong is a nuclear installation for researchon post irradiation of high radioactive spent fuel element, its processingand storage. The installation has risk on threat of a sabotage, which isdominant than thieve. The RMI building was designed and constructed ofphysical protection components and have been integrated with the BATAN Safetyand Security System and the Security Guards functions to be PhysicalProtection System for the RMI. By using the SAVI Computer Program with inputdata from the existing standards, assumptions for detection possibility,delay and response, that will result the probability of interruptions of theworst adversary paths PI = 0.1. These mean that the physical protectionsystems of the RMI shall be upgraded and improved in order to be reliable orbetter if the most of paths to the target PI = 1.0. (author)

Prototype steam generator test at SCTI/ETEC. Acoustic program test plan

International Nuclear Information System (INIS)

Greene, D.A.; Thiele, A.; Claytor, T.N.

1981-10-01

This document is an integrated test plan covering programs at General Electric (ARSD), Rockwell International (RI) and Argonne National Laboratory (CT). It provides an overview of the acoustic leak detection test program which will be completed in conjunction with the prototype LMFBR steam generator at the Energy Technology Engineering Laboratory. The steam generator is installed in the Sodium Components Test Installation (SCTI). Two acoustic detection systems will be used during the test program, a low frequency system developed by GE-ARSD (GAAD system) and a high frequency system developed by RI-AI (HALD system). These systems will be used to acquire data on background noise during the thermal-hydraulic test program. Injection devices were installed during fabrication of the prototype steam generator to provide localized noise sources in the active region of the tube bundle. These injectors will be operated during the steam generator test program, and it will be shown that they are detected by the acoustic systems

Towards a Theory for Testing Non-terminating Programs

DEFF Research Database (Denmark)

Gotlieb, Arnaud; Petit, Matthieu

2009-01-01

Non-terminating programs are programs that legally perform unbounded computations. Though they are ubiquitous in real-world applications, testing these programs requires new theoretic developments as usual definitions of test data adequacy criteria ignore infinite paths. This paper develops...... a theory of program-based structural testing based on operational semantics. Reasoning at the program semantics level permits to cope with infinite paths (and non-feasible paths) when defining test data adequacy criteria. As a result, our criteria respect the first Weyuker’s property on finite...... applicability, even for non-terminating programs. We discuss the consequences of this re-interpretation of test data adequacy criteria w.r.t. existing test coverage criteria....

Using Virtual ATE Model to Migrate Test Programs

Institute of Scientific and Technical Information of China (English)

王晓明; 杨乔林

1995-01-01

Bacause of high development costs of IC (Integrated Circuit)test programs,recycling existing test programs from one kind of ATE (Automatic Test Equipment) to another or generating directly from CAD simulation modules to ATE is more and more valuable.In this paper,a new approach to migrating test programs is presented.A virtual ATE model based on object-oriented paradigm is developed;it runs Test C++ (an intermediate test control language) programs and TeIF(Test Inftermediate Format-an intermediate pattern),migrates test programs among three kinds of ATE (Ando DIC8032,Schlumberger S15 and GenRad 1732) and generates test patterns from two kinds of CAD 9Daisy and Panda) automatically.

47 CFR 73.713 - Program tests.

Science.gov (United States)

2010-10-01

... International Broadcast Stations § 73.713 Program tests. (a) Upon completion of construction of an international.... The Commission reserves the right to change the date of the beginning of such tests or to suspend or revoke the authority for program tests as and when such action may appear to be in the public interest...

Nevada Test Site closure program

International Nuclear Information System (INIS)

Shenk, D.P.

1994-08-01

This report is a summary of the history, design and development, procurement, fabrication, installation and operation of the closures used as containment devices on underground nuclear tests at the Nevada Test Site. It also addresses the closure program mothball and start-up procedures. The Closure Program Document Index and equipment inventories, included as appendices, serve as location directories for future document reference and equipment use

Recommended well drilling and testing program

International Nuclear Information System (INIS)

Long, J.; Wilson, C.

1978-07-01

A well drilling and testing program is recommended by Lawrence Berkeley Laboratory to identify the hydrology of deep basalts in the Pasco Basin. The ultimate objective of this program is to assist in determining the feasibility of locating a nuclear waste repository on the Hanford Reservation. The recommended program has been staged for maximum effectiveness. In the first stage, six wells have been identified for drilling and testing which, when coupled with existing wells, will provide sufficient data for a preliminary overview of basin hydrology and a preliminary determination of the hydrologic suitability of the deep basalt for a repository site. The rate at which the first stage wells are drilled and tested will depend upon the date at which a preliminary determination of site suitability is required. It was assumed that a preliminary determination of suitability would be required in 1980, in which case all six first stage wells would be drilled in FY 1979. If the results of the first stage analysis are favorable for repository siting, tentative repository sites can be identified and a second stage hydrology program can be implemented to provide the necessary details of the flow system. To accomplish this stage, a number of deep wells would be required at locations both inside and outside the basin, with specific sites to be identified as the work progresses to obtain maximum utility of existing data. A program is recommended for testing in each new well and for completion of testing in each existing well. Recommended tests include borehole geophysics, pressure and permeability testing, geochemical sampling, tracer testing, hydrofracturing and borehole fracture logging. The entire data collection program is oriented toward providing the information required to establish and verify an accurate numerical model of the Pasco Basin

Manipulator comparative testing program

International Nuclear Information System (INIS)

Draper, J.V.; Handel, S.J.; Sundstrom, E.; Herndon, J.N.; Fujita, Y.; Maeda, M.

1986-01-01

The Manipulator Comparative Testing Program examined differences among manipulator systems from the United States and Japan. The manipulator systems included the Meidensha BILARM 83A, the Model M-2 of Central Research Laboratories Division of Sargent Industries (CRL), and the GCA Corporation PaR Systems Model 6000. The site of testing was the Remote Operations Maintenance Demonstration (ROMD) facility, operated by the Fuel Recycle Division in the Consolidated Fuel Reprocessing Program at the Oak Ridge National Laboratory (ORNL). In all stages of testing, operators using the CRL Model M-2 manipulator had consistently lower times to completion and error rates than they did using other machines. Performance was second best with the Meidensha BILARM 83A in master-slave mode. Performance with the BILARM in switchbox mode and the PaR 6000 manipulator was approximately equivalent in terms of criteria recorded in testing. These data show no impact of force reflection on task performance

Periodical test program in depth revision

International Nuclear Information System (INIS)

Feltin, C.; Zermizoglou, R.

1987-11-01

Inspection visits made to different sites during 1980 and 1981 evidenced the need to extend and define more precisely the periodical tests performed on safety related systems; thus Electricite de France was requested by the Safety Authorities to re-examine the periodical test program for all safety related systems. This paper presents the methodology adopted by Electricite de France in order to perform an exhaustive analysis of the periodical test program for the 900 and 1300 MWe plants, and the organization set up at the IPSN at one hand and Electricite de France on the other hand for the purpose of elaborating a periodical test program which would be ratified by the Safety Authorities

Evaluation of physical-protection elements for interior applications

International Nuclear Information System (INIS)

Scott, S.H.

1983-01-01

Considerable emphasis has been given in recent years to the threat of sabotage by an insider at nuclear facilities. This threat is inherently different from the outsider threat of theft or sabotage because of the insiders' unique knowledge and access to vital material and equipment. Thus, special safeguards elements are needed in order to counter the insider threat. In addition, insider physical protection system elements must be compatible with the operations, safety, and maintenance programs at the facility. To help identify elements which meet these needs, field evaluations were performed on an interior access control system, piping sensors, interior video motion detectors, and valve monitoring devices. These elements were tested in a realistic operating environment and both technical and operational evaluation data were obtained. Safeguards element descriptions and the results of the operational tests and evaluations are outlined

The PUMA test program and data analysis

International Nuclear Information System (INIS)

Han, J.T.; Morrison, D.L.

1997-01-01

The PUMA test program is sponsored by the U.S. Nuclear Regulatory Commission to provide data that are relevant to various Boiling Water Reactor phenomena. The author briefly describes the PUMA test program and facility, presents the objective of the program, provides data analysis for a large-break loss-of-coolant accident test, and compares the data with a RELAP5/MOD 3.1.2 calculation

FRAUD/SABOTAGE Killing Nuclear-Reactors Need Modeling!!!: ``Super'' alloys GENERIC ENDEMIC Wigner's-Disease/.../IN-stability: Ethics? SHMETHICS!!!

Science.gov (United States)

O'Grady, Joseph; Bument, Arlden; Siegel, Edward

2011-03-01

Carbides solid-state chemistry domination of old/new nuclear-reactors/spent-fuel-casks/refineries/jet/missile/rocket-engines is austenitic/FCC Ni/Fe-based (so miscalled)"super"alloys(182/82;Hastelloy-X,600,304/304L-SSs,...690!!!) GENERIC ENDEMIC EXTANT detrimental(synonyms): Wigner's-disease(WD) [J.Appl.Phys.17,857 (46)]/Ostwald-ripening/spinodal-decomposition/overageing-embrittlement/thermal-leading-to-mechanical(TLTM)-INstability: Mayo[Google: fLeaksCouldKill > ; - Siegel [ J . Mag . Mag . Mtls . 7 , 312 (78) = atflickr . comsearchonGiant - Magnotoresistance [Fert" [PRL(1988)]-"Gruenberg"[PRL(1989)] 2007-Nobel]necessitating NRC inspections on 40+25=65 Westin"KL"ouse PWRs(12/2006)]-Lai [Met.Trans.AIME, 9A,827(78)]-Sabol-Stickler[Phys.Stat.Sol.(70)]-Ashpahani[ Intl.Conf. Hydrogen in Metals, Paris(1977]-Russell [Prog.Mtls.Sci.(1983)]-Pollard [last UCS rept.(9/1995)]-Lofaro [BNL/DOE/NRC Repts.]-Pringle [ Nuclear-Power:From Physics to Politics(1979)]-Hoffman [animatedsoftware.com], what DOE/NRC MISlabels as "butt-welds" "stress-corrosion cracking" endpoint's ROOT-CAUSE ULTIMATE-ORIGIN is WD overageing-embrittlement caused brittle-fracture cracking from early/ongoing AEC/DOE-n"u"tional-la"v"atories sabotage!!!

Implementing an Information Security Program

Energy Technology Data Exchange (ETDEWEB)

Glantz, Clifford S.; Lenaeus, Joseph D.; Landine, Guy P.; O' Neil, Lori Ross; Leitch, Rosalyn; Johnson, Christopher; Lewis, John G.; Rodger, Robert M.

2017-11-01

The threats to information security have dramatically increased with the proliferation of information systems and the internet. Chemical, biological, radiological, nuclear, and explosives (CBRNe) facilities need to address these threats in order to protect themselves from the loss of intellectual property, theft of valuable or hazardous materials, and sabotage. Project 19 of the European Union CBRN Risk Mitigation Centres of Excellence Initiative is designed to help CBRN security managers, information technology/cybersecurity managers, and other decision-makers deal with these threats through the application of cost-effective information security programs. Project 19 has developed three guidance documents that are publically available to cover information security best practices, planning for an information security management system, and implementing security controls for information security.

Testing programs for the Multimission Modular Spacecraft

Science.gov (United States)

Greenwell, T. J.

1978-01-01

The Multimission Modular Spacecraft (MMS) provides a standard spacecraft bus to a user for a variety of space missions ranging from near-earth to synchronous orbits. The present paper describes the philosophy behind the MMS module test program and discusses the implementation of the test program. It is concluded that the MMS module test program provides an effective and comprehensive customer buy-off at the subsystem contractor's plant, is an optimum approach for checkout of the subsystems prior to use for on-orbit servicing in the Shuttle Cargo Bay, and is a cost-effective technique for environmental testing.

LANL Safeguards and Security Assurance Program. Revision 6

International Nuclear Information System (INIS)

1995-01-01

The Safeguards and Security (S and S) Assurance Program provides a continuous quality improvement approach to ensure effective, compliant S and S program implementation throughout the Los Alamos National Laboratory. Any issues identified through the various internal and external assessments are documented, tracked and closed using the Safeguards and Security Issue Management Program. The Laboratory utilizes an integrated S and S systems approach to protect US Department of Energy (DOE) interests from theft or diversion of special nuclear material (SNM), sabotage, espionage, loss or theft of classified/controlled matter or government property, and other hostile acts that may cause unacceptable impacts on national security, health and safety of employees and the public, and the environment. This document explains the basis, scope, and conduct of the S and S process to include: self-assessments, issue management, risk assessment, and root cause analysis. It also provides a discussion of S and S topical areas, roles and responsibilities, process flow charts, minimum requirements, methodology, terms, and forms

Quality Assurance Program Plan for TRUPACT-II Gas Generation Test Program

International Nuclear Information System (INIS)

2002-01-01

The Gas Generation Test Program (GGTP), referred to as the Program, is designed to establish the concentration of flammable gases and/or gas generation rates in a test category waste container intended for shipment in the Transuranic Package Transporter-II (TRUPACT-II). The phrase 'gas generationtesting' shall refer to any activity that establishes the flammable gas concentration or the flammable gas generation rate. This includes, but is not limited to, measurements performed directly on waste containers or during tests performed on waste containers. This Quality Assurance Program Plan (QAPP) documents the quality assurance (QA) and quality control (QC) requirements that apply to the Program. The TRUPACT-II requirements and technical bases for allowable flammable gas concentration and gas generation rates are described in the TRUPACT-II Authorized Methods for Payload Control (TRAMPAC).

The NRU blowdown test facility commissioning program

Energy Technology Data Exchange (ETDEWEB)

Walsworth, J A; Zanatta, R J; Yamazaki, A R; Semeniuk, D D; Wong, W; Dickson, L W; Ferris, C E; Burton, D H [Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.

1990-12-31

A major experimental program has been established at the Chalk River Nuclear Laboratories (CRL) that will provide essential data on the thermal and mechanical behaviour of nuclear fuel under abnormal reactor operating conditions and on the transient release, transport and deposition of fission product activity from severely degraded fuel. A number of severe fuel damage (SFD) experiments will be conducted within the Blowdown Test Facility (BTF) at CRL. A series of experiments are being conducted to commission this new facility prior to the SFD program. This paper describes the features and the commissioning program for the BTF. A development and testing program is described for critical components used on the reactor test section. In-reactor commissioning with a fuel assembly simulator commenced in 1989 June and preliminary results are given. The paper also outlines plans for future all-effects, in-reactor tests of CANDU-designed fuel. (author). 11 refs., 3 tabs., 7 figs.

Sheath insulator final test report, TFE Verification Program

Energy Technology Data Exchange (ETDEWEB)

1994-07-01

The sheath insulator in a thermionic cell has two functions. First, the sheath insulator must electrically isolate the collector form the outer containment sheath tube that is in contact with the reactor liquid metal coolant. Second, The sheath insulator must provide for high uniform thermal conductance between the collector and the reactor coolant to remove away waste heat. The goals of the sheath insulator test program were to demonstrate that suitable ceramic materials and fabrication processes were available, and to validate the performance of the sheath insulator for TFE-VP requirements. This report discusses the objectives of the test program, fabrication development, ex-reactor test program, in-reactor test program, and the insulator seal specifications.

Sheath insulator final test report, TFE Verification Program

International Nuclear Information System (INIS)

1994-07-01

The sheath insulator in a thermionic cell has two functions. First, the sheath insulator must electrically isolate the collector form the outer containment sheath tube that is in contact with the reactor liquid metal coolant. Second, The sheath insulator must provide for high uniform thermal conductance between the collector and the reactor coolant to remove away waste heat. The goals of the sheath insulator test program were to demonstrate that suitable ceramic materials and fabrication processes were available, and to validate the performance of the sheath insulator for TFE-VP requirements. This report discusses the objectives of the test program, fabrication development, ex-reactor test program, in-reactor test program, and the insulator seal specifications

Definition study of a Variable Cycle Experimental Engine (VCEE) and associated test program and test plan

Science.gov (United States)

Allan, R. D.

1978-01-01

The Definition Study of a Variable Cycle Experimental Engine (VCEE) and Associated Test Program and Test Plan, was initiated to identify the most cost effective program for a follow-on to the AST Test Bed Program. The VCEE Study defined various subscale VCE's based on different available core engine components, and a full scale VCEE utilizing current technology. The cycles were selected, preliminary design accomplished and program plans and engineering costs developed for several program options. In addition to the VCEE program plans and options, a limited effort was applied to identifying programs that could logically be accomplished on the AST Test Bed Program VCE to extend the usefulness of this test hardware. Component programs were provided that could be accomplished prior to the start of a VCEE program.

IFE chamber technology testing program in NIF and chamber development test plan

International Nuclear Information System (INIS)

Abdou, M.A.

1995-01-01

Issues concerning chamber technology testing program in NIF involving: criteria for evaluation/prioritization of experiments, engineering scaling requirements for test article design and material selection and R and D plan prior to NIF testing were addressed in this paper. In order to maximize the benefits of testing program in NIF, the testing in NIF should provide the experimental data relevant to DEMO design choice or to DEMO design predictive capability by utilizing engineering scaling test article designs. Test plans were developed for 2 promising chamber design concepts. Early testing in non-fusion/non-ignition prior to testing in ignition facility serves a critical role in chamber R and D test plans in order to reduce the risks and costs of the more complex experiments in NIF

SAPE Database Building for a Security System Test Bed

International Nuclear Information System (INIS)

Jo, Kwangho; Kim, Woojin

2013-01-01

Physical protection to prevent radiological sabotage and the unauthorized removal of nuclear material is one of the important activities. Physical protection system (PPS) of nuclear facilities needs the effectiveness analysis. This effectiveness analysis of PPS is evaluated by the probability of blocking the attack at the most vulnerable path. Systematic Analysis of Physical Protection Effectiveness (SAPE) is one of a computer code developed for the vulnerable path analysis. SAPE is able to analyze based on the data of the experimental results that can be obtained through the Test Bed. In order to utilize the SAPE code, we conducted some field tests on several sensors and acquired data. This paper aims at describing the way of DB (database) establishment

Spacecraft Testing Programs: Adding Value to the Systems Engineering Process

Science.gov (United States)

Britton, Keith J.; Schaible, Dawn M.

2011-01-01

Testing has long been recognized as a critical component of spacecraft development activities - yet many major systems failures may have been prevented with more rigorous testing programs. The question is why is more testing not being conducted? Given unlimited resources, more testing would likely be included in a spacecraft development program. Striking the right balance between too much testing and not enough has been a long-term challenge for many industries. The objective of this paper is to discuss some of the barriers, enablers, and best practices for developing and sustaining a strong test program and testing team. This paper will also explore the testing decision factors used by managers; the varying attitudes toward testing; methods to develop strong test engineers; and the influence of behavior, culture and processes on testing programs. KEY WORDS: Risk, Integration and Test, Validation, Verification, Test Program Development

Extending the multifoci perspective: The role of supervisor justice and moral identity in the relationship between customer justice and customer-directed sabotage.

Science.gov (United States)

Skarlicki, Daniel P; van Jaarsveld, Danielle D; Shao, Ruodan; Song, Young Ho; Wang, Mo

2016-01-01

The multifoci perspective of justice proposes that individuals tend to target their (in)justice reactions toward the perceived source of the mistreatment. Empirical support for target-specific reactions, however, has been mixed. To explore theoretically relevant reasons for these discrepant results and address unanswered questions in the multifoci justice literature, the present research examines how different justice sources might interactively predict target-specific reactions, and whether these effects occur as a function of moral identity. Results from a sample of North American frontline service employees (N = 314, Study 1) showed that among employees with lower levels of moral identity, low supervisor justice exacerbated the association between low customer justice and customer-directed sabotage, whereas this exacerbation effect was not observed among employees with higher levels of moral identity. This 3-way interaction effect was replicated in a sample of South Korean employees (N = 265, Study 2). (c) 2016 APA, all rights reserved).

Audit program for physical security systems at nuclear power plants

International Nuclear Information System (INIS)

Minichino, C.

1982-01-01

Licensees of nuclear power plants conduct audits of their physical security systems to meet the requirements of 10 CFR 73, Physical Protection of Plants and Materials. Section 73.55, Requirements for physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage, requires that the security programs be reviewed at least every 12 months, that the audit be conducted by individuals independent of both security management and security supervision, and that the audit program review all aspects of the physical security system: hardware, personnel, and operational and maintenance procedures. This report contains information for the Nuclear Regulatory Commission (NRC) and for the licensees of nuclear power reactors who carry out these comprehensive audits. Guidance on the overall management of the audit function includes organizational structure and issues concerning the auditors who perform the review: qualifications, independence, due professional care, and standards. Guidance in the audit program includes purpose and scope of the audit, planning, techniques, post-audit procedures, reporting, and follow-up

Cooperative field test program for wind systems

Energy Technology Data Exchange (ETDEWEB)

Bollmeier, W.S. II; Dodge, D.M.

1992-03-01

The objectives of the Federal Wind Energy Program, managed by the US Department of Energy (DOE), are (1) to assist industry and utilities in achieving a multi-regional US market penetration of wind systems, and (2) to establish the United States as the world leader in the development of advanced wind turbine technology. In 1984, the program conducted a series of planning workshops with representatives from the wind energy industry to obtain input on the Five-Year Research Plan then being prepared by DOE. One specific suggestion that came out of these meetings was that the federal program should conduct cooperative research tests with industry to enhance the technology transfer process. It was also felt that the active involvement of industry in DOE-funded research would improve the state of the art of wind turbine technology. DOE established the Cooperative Field Test Program (CFTP) in response to that suggestion. This program was one of the first in DOE to feature joint industry-government research test teams working toward common objectives.

Test Program Set (TPS) Lab

Data.gov (United States)

Federal Laboratory Consortium — The ARDEC TPS Laboratory provides an organic Test Program Set (TPS) development, maintenance, and life cycle management capability for DoD LCMC materiel developers....

Stuxnet. First strike in the cyber war?; Stuxnet. Erstschlag im Cyberkrieg?

Energy Technology Data Exchange (ETDEWEB)

Weinberger, Sharon [Alicia Patterson Foundation, Washington, DC (United States)

2011-10-15

In June 2010, the computer virus Stuxnet was discovered in Iran. This virus was more complex than any previously known malicious programs. In special test laboratories it could be shown that this virus had been developed by experts in order to sabotage industrial production processes. Since Stuxnet can be installed on a USB flash drive, it does not require an internet access for infection.

77 FR 18793 - Spectrum Sharing Innovation Test-Bed Pilot Program

Science.gov (United States)

2012-03-28

.... 120322212-2212-01] Spectrum Sharing Innovation Test-Bed Pilot Program AGENCY: National Telecommunications... Innovation Test-Bed pilot program to assess whether devices employing Dynamic Spectrum Access techniques can... Spectrum Sharing Innovation Test-Bed (Test-Bed) pilot program to examine the feasibility of increased...

NRC valve performance test program - check valve testing

International Nuclear Information System (INIS)

Jeanmougin, N.M.

1987-01-01

The Valve Performance Test Program addresses the current requirements for testing of pressure isolation valves (PIVs) in light water reactors. Leak rate monitoring is the current method used by operating commercial power plants to survey the condition of their PIVs. ETEC testing of three check valves (4-inch, 6-inch, and 12-inch nominal diameters) indicates that leak rate testing is not a reliable method for detecting impending valve failure. Acoustic emission monitoring of check valves shows promise as a method of detecting loosened internals damage. Future efforts will focus on evaluation of acoustic emission monitoring as a technique for determining check valve condition. Three gate valves also will be tested to evaluate whether the check valve results are applicable to gate type PIVs

Programmed Death-Ligand 1 Immunohistochemistry Testing

DEFF Research Database (Denmark)

Büttner, Reinhard; Gosney, John R; Skov, Birgit Guldhammer

2017-01-01

Purpose Three programmed death-1/programmed death-ligand 1 (PD-L1) inhibitors are currently approved for treatment of non-small-cell lung cancer (NSCLC). Treatment with pembrolizumab in NSCLC requires PD-L1 immunohistochemistry (IHC) testing. Nivolumab and atezolizumab are approved without PD-L1...

NRC Confirmatory Testing Program for SBWR

International Nuclear Information System (INIS)

Han, J.T.; Bessette, D.E.; Shotkin, L.M.

1994-01-01

The objective of the NRC Confirmatory Testing Program for SBWR is to provide integral data for code assessment, which reasonably reproduce the important phenomena and processes expected in the SBWR under various loss-of-coolant accident (LOCA) and transient conditions. To achieve this objective, the Program consists of four coupled elements: (1) to design and construct an integral, carefully-scaled SBWR test facility at Purdue Univ., (2) to provide pre-construction RELAP5/CONTAIN predictions of the facility design, (3) to provide confirmatory data for code assessment, and (4) to assess the RELAP5/CONTAIN code with data. A description of the open-quotes preliminary designclose quotes of the Purdue test facility and test matrix is presented. The facility is scheduled to be built by December 1994. Approximately 50 tests will be performed from April 1995 through April 1996 and documented by interim data reports. A final and complete data report is scheduled to be published by July 31, 1996

Programs for Testing Processor-in-Memory Computing Systems

Science.gov (United States)

Katz, Daniel S.

2006-01-01

The Multithreaded Microbenchmarks for Processor-In-Memory (PIM) Compilers, Simulators, and Hardware are computer programs arranged in a series for use in testing the performances of PIM computing systems, including compilers, simulators, and hardware. The programs at the beginning of the series test basic functionality; the programs at subsequent positions in the series test increasingly complex functionality. The programs are intended to be used while designing a PIM system, and can be used to verify that compilers, simulators, and hardware work correctly. The programs can also be used to enable designers of these system components to examine tradeoffs in implementation. Finally, these programs can be run on non-PIM hardware (either single-threaded or multithreaded) using the POSIX pthreads standard to verify that the benchmarks themselves operate correctly. [POSIX (Portable Operating System Interface for UNIX) is a set of standards that define how programs and operating systems interact with each other. pthreads is a library of pre-emptive thread routines that comply with one of the POSIX standards.

Mobile Energy Laboratory energy-efficiency testing programs

International Nuclear Information System (INIS)

Parker, G.B.; Currie, J.W.

1992-03-01

This report summarizes energy-efficiency testing activities applying the Mobile Energy Laboratory (MEL) testing capabilities during the third and fourth quarters of fiscal year (FY) 1991. The MELs, developed by the US Department of Energy (DOE) Federal Energy Management Program (FEMP), are administered by Pacific Northwest Laboratory (PNL) and the Naval Energy and Environmental Support Activity (NEESA) for energy testing and energy conservation program support functions at federal facilities. The using agencies principally fund MEL applications, while DOE/FEMP funds program administration and capability enhancement activities. This report fulfills the requirements established in Section 8 of the MEL Use Plan (PNL-6861) for semi-annual reporting on energy-efficiency testing activities using the MEL capabilities. The MEL Use Committee, formally established in 1989, developed the MEL Use Plan and meets semi-annually to establish priorities for energy-efficient testing applications using the MEL capabilities. The MEL Use Committee is composed of one representative each of the US Department of Energy, US Army, US Air Force, US Navy, and other federal agencies

Mobile Energy Laboratory energy-efficiency testing programs

Energy Technology Data Exchange (ETDEWEB)

Parker, G B; Currie, J W

1992-03-01

This report summarizes energy-efficiency testing activities applying the Mobile Energy Laboratory (MEL) testing capabilities during the third and fourth quarters of fiscal year (FY) 1991. The MELs, developed by the US Department of Energy (DOE) Federal Energy Management Program (FEMP), are administered by Pacific Northwest Laboratory (PNL) and the Naval Energy and Environmental Support Activity (NEESA) for energy testing and energy conservation program support functions at federal facilities. The using agencies principally fund MEL applications, while DOE/FEMP funds program administration and capability enhancement activities. This report fulfills the requirements established in Section 8 of the MEL Use Plan (PNL-6861) for semi-annual reporting on energy-efficiency testing activities using the MEL capabilities. The MEL Use Committee, formally established in 1989, developed the MEL Use Plan and meets semi-annually to establish priorities for energy-efficient testing applications using the MEL capabilities. The MEL Use Committee is composed of one representative each of the US Department of Energy, US Army, US Air Force, US Navy, and other federal agencies.

BNL NONLINEAR PRE TEST SEISMIC ANALYSIS FOR THE NUPEC ULTIMATE STRENGTH PIPING TEST PROGRAM

International Nuclear Information System (INIS)

DEGRASSI, G.; HOFMAYER, C.; MURPHY, C.; SUZUKI, K.; NAMITA, Y.

2003-01-01

The Nuclear Power Engineering Corporation (NUPEC) of Japan has been conducting a multi-year research program to investigate the behavior of nuclear power plant piping systems under large seismic loads. The objectives of the program are: to develop a better understanding of the elasto-plastic response and ultimate strength of nuclear piping; to ascertain the seismic safety margin of current piping design codes; and to assess new piping code allowable stress rules. Under this program, NUPEC has performed a large-scale seismic proving test of a representative nuclear power plant piping system. In support of the proving test, a series of materials tests, static and dynamic piping component tests, and seismic tests of simplified piping systems have also been performed. As part of collaborative efforts between the United States and Japan on seismic issues, the US Nuclear Regulatory Commission (USNRC) and its contractor, the Brookhaven National Laboratory (BNL), are participating in this research program by performing pre-test and post-test analyses, and by evaluating the significance of the program results with regard to safety margins. This paper describes BNL's pre-test analysis to predict the elasto-plastic response for one of NUPEC's simplified piping system seismic tests. The capability to simulate the anticipated ratcheting response of the system was of particular interest. Analyses were performed using classical bilinear and multilinear kinematic hardening models as well as a nonlinear kinematic hardening model. Comparisons of analysis results for each plasticity model against test results for a static cycling elbow component test and for a simplified piping system seismic test are presented in the paper

NCAA Drug-Testing Program 2010-11

Science.gov (United States)

National Collegiate Athletic Association (NJ1), 2010

2010-01-01

The National Collegiate Athletic Association (NCAA) Drug-Testing Program was created to protect the health and safety of student-athletes and to ensure that no one participant might have an artificially induced advantage or be pressured to use chemical substances. This publication describes this program in the following chapters: (1) NCAA…

Helping Students Test Programs That Have Graphical User Interfaces

Directory of Open Access Journals (Sweden)

Matthew Thornton

2008-08-01

Full Text Available Within computer science education, many educators are incorporating software testing activities into regular programming assignments. Tools like JUnit and its relatives make software testing tasks much easier, bringing them into the realm of even introductory students. At the same time, many introductory programming courses are now including graphical interfaces as part of student assignments to improve student interest and engagement. Unfortunately, writing software tests for programs that have significant graphical user interfaces is beyond the skills of typical students (and many educators. This paper presents initial work at combining educationally oriented and open-source tools to create an infrastructure for writing tests for Java programs that have graphical user interfaces. Critically, these tools are intended to be appropriate for introductory (CS1/CS2 student use, and to dovetail with current teaching approaches that incorporate software testing in programming assignments. We also include in our findings our proposed approach to evaluating our techniques.

Physical protection of shipments of irradiated reactor fuel

International Nuclear Information System (INIS)

Kasun, D.J.

1979-05-01

During May 1979 the U.S. Nuclear Regulatory Commission approved for issuance in effective form new interim regulations for strengthening the protection of spent fuel shipments against sabotage and diversion. The new regulations will likely continue in force until the completion of an ongoing research program concerning the response of spent fuel to certain forms of sabotage. At that time the regulations may be rescinded, modified, or made permanent, as appropriate. This report discusses the new regulations and provides a basis on which licensees can develop an acceptable interim program for the protection of spent fuel shipments

Accelerated Leach Test(s) Program. Annual report

International Nuclear Information System (INIS)

Dougherty, D.R.; Fuhrmann, M.; Colombo, P.

1985-09-01

This report summarizes the work performed for the Accelerated Leach Test(s) Program at Brookhaven National Laboratory in Fiscal Year 1985 under the sponsorship of the US Department of Energy's Low-Level Waste Management Program (LLWMP). Programmatic activities were concentrated in three areas, as listed and described in the following paragraphs. (1) A literature survey of reported leaching mechanisms, available mathematical models and factors that affect leaching of LLW forms has been compiled. Mechanisms which have been identified include diffusion, dissolution, ion exchange, corrosion and surface effects. Available mathematical models are based on diffusion as the predominant mechanism. Although numerous factors that affect leaching have been identified, they have been conveniently categorized as factors related to the entire leaching system, to the leachant or to the waste form. A report has been published on the results of this literature survey. (2) A computerized data base of LLW leaching data and mathematical models is being developed. The data are being used for model evaluation by curve fitting and statistical analysis according to standard procedures of statistical quality control. (3) Long-term tests on portland cement, bitumen and vinyl ester-styrene (VES) polymer waste forms are underway which are designed to identify and evaluate factors that accelerate leaching without changing the mechanisms. Results on the effect of temperature on leachability indicate that the leach rates of cement and VES waste forms increase with increasing temperature, whereas, the leach rate of bitumen is little affected

Collider Dipole Magnet test program from development through production

International Nuclear Information System (INIS)

Bailey, R.E.

1991-01-01

Verification of CDM performance, reliability, and magnet production processes will be accomplished during the development phase of the program. Key features of this program include thorough in process testing of magnet subassemblies, verification of the magnetic field quality, and demonstration of the CDM performance during the formal qualification program. Reliability demonstration of the CDM design includes component tests and an accelerated life test program. Prototype magnet phase will address achievement of magnet performance goals through a program of fabrications, test, analysis, redesign as required and procurement of modified parts for a second fabrication run. This process would be repeated again if necessary, and would conclude with a final design for the production magnets. Production process validation will address the effects that key production processes have upon magnet performance, using the magnets produced during the Preproduction phase

Open literature review of threats including sabotage and theft of fissile material transport in Japan

International Nuclear Information System (INIS)

Cochran, John Russell; Furaus, James Phillip; Marincel, Michelle K.

2005-01-01

This report is a review of open literature concerning threats including sabotage and theft related to fissile material transport in Japan. It is intended to aid Japanese officials in the development of a design basis threat. This threat includes the external threats of the terrorist, criminal, and extremist, and the insider threats of the disgruntled employee, the employee forced into cooperation via coercion, the psychotic employee, and the criminal employee. Examination of the external terrorist threat considers Japanese demographics, known terrorist groups in Japan, and the international relations of Japan. Demographically, Japan has a relatively homogenous population, both ethnically and religiously. Japan is a relatively peaceful nation, but its history illustrates that it is not immune to terrorism. It has a history of domestic terrorism and the open literature points to the Red Army, Aum Shinrikyo, Chukaku-Ha, and Seikijuku. Japan supports the United States in its war on terrorism and in Iraq, which may make Japan a target for both international and domestic terrorists. Crime appears to remain low in Japan; however sources note that the foreign crime rate is increasing as the number of foreign nationals in the country increases. Antinuclear groups' recent foci have been nuclear reprocessing technology, transportation of MOX fuel, and possible related nuclear proliferation issues. The insider threat is first defined by the threat of the disgruntled employee. This threat can be determined by studying the history of Japan's employment system, where Keiretsu have provided company stability and lifetime employment. Recent economic difficulties and an increase of corporate crime, due to sole reliability on the honor code, have begun to erode employee loyalty

Single event upset test programs

International Nuclear Information System (INIS)

Russen, L.C.

1984-11-01

It has been shown that the heavy ions in cosmic rays can give rise to single event upsets in VLSI random access memory devices (RAMs). Details are given of the programs written to test 1K, 4K, 16K and 64K memories during their irradiation with heavy charged ions, in order to simulate the effects of cosmic rays in space. The test equipment, which is used to load the memory device to be tested with a known bit pattern, and subsequently interrogate it for upsets, or ''flips'', is fully described. (author)

DWPF Stage 2: precipitation test program at Mott

International Nuclear Information System (INIS)

Schmitz, M.A.

1981-01-01

This memorandum covers the results of the test program conducted at Mott Metallurgical to determine cross-flow filter performance on potassium/cesium tetraphenylborate (K/Cs TPB)-sodium titanate slurries. The test program was designed to provide essential basic operating data to supplement the 1000-gallon cold process tests planned at TNX and the shielded cell tests with actual waste supernate planned by Chemical Technology. The specific Mott Metallurgical test objectives are outlined in DPST-81-722. During the Mott Metallurgical test program an average filtrate flow rate of approximately 0.05 gpm/ft 2 was repeatedly demonstrated over an 8-hr run with 0.5 micron filter elements. Initial Fe/Al sludge concentrations up to 150 ppM did not affect filter performance. Rheologies of the K/Cs TPB-sodium titanate slurries up to 13% by weight, the maximum concentration achieved, are summarized. Several recommendations are made to act as a guide for optimal filter performance

The advanced test reactor strategic evaluation program

International Nuclear Information System (INIS)

Buescher, B.J.

1989-01-01

Since the Chernobly accident, the safety of test reactors and irradiation facilities has been critically evaluated from the public's point of view. A systematic evaluation of all safety, environmental, and operational issues must be made in an integrated manner to prioritize actions to maximize benefits while minimizing costs. Such a proactive program has been initiated at the Advanced Test Reactor (ATR). This program, called the Strategic Evaluation Program (STEP), is being conducted for the ATR to provide integrated safety and operational reviews of the reactor against the standards applied to licensed commercial power reactors. This has taken into consideration the lessons learned by the US Nuclear Regulatory Commission (NRC) in its Systematic Evaluation Program (SEP) and the follow-on effort known as the Integrated Safety Assessment Program (ISAP). The SEP was initiated by the NRC to review the designs of older operating nuclear power plants to confirm and document their safety. The ATR STEP objectives are discussed

Automated [inservice testing] IST program

International Nuclear Information System (INIS)

Wright, W.M.

1990-01-01

There are two methods used to manage a Section XI program: Manual and Automated. The manual method usually consists of hand written records of test results and scheduling requirements. This method while initially lower in cost, results in problems later on in the life of a plant as data continues to accumulate. Automation allows instant access to forty years of test results. Due to the lower cost and higher performance of todays' personal computers, an automated method via a computer program provides an excellent method for managing the vast amount of data that accumulates over the forty year life of a plant. Through the use of a computer, special functions involving this data are available, which through a manual method would not be practical. This paper will describe some of the advantages in using a computer program to manage the Section XI 1ST program. The ISTBASE consists of program code and numerous databases. The source code is written and complied in CLIPPER (tm) language. Graphing routines are performed by dGE (tm) graphics library. Graphs are displayed in EGA form. Since it was estimated that the total complied code, would exceed 640K of ram, overlays through the use of modular programming were used to facilitate the DOS restrictions of 640K ram. The use of overlays still require the user to gain access to ISTBASE through the PASSWORD module. The database files are designed to be compatible with dBASE III+ (tm) data structure. This allows transfer of data between ISTBASE and other database managers/applications. A math co-processor is utilized to speed up calculations on graphs and other mathematical calculations. Program code and data files require a hard disk drive with at least 28 Meg capacity. While ISTBASE will execute on a 8088 based computer, an 80286 computer with a 12 MHz operating speed should be considered the minimum system configuration

PBF/LOFT Lead Rod Test Program experiment operating specification

International Nuclear Information System (INIS)

Varacalle, D.J. Jr.

1978-11-01

The PBF/LOFT Lead Rod (LLR) Test Program is being conducted to provide experimental information on the behavior of nuclear fuel under normal and accident conditions in the Power Burst Facility at the Idaho National Engineering Laboratory. Understanding the behavior of light-water reactors (LWR) under loss-of-coolant conditions is a major objective of the NRC Reactor Safety Research Program. The Loss of Fluid Test (LOFT) facility is the major testing facility to evaluate the systems response of an LWR over a wide range of Loss of Coolant Experment (LOCE) conditions. As such, the LOFT core is intended to be used for sequential LOCE tests provided no significant fuel rod failures occur. The PFB/LLR tests are designed to simulate the test conditions for the LOFT Power Ascension Tests L2-2 through L2-5. The test program has been designed to provide a parametric evaluation of the LOFT fuel over a wide range of power. Thus, a relatively accurate assessment of the state of the LOFT core after the completion of each subtest and the anticipated effect of the next test can be obtained by utilizing a combination of LLR test data and analytical predictions. Specifications for the test program are presented

Plutonium Immobilization Program cold pour tests

International Nuclear Information System (INIS)

Hovis, G.L.; Stokes, M.W.; Smith, M.E.; Wong, J.W.

1999-01-01

The Plutonium Immobilization Program (PIP) is a joint venture between the Savannah River Site, Lawrence Livermore National Laboratory, Argonne National Laboratory, and Pacific Northwest National Laboratory to carry out the disposition of excess weapons-grade plutonium. This program uses the can-in-canister (CIC) approach. CIC involves encapsulating plutonium in ceramic forms (or pucks), placing the pucks in sealed stainless steel cans, placing the cans in long cylindrical magazines, latching the magazines to racks inside Defense Waste Processing Facility (DWPF) canisters, and filling the DWPF canisters with high-level waste glass. This process puts the plutonium in a stable form and makes it attractive for reuse. At present, the DWPF pours glass into empty canisters. In the CIC approach, the addition of a stainless steel rack, magazines, cans, and ceramic pucks to the canisters introduces a new set of design and operational challenges: All of the hardware installed in the canisters must maintain structural integrity at elevated (molten-glass) temperatures. This suggests that a robust design is needed. However, the amount of material added to the DWPF canister must be minimized to prevent premature glass cooling and excessive voiding caused by a large internal thermal mass. High metal temperatures, minimizing thermal mass, and glass flow paths are examples of the types of technical considerations of the equipment design process. To determine the effectiveness of the design in terms of structural integrity and glass-flow characteristics, full-scale testing will be conducted. A cold (nonradioactive) pour test program is planned to assist in the development and verification of a baseline design for the immobilization canister to be used in the PIP process. The baseline design resulting from the cold pour test program and CIC equipment development program will provide input to Title 1 design for second-stage immobilization. The cold pour tests will be conducted in two

Evaluation of a Secure Laptop-Based Testing Program in an Undergraduate Nursing Program: Students' Perspective.

Science.gov (United States)

Tao, Jinyuan; Gunter, Glenda; Tsai, Ming-Hsiu; Lim, Dan

2016-01-01

Recently, the many robust learning management systems, and the availability of affordable laptops, have made secure laptop-based testing a reality on many campuses. The undergraduate nursing program at the authors' university began to implement a secure laptop-based testing program in 2009, which allowed students to use their newly purchased laptops to take quizzes and tests securely in classrooms. After nearly 5 years' secure laptop-based testing program implementation, a formative evaluation, using a mixed method that has both descriptive and correlational data elements, was conducted to seek constructive feedback from students to improve the program. Evaluation data show that, overall, students (n = 166) believed the secure laptop-based testing program helps them get hands-on experience of taking examinations on the computer and gets them prepared for their computerized NCLEX-RN. Students, however, had a lot of concerns about laptop glitches and campus wireless network glitches they experienced during testing. At the same time, NCLEX-RN first-time passing rate data were analyzed using the χ2 test, and revealed no significant association between the two testing methods (paper-and-pencil testing and the secure laptop-based testing) and students' first-time NCLEX-RN passing rate. Based on the odds ratio, however, the odds of students passing NCLEX-RN the first time was 1.37 times higher if they were taught with the secure laptop-based testing method than if taught with the traditional paper-and-pencil testing method in nursing school. It was recommended to the institution that better quality of laptops needs to be provided to future students, measures needed to be taken to further stabilize the campus wireless Internet network, and there was a need to reevaluate the Laptop Initiative Program.

Test results of Nb3Sn ribbons for the Princeton D coil test program

International Nuclear Information System (INIS)

Kaugerts, J.; File, J.; Willard, J.W.

1974-10-01

A previously described D coil test program was modified. Details of a smaller Nb 3 Sn D coil test program are described. Cusp coil tests were made with several Nb 3 Sn composite ribbons. Measurements of both the quench and recovery currents as a function of magnetic field component perpendicular to the wide edge of the ribbon are presented. (auth)

The MuCool Test Area and RF Program

International Nuclear Information System (INIS)

Torun, Y.; Huang, D.; Norem, J.; Palmer, Robert B.; Stratakis, Diktys; Bross, A.; Chung, M.; Jansson, A.; Moretti, A.; Yonehara, K.; Li, D.

2010-01-01

The MuCool RF Program focuses on the study of normal conducting RF structures operating in high magnetic field for applications in muon ionization cooling for Neutrino Factories and Muon Colliders. Here we give an overview of the program, which includes a description of the test facility and its capabilities, the current test program, and the status of a cavity that can be rotated in the magnetic field, which allows for a detailed study of the maximum stable operating gradient vs. magnetic field strength and angle.

Testing Object-Oriented Programs using Dynamic Aspects and Non-Determinism

DEFF Research Database (Denmark)

Achenbach, Michael; Ostermann, Klaus

2010-01-01

decisions exposing private data. We present an approach that both improves the expressiveness of test cases using non-deterministic choice and reduces design modifications using dynamic aspect-oriented programming techniques. Non-deterministic choice facilitates local definitions of multiple executions...... without parameterization or generation of tests. It also eases modelling naturally non-deterministic program features like IO or multi-threading in integration tests. Dynamic AOP facilitates powerful design adaptations without exposing test features, keeping the scope of these adaptations local to each...... test. We also combine non-determinism and dynamic aspects in a new approach to testing multi-threaded programs using co-routines....

Simultaneous test construction by zero-one programming

NARCIS (Netherlands)

Boekkooi-Timminga, Ellen

1986-01-01

A method is described for simultaneous test construction using the Operations Research technique zero-one programming. The model for zero-one programming consists of two parts. The first contains the objective function that describes the aspect to be optimized. The second part contains the

Oil spill sorbents: Testing protocol and certification listing program

International Nuclear Information System (INIS)

Cooper, D.; Gausemel, I.

1993-01-01

Environment Canada's Emergencies Engineering Division is spearheading a program in conjunction with the Canadian General Standards Board that would see the development of a certification and listing program in addition to a national standard for the testing of sorbent materials. Funding for this program is provided by Environment Canada (EC), Canadian Coast Guard (CCG), Marine Spill Response Corporation (MSRC), US Coast Guard (USCG), and US Minerals Management Service (MMS). The test methods are based upon those defined by the American Society for Testing and Materials and previous test methods developed by Environment Canada for our series of reports entitled Selection Criteria and Laboratory Evaluation of Oil Spill Sorbents. This series, which was started in 1975, encompasses a number of commercially available oil spill sorbents tested with different petroleum products and hydrocarbon solvents. The testing program will categorize the sorbents according to their operating characteristics. The main categories are oil spills on water, oil spills on land, and industrial use. The characteristics to be evaluated with the new test protocols include initial and maximum sorption capacities, water pickup, buoyancy, reuse potential, retention profile, disintegration (material integrity), and ease of application and retrieval. In the near future are plans to incorporate changes to the test that would involve increasing the list of test liquids to encompass spills in an industrial setting, in addition to testing sorbent booms and addressing the disposal problem

NedWind 25 Blade Testing at NREL for the European Standards Measurement and Testing Program

Energy Technology Data Exchange (ETDEWEB)

Larwood, S.; Musial, W.; Freebury, G.; Beattie, A.G.

2001-04-19

In the mid-90s the European community initiated the Standards, Measurements, and Testing (SMT) program to harmonize testing and measurement procedures in several industries. Within the program, a project was carried out called the European Wind Turbine Testing Procedure Development. The second part of that project, called Blade Test Methods and Techniques, included the United States and was devised to help blade-testing laboratories harmonize their testing methods. This report provides the results of those tests conducted by the National Renewable Energy Laboratory.

10 CFR 709.2 - Definitions.

Science.gov (United States)

2010-01-01

... or communications security programs. Counterintelligence evaluation or CI evaluation means the... questions relating to espionage, sabotage, terrorism, unauthorized disclosure of classified information...

Framework for a National Testing and Evaluation Program ...

Science.gov (United States)

Abstract:The National STEPP Program seeks to improve water quality by accelerating the effective implementation and adoption of innovative stormwater management technologies. Itwill attempt to accomplish this by establishing practices through highly reliable, and cost-effective Stormwater control measures (SCM) testing, evaluation, and verification services. The program will aim to remove barriers to innovation, minimize duplicative performance evaluation needs, increase confidence that regulatory requirements are met by creating consistency among testing and evaluation protocols, and establishing equity between public domain and proprietary SCM evaluation approaches.The Environmental Technology Verification Program, established by the U.S. Environmental Protection Agency (EPA) 18 years ago, was the only national program of its kindin the stormwater sector, but is now defunct, leaving a national leadership void. The STEPP initiative was triggered in part by regulatory demands in the government and private sectors to fill this vacuum. A concerted focus and study of this matter led to the release of a Water Environment Federation (WEF) white paper entitled “Investigation into the Feasibility of a National Testing and Evaluation Program for Stormwater Products and Practices” in February 2014. During this second phase of the STEPP initiative, and with EPA support, five analogous technology evaluation programs related to both stormwater and non-stormwater were an

Tritium systems test assembly quality assurance program

International Nuclear Information System (INIS)

Kerstiens, F.L.; Wilhelm, R.C.

1986-07-01

A quality assurance program should establish the planned and systematic actions necessary to provide adequate confidence that fusion facilities and their subsystems will perform satisfactorily in service. The Tritium Systems Test Assembly (TSTA) Quality Assurance Program has been designed to assure that the designs, tests, data, and interpretive reports developed at TSTA are valid, accurate, and consistent with formally specified procedures and reviews. The quality consideration in all TSTA activities is directed toward the early detection of quality problems, coupled with timely and positive disposition and corrective action

The Yucca Mountain Project Prototype Testing Program

International Nuclear Information System (INIS)

1989-10-01

The Yucca Mountain Project is conducting a Prototype Testing Program to ensure that the Exploratory Shaft Facility (ESF) tests can be completed in the time available and to develop instruments, equipment, and procedures so the ESF tests can collect reliable and representative site characterization data. This report summarizes the prototype tests and their status and location and emphasizes prototype ESF and surface tests, which are required in the early stages of the ESF site characterization tests. 14 figs

Material testing facilities and programs for plasma-facing component testing

Science.gov (United States)

Linsmeier, Ch.; Unterberg, B.; Coenen, J. W.; Doerner, R. P.; Greuner, H.; Kreter, A.; Linke, J.; Maier, H.

2017-09-01

Component development for operation in a large-scale fusion device requires thorough testing and qualification for the intended operational conditions. In particular environments are necessary which are comparable to the real operation conditions, allowing at the same time for in situ/in vacuo diagnostics and flexible operation, even beyond design limits during the testing. Various electron and neutral particle devices provide the capabilities for high heat load tests, suited for material samples and components from lab-scale dimensions up to full-size parts, containing toxic materials like beryllium, and being activated by neutron irradiation. To simulate the conditions specific to a fusion plasma both at the first wall and in the divertor of fusion devices, linear plasma devices allow for a test of erosion and hydrogen isotope recycling behavior under well-defined and controlled conditions. Finally, the complex conditions in a fusion device (including the effects caused by magnetic fields) are exploited for component and material tests by exposing test mock-ups or material samples to a fusion plasma by manipulator systems. They allow for easy exchange of test pieces in a tokamak or stellarator device, without opening the vessel. Such a chain of test devices and qualification procedures is required for the development of plasma-facing components which then can be successfully operated in future fusion power devices. The various available as well as newly planned devices and test stands, together with their specific capabilities, are presented in this manuscript. Results from experimental programs on test facilities illustrate their significance for the qualification of plasma-facing materials and components. An extended set of references provides access to the current status of material and component testing capabilities in the international fusion programs.

PBF/LOFT Lead Rod Test Program experiment predictions document

International Nuclear Information System (INIS)

Varacalle, D.J.; Cox, W.R.; Niebruegge, D.A.; Seiber, S.J.; Brake, T.E.; Driskell, W.E.; Nigg, D.W.; Tolman, E.L.

1978-12-01

The PBF/LOFT Lead Rod (LLR) Test Program is being conducted to provide experimental information on the behavior of nuclear fuel under normal and accident conditions in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory. The PBF/LLR tests are designed to simulate the test conditions for the LOFT Power Ascension Tests L2-3 through L2-5. The test program has been designed to provide a parametric evaluation of the LOFT fuel (center and peripheral modules) over a wide range of power. This report presents the experiment predictions for the three four-rod LOCA tests

SPSS and SAS programming for the testing of mediation models.

Science.gov (United States)

Dudley, William N; Benuzillo, Jose G; Carrico, Mineh S

2004-01-01

Mediation modeling can explain the nature of the relation among three or more variables. In addition, it can be used to show how a variable mediates the relation between levels of intervention and outcome. The Sobel test, developed in 1990, provides a statistical method for determining the influence of a mediator on an intervention or outcome. Although interactive Web-based and stand-alone methods exist for computing the Sobel test, SPSS and SAS programs that automatically run the required regression analyses and computations increase the accessibility of mediation modeling to nursing researchers. To illustrate the utility of the Sobel test and to make this programming available to the Nursing Research audience in both SAS and SPSS. The history, logic, and technical aspects of mediation testing are introduced. The syntax files sobel.sps and sobel.sas, created to automate the computation of the regression analysis and test statistic, are available from the corresponding author. The reported programming allows the user to complete mediation testing with the user's own data in a single-step fashion. A technical manual included with the programming provides instruction on program use and interpretation of the output. Mediation modeling is a useful tool for describing the relation between three or more variables. Programming and manuals for using this model are made available.

Status of CCTF test program

International Nuclear Information System (INIS)

Murao, Y.; Iguchi, T.; Sugimoto, J.; Akimoto, H.; Okubo, T.; Okabe, K.

1984-01-01

The cylindrical core test facility (CCTF) is one of the facilities of the large scale reflood test program which was initiated in April, 1976. The first series of the CCTF test (CCTF CORE I Test) was completed in April, 1981 and the second series (CCTF Core II Test) has been conducted since April, 1982. In the test, the following has been intended to be examined: (1) The conservativeness of the assumption of the safety analysis with the evaluation model (EM) code. (2) The refill and reflood phenomena for analytical modeling of thermo-hydrodynamics in the core and the system. (3) The validity of the models in the EM code and the application to the best estimate code development. In this paper, presented are the quantative evaluation of the REFLA code and the discussion of some CCTF Core II Test results. The REFLA code consists of REFLA-1D core code developed with the results of small scale tests and a simple system model developed with the results of the CCTF Core I Test. The CCTF Core II Test was perfored for developing more realistic model for the alternative ECCS as well as for the cold leg injection type ECCS

19 CFR 101.9 - Test programs or procedures; alternate requirements.

Science.gov (United States)

2010-04-01

... basis for selecting participants. (b) NCAP testing. For purposes of conducting an approved test program or procedure designed to evaluate planned components of the National Customs Automation Program (NCAP... publication requirement. For tests affecting the NCAP, notice shall be published in the Federal Register not...

The high level vibration test program

International Nuclear Information System (INIS)

Hofmayer, C.H.; Curreri, J.R.; Park, Y.J.; Kato, W.Y.; Kawakami, S.

1989-01-01

As part of cooperative agreements between the US and Japan, tests have been performed on the seismic vibration table at the Tadotsu Engineering Laboratory of Nuclear Power Engineering Test Center (NUPEC) in Japan. The objective of the test program was to use the NUPEC vibration table to drive large diameter nuclear power piping to substantial plastic strain with an earthquake excitation and to compare the results with state-of-the-art analysis of the problem. The test model was subjected to a maximum acceleration well beyond what nuclear power plants are designed to withstand. A modified earthquake excitation was applied and the excitation level was increased carefully to minimize the cumulative fatigue damage due to the intermediate level excitations. Since the piping was pressurized, and the high level earthquake excitation was repeated several times, it was possible to investigate the effects of ratchetting and fatigue as well. Elastic and inelastic seismic response behavior of the test model was measured in a number of test runs with an increasing excitation input level up to the limit of the vibration table. In the maximum input condition, large dynamic plastic strains were obtained in the piping. Crack initiation was detected following the second maximum excitation run. Crack growth was carefully monitored during the next two additional maximum excitation runs. The final test resulted in a maximum crack depth of approximately 94% of the wall thickness. The HLVT (high level vibration test) program has enhanced understanding of the behavior of piping systems under severe earthquake loading. As in other tests to failure of piping components, it has demonstrated significant seismic margin in nuclear power plant piping

KNK I Test Program, Final Report Part 1

International Nuclear Information System (INIS)

Kathol, W.

1976-01-01

The compact sodium cooled nuclear reactor KNK I of the Karlsruhe Research Center reached full power for the first time in February 1974. The goal of KNK I is to collect experience for the construction and operation of larger reactors, such as SNR 300. In order to deepen these experiences, a test program was drawn up and conducted from 1973 until 1975 within the framework of R and D work on the development of fast breeder reactors. The program included individual tasks concerning reactor design, safety instrumentation, irradiation and post-examination as well as behavior of components during operation. The performance of the tests was essentially governed by the licensing procedure imposed under the atomic energy act for the construction and operation of nuclear facilities. This report is the first part of the final report of the test program

Material control and accounting self-test program design

International Nuclear Information System (INIS)

Eggers, R.F.; Wilson, R.L.; Byers, K.R.

1981-01-01

This paper describes a controversial but potentially beneficial MCandA strategy that has not been widely attempted in the past, called Self-Test. In this strategy a processor of Strategic Special Nuclear Material (SSNM) devises a program of internally administered tests to determine if the MCandA system performs in a reliable, expedient manner in the face of a simulated loss or compromise. Self-Test procedures would include, for example, the actual removal of SSNM from process equipment in order to determine whether the MCandA system will detect the simulated theft. Self-Test programs have several potential problems. However, an approach with the potential for solving many of these problems has been devised and is discussed

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

Science.gov (United States)

2010-09-27

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

Means-Tested Public Assistance Programs and Adolescent Political Socialization.

Science.gov (United States)

Barnes, Carolyn Y; Hope, Elan C

2017-07-01

In recent years, scholars have pointed to the politically demobilizing effects of means-tested assistance programs on recipients. In this study, we bridge the insights from policy feedback literature and adolescent political socialization research to examine how receiving means-tested programs shapes parent influence on adolescent political participation. We argue that there are differences in pathways to political participation through parent political socialization and youth internal efficacy beliefs for adolescents from households that do or do not receive means-tested assistance. Using data from a nationally representative sample of 536 Black, Latino, and White adolescents (50.8% female), we find that adolescents from means-tested assistance households report less parent political socialization and political participation. For all youth, parent political socialization predicts adolescent political participation. Internal political efficacy is a stronger predictor of political participation for youth from a non-means-tested assistance household than it is for youth from a household receiving means-tested assistance. These findings provide some evidence of differential paths to youth political participation via exposure to means-tested programs.

Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users’ Manual

Energy Technology Data Exchange (ETDEWEB)

Dr. Bradley J Schrader

2009-03-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

Radiological Safety Analysis Computer (RSAC) Program Version 7.2 Users’ Manual

Energy Technology Data Exchange (ETDEWEB)

Dr. Bradley J Schrader

2010-10-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.2 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users Manual

International Nuclear Information System (INIS)

Schrader, Bradley J.

2009-01-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods

LWR aerosol containment experiments (LACE) program and initial test results

International Nuclear Information System (INIS)

Muhlestein, L.D.; Hilliard, R.K.; Bloom, G.R.; McCormack, J.D.; Rahn, F.J.

1985-01-01

The LWR aerosol containment experiments (LACE) program is described. The LACE program is being performed at the Hanford Engineer Development Laboratory (operated by Westinghouse Hanford Company) and the initial tests are sponsored by EPRI. The objectives of the LACE program are: to demonstrate, at large-scale, inherent radioactive aerosol retention behavior for postulated high consequence LWR accident situations; and to provide a data base to be used for aerosol behavior . Test results from the first phase of the LACE program are presented and discussed. Three large-scale scoping tests, simulating a containment bypass accident sequence, demonstrated the extent of agglomeration and deposition of aerosols occurring in the pipe pathway and vented auxiliary building under realistic accident conditions. Parameters varied during the scoping tests were aerosol type and steam condensation

The plane strain tests in the PROMETRA program

International Nuclear Information System (INIS)

Cazalis, B.; Desquines, J.; Carassou, S.; Le Jolu, T.; Bernaudat, C.

2016-01-01

A fuel cladding mechanical test, performed under conditions of plane strain deformation in the transverse direction of tube axis, was originally developed at Pennsylvania State University. It was decided to implement this original test within the PROMETRA program using the same experimental procedure and its optimization for a ring mechanical testing on plane strain conditions (PST tests) in hot cells laboratory. This paper presents a detailed description and an interpretation of the Plane Strain Tensile (PST) tests performed in the framework of the PROMETRA program on fresh and irradiated claddings. At first, the context of the PST tests is situated and the specificities of these tests implemented at CEA are justified. Indeed, a significant adjustment of the original experimental procedure is carried out in order to test the irradiated fuel cladding in the best possible conditions. Then, the tests results on fresh Zircaloy-4 and on irradiated Zircaloy-4, M5™ and ZIRLO ® specimens are gathered. The main analyses in support of these tests, such as metallographies, fractographic examinations and finite element simulations are detailed. Finally, a synthesis of the interpretation of the tests is proposed. The PST test seems only representative of plane strain fracture conditions when the test material is very ductile (fresh or high temperature or low hydride material like M5TM). However, it provides a relevant representation of the RIA rupture initiation which is observed in irradiated cladding resulting from hydride rim damage due to the strong irradiation of a fuel rod. - Highlights: • A plane strain mechanical test performed on fuel rod claddings is described. • The tests are performed in the framework of the French PROMETRA program. • Fresh Zircaloy-4 and irradiated Zircaloy-4, M5 and ZIRLO specimens are tested. • The main analyses in support of these tests are detailed. • A synthesis of the interpretation of the PST tests is proposed.

The plane strain tests in the PROMETRA program

Energy Technology Data Exchange (ETDEWEB)

Cazalis, B., E-mail: bernard.cazalis@irsn.fr [Institut de Radioprotection et de Sûreté Nucléaire, IRSN/PSN-RES, F-13115 Saint-Paul Lez Durance BP3 (France); Desquines, J. [Institut de Radioprotection et de Sûreté Nucléaire, IRSN/PSN-RES, F-13115 Saint-Paul Lez Durance BP3 (France); Carassou, S.; Le Jolu, T. [Commissariat à l' Energie Atomique, CEA/DEN/DMN, F- 91191 Gif-sur-Yvette (France); Bernaudat, C. [Electricité de France, EDF/SEPTEN, F-69628 Villeurbanne (France)

2016-04-15

A fuel cladding mechanical test, performed under conditions of plane strain deformation in the transverse direction of tube axis, was originally developed at Pennsylvania State University. It was decided to implement this original test within the PROMETRA program using the same experimental procedure and its optimization for a ring mechanical testing on plane strain conditions (PST tests) in hot cells laboratory. This paper presents a detailed description and an interpretation of the Plane Strain Tensile (PST) tests performed in the framework of the PROMETRA program on fresh and irradiated claddings. At first, the context of the PST tests is situated and the specificities of these tests implemented at CEA are justified. Indeed, a significant adjustment of the original experimental procedure is carried out in order to test the irradiated fuel cladding in the best possible conditions. Then, the tests results on fresh Zircaloy-4 and on irradiated Zircaloy-4, M5™ and ZIRLO{sup ®} specimens are gathered. The main analyses in support of these tests, such as metallographies, fractographic examinations and finite element simulations are detailed. Finally, a synthesis of the interpretation of the tests is proposed. The PST test seems only representative of plane strain fracture conditions when the test material is very ductile (fresh or high temperature or low hydride material like M5TM). However, it provides a relevant representation of the RIA rupture initiation which is observed in irradiated cladding resulting from hydride rim damage due to the strong irradiation of a fuel rod. - Highlights: • A plane strain mechanical test performed on fuel rod claddings is described. • The tests are performed in the framework of the French PROMETRA program. • Fresh Zircaloy-4 and irradiated Zircaloy-4, M5 and ZIRLO specimens are tested. • The main analyses in support of these tests are detailed. • A synthesis of the interpretation of the PST tests is proposed.

EBR-2 [Experimental Breeder Reactor-2] test programs

International Nuclear Information System (INIS)

Sackett, J.I.; Lehto, W.K.; Lindsay, R.W.; Planchon, H.P.; Lambert, J.D.B.; Hill, D.J.

1990-01-01

The Experimental Breeder Reactor-2 (EBR-2) is a sodium cooled power reactor supplying about 20 MWe to the Idaho National Engineering Laboratory (INEL) grid and, in addition, is the key component in the development of the Integral Fast Reactor (IFR). EBR-2's testing capability is extensive and has seen four major phases: (1) demonstration of LMFBR power plant feasibility, (2) irradiation testing for fuel and material development, (3) testing the off-normal performance of fuel and plant systems and (4) operation as the IFR prototype, developing and demonstrating the IFR technology associated with fuel and plant design. Specific programs being carried out in support of the IFR include advanced fuels and materials development, advanced control system development, plant diagnostics development and component testing. This paper discusses EBR-2 as the IFR prototype and the associated testing programs. 29 refs

WIPP R and D in situ test program

International Nuclear Information System (INIS)

Tyler, L.D.

1987-01-01

The Waste Isolation Pilot Plant (WIPP) is a Department of Energy (DOE) RandD Facility for the purpose of developing the technology needed for the safe disposal of the United States' defense-related radioactive waste. The in situ test program focus is to provide the models and data to demonstrate the facility performance for isolation of waste at WIPP. The program is defined for the WIPP sealing system, thermal-structural interactions and waste package performance. A number of integrated large-scale underground tests have been operational since 1983 and are ongoing. The tests address the issues of both systems design and long-term isolation performance of the WIPP repository

Cooperative field test program for wind systems. Final report

Energy Technology Data Exchange (ETDEWEB)

Bollmeier, W.S. II; Dodge, D.M.

1992-03-01

The objectives of the Federal Wind Energy Program, managed by the US Department of Energy (DOE), are (1) to assist industry and utilities in achieving a multi-regional US market penetration of wind systems, and (2) to establish the United States as the world leader in the development of advanced wind turbine technology. In 1984, the program conducted a series of planning workshops with representatives from the wind energy industry to obtain input on the Five-Year Research Plan then being prepared by DOE. One specific suggestion that came out of these meetings was that the federal program should conduct cooperative research tests with industry to enhance the technology transfer process. It was also felt that the active involvement of industry in DOE-funded research would improve the state of the art of wind turbine technology. DOE established the Cooperative Field Test Program (CFTP) in response to that suggestion. This program was one of the first in DOE to feature joint industry-government research test teams working toward common objectives.

Large-Scale Seismic Test Program at Hualien, Taiwan

International Nuclear Information System (INIS)

Tang, H.T.; Graves, H.L.; Yeh, Y.S.

1991-01-01

The Large-Scale Seismic Test (LSST) Program at Hualien, Taiwan, is a follow-on to the soil-structure interaction (SSI) experiments at Lotung, Taiwan. The planned SSI studies will be performed at a stiff soil site in Hualien, Taiwan, that historically has had slightly more destructive earthquakes in the past than Lotung. The objectives of the LSST project is as follows: To obtain earthquake-induced SSI data at a stiff soil site having similar prototypical nuclear power plant soil conditions. To confirm the findings and methodologies validated against the Lotung soft soil SSI data for prototypical plant condition applications. To further validate the technical basis of realistic SSI analysis approaches. To further support the resolution of USI A-40 Seismic Design Criteria issue. These objectives will be accomplished through an integrated and carefully planned experimental program consisting of: soil characterization, test model design and field construction, instrumentation layout and deployment, in-situ geophysical information collection, forced vibration test, and synthesis of results and findings. The LSST is a joint effort among many interested parties. EPRI and Taipower are the organizers of the program and have the lead in planning and managing the program

Spillover effects of HIV testing policies: changes in HIV testing guidelines and HCV testing practices in drug treatment programs in the United States

Directory of Open Access Journals (Sweden)

Jemima A. Frimpong

2016-07-01

Full Text Available Abstract Background To examine the extent to which state adoption of the Centers for Disease Control and Prevention (CDC 2006 revisions to adult and adolescent HIV testing guidelines is associated with availability of other important prevention and medical services. We hypothesized that in states where the pretest counseling requirement for HIV testing was dropped from state legislation, substance use disorder treatment programs would have higher availability of HCV testing services than in states that had maintained this requirement. Methods We analyzed a nationally representative sample of 383 opioid treatment programs from the 2005 and 2011 National Drug Abuse Treatment System Survey (NDATSS. Data were collected from program directors and clinical supervisors through telephone surveys. Multivariate logistic regression models were used to measure associations between state adoption of CDC recommended guidelines for HIV pretest counseling and availability of HCV testing services. Results The effects of HIV testing legislative changes on HCV testing practices varied by type of opioid treatment program. In states that had removed the requirement for HIV pretest counseling, buprenorphine-only programs were more likely to offer HCV testing to their patients. The positive spillover effect of HIV pretest counseling policies, however, did not extend to methadone programs and did not translate into increased availability of on-site HCV testing in either program type. Conclusions Our findings highlight potential positive spillover effects of HIV testing policies on HCV testing practices. They also suggest that maximizing the benefits of HIV policies may require other initiatives, including resources and programmatic efforts that support systematic integration with other services and effective implementation.

47 CFR 73.1620 - Program tests.

Science.gov (United States)

2010-10-01

... integration of ownership and management and diversification of the media of mass communciation contained in... 47 Telecommunication 4 2010-10-01 2010-10-01 false Program tests. 73.1620 Section 73.1620 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) BROADCAST RADIO SERVICES RADIO BROADCAST SERVICES...

Advanced Utility Mercury-Sorbent Field-Testing Program

Energy Technology Data Exchange (ETDEWEB)

Ronald Landreth

2007-12-31

This report summarizes the work conducted from September 1, 2003 through December 31, 2007 on the project entitled Advanced Utility Mercury-Sorbent Field-Testing Program. The project covers the testing at the Detroit Edison St. Clair Plant and the Duke Power Cliffside and Buck Stations. The St. Clair Plant used a blend of subbituminous and bituminous coal and controlled the particulate emissions by means of a cold-side ESP. The Duke Power Stations used bituminous coals and controlled their particulate emissions by means of hot-side ESPs. The testing at the Detroit Edison St. Clair Plant demonstrated that mercury sorbents could be used to achieve high mercury removal rates with low injection rates at facilities that burn subbituminous coal. A mercury removal rate of 94% was achieved at an injection rate of 3 lb/MMacf over the thirty day long-term test. Prior to this test, it was believed that the mercury in flue gas of this type would be the most difficult to capture. This is not the case. The testing at the two Duke Power Stations proved that carbon- based mercury sorbents can be used to control the mercury emissions from boilers with hot-side ESPs. It was known that plain PACs did not have any mercury capacity at elevated temperatures but that brominated B-PAC did. The mercury removal rate varies with the operation but it appears that mercury removal rates equal to or greater than 50% are achievable in facilities equipped with hot-side ESPs. As part of the program, both sorbent injection equipment and sorbent production equipment was acquired and operated. This equipment performed very well during this program. In addition, mercury instruments were acquired for this program. These instruments worked well in the flue gas at the St. Clair Plant but not as well in the flue gas at the Duke Power Stations. It is believed that the difference in the amount of oxidized mercury, more at Duke Power, was the difference in instrument performance. Much of the equipment was

Nevada Test Site Radiation Protection Program

Energy Technology Data Exchange (ETDEWEB)

Radiological Control Managers' Council, Nevada Test Site

2007-08-09

Title 10 Code of Federal Regulations (CFR) 835, 'Occupational Radiation Protection', establishes radiation protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of U.S. Department of Energy (DOE) activities. 10 CFR 835.101(a) mandates that DOE activities be conducted in compliance with a documented Radiation Protection Program (RPP) as approved by DOE. This document promulgates the RPP for the Nevada Test Site (NTS), related (onsite or offsite) DOE National Nuclear Security Administration Nevada Site Office (NNSA/NSO) operations, and environmental restoration offsite projects.

Program Helps Design Tests Of Developmental Software

Science.gov (United States)

Hops, Jonathan

1994-01-01

Computer program called "A Formal Test Representation Language and Tool for Functional Test Designs" (TRL) provides automatic software tool and formal language used to implement category-partition method and produce specification of test cases in testing phase of development of software. Category-partition method useful in defining input, outputs, and purpose of test-design phase of development and combines benefits of choosing normal cases having error-exposing properties. Traceability maintained quite easily by creating test design for each objective in test plan. Effort to transform test cases into procedures simplified by use of automatic software tool to create cases based on test design. Method enables rapid elimination of undesired test cases from consideration and facilitates review of test designs by peer groups. Written in C language.

Quality assurance in the nuclear test program

International Nuclear Information System (INIS)

Shearer, J.N.

1979-01-01

In February 1979 Test Program laid the ground work for a new quality assurance structure. The new approach was based on the findings and recommendations of the Ad Hoc QA Program Review panel, which are summarized in this report. The new structure places the responsibility for quality assurance in the hands of the line organizations, both in the programmatic and functional elements of the LLL matrix

75 FR 22809 - Mandatory Guidelines for Federal Workplace Drug Testing Programs

Science.gov (United States)

2010-04-30

... time for related training in Federal and federally-regulated workplace drug testing programs and will... related training in Federal and federally-regulated workplace drug testing programs, including HHS... DEPARTMENT OF HEALTH AND HUMAN SERVICES Mandatory Guidelines for Federal Workplace Drug Testing...

Adaptive Test Selection for Factorization-based Surrogate Fitness in Genetic Programming

Directory of Open Access Journals (Sweden)

Krawiec Krzysztof

2017-12-01

Full Text Available Genetic programming (GP is a variant of evolutionary algorithm where the entities undergoing simulated evolution are computer programs. A fitness function in GP is usually based on a set of tests, each of which defines the desired output a correct program should return for an exemplary input. The outcomes of interactions between programs and tests in GP can be represented as an interaction matrix, with rows corresponding to programs in the current population and columns corresponding to tests. In previous work, we proposed SFIMX, a method that performs only a fraction of interactions and employs non-negative matrix factorization to estimate the outcomes of remaining ones, shortening GP’s runtime. In this paper, we build upon that work and propose three extensions of SFIMX, in which the subset of tests drawn to perform interactions is selected with respect to test difficulty. The conducted experiment indicates that the proposed extensions surpass the original SFIMX on a suite of discrete GP benchmarks.

Minimum Leakage Condenser Test Program

International Nuclear Information System (INIS)

1978-05-01

This report presents the results and analysis of tests performed on four critical areas of large surface condensers: the tubes, tubesheets, tube/tubesheet joints and the water chambers. Significant changes in operation, service duty and the reliability considerations require that certain existing design criteria be verified and that improved design features be developed. The four critical areas were treated analytically and experimentally. The ANSYS finite element computer program was the basic analytical method and strain gages were used for obtaining experimental data. The results of test and analytical data are compared and recommendations made regarding potential improvement in condenser design features and analytical techniques

The importance of pre-planning for large hydrostatic test programs

Energy Technology Data Exchange (ETDEWEB)

Bennett, Andrew Keith [WorleyParsons Calgary, Calgary, AB (Canada); Wong, Everett Clementi [Enbridge Pipelines Inc., Edmonton, AB (Canada)

2010-07-01

During the design phase of a pipeline project, large hydrostatic test programs are required to locate and secure water sources. Many companies complete hydrostatic test planning through high level desktop analysis, however this technique can result in important unplanned costs and schedule delays. The aim of this paper is to assess the cost benefits of pre-planning large hydrostatic test programs versus the costs of unplanned delays in the execution of hydrostatic testing. This comparison was based on the successful application of pre-planning of 57 mainline hydrostatic tests in the construction of the Line 4 Extension and Alberta Clipper Expansion oil pipelines by Enbridge Pipelines Inc. Results showed that costs of delays and uncertainty during construction far outweigh the costs of pre-planning. This study highlighted that pre-planning for large hydrostatic test programs should be carried out in the execution of large pipeline projects to ensure success.

History of ground motion programs at the Nevada Test Site

International Nuclear Information System (INIS)

Banister, J.R.

1984-01-01

Some measurements were made in the atmospheric testing era, but the study of ground motion from nuclear tests became of wider interest after the instigation of underground testing. The ground motion generated by underground nuclear test has been investigated for a number of reasons including understanding basic phenomena, operational and safety concerns, yield determination, stimulation of earthquake concerns, and developing methods to aid in treaty verifications. This history of ground motion programs will include discussing early studies, high yield programs, Peaceful Nuclear Explosions tests, and some more recent developments. 6 references, 10 figures

Environmental test program for superconducting materials and devices

Science.gov (United States)

Haertling, Gene; Randolph, Henry; Hsi, Chi-Shiung; Verbelyi, Darren

1991-01-01

This report is divided into two parts. The first dealing with work involved with Clemson University and the second with the results from Westinghouse/Savannah River. Both areas of work involved low noise, low thermal conductivity superconducting grounding links used in the NASA-sponsored Spectroscopy of the Atmosphere using Far Infrared Emission (SAFIRE) Project. Clemson prepared the links from YBa2Cu3O(7-x) superconductor tape that was mounted on a printed circuit board and encapsulated with epoxy resin. The Clemson program includes temperature vs. resistance, liquid nitrogen immersion, water immersion, thermal cycling, humidity, and radiation testing. The evaluation of the links under a long term environmental test program is described. The Savannah River program includes gamma irradiation, vibration, and long-term evaluation. The progress made in these evaluations is discussed.

The joint EC/EPA mid-Connecticut test program

International Nuclear Information System (INIS)

Kilgroe, J.D.; Brna, T.G.

1991-01-01

In early 1989, Environment Canada and the U.S. Environmental Protection Agency sponsored a comprehensive test program on a refuse-derived fuel (RDF) unit of the Mid-Connecticut facility in Hartford. The program, conducted in cooperation with the Connecticut Resource Recovery Authority (CRRA), the facility's operator, included characterization and performance test phases. The results of the characterization tests were used in defining both the combustion and flue gas cleaning system operating conditions for the performance tests. The results of the performance tests are emphasized in this paper and are summarized in three parts. First, the combustion tests results will be addressed and related to good combustion practice for RDF combustors. Then, the performance of the lime spray dryer absorber/fabric filter system in controlling acid gas (hydrogen chloride, sulfur dioxide), trace organic [polychlorinated dibenzodioxin (PCDD) and polychlorinated dibenzofuran (PCDF)], trace metal [arsenic (as), cadmium (Cd), chromium (Cr), lead (Pb), mercury (Hg), nickel (Ni), and zinc (Zn)], and particulate matter (PM) emissions will be discussed. Finally, the results of ash/residue analyses will be presented

A compliance testing program for diagnostic X-ray equipment

International Nuclear Information System (INIS)

Hutchinson, D.E.; Cobb, B.J.; Jacob, C.S.

1999-01-01

Compliance testing is nominally that part of a quality assurance program dealing with those aspects of X-ray equipment performance that are subject to radiation control legislation. Quality assurance programs for medical X-ray equipment should be an integral part of the quality culture in health care. However while major hospitals and individual medical centers may implement such programs with some diligence, much X-ray equipment can remain unappraised unless there is a comprehensive regulatory inspection program or some form of compulsion on the equipment owner to implement a testing program. Since the late 1950s all X-ray equipment in the State of Western Australia has been inspected by authorized officers acting on behalf of the Radiological Council, the regulatory authority responsible for administration of the State's Radiation Safety Act. However, economic constraints, coupled with increasing X-ray equipment numbers and a geographically large State have significantly affected the inspection rate. Data available from inspections demonstrate that regular compliance and performance checks are essential in order to ensure proper performance and to minimize unnecessary patient and operator dose. To ensure that diagnostic X-ray equipment complies with accepted standards and performance criteria, the regulatory authority introduced a compulsory compliance testing program for all medical, dental and chiropractic diagnostic X-ray equipment effective from 1 January 1997

Training programs for the systems approach to nuclear security

International Nuclear Information System (INIS)

Ellis, D.

2005-01-01

Full text: In support of United States Government (USG) and International Atomic Energy Agency (IAEA) nuclear security programs, Sandia National Laboratories (SNL) has advocated and practiced a risk-based, systematic approach to nuclear security. The risk equation has been developed and implemented as the basis for a performance-based methodology for the design and evaluation of physical protection systems against a design basis threat (DBT) for theft and sabotage of nuclear and/or radiological materials. Integrated systems must include technology, people, and the man-machine interface. A critical aspect of the human element is training on the systems-approach for all the stakeholders in nuclear security. Current training courses and workshops have been very beneficial but are still rather limited in scope. SNL has developed two primary international classes - the international training course on the physical protection of nuclear facilities and materials, and the design basis threat methodology workshop. SNL is also completing the development of three new courses that will be offered and presented in the near term. They are vital area identification methodology focused on nuclear power plants to aid in their protection against radiological sabotage, insider threat analysis methodology and protection schemes, and security foundations for competent authority and facility operator stakeholders who are not security professionals. In the long term, we envision a comprehensive nuclear security curriculum that spans policy and technology, regulators and operators, introductory and expert levels, classroom and laboratory/field, and local and offsite training options. This training curriculum will be developed in concert with a nuclear security series of guidance documents that is expected to be forthcoming from the IAEA. It is important to note that while appropriate implementation of systems based on such training and documentation can improve the risk reduction, such a

How My Program Passed the Turing Test

Science.gov (United States)

Humphrys, Mark

In 1989, the author put an ELIZA-like chatbot on the Internet. The conversations this program had can be seen - depending on how one defines the rules (and how seriously one takes the idea of the test itself) - as a passing of the Turing Test. This is the first time this event has been properly written. This chatbot succeeded due to profanity, relentless aggression, prurient queries about the user, and implying that they were a liar when they responded. The element of surprise was also crucial. Most chatbots exist in an environment where people expectto find some bots among the humans. Not this one. What was also novel was the onlineelement. This was certainly one of the first AI programs online. It seems to have been the first (a) AI real-time chat program, which (b) had the element of surprise, and (c) was on the Internet. We conclude with some speculation that the future of all of AI is on the Internet, and a description of the "World- Wide-Mind" project that aims to bring this about.

Model-based automated testing of critical PLC programs.

CERN Document Server

Fernández Adiego, B; Tournier, J-C; González Suárez, V M; Bliudze, S

2014-01-01

Testing of critical PLC (Programmable Logic Controller) programs remains a challenging task for control system engineers as it can rarely be automated. This paper proposes a model based approach which uses the BIP (Behavior, Interactions and Priorities) framework to perform automated testing of PLC programs developed with the UNICOS (UNified Industrial COntrol System) framework. This paper defines the translation procedure and rules from UNICOS to BIP which can be fully automated in order to hide the complexity of the underlying model from the control engineers. The approach is illustrated and validated through the study of a water treatment process.

High Performance Computing Modernization Program Kerberos Throughput Test Report

Science.gov (United States)

2017-10-26

Naval Research Laboratory Washington, DC 20375-5320 NRL/MR/5524--17-9751 High Performance Computing Modernization Program Kerberos Throughput Test ...NUMBER 5d. PROJECT NUMBER 5e. TASK NUMBER 5f. WORK UNIT NUMBER 2. REPORT TYPE1. REPORT DATE (DD-MM-YYYY) 4. TITLE AND SUBTITLE 6. AUTHOR(S) 8. PERFORMING...PAGE 18. NUMBER OF PAGES 17. LIMITATION OF ABSTRACT High Performance Computing Modernization Program Kerberos Throughput Test Report Daniel G. Gdula* and

Testing the Structure of Hydrological Models using Genetic Programming

Science.gov (United States)

Selle, B.; Muttil, N.

2009-04-01

Genetic Programming is able to systematically explore many alternative model structures of different complexity from available input and response data. We hypothesised that genetic programming can be used to test the structure hydrological models and to identify dominant processes in hydrological systems. To test this, genetic programming was used to analyse a data set from a lysimeter experiment in southeastern Australia. The lysimeter experiment was conducted to quantify the deep percolation response under surface irrigated pasture to different soil types, water table depths and water ponding times during surface irrigation. Using genetic programming, a simple model of deep percolation was consistently evolved in multiple model runs. This simple and interpretable model confirmed the dominant process contributing to deep percolation represented in a conceptual model that was published earlier. Thus, this study shows that genetic programming can be used to evaluate the structure of hydrological models and to gain insight about the dominant processes in hydrological systems.

Preliminary irradiation test results from the Yankee Atomic Electric Company reactor vessel test irradiation program

International Nuclear Information System (INIS)

Biemiller, E.C.; Fyfitch, S.; Campbell, C.A.

1993-01-01

The Yankee Atomic Electric Company test irradiation program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials and to remove uncertainties in the analysis of existing irradiation data on the Yankee Rowe reactor vessel steel. Plate materials each containing 0.24 w/o copper, but different nickel contents at 0.63 w/o and 0.19 w/o, were heat treated to simulate the Yankee vessel heat treatment (austenitized at 1800 deg F) and to simulate Regulatory Guide 1.99 database materials (austenitized at 1600 deg. F). These heat treatments produced different microstructures so the effect of microstructure on irradiation damage sensitivity could be tested. Because the nickel content of the test plates varied and the copper level was constant, the effect of nickel on irradiation embrittlement was also tested. Correlation monitor material, HSST-02, was included in the program to benchmark the Ford Nuclear Reactor (U. of Michigan Test Reactor) which had never been used for this type of irradiation program. Materials taken from plate surface locations (vs. 1/4T) were included to test whether or not the improved toughness properties of the plate surface layer, resulting from the rapid quench, is maintained after irradiation. If the improved properties are maintained, pressurized thermal shock calculations could utilize this margin. Finally, for one experiment, irradiations were conducted at two irradiation temperatures (500 deg. F and 550 deg. F) to determine the effect of irradiation temperature on embrittlement. The preliminary results of the irradiation program show an increase in T 30 shift of 69 deg. F for a decrease in irradiation temperature of 50 deg. F. The results suggest that for nickel bearing steels, the superior toughness of plate surface material is maintained after irradiation and for the copper content tested, nickel had no apparent effect on irradiation response. No apparent microstructure

The High Level Vibration Test Program

International Nuclear Information System (INIS)

Hofmayer, C.H.; Curreri, J.R.; Park, Y.J.; Kato, W.Y.; Kawakami, S.

1989-01-01

As part of cooperative agreements between the United States and Japan, tests have been performed on the seismic vibration table at the Tadotsu Engineering Laboratory of Nuclear Power Engineering Test Center (NUPEC) in Japan. The objective of the test program was to use the NUPEC vibration table to drive large diameter nuclear power piping to substantial plastic strain with an earthquake excitation and to compare the results with state-of-the-art analysis of the problem. The test model was designed by modifying the 1/2.5 scale model of the PWR primary coolant loop. Elastic and inelastic seismic response behavior of the test model was measured in a number of test runs with an increasing excitation input level up to the limit of the vibration table. In the maximum input condition, large dynamic plastic strains were obtained in the piping. Crack initiation was detected following the second maximum excitation run. The test model was subjected to a maximum acceleration well beyond what nuclear power plants are designed to withstand. This paper describes the overall plan, input motion development, test procedure, test results and comparisons with pre-test analysis. 4 refs., 16 figs., 2 tabs

The High Level Vibration Test program

International Nuclear Information System (INIS)

Hofmayer, C.H.; Curreri, J.R.; Park, Y.J.; Kato, W.Y.; Kawakami, S.

1990-01-01

As part of cooperative agreements between the United States and Japan, tests have been performed on the seismic vibration table at the Tadotsu Engineering Laboratory of Nuclear Power Engineering Test Center (NUPEC) in Japan. The objective of the test program was to use the NUPEC vibration table to drive large diameter nuclear power piping to substantial plastic strain with an earthquake excitation and to compare the results with state-of-the-art analysis of the problem. The test model was designed by modifying the 1/2.5 scale model of the pressurized water reactor primary coolant loop. Elastic and inelastic seismic response behavior of the test model was measured in a number of test runs with an increasing excitation input level up to the limit of the vibration table. In the maximum input condition, large dynamic plastic strains were obtained in the piping. Crack initiation was detected following the second maximum excitation run. The test model was subjected to a maximum acceleration well beyond what nuclear power plants are designed to withstand. This paper describes the overall plan, input motion development, test procedure, test results and comparisons with pre-test analysis

Performance-based improvement of the leakage rate test program for the reactor containment of HTTR. Adoption of revised test programs containing 'Type A, Type B and Type C tests'

International Nuclear Information System (INIS)

Kondo, Masaaki; Emori, Koichi; Sekita, Kenji; Furusawa, Takayuki; Hayakawa, Masato; Kozawa, Takayuki; Aono, Tetsuya; Kuroha, Misao; Ouchi, Hiroshi; Kimishima, Satoru

2008-10-01

The reactor containment of HTTR is periodically tested to confirm leak-tight integrity by conducting overall integrated leakage rate tests, so-called 'Type A tests,' in accordance with a standard testing method provided in Japan Electric Association Code (JEAC) 4203. 'Type A test' is identified as a basic one for measuring whole leakage rates for reactor containments, it takes, however, much of cost and time of preparation, implementation and restoration of itself. Therefore, in order to upgrade the maintenance technology of HTTR, the containment leakage rate test program for HTTR was revised by adopting efficient and economical alternatives including Type B and Type C tests' which intend to measure leakage rates for containment penetrations and isolation valves, respectively. In JEAC4203-2004, following requirements are specified for adopting an alternative program: upward trend of the overall integrated leakage rate due to aging affection should not be recognized; performance criterion for combined leakage rate, that is a summation of local leakage rates evaluated by Type B and Type C tests and converted to whole leakage rates, should be established; the criterion of the combined leakage rate should be satisfied as well as of the overall integrated leakage rate; correlation between the overall integrated and combined leakage rates should be recognized. Considering the historical performances, policies of conforming to the forgoing requirements and of carrying out the revised test program were developed, which were accepted by the regulatory agency. This report presents an outline of the leakage rate tests for the reactor containment of HTTR, identifies practical issues of conventional Type A tests, and describes the conforming and implementing policies mentioned above. (author)

Safety Test Program Summary SNAP 19 Pioneer Heat Source Safety Program

Energy Technology Data Exchange (ETDEWEB)

None,

1971-07-01

Sixteen heat source assemblies have been tested in support of the SNAP 19 Pioneer Safety Test Program. Seven were subjected to simulated reentry heating in various plasma arc facilities followed by impact on earth or granite. Six assemblies were tested under abort accident conditions of overpressure, shrapnel impact, and solid and liquid propellant fires. Three capsules were hot impacted under Transit capsule impact conditions to verify comparability of test results between the two similar capsule designs, thus utilizing both Pioneer and Transit Safety Test results to support the Safety Analysis Report for Pioneer. The tests have shown the fuel is contained under all nominal accident environments with the exception of minor capsule cracks under severe impact and solid fire environments. No catastrophic capsule failures occurred in this test which would release large quantities of fuel. In no test was fuel visible to the eye following impact or fire. Breached capsules were defined as those which exhibit thoria contamination on its surface following a test, or one which exhibited visible cracks in the post test metallographic analyses.

Analysis of well ER-18-2 testing, Western Pahute Mesa - Oasis Valley FY 2000 testing program

Energy Technology Data Exchange (ETDEWEB)

None

2002-09-30

This report documents the analysis of the data collected for Well ER-18-2 during the Western Pahute Mesa - Oasis Valley (WPM-OV) well development and testing program that was conducted during fiscal year (FY) 2000. The data collection for that program is documented in Appendix A, Western Pahute Mesa - Oasis Valley, Well ER-18-2 Data Report for Development and Hydraulic Testing.

Analysis of Well ER-EC-7 Testing, Western Pahute Mesa - Oasis Valley FY 2000 Testing Program

Energy Technology Data Exchange (ETDEWEB)

None

2002-09-30

This report documents the analysis of the data collected for Well ER-EC-7 during the Western Pahute Mesa - Oasis Valley (WPM-OV) well development and testing program that was conducted during fiscal year (FY) 2000. The data collection for that program was documented in Appendix A, Western Pahute Mesa - Oasis Valley, Well ER-EC-7 Data Report for Development and Hydraulic Testing.

Analysis of Well ER-EC-8 testing, Western Pahute Mesa-Oasis Valley FY 2000 testing program

Energy Technology Data Exchange (ETDEWEB)

None

2002-09-30

This report documents the analysis of the data collected for Well ER-EC-8 during the Western Pahute Mesa - Oasis Valley (WPM-OV) well development and testing program that was conducted during fiscal year (FY) 2000. The data collection for that program is documented in Appendix A, Western Pahute Mesa-Oasis Valley, Well ER-EC-8 Data Report for development and Hydraulic Testing.

Analysis of Well ER-EC-4 Testing, Western Pahute Mesa-Oasis Valley FY 2000 Testing Program

Energy Technology Data Exchange (ETDEWEB)

None

2002-09-30

This report documents the analysis of the data collected for Well ER-EC-4 during the Western Pahute Mesa-Oasis Valley (WPM-OV) well development and testing program that was conducted during fiscal year (FY) 2000. The data collection for that program is documented in Appendix A, Western Pahute Mesa - Oasis Valley, Well ER-EC-4 Data Report for Development and Hydraulic Testing.

Analysis of Well ER-EC-5 Testing, Western Pahute Mesa-Oasis Valley FY 2000 Testing Program

Energy Technology Data Exchange (ETDEWEB)

None

2002-09-30

This report documents the analysis of the data collected for Well ER-EC-5 during the Western Pahute Mesa - Oasis Valley (WPM-OV) well development and testing program that was conducted during fiscal year (FY) 2000. The data collection for that program is documented in Appendix A, Western Pahute Mesa - Oasis Valley, Well ER-EC-5 Data Report for Development and Hydraulic Testing.

Analysis of Well ER-EC-6 Testing, Western Pahute Mesa - Oasis Valley FY 2000 Testing Program

Energy Technology Data Exchange (ETDEWEB)

None

2002-09-30

This report documents the analysis of the data collected for Well ER-EC-6 during the Western Pahute Mesa-Oasis Valley (WPM-OV) well development and testing program that was conducted during fiscal year (FY) 2000. The data collection for that program is documented in Appendix A, Western Pahute Mesa-Oasis Valley, Well ER-EC-6 Data Report for Development and Hydraulic Testing.

Analysis of Well ER-EC-1 Testing, Western Pahute Mesa-Oasis Valley FY 2000 Testing Program

Energy Technology Data Exchange (ETDEWEB)

None

2002-09-30

This report documents the analysis of the data collected for Well ER-EC-1 during the Western Pahute Mesa - Oasis Valley (WPM-OV) well development and testing program that was conducted during fiscal year (FY) 2000. The data collection for that program is documented in Appendix A, Western Pahute Mesa - Oasis Valley, Well ER-EC-1 Data Report for Development and Hydraulic Testing.

Development, implementation and management of a drug testing program in the workplace

Energy Technology Data Exchange (ETDEWEB)

Burtis, C.A.

1990-01-01

To combat the rising use of drugs in the workplace many American companies have implemented drug testing programs and are testing employees and job applicants for use of illegal drugs. In addition, on September 15, 1986, Executive Order No.12564 was issued by President Reagan, which requires all federal agencies to develop programs and policies, one of the goals of which is to achieve a drug-free federal workplace. Included in this Executive Order is the requirement that federal agencies implement drug testing has become a prevalent practice as a means to detect and deter drug use in the workplace. Before a drug testing program is implemented, it is imperative that policies and procedures are developed that (1) ensure the accuracy of test results, (2) protect the validity and integrity of the specimen, (3) guarantee due process, and (4) maintain confidentiality. To make certain that these prerequisites were met in the government drug testing programs, the US Department of Health and Human Services (HHS) was directed to develop technical and scientific guidelines for conducting such programs. 15 refs., 1 fig., 2 tabs.

Containment Leakage Rate Testing Program in NPP Krsko

International Nuclear Information System (INIS)

Dudas, M.; Heruc, Z.

2002-01-01

NPP Krsko adopted new regulations for testing of the reactor building containment as stipulated by 10CFR50 (Code of Federal Regulation) Appendix J, Option B instead of the previous requirement 10CFR50 Appendix J now renamed to 10CFR50 Appendix J, Option A. In the USA a thorough analyses of nuclear power plants reactor building containment testing was conducted. As part of these analyses the test results obtained from testing of various reactor-building containments in the last ten years were reviewed. It was concluded that it would be meaningful to, based on test results historical data, reconsider possibility of redefining testing intervals. The official proposal of such approach was reviewed and approved by the NRC and published in September of 1995 in the FR Vol.60 No.186. Based on directions from 10CFR50 Appendix J, Option B, the new criteria for definition of test intervals were created. Criteria were based upon past performance during testing (Performance-based Requirements) and safety impact. At NPP Krsko, the analyses of the Reactor Building Containment. Integrity Test results was performed . This included test results of the Containment Integrated Leak Rate Testing (CILRT or Type A tests), Containment Isolation Valves Local Leak Rater Tests (Type C tests) and Mechanical and Electrical Penetrations Local Leak Rate tests (Type B tests). In accordance with instructions from NEI 94-01 and based on analyses of test results, NPP Krsko created Containment Leakage Rate Testing Program with the purpose to establish the performance-based definition of test intervals, inspection scope, trending and reporting. Equally, the program gives instructions how to evaluate test results and how to deal with the containment penetration or isolation valve repair contingency. All changes caused with transition from Option A to Option B are marginal to public safety. (author)

Large-Scale Seismic Test Program at Hualien, Taiwan

International Nuclear Information System (INIS)

Tang, H.T.; Graves, H.L.; Chen, P.C.

1992-01-01

The Large-Scale Seismic Test (LSST) Program at Hualien, Taiwan, is a follow-on to the soil-structure interaction (SSI) experiments at Lotung, Taiwan. The planned SSI studies will be performed at a stiff soil site in Hualien, Taiwan, that historically has had slightly more destructive earthquakes in the past than Lotung. The LSST is a joint effort among many interested parties. Electric Power Research Institute (EPRI) and Taipower are the organizers of the program and have the lead in planning and managing the program. Other organizations participating in the LSST program are US Nuclear Regulatory Commission, the Central Research Institute of Electric Power Industry, the Tokyo Electric Power Company, the Commissariat A L'Energie Atomique, Electricite de France and Framatome. The LSST was initiated in January 1990, and is envisioned to be five years in duration. Based on the assumption of stiff soil and confirmed by soil boring and geophysical results the test model was designed to provide data needed for SSI studies covering: free-field input, nonlinear soil response, non-rigid body SSI, torsional response, kinematic interaction, spatial incoherency and other effects. Taipower had the lead in design of the test model and received significant input from other LSST members. Questions raised by LSST members were on embedment effects, model stiffness, base shear, and openings for equipment. This paper describes progress in site preparation, design and construction of the model and development of an instrumentation plan

Hardware test program for evaluation of baseline range/range rate sensor concept

Science.gov (United States)

Pernic, E.

1985-01-01

The test program Phase II effort provides additional design information in terms of range and range rate (R/R) sensor performance when observing and tracking a typical spacecraft target. The target used in the test program was a one-third scale model of the Hubble Space Telescope (HST) available at the MSFC test site where the tests were performed. A modified Bendix millimeter wave radar served as the R/R sensor test bed for evaluation of range and range rate tracking performance, and generation of radar signature characteristics of the spacecraft target. A summary of program test results and conclusions are presented along with detailed description of the Bendix test bed radar with accompaning instrumentation. The MSFC test site and facilities are described. The test procedures used to establish background levels, and the calibration procedures used in the range accuracy tests and RCS (radar cross section) signature measurements, are presented and a condensed version of the daily log kept during the 5 September through 17 September test period is also presented. The test program results are given starting with the RCS signature measurements, then continuing with range measurement accuracy test results and finally the range and range rate tracking accuracy test results.

Sandia Laboratories plutonium protection system

International Nuclear Information System (INIS)

Bernard, E.A.; Miyoshi, D.S.; Gutierrez, F.D.

1977-01-01

Sandia Laboratories is developing an improved plutonium protection system (PPS) to demonstrate new concepts for enhancing special nuclear materials safeguards. PPS concepts include separation of functions, real-time item accountability and improved means for control of materials, activities and personnel access. Physical barriers and a secure communications network are designed into the system to offer greater protection against sabotage, diversion and theft attempts. Prototype systems are being constructed at Hanford, Washington and Albuquerque, New Mexico and will be subjected to a comprehensive testing and evaluation program

Mechanical properties test program on structural materials in a sodium environment

International Nuclear Information System (INIS)

Natesan, K.; Chopra, O.K.; Kassner, T.F.

1979-10-01

This document describes in detail the ongoing and planned US Test program on the mechanical properties of sodium-exposed Type 316 austenitic stainless and Fe-2 1/4 Cr-1 Mo ferritic steels. The test program is based on the Development Requirement Specifications (DRS) established by the DOE/Clinch River Breeder Reactor Project (CRBRP) Program Office, the general need for the development of LMFBR structural-design criteria established by the Nuclear Systems Materials Handbook, and the need for a fundamental understanding of materials behavior in a sodium environment, which is generic to LMFBR systems. The planned test program is an extension of work based on current knowledge of sodium chemistry and the influence of sodium purity on the mechanical properties of structural materials

Testing program for concrete at temperatures to 8940K

International Nuclear Information System (INIS)

Naus, D.J.; Oland, C.B.; Robinson, G.C.

1981-01-01

A test program was conducted to define the variations in mechanical properties of a limestone aggregate concrete and a lightweight insulating concrete exposed to elevated temperatures. Four test series were conducted: (1) unconfined compression; (2) shear; (3) rebar bond; and (4) sustained loading (creep). Tests results are presented

76 FR 23914 - National Organic Program; Periodic Residue Testing

Science.gov (United States)

2011-04-29

... NOP. Residue testing plays an important role in organic certification by providing a means for... OFPA (7 U.S.C. 6503 through 6507) from creating certification programs to certify organic farms or... State organic certification program may contain additional requirements for the production and handling...

Assessment of the safety of spent fuel transportation in urban environs

International Nuclear Information System (INIS)

Sandoval, R.P.; Weber, J.P.; Levine, H.S.

1983-06-01

The results of a program to provide an experimental data base for estimating the radiological consequences from a hypothetical sabotage attack on a light-water-reactor spent fuel shipping cask in a densely populated area are presented. The results of subscale and full-scale experiments in conjunction with an analytical modeling study are described. The experimental data were used as input to a reactor-safety consequence model to predict radiological health consequences resulting from a hypothetical sabotage attack on a spent-fuel shipping cask in the Manhattan borough of New York City. The results of these calculations are presented

[Vision test program for ophthalmologists on Apple II, IIe and IIc computers].

Science.gov (United States)

Huber, C

1985-03-01

A microcomputer program for the Apple II family of computers on a monochrome and a color screen is described. The program draws most of the tests used by ophthalmologists, and is offered as an alternative to a projector system. One advantage of the electronic generation of drawings is that true random orientation of Pflueger's E is possible. Tests are included for visual acuity (Pflueger's E, Landolt rings, numbers and children's drawings). Colored tests include a duochrome test, simple color vision tests, a fixation help with a musical background, a cobalt blue test and a Worth figure. In the astigmatic dial a mobile pointer helps to determine the axis. New tests can be programmed by the user and exchanged on disks among collageues.

Testing the structure of a hydrological model using Genetic Programming

Science.gov (United States)

Selle, Benny; Muttil, Nitin

2011-01-01

SummaryGenetic Programming is able to systematically explore many alternative model structures of different complexity from available input and response data. We hypothesised that Genetic Programming can be used to test the structure of hydrological models and to identify dominant processes in hydrological systems. To test this, Genetic Programming was used to analyse a data set from a lysimeter experiment in southeastern Australia. The lysimeter experiment was conducted to quantify the deep percolation response under surface irrigated pasture to different soil types, watertable depths and water ponding times during surface irrigation. Using Genetic Programming, a simple model of deep percolation was recurrently evolved in multiple Genetic Programming runs. This simple and interpretable model supported the dominant process contributing to deep percolation represented in a conceptual model that was published earlier. Thus, this study shows that Genetic Programming can be used to evaluate the structure of hydrological models and to gain insight about the dominant processes in hydrological systems.

Summary of ROSA-4 LSTF first phase test program and station blackout (TMLB) test results

International Nuclear Information System (INIS)

Tasaka, K.; Kukita, Y.; Anoda, Y.

1990-01-01

This paper summarizes major test results obtained at the ROSA-4 Large Scale Test Facility (LSTF) during the first phase of the test program. The results from a station blackout (TMLB) test conducted at the end of the first-phase program are described in some detail. The LSTF is an integral test facility being operated by the Japan Atomic Energy Research Institute for simulation of pressurized water reactor (PWR) thermal-hydraulic responses during small-break loss-of-coolant accidents (SBLOCAs) and operational/abnormal transients. It is a 1/48 volumetrically scaled, full-height, full-pressure simulator of a Westinghouse-type 4-loop PWR. The facility includes two symmetric primary loops each one containing an active inverted-U tube steam generator and an active reactor coolant pump. The loop horizontal legs are sized to conserve the scaled (1/24) volumes as well as the length to the square root of the diameter ratio in order to simulate the two-phase flow regime transitions. The primary objective of the LSTF first-phase program was to define the fundamental PWR thermal-hydraulic responses during SBLOCAs and transients. Most of the tests were conducted with simulated component/operator failures, including unavailability of the high pressure injection system and auxiliary feedwater system, as well as operator failure to take corrective actions. The forty-two first phase tests included twenty-nine SBLOCA tests conducted mainly for cold leg breaks, three abnormal transient tests and ten natural circulation tests. Attempts were made in several of the SBLOCA tests to simulate the plant recovery procedures as well as candidate accident management measures for prevention of high-pressure core melt situation. The natural circulation tests simulated the single-phase and two-phase natural circulation as well as reflux condensation behavior in the primary loops in steady or quasi-steady states

Describing of elements IO field in a testing computer program

Directory of Open Access Journals (Sweden)

Igor V. Loshkov

2017-01-01

Full Text Available A standard of describing the process of displaying interactive windows on a computer monitor, through which an output of questions and input of answers are implemented during computer testing, is presented in the article [11]. According to the proposed standard, the description of the process mentioned above is performed with a format line, containing element names, their parameters as well as grouping and auxiliary symbols. Program objects are described using elements of standard. The majority of objects create input and output windows on a computer monitor. The aim of our research was to develop a minimum possible set of elements of standard to perform mathematical and computer science testing.The choice of elements of the standard was conducted in parallel with the development and testing of the program that uses them. This approach made it possible to choose a sufficiently complete set of elements for testing in fields of study mentioned above. For the proposed elements, names were selected in such a way: firstly, they indicate their function and secondly, they coincide with the names of elements in other programming languages that are similar by function. Parameters, their names, their assignments and accepted values are proposed for the elements. The principle of name selection for the parameters was the same as for elements of the standard: the names should correspond to their assignments or coincide with names of similar parameters in other programming languages. The parameters define properties of objects. Particularly, while the elements of standard create windows, the parameters define object properties (location, size, appearance and the sequence in which windows are created. All elements of standard, proposed in this article are composed in a table, the columns of which have names and functions of these elements. Inside the table, the elements of standard are grouped row by row into four sets: input elements, output elements, input

The U.S. Department of Energy Laboratory Accreditation Program for testing the performance of extremity dosimetry systems: a summary of the program status

International Nuclear Information System (INIS)

Cummings, F.M.; Carlson, R.D.; Gesell, T.F.; Loesch, R.M.

1992-01-01

In 1986, The U.S. Department of Energy (DOE) implemented a program to test the performance of its personnel whole-body dosimetry systems. This program was the DOE Laboratory Accreditation Program (DOELAP). The program parallels the performance testing program specified in the American National Standard for Dosimetry - Personnel Dosimetry Performance -Criteria for Testing (ANSI N13.11-1983), but also addresses the additional dosimetry needs of DOE facilities. As an extension of the whole-body performance testing program, the DOE is now developing a program to test the performance of personnel extremity dosimetry systems. The draft DOE standard for testing extremity dosimetry systems is much less complex than the whole-body dosimetry standard and reflects the limitations imposed on extremity dosimetry by dosimeter design and irradiation geometry. A pilot performance test session has been conducted to evaluate the proposed performance-testing standard. (author)

Technical requirements for the actinide source-term waste test program

Energy Technology Data Exchange (ETDEWEB)

Phillips, M.L.F.; Molecke, M.A.

1993-10-01

This document defines the technical requirements for a test program designed to measure time-dependent concentrations of actinide elements from contact-handled transuranic (CH TRU) waste immersed in brines similar to those found in the underground workings of the Waste Isolation Pilot Plant (WIPP). This test program wig determine the influences of TRU waste constituents on the concentrations of dissolved and suspended actinides relevant to the performance of the WIPP. These influences (which include pH, Eh, complexing agents, sorbent phases, and colloidal particles) can affect solubilities and colloidal mobilization of actinides. The test concept involves fully inundating several TRU waste types with simulated WIPP brines in sealed containers and monitoring the concentrations of actinide species in the leachate as a function of time. The results from this program will be used to test numeric models of actinide concentrations derived from laboratory studies. The model is required for WIPP performance assessment with respect to the Environmental Protection Agency`s 40 CFR Part 191B.

Technical requirements for the actinide source-term waste test program

International Nuclear Information System (INIS)

Phillips, M.L.F.; Molecke, M.A.

1993-10-01

This document defines the technical requirements for a test program designed to measure time-dependent concentrations of actinide elements from contact-handled transuranic (CH TRU) waste immersed in brines similar to those found in the underground workings of the Waste Isolation Pilot Plant (WIPP). This test program wig determine the influences of TRU waste constituents on the concentrations of dissolved and suspended actinides relevant to the performance of the WIPP. These influences (which include pH, Eh, complexing agents, sorbent phases, and colloidal particles) can affect solubilities and colloidal mobilization of actinides. The test concept involves fully inundating several TRU waste types with simulated WIPP brines in sealed containers and monitoring the concentrations of actinide species in the leachate as a function of time. The results from this program will be used to test numeric models of actinide concentrations derived from laboratory studies. The model is required for WIPP performance assessment with respect to the Environmental Protection Agency's 40 CFR Part 191B

PWR blowdown heat transfer separate-effects program: thermal-hydraulic test facility experimental data report for test 104

International Nuclear Information System (INIS)

Leon, D.M.; White, M.D.; Moore, P.A.; Hedrick, R.A.

1978-01-01

Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 104, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in the PWR system. Test 104 was conducted to obtain CHF in bundle 1 under blowdown conditions. The primary purpose of this report is to make the reduced instrument responses during test 104 available

The WIPP research and development test program

International Nuclear Information System (INIS)

Tyler, L.D.

1985-01-01

The WIPP (Waste Isolation Pilot Plant) is a DOE RandD Facility for the purpose of developing the technology needed for the safe disposal of the United States defense-related radioactive waste. The in-situ test program is defined for the thermal-structural interactions, plugging and sealing, and waste package interactions in a salt environment. An integrated series of large-scale underground tests address the issues of both systems and long-term isolation performance of a repository

BWR Full Integral Simulation Test (FIST) program: facility description report

International Nuclear Information System (INIS)

Stephens, A.G.

1984-09-01

A new boiling water reactor safety test facility (FIST, Full Integral Simulation Test) is described. It will be used to investigate small breaks and operational transients and to tie results from such tests to earlier large-break test results determined in the TLTA. The new facility's full height and prototypical components constitute a major scaling improvement over earlier test facilities. A heated feedwater system, permitting steady-state operation, and a large increase in the number of measurements are other significant improvements. The program background is outlined and program objectives defined. The design basis is presented together with a detailed, complete description of the facility and measurements to be made. An extensive component scaling analysis and prediction of performance are presented

SSC string test facility for superconducting magnets: Testing capabilities and program for collider magnets

International Nuclear Information System (INIS)

Kraushaar, P.; Burgett, W.; Dombeck, T.; McInturff, A.; Robinson, W.; Saladin, V.

1993-05-01

The Accelerator Systems String Test (ASST) R ampersand D Testing Facility has been established at the SSC Laboratory to test Collider and High Energy Booster (HEB) superconducting magnet strings. The facility is operational and has had two testing periods utilizing a half cell of collider prototypical magnets with the associated spool pieces and support systems. This paper presents a description of the testing capabilities of the facility with respect to components and supporting subsystems (cryogenic, power, quench protection, controls and instrumentation), the planned testing program for the collider magnets

Data report of BWR post-CHF tests. Transient core thermal-hydraulic test program. Contract research

International Nuclear Information System (INIS)

Iguchi, Tadashi; Itoh, Hideo; Kiuchi, Toshio; Watanabe, Hironori; Kimura, Mamoru; Anoda, Yoshinari

2001-03-01

JAERI has been performing transient core thermal-hydraulic test program. In the program, authors performed BWR/ABWR DBE simulation tests with a test facility, which can simulate BWR/ABWR transients. The test facility has a 4 x 4 bundle core simulator with 15-rod heaters and one non-heated rod. Through the tests, authors quantified the thermal safety margin for core cooling. In order to quantify the thermal safety margin, authors collected experimental data on post-CHF. The data are essential for the evaluation of clad temperature transient when core heat-up occurs during DBEs. In comparison with previous post-CHF tests, present experiments were performed in much wider experimental condition, covering high clad temperature, low to high pressure and low to high mass flux. Further, data at wider elevation (lower to higher elevation of core) were obtained in the present experiments, which make possible to discuss the effect of axial position on thermal-hydraulics, while previous works usually discuss the thermal-hydraulics at the position where the first heat-up occurs. This data report describes test procedure, test condition and major experimental data of post-CHF tests. (author)

EPRI flow-loop/in situ test program for motor-operated valves

International Nuclear Information System (INIS)

Hosler, J.F.; Dorfman, L.S.

1994-01-01

The Electric Power Research Institute is undertaking a comprehensive research program to develop and validate methods for predicting the performance of common motor-operated gate, global, and butterfly valves. To assess motor-operated valve (MOV) performance characteristics and provide a basis for methods validation, full-scale testing was conducted on 62 MOVs. Tests were performed in four flow-loop facilities and in nine nuclear units. Forty-seven gate, five globe, and 10 butterfly valves were tested under a wide range of flow and differential pressure conditions. The paper describes the test program scope, test configurations, instrumentation and data acquisition, testing approach, and data analysis methods. Key results are summarized

Light Water Reactor Sustainability Program: Evaluation of Localized Cable Test Methods for Nuclear Power Plant Cable Aging Management Programs

Energy Technology Data Exchange (ETDEWEB)

Glass, Samuel W. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Fifield, Leonard S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hartman, Trenton S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2016-05-30

This Pacific Northwest National Laboratory (PNNL) milestone report describes progress to date on the investigation of nondestructive test (NDE) methods focusing particularly on local measurements that provide key indicators of cable aging and damage. The work includes a review of relevant literature as well as hands-on experimental verification of inspection capabilities. As NPPs consider applying for second, or subsequent, license renewal (SLR) to extend their operating period from 60 years to 80 years, it important to understand how the materials installed in plant systems and components will age during that time and develop aging management programs (AMPs) to assure continued safe operation under normal and design basis events (DBE). Normal component and system tests typically confirm the cables can perform their normal operational function. The focus of the cable test program is directed toward the more demanding challenge of assuring the cable function under accident or DBE. Most utilities already have a program associated with their first life extension from 40 to 60 years. Regrettably, there is neither a clear guideline nor a single NDE that can assure cable function and integrity for all cables. Thankfully, however, practical implementation of a broad range of tests allows utilities to develop a practical program that assures cable function to a high degree. The industry has adopted 50% elongation at break (EAB) relative to the un-aged cable condition as the acceptability standard. All tests are benchmarked against the cable EAB test. EAB is a destructive test so the test programs must apply an array of other NDE tests to assure or infer the overall set of cable’s system integrity. These cable NDE programs vary in rigor and methodology. As the industry gains experience with the efficacy of these programs, it is expected that implementation practice will converge to a more common approach. This report addresses the range of local NDE cable tests that are

78 FR 53466 - Modification of Two National Customs Automation Program (NCAP) Tests Concerning Automated...

Science.gov (United States)

2013-08-29

... Customs Automation Program (NCAP) Tests Concerning Automated Commercial Environment (ACE) Document Image... National Customs Automation Program (NCAP) tests concerning document imaging, known as the Document Image... the National Customs Automation Program (NCAP) tests concerning document imaging, known as the...

75 FR 58329 - Federal Travel Regulation (FTR); Relocation Expenses Test Programs

Science.gov (United States)

2010-09-24

... of test programs and possible extensions from 24 months to four years; Redesignates current section... conducting test programs. C. Executive Order 12866 This regulation is excepted from the definition of... adding ``12'' in its place. Sec. 300-80.6 [Amended] 0 3. Amend Sec. 300.80-6 by-- 0 a. Removing the word...

Metamorphic Testing Integer Overflow Faults of Mission Critical Program: A Case Study

Directory of Open Access Journals (Sweden)

Zhanwei Hui

2013-01-01

Full Text Available For mission critical programs, integer overflow is one of the most dangerous faults. Different testing methods provide several effective ways to detect the defect. However, it is hard to validate the testing outputs, because the oracle of testing is not always available or too expensive to get, unless the program throws an exception obviously. In the present study, the authors conduct a case study, where the authors apply a metamorphic testing (MT method to detect the integer overflow defect and alleviate the oracle problem in testing critical program of Traffic Collision Avoidance System (TCAS. Experimental results show that, in revealing typical integer mutations, compared with traditional safety property testing method, MT with a novel symbolic metamorphic relation is more effective than the traditional method in some cases.

Experimental Program for the CLIC test facility 3 test beam line

CERN Document Server

Adli, E; Dobert, S; Olvegaard, M; Schulte, D; Syratchev, I; Lillestol, Reidar

2010-01-01

The CLIC Test Facility 3 Test Beam Line is the first prototype for the CLIC drive beam decelerator. Stable transport of the drive beam under deceleration is a mandatory component in the CLIC two-beam scheme. In the Test Beam Line more than 50% of the total energy will be extracted from a 150 MeV, 28 A electron drive beam, by the use of 16 power extraction and transfer structures. A number of experiments are foreseen to investigate the drive beam characteristics under deceleration in the Test Beam Line, including beam stability, beam blow up and the efficiency of the power extraction. General benchmarking of decelerator simulation and theory studies will also be performed. Specially designed instrumentation including precision BPMs, loss monitors and a time-resolved spectrometer dump will be used for the experiments. This paper describes the experimental program foreseen for the Test Beam Line, including the relevance of the results for the CLIC decelerator studies.

CRIEPI test program for seismic isolation of the FBR

International Nuclear Information System (INIS)

Shiojiri, Hiroo

1989-01-01

This paper describes the Central Research Institute of Electric Power Industry's (CRIEPIs) seismic isolation program. The test and research program on seismic isolation was started in 1987 by CRIEPI under contract with the Ministry of International Trade and Industry (MITI) of Japan. It was intended to establish a technical basis for the application of seismic isolation to fast breeder reactors (FBRs). In this paper, some details of the program and results of the preliminary study are described

Active vibration control testing of the SPICES program: final demonstration article

Science.gov (United States)

Dunne, James P.; Jacobs, Jack H.

1996-05-01

The Synthesis and Processing of Intelligent Cost Effective Structures (SPICES) Program is a partnership program sponsored by the Advanced Research Projects Agency. The mission of the program is to develop cost effective material processing and synthesis technologies to enable new products employing active vibration suppression and control devices to be brought to market. The two year program came to fruition in 1995 through the fabrication of the final smart components and testing of an active plate combined with two trapezoidal rails, forming an active mount. Testing of the SPICES combined active mount took place at McDonnell Douglas facilities in St. Louis, MO, in October-December 1995. Approximately 15 dB reduction in overall response of a motor mounted on the active structure was achieved. Further details and results of the SPICES combined active mount demonstration testing are outlined. Results of numerous damping and control strategies that were developed and employed in the testing are presented, as well as aspects of the design and fabrication of the SPICES active mount components.

Testing program PIN on experiments reported in EPRI-NP-369

International Nuclear Information System (INIS)

Kunt, J.; Pazdera, F.

1980-03-01

The testing is described of the applicability of program PIN for the thermomechanical simulation of PWR fuel elements. Program PIN is a modified program GAPCON-THERMAL-2. Four modifications are presented mostly affecting the results, viz., the fuel restructuring model, the fuel densification model, the gaseous fission product release model, and the fuel cladding creep model. The results show that the initial data for simulating fuel element behaviour in accident situations are determined using program PIN with accuracy comparable to that using other programs. (J.P.)

ABCOVE program: preliminary results of tests AB5 and AB6

International Nuclear Information System (INIS)

Hilliard, R.K.; Muhlestein, L.D.

1984-01-01

A program for aerosol behavior code validation and evaluation (ABCOVE) is in progress in the United States. Purpose of the ABCOVE program is to provide a basis for judging the adequacy of existing aerosol behavior computer codes to describe inherent aerosol behavior in containment buildings during postulated breeder reactor accidents. The program involves pretest calculations by code developers and users, large-scale confirmatory tests in the 850-m 3 containment vessel of the Containment Systems Test Facility (CSTF), and blind post-test analyses and comparisons with experimental data. Two ABCOVE tests have been performed in the CSTF to date. In the first test, a single-species aerosol was used, with the aerosol being generated by spraying sodium at a high rate into an air atmosphere. In the second test, the experimental conditions simulated an accident environment in which a fission product aerosol, NaI, was released in the presence of a sodium fire. Pretest computer code predictions were made by seven organizations using eight computer codes (HAA-3, HAA-4, HAARM-3, SOFIA, QUICK, QUICKM, MAEROS, and CONTAIN)

Testing Automation of Context-Oriented Programs Using Separation Logic

Directory of Open Access Journals (Sweden)

Mohamed A. El-Zawawy

2014-01-01

Full Text Available A new approach for programming that enables switching among contexts of commands during program execution is context-oriented programming (COP. This technique is more structured and modular than object-oriented and aspect-oriented programming and hence more flexible. For context-oriented programming, as implemented in COP languages such as ContextJ* and ContextL, this paper introduces accurate operational semantics. The language model of this paper uses Java concepts and is equipped with layer techniques for activation/deactivation of layer contexts. This paper also presents a logical system for COP programs. This logic is necessary for the automation of testing, developing, and validating of partial correctness specifications for COP programs and is an extension of separation logic. A mathematical soundness proof for the logical system against the proposed operational semantics is presented in the paper.

Analysis of Well ER-EC-2a Testing, Western Pahute Mesa-Oasis Valley FY 2000 Testing Program

Energy Technology Data Exchange (ETDEWEB)

None

2002-09-30

This report documents the analysis of the data collected for Well ER-EC-2a during the Western Pahute Mesa - Oasis Valley (WPM-OV) well development and testing program that was conducted during fiscal year (FY) 2000. The data collection for that program is documented in Appendix A, Western Pahute Mesa - Oasis Valley, Well ER-EC-2a Data Report for Development and Hydraulic Testing.

Indicators for monitoring screening programs with primary HPV test.

Science.gov (United States)

Zorzi, Manuel; Giorgi Rossi, Paolo

2017-01-01

following scientific evidence produced in numerous studies, as well as national and international guidelines, organized cervical cancer screening programs in Italy have gradually introduced the HPV test as primary screening test, replacing cytology. As public health interventions, screening programs must ensure equity, improvement in quality of life, and adequate information for the population involved with regards to benefits and possible risks; therefore, it is essential for quality to be constantly checked at every phase of the project.The Italian Cervical Screening Group (Gruppo Italiano per lo Screening Cervicale, GISCi) has written a handbook for the calculation and interpretation of cervical screening program monitoring indicators that take into account the new protocol based on primary HPV test with cytology triage. based on the European guidelines and Italian recommendations on primary HPVbased screening, the working group, which includes professionals from all the fields involved in cervical screening, identified the essential points needed to monitor the screening process, the accuracy of individual tests, and early outcomes, defining a specific indicator for each aspect. The indicators were grouped as follows: baseline indicators, indicators for test repeat after one year, cumulative indicators, and waiting times. For every indicator, the source of data, calculation formula, any standards or critical thresholds, and interpretation were defined. The standards are based on the results of NTCC trials or Italian pilot studies. the main indicators proposed for the organization are the following: number of invitations, compliance with first invitation, with one-year test repeat and with colposcopy; for test and process accuracy, a cohort approach was utilised, where indicators are based on women who must be followed for at least one year, so as to integrate the results obtained after the first HPV test with the outcome of the test's repetition after one year

The Advanced Test Reactor Strategic Evaluation Program

International Nuclear Information System (INIS)

Buescher, B.J.

1990-01-01

A systematic evaluation of safety, environmental, and operational issues has been initiated at the Advanced Test Reactor (ATR). This program, the Strategic Evaluation Program (STEP), provides an integrated review of safety and operational issues against the standards applied to licensed commercial facilities. In the review of safety issues, 18 deviations were identified which required prompt attention. Resolution of these items has been accelerated in the program. An integrated living schedule is being developed to address the remaining findings. A risk evaluation is being performed on the proposed corrective actions and these actions will then be formally ranked in order of priority based on considerations of safety and operational significance. Once the final ranking is completed, an integrated schedule will be developed, which will include considerations of availability of funding and operating schedule. 3 refs., 2 figs

Integrated Data Collection Analysis (IDCA) Program - SSST Testing Methods

Energy Technology Data Exchange (ETDEWEB)

Sandstrom, Mary M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Brown, Geoffrey W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Preston, Daniel N. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Pollard, Colin J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Warner, Kirstin F. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Remmers, Daniel L. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Sorensen, Daniel N. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Whinnery, LeRoy L. [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Phillips, Jason J. [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Shelley, Timothy J. [Bureau of Alcohol, Tobacco and Firearms (ATF), Huntsville, AL (United States); Reyes, Jose A. [Applied Research Associates, Tyndall AFB, FL (United States); Hsu, Peter C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Reynolds, John G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2013-03-25

The Integrated Data Collection Analysis (IDCA) program is conducting a proficiency study for Small- Scale Safety and Thermal (SSST) testing of homemade explosives (HMEs). Described here are the methods used for impact, friction, electrostatic discharge, and differential scanning calorimetry analysis during the IDCA program. These methods changed throughout the Proficiency Test and the reasons for these changes are documented in this report. The most significant modifications in standard testing methods are: 1) including one specified sandpaper in impact testing among all the participants, 2) diversifying liquid test methods for selected participants, and 3) including sealed sample holders for thermal testing by at least one participant. This effort, funded by the Department of Homeland Security (DHS), is putting the issues of safe handling of these materials in perspective with standard military explosives. The study is adding SSST testing results for a broad suite of different HMEs to the literature. Ultimately the study will suggest new guidelines and methods and possibly establish the SSST testing accuracies needed to develop safe handling practices for HMEs. Each participating testing laboratory uses identical test materials and preparation methods wherever possible. The testing performers involved are Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Indian Head Division, Naval Surface Warfare Center, (NSWC IHD), Sandia National Laboratories (SNL), and Air Force Research Laboratory (AFRL/RXQL). These tests are conducted as a proficiency study in order to establish some consistency in test protocols, procedures, and experiments and to compare results when these testing variables cannot be made consistent.

Preliminary irradiation test results from the Yankee Atomic Electric Company reactor vessel test irradiation program

International Nuclear Information System (INIS)

Biemiller, E.C.; Fyfitch, Stephen; Campbell, C.A.

1994-01-01

The Yankee Atomic Electric Company test irradiation program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials and to remove uncertainties in the analysis of existing irradiation data on the Yankee Rowe reactor vessel steel. Plate materials each containing 0.24 w/o copper, but different nickel contents at 0.63 w/o and 0.19 w/o, were heat treated to simulate the Yankee vessel heat treatment (austenitized at 982 o C (1800 o F)) and to simulate Regulatory Guide 1.99 database materials (austenitized at 871 o C (1600 o F)). These heat treatments produced different microstructures so the effect of microstructure on irradiation damage sensitivity could be tested. Because the nickel content of the test plates varied and the copper level was constant, the effect of nickel on irradiation embrittlement was also tested. Correlation monitor material, HSST-02, was included in the program to benchmark the Ford Nuclear Reactor (University of Michigan Test Reactor) which had never been used before for this type of irradiation program. Materials taken from plate surface locations (versus 1/4 T) were included to test whether or not the improved toughness properties of the plate surface layer, resulting from the rapid quench, are maintained after irradiation. If the improved properties are maintained, pressurized thermal shock calculations could utilize this margin. Finally, for one experiment, irradiations were conducted at two irradiation temperatures (260 o C and 288 o C) to determine the effect of irradiation temperature on embrittlement. (Author)

Procedures and reasoning for skill proficiency testing in physical education teacher education programs

Directory of Open Access Journals (Sweden)

Timothy Baghurst

2015-12-01

Full Text Available This study sought to determine how the testing of skill proficiency is being conducted in physical education teacher education (PETE programs in the USA and how fitness or skill proficiencies, as attributes of a physical educator, are perceived. Participants were 312 college PETE program coordinators who completed an online survey about skill testing in their program. The eligible respondents yielded a 52.7% total response rate. Most participants believed that skill proficiency for PETE students was important, but only 46% of programs reported testing within their program. Many participants stated it was possible for their students to graduate without demonstrating proficiency in skill technique, yet were confident their students would pass an independent skill test. Only 46.2% of respondents indicated their students needed to demonstrate proper skill technique in order to graduate, and there was no consistent method of assessment. Responses were evenly split regarding the importance of a physical educator being able to demonstrate proper skill technique or be physically fit. The lack of skill testing in programs, combined with the variation in assessment, is concerning, and the development of a standardized skill-based test may provide more rigor to this important area of teacher credibility and effectiveness.

78 FR 66039 - Modification of National Customs Automation Program Test Concerning Automated Commercial...

Science.gov (United States)

2013-11-04

... Customs Automation Program Test Concerning Automated Commercial Environment (ACE) Cargo Release (Formerly...) plan to both rename and modify the National Customs Automation Program (NCAP) test concerning the... data elements required to obtain release for cargo transported by air. The test will now be known as...

Test Program for the Performance Analysis of DNS64 Servers

Directory of Open Access Journals (Sweden)

Gábor Lencse

2015-09-01

Full Text Available In our earlier research papers, bash shell scripts using the host Linux command were applied for testing the performance and stability of different DNS64 server imple­mentations. Because of their inefficiency, a small multi-threaded C/C++ program (named dns64perf was written which can directly send DNS AAAA record queries. After the introduction to the essential theoretical background about the structure of DNS messages and TCP/IP socket interface programming, the design decisions and implementation details of our DNS64 performance test program are disclosed. The efficiency of dns64perf is compared to that of the old method using bash shell scripts. The result is convincing: dns64perf can send at least 95 times more DNS AAAA record queries per second. The source code of dns64perf is published under the GNU GPLv3 license to support the work of other researchers in the field of testing the performance of DNS64 servers.

75 FR 38422 - Procedures for Transportation Workplace Drug and Alcohol Testing Programs

Science.gov (United States)

2010-07-02

... 2105-AD84 Procedures for Transportation Workplace Drug and Alcohol Testing Programs AGENCY: Office of..., 2011. DATES: This rule is effective July 2, 2010. FOR FURTHER INFORMATION CONTACT: For program issues... Federal Regulations, as follows: PART 40--PROCEDURES FOR TRANSPORTATION WORKPLACE DRUG AND ALCOHOL TESTING...

Inmate must take HIV test if he wants to enroll in program.

Science.gov (United States)

1999-10-29

An inmate cannot sue the Taylorville Correctional Center in Illinois under the Americans with Disabilities Act (ADA) for requiring an HIV test for enrollment in a prison program. [Name removed] wanted to participate in the prison's culinary arts program, but did not want to take the HIV test. The 7th U.S. Circuit Court of Appeals ruled that [name removed] was not a "qualified individual with a disability" and therefore could not sue under ADA. The policy justification for the HIV test, which is required of all inmates enrolling in the program, was not addressed by the court.

40 CFR 91.803 - Manufacturer in-use testing program.

Science.gov (United States)

2010-07-01

... PROGRAMS (CONTINUED) CONTROL OF EMISSIONS FROM MARINE SPARK-IGNITION ENGINES In-Use Testing and Recall... failing engine, two more engines shall be tested until the total number of engines equals ten (10). (2... the total number of engines equals ten (10). (3) If an engine family was certified using carry over...

Restart Testing Program for piping following steam generator replacement at North Anna Unit 1

International Nuclear Information System (INIS)

Bain, R.A.; Bayer, R.K.

1993-01-01

In order to provide assurance that the effects of performing steam generator replacement (SGR) at North Anna unit 1 had no adverse impact on plant piping systems, a cold functional verification restart testing program was developed. This restart testing program was implemented in lieu of a hot functional testing program normally used during the initial startup of a nuclear plant. A review of North Anna plant-specific and generic U.S. Nuclear Regulatory Commission requirements for restart testing was performed to ensure that no mandatory hot functional testing was required. This was determined to be the case, and the development of a cold functional test program was initiated. The cold functional test had inherent advantages as compared to the hot functional testing, while still providing assurance of piping system adequacy. The advantages of the cold verification program included reducing risk to personnel from hot piping, increasing the accuracy of measurements with the improvement in work conditions, eliminating engineering activities during the heatup process, and being able to record measurements as construction work was completed allowing for rework or repair of components if required. To ensure the effectiveness of the cold verification program, a project procedure was generated to identify the personnel, equipment, and measurement requirements. An engineering calculation was issued to document the scope of the restart test program, and an additional calculation was developed to provide acceptance criteria for the critical commodity measurements

1/3-scale model testing program

International Nuclear Information System (INIS)

Yoshimura, H.R.; Attaway, S.W.; Bronowski, D.R.; Uncapher, W.L.; Huerta, M.; Abbott, D.G.

1989-01-01

This paper describes the drop testing of a one-third scale model transport cask system. Two casks were supplied by Transnuclear, Inc. (TN) to demonstrate dual purpose shipping/storage casks. These casks will be used to ship spent fuel from DOEs West Valley demonstration project in New York to the Idaho National Engineering Laboratory (INEL) for long term spent fuel dry storage demonstration. As part of the certification process, one-third scale model tests were performed to obtain experimental data. Two 9-m (30-ft) drop tests were conducted on a mass model of the cask body and scaled balsa and redwood filled impact limiters. In the first test, the cask system was tested in an end-on configuration. In the second test, the system was tested in a slap-down configuration where the axis of the cask was oriented at a 10 degree angle with the horizontal. Slap-down occurs for shallow angle drops where the primary impact at one end of the cask is followed by a secondary impact at the other end. The objectives of the testing program were to (1) obtain deceleration and displacement information for the cask and impact limiter system, (2) obtain dynamic force-displacement data for the impact limiters, (3) verify the integrity of the impact limiter retention system, and (4) examine the crush behavior of the limiters. This paper describes both test results in terms of measured deceleration, post test deformation measurements, and the general structural response of the system

Safeguards system testing WSRC Insider Exercise Program (U)

International Nuclear Information System (INIS)

Robichaux, J.J.

1991-01-01

One of the major concerns related to the control and accountability of nuclear material located at DOE facilities is the theft or diversion of material by an insider. Many complex safeguards and security systems have been installed to provide timely detection and prevention of the removal of nuclear materials. The Westinghouse Savannah River Company's (WSRC) Material Control and Accountability (MC and A) section has implemented an insider exercise program designed to evaluate the effectiveness of these safeguards systems. Exercises consist of limited scope performance test. This paper describes the structure and controls for the insider exercise program at the Savannah River Site, the lessons learned over the past several years, and methods being utilized to improve the program

A Study of Minimum Competency Testing Programs. Final Summary and Analysis Report.

Science.gov (United States)

Gorth, William Phillip; Perkins, Marcy R.

To portray the status of minimum competency testing programs nationwide; as of June 30, 1979, on-site visits were conducted with directors of all 31 state programs and 20 local district programs. Most programs were developed since 1976; 14 state and 13 local programs are fully implemented. The state board of education mandated 16 state programs;…

Japanese contributions to ITER testing program of solid breeder blankets for DEMO

International Nuclear Information System (INIS)

Kuroda, Toshimasa; Yoshida, Hiroshi; Takatsu, Hideyuki; Maki, Koichi; Mori, Seiji; Kobayashi, Takeshi; Suzuki, Tatsushi; Hirata, Shingo; Miura, Hidenori.

1991-04-01

ITER Conceptual Design Activity (CDA), which has been conducted by four parties (Japan, EC, USA and USSR) since May 1988, has been finished on December 1990 with a great achievement of international design work of the integrated fusion experimental reactor. Numerous issues of physics and technology have been clarified for providing a framework of the next phase of ITER (Engineering Design Activity; EDA). Establishment of an ITER testing program, which includes technical test issues of neutronics, solid breeder blankets, liquid breeder blankets, plasma facing components, and materials, has been one of the goals of the CDA. This report describes Japanese proposal for the testing program of DEMO/power reactor blanket development. For two concepts of solid breeder blanket (helium-cooled and water-cooled), identification of technical issues, scheduling of test program, and conceptual design of test modules including required test facility such as cooling and tritium recovery systems have been carried out as the Japanese contribution to the CDA. (author)

Physical Education Experimental Program to Test the Effect on Perceived Competence

Directory of Open Access Journals (Sweden)

Edin Brankovic

2017-06-01

Full Text Available The first purpose of this study was to test effect of multidisciplinary and holistic experimental program (EP in physical education program effect on the soul need perceived competence. The second purpose of this study was to analyse the relationship between attitudes of perceived competence in the experimental group before and after the application of program, mostly due the theoretical reason that perceived competence is predictor of Flow. The data was collected from 74 students of the 8th grade of elementary schools randomly divided in two groups (experimental: 53; control: 21. The system of variables consisted of perceived competence scale items. The t-test analysis was applied to test perceived competence attitudes before and after the EP. The experimental group attitudes of perceived competence after the EP were significantly more positive than before participation in it, while control group attitudes of perceived competence decreased after participation in the regular school program. The current findings support the authors’ hypothesis that the holistic program has significant effect on the soul need perceived competence which is closest predictor of Flow. This study applied multidisciplinary EP which was designed on growth-mind set practices and sparks findings–both connected to flow experience and intrinsic motivation–to suggest future comprehensive program that could be potentially used as a regular tool for achieving both, Flow and intrinsic motivation. Findings with certainty provide a basis for future necessary qualitative research of the program effects on the intrinsic motivation.

77 FR 36014 - Initial Test Program of Emergency Core Cooling Systems for Boiling-Water Reactors

Science.gov (United States)

2012-06-15

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0134] Initial Test Program of Emergency Core Cooling... for public comment draft regulatory guide (DG), DG-1277, ``Initial Test Program of Emergency Core..., entitled, ``Initial Test Program of Emergency Core Cooling Systems for Boiling-Water Reactors,'' is...

78 FR 27984 - Modification of the National Customs Automation Program Test (NCAP) Regarding Reconciliation for...

Science.gov (United States)

2013-05-13

... Customs Automation Program Test (NCAP) Regarding Reconciliation for Filing Certain Post-Importation Claims... Automation Program (NCAP) Reconciliation prototype test to include the filing of post-importation [[Page... of the Test Reconciliation, a planned component of the National Customs Automation Program (NCAP), as...

The implementation of nuclear security program and the improvement of physical protection in Indonesia: progress and challenges

International Nuclear Information System (INIS)

Khairul

2009-01-01

facilities. The nuclear material and its installation is potential target in the facilities so that they needed physical protection measures in prevention and protection of nuclear material and radioactive source against theft and sabotage. The implementation of physical protection of nuclear material and radioactive sources in Indonesia complied with the international instruments such as the Convention of the Physical Protection on Nuclear Material and Facilities, amended on July 2005, and INFCIRC/225/Rev. 4, (corrected), the physical protection of nuclear material and nuclear facilities, June 1999. The application of nuclear energy for power program generation involve in the management of nuclear materials and other radioactive substance. According to international regulation and convention, an effective physical protection system is needed to protect nuclear materials and its facilities against theft and sabotage for both non-proliferation and radiation safety purpose. Further to implementation of the IAEA nuclear security program in the region, Indonesia received two nuclear security services, IPPAS and INSServ mission. Based on the expert mission recommendation, therefore Indonesia improved their physical protection system on nuclear material and facilities against theft and sabotage. One thing that should be considered by the Government of Indonesia is human resource development programmes. So far, some effort has developed to enhance the knowledge of the employee who deals with nuclear material and radioactive substances. It still needed to increase the awareness in particular to personal and other related agencies as well. The Department of Energy's National Nuclear Security Administration discussed security assistance with Indonesia's National Nuclear Energy Agency, BATAN. These upgrades not only reduced the threat of theft at the three research reactors, but also provided local physical protection expertise to use during the concept, design, and operation of

75 FR 9958 - Carolina Power & Light Company, Shearon Harris Nuclear Power Plant, Unit 1; Exemption

Science.gov (United States)

2010-03-04

... and Qualification Plan, Safeguards Contingency Plan, and Cyber Security Plan referred to collectively... licensee), now doing business as Progress Energy Carolinas, Inc. (PEC), is the holder of Renewed Facility..., against radiological sabotage by designing and implementing comprehensive site security programs. The...

We Will Find A Way: Understanding the Legacy of Canadian Special Operations Forces

Science.gov (United States)

2012-02-01

planners briefed him on the Commando raiding program and, more importantly, the work of Brigadier Colin Gubbins’ SOE and their Norwegian sabotage... Drury , Assistant Military Attaché, Canadian 53. Legation, Washington to the Directorate of Military Operations & Intelligence, NDHQ, Washington, 7

Test Report Emission Test Program EPA Information Collection Request for Delayed Coking Units 736 Coker Unit

Science.gov (United States)

ARI Environmental, Inc. (ARI) was retained by Houston Refining LP (HRO) to conduct an emission test program at their refinery located in Houston, Texas. The testing was conducted on on the 736 Delayed Coking Unit (DCU) in response to EPA's ICR.

An Airborne Parachute Compartment Test Bed for the Orion Parachute Test Program

Science.gov (United States)

Moore, James W.; Romero, Leah M.

2013-01-01

The test program developing parachutes for the Orion/MPCV includes drop tests with parachutes deployed from an Orion-like parachute compartment at a wide range of dynamic pressures. Aircraft and altitude constraints precluded the use of an Orion boilerplate capsule for several test points. Therefore, a dart-shaped test vehicle with a hi-fidelity mock-up of the Orion parachute compartment has been developed. The available aircraft options imposed constraints on the test vehicle development and concept of operations. Delivery of this test vehicle to the desired velocity, altitude, and orientation required for the test is a di cult problem involving multiple engineering disciplines. This paper describes the development of the test technique. The engineering challenges include extraction from an aircraft, reposition of the extraction parachute, and mid-air separation of two vehicles, neither of which has an active attitude control system. The desired separation behavior is achieved by precisely controlling the release point using on-board monitoring of the motion. The design of the test vehicle is also described. The trajectory simulations and other analyses used to develop this technique and predict the behavior of the test vehicle are reviewed in detail. The application of the technique on several successful drop tests is summarized.

Justice downwind: America's atomic testing program in the 1950s

International Nuclear Information System (INIS)

Ball, H.

1986-01-01

Drawing on personal interviews, case histories, and the archives of the Atomic Energy Commission, Professor Ball discusses the American nuclear-testing program from 1951 to 1963, the impact of the testing on people living downwind from the Nevada Test Site, long-term effects of radiation exposure, and the clash between the ''downwinders'' and the government

75 FR 3153 - Drug and Alcohol Testing Program; Correction

Science.gov (United States)

2010-01-20

... definition of prohibited drugs. In Sec. Sec. 120.103 and 120.211, we omitted the reference to Sec. 135.1 from.... FAA-2008-0937; Amendment No. 120-0A, 135-117A] RIN 2120-AJ37 Drug and Alcohol Testing Program... Aviation Administration (FAA) is correcting its drug and alcohol testing regulations published on May 14...

History and Benefits of Engine Level Testing Throughout the Space Shuttle Main Engine Program

Science.gov (United States)

VanHooser, Katherine; Kan, Kenneth; Maddux, Lewis; Runkle, Everett

2010-01-01

Rocket engine testing is important throughout a program s life and is essential to the overall success of the program. Space Shuttle Main Engine (SSME) testing can be divided into three phases: development, certification, and operational. Development tests are conducted on the basic design and are used to develop safe start and shutdown transients and to demonstrate mainstage operation. This phase helps form the foundation of the program, demands navigation of a very steep learning curve, and yields results that shape the final engine design. Certification testing involves multiple engine samples and more aggressive test profiles that explore the boundaries of the engine to vehicle interface requirements. The hardware being tested may have evolved slightly from that in the development phase. Operational testing is conducted with mature hardware and includes acceptance testing of flight assets, resolving anomalies that occur in flight, continuing to expand the performance envelope, and implementing design upgrades. This paper will examine these phases of testing and their importance to the SSME program. Examples of tests conducted in each phase will also be presented.

PWR blowdown heat transfer separate-effects program: Thermal-Hydraulic Test Facility experimental data report for test 100

International Nuclear Information System (INIS)

White, M.D.; Hedrick, R.A.

1977-01-01

Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 100, which is part of the ORNL Pressurized-Water-Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system. Test 100 was conducted to investigate the response of heater rod bundle 1 and instrumented spool pieces with flow homogenizing screens to a double-ended rupture with equal break areas at the test section inlet and outlet. The primary purpose of this report is to make the reduced instrument responses during test 100 available. The responses are presented in graphical form in engineering units and have been analyzed only to the extent necessary to assure reasonableness and consistency

Modeling a forced to natural convection boiling test with the program LOOP-W

International Nuclear Information System (INIS)

Carbajo, J.J.

1984-01-01

Extensive testing has been conducted in the Simulant Boiling Flow Visualization (SBFV) loop in which water is boiled in a vertical transparent tube by circulating hot glycerine in an annulus surrounding the tube. Tests ranged from nonboiling forced convection to oscillatory boiling natural convection. The program LOOP-W has been developed to analyze these tests. This program is a multi-leg, one-dimensional, two-phase equilibrium model with slip between the phases. In this study, a specific test, performed at low power where non-boiling forced convection was changed to boiling natural convection and then to non-boiling again, has been modeled with the program LOOP-W

Nuclear systems and testing programs for ITER. Progress report for FY 1998

International Nuclear Information System (INIS)

1998-01-01

The effort during this performance period focused on a number of TBWG activities (including test module design and analysis) that were identified and agreed upon (in the presence of the ITER Director and Deputy Director) at TBWG-4. These include: (a) DEMO test module design and performance analysis under pulsed operation; (b) Test program operation plan; (c) Test port design and analysis; (d) Decay heat calculations and safety analysis; (e) Further discussion among the parties to define collaboratory on R and D for the test program as well as possible collaboration on the construction and operation of test articles; (f) Remote handling and ancillary equipment; (g) Criteria for qualifying a blanket module or submodule for actual insertion and testing in ITER; (h) Definition of test module instrumentation and verification of capability to perform in the ITER fusion environment (magnetic field, radiation, heating, etc.); and (i) Analysis to show that the results to be obtained from the test modules as designed can be extrapolated to DEMO and reactor conditions (e.g., higher wall loads and the need to demonstrate tritium self-sufficiency). The main achievements during this performance period include: (1) updating and finalizing the US DDDs for the ITER Blanket Program to form part of the ITER Final Design Report (FDR). Specific revisions were in response to the minimal lithium volume test blanket design requirements and safety impact and (2) evaluating the feasibility of the US test program, including instrumentation and the benefits of the ITER test program. Details of this assessment, including solid breeder and liquid breeder blanket test plans, are documented in UCLA-IFNT-13 (attached). In addition, dose mapping calculations were performed for the ITER Building, including equipment and layout of coolant pipes/heat exchangers. A report on ITER Building dose calculations was sent to UD ITER management and to the Garching Task Coordinator in April, 1998. The report

78 FR 63823 - Energy Conservation Program: Test Procedures for Television Sets

Science.gov (United States)

2013-10-25

..., Building Technologies Program, EE-2J, 1000 Independence Avenue SW., Washington, DC 20585-0121. Telephone... test signals for test content and was geared heavily for older screen technologies like cathode ray... tested. For example, in Figure 5, testing would not be required with Eco mode both enabled and disabled...

Mathematical-programming approaches to test item pool design

NARCIS (Netherlands)

Veldkamp, Bernard P.; van der Linden, Willem J.; Ariel, A.

2002-01-01

This paper presents an approach to item pool design that has the potential to improve on the quality of current item pools in educational and psychological testing andhence to increase both measurement precision and validity. The approach consists of the application of mathematical programming

Analysis of KC-46 Live-Fire Risk Mitigation Program Testing

Science.gov (United States)

2012-03-01

the use of real hardware such as electrohydraulic actuators , electrical units, and converter regulators (Andrus, 2010). The only feasible method for...worked with the MQ-9 as a test engineer and analyst for the programs IOT &E, RQ-4 as lead engineer and program lead for the block 3 and the block 4

40 CFR 80.156 - Liability for violations of the interim detergent program controls and prohibitions.

Science.gov (United States)

2010-07-01

... gasoline or detergent carrier caused the violation. (4) Volumetric additive reconciliation. Where a violation of the volumetric additive reconciliation requirements established by § 80.155(b) has occurred... violation of law (other than these regulations), or an act of sabotage or vandalism, whether or not such...

Overview and status of the SIMMER testing program

International Nuclear Information System (INIS)

Scott, J.H.

1979-01-01

Los Alamos Scientific Laboratory has undertaken an extensive experiment analysis program to test the results of SIMMER Liquid Metal Fast Breeder Reactor (LMFBR) accident calculations. Initially, we will test the postdisassembly work-energy partition problem. The SIMMER-calculated order-of-magnitude reduction of available kinetic energy following a severe hypothetical core-disruptive accident (HCDA) can be attributed to (1) purely fluid-dynamic effects; and (2) rate-controlled effects, such as phase transitions and heat transfer. We have chosen to test separately each class of mitigator. In this paper we review the experiments initially chosen for testing of each class of mitigator and report on the status of the analyses. We enumerate several problems in SIMMER that experiment analysis has disclosed. Finally, needs for future experiments are discussed

Risk-based inservice testing program modifications at Palo Verde nuclear generating station

International Nuclear Information System (INIS)

Knauf, S.; Lindenlaub, B.; Linthicum, R.

1996-01-01

Arizona Public Service Company (APS) is investigating changes to the Palo Verde Inservice Testing (IST) Program that are intended to result in the reduction of the required test frequency for various valves in the American Society of Mechanical Engineers (ASME) Section XI IST program. The analytical techniques employed to select candidate valves and to demonstrate that these frequency reductions are acceptable are risk based. The results of the Palo Verde probabilistic risk assessment (PRA), updated in June 1994, and the risk significant determination performed as part of the implementation efforts for 10 CFR 50.65 (the maintenance rule) were used to select candidate valves for extended test intervals. Additional component level evaluations were conducted by an 'expert panel.' The decision to pursue these changes was facilitated by the ASME Risk-Based Inservice Testing Research Task Force for which Palo Verde is participating as a pilot plant. The NRC's increasing acceptance of cost beneficial licensing actions and risk-based submittals also provided incentive to seek these changes. Arizona Public Service is pursuing the risk-based IST program modification in order to reduce the unnecessary regulatory burden of the IST program through qualitative and quantitative analysis consistent with maintaining a high level of plant safety. The objectives of this project at Palo Verde are as follows: (1) Apply risk-based technologies to IST components to determine their risk significance (i.e., high or low). (2) Apply a combination of deterministic and risk-based methods to determine appropriate testing requirements for IST components including improvement of testing methods and frequency intervals for high-risk significant components. (3) Apply risk-based technologies to high-risk significant components identified by the open-quotes expert panelclose quotes and outside of the IST program to determine whether additional testing requirements are appropriate

Risk-based inservice testing program modifications at Palo Verde nuclear generating station

Energy Technology Data Exchange (ETDEWEB)

Knauf, S.; Lindenlaub, B.; Linthicum, R.

1996-12-01

Arizona Public Service Company (APS) is investigating changes to the Palo Verde Inservice Testing (IST) Program that are intended to result in the reduction of the required test frequency for various valves in the American Society of Mechanical Engineers (ASME) Section XI IST program. The analytical techniques employed to select candidate valves and to demonstrate that these frequency reductions are acceptable are risk based. The results of the Palo Verde probabilistic risk assessment (PRA), updated in June 1994, and the risk significant determination performed as part of the implementation efforts for 10 CFR 50.65 (the maintenance rule) were used to select candidate valves for extended test intervals. Additional component level evaluations were conducted by an `expert panel.` The decision to pursue these changes was facilitated by the ASME Risk-Based Inservice Testing Research Task Force for which Palo Verde is participating as a pilot plant. The NRC`s increasing acceptance of cost beneficial licensing actions and risk-based submittals also provided incentive to seek these changes. Arizona Public Service is pursuing the risk-based IST program modification in order to reduce the unnecessary regulatory burden of the IST program through qualitative and quantitative analysis consistent with maintaining a high level of plant safety. The objectives of this project at Palo Verde are as follows: (1) Apply risk-based technologies to IST components to determine their risk significance (i.e., high or low). (2) Apply a combination of deterministic and risk-based methods to determine appropriate testing requirements for IST components including improvement of testing methods and frequency intervals for high-risk significant components. (3) Apply risk-based technologies to high-risk significant components identified by the {open_quotes}expert panel{close_quotes} and outside of the IST program to determine whether additional testing requirements are appropriate.

State-of-the-art report for the testing and formal verification methods for FBD program

International Nuclear Information System (INIS)

Jee, Eun Kyoung; Lee, Jang Soo; Lee, Young Jun; Yoo, Jun Beom

2011-10-01

The importance of PLC testing has increased in the nuclear I and C domain. While regulation authorities require both functional and structural testing for safety system software, FBD testing relies only on functional testing and there has been little research on structural testing techniques for FBD programs. We aim to analyze current techniques related to FBD testing and develop a structural testing technique appropriate to FBD programs. We developed structural test coverage criteria applicable to FBD programs, focusing on data paths from input edges to output edges of FBD programs. A data path condition (DPC), under which input data can flow into the output edge, is defined for each data path. We defined basic coverage, input condition coverage and complex condition coverage criteria based on the formal definition of DPC. We also developed a measurement procedure for FBD testing adequacy and a supporting tool prototype

The integrated in situ testing program for the Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

Matalucci, R.V.

1987-03-01

The US Department of Energy (DOE) is developing the Waste Isolation Pilot Plant (WIPP) Project in southeastern New Mexico as a research and development (R and D) facility for examining the response of bedded (layered) salt to the emplacement of radioactive wastes generated from defense programs. The WIPP Experimental Program consists of a technology development program, including laboratory testing and theoretical analysis activities, and an in situ testing program that is being done 659 m underground at the project site. This experimental program addresses three major technical areas that concern (1) thermal/structural interactions, (2) plugging and sealing, and (3) waste package performance. To ensure that the technical issues involved in these areas are investigated with appropriate emphasis and timing, an in situ testing plan was developed to integrate the many activities and tasks associated with the technical issues of waste disposal. 5 refs., 4 figs

76 FR 34086 - Mandatory Guidelines for Federal Workplace Drug Testing Programs; Request for Information...

Science.gov (United States)

2011-06-10

... Mandatory Guidelines for Federal Workplace Drug Testing Programs; Request for Information Regarding Specific Issues Related to the Use of the Oral Fluid Specimen for Drug Testing AGENCY: Substance Abuse and Mental... may be applied to the Mandatory Guidelines for Federal Workplace Drug Testing Programs (oral fluid...

78 FR 75961 - Energy Conservation Program: Test Procedures for Electric Motors

Science.gov (United States)

2013-12-13

... Conservation Program: Test Procedures for Electric Motors; Final Rule #0;#0;Federal Register / Vol. 78 , No... Procedures for Electric Motors AGENCY: Office of Energy Efficiency and Renewable Energy, Department of Energy... procedures for electric motors to allow currently unregulated motors to be tested by clarifying the test...

77 FR 28805 - Energy Conservation Program: Test Procedures for Microwave Ovens

Science.gov (United States)

2012-05-16

... Energy Conservation Program: Test Procedures for Microwave Ovens AGENCY: Office of Energy Efficiency and... (SNOPR) to amend the test procedures for microwave ovens. That SNOPR proposed amendments to the DOE test... mode energy use of products that combine a microwave oven with other appliance functionality, as well...

Definition study for variable cycle engine testbed engine and associated test program

Science.gov (United States)

Vdoviak, J. W.

1978-01-01

The product/study double bypass variable cycle engine (VCE) was updated to incorporate recent improvements. The effect of these improvements on mission range and noise levels was determined. This engine design was then compared with current existing high-technology core engines in order to define a subscale testbed configuration that simulated many of the critical technology features of the product/study VCE. Detailed preliminary program plans were then developed for the design, fabrication, and static test of the selected testbed engine configuration. These plans included estimated costs and schedules for the detail design, fabrication and test of the testbed engine and the definition of a test program, test plan, schedule, instrumentation, and test stand requirements.

Full-Scale Cask Testing and Public Acceptance of Spent Nuclear Fuel Shipments - 12254

Energy Technology Data Exchange (ETDEWEB)

Dilger, Fred [Black Mountain Research, Henderson, NV 81012 (United States); Halstead, Robert J. [State of Nevada Agency for Nuclear Projects Carson City, NV 80906 (United States); Ballard, James D. [Department of Sociology, California State University, Northridge Northridge, CA 91330 (United States)

2012-07-01

Full-scale physical testing of spent fuel shipping casks has been proposed by the National Academy of Sciences (NAS) 2006 report on spent nuclear fuel transportation, and by the Presidential Blue Ribbon Commission (BRC) on America's Nuclear Future 2011 draft report. The U.S. Nuclear Regulatory Commission (NRC) in 2005 proposed full-scale testing of a rail cask, and considered 'regulatory limits' testing of both rail and truck casks (SRM SECY-05-0051). The recent U.S. Department of Energy (DOE) cancellation of the Yucca Mountain project, NRC evaluation of extended spent fuel storage (possibly beyond 60-120 years) before transportation, nuclear industry adoption of very large dual-purpose canisters for spent fuel storage and transport, and the deliberations of the BRC, will fundamentally change assumptions about the future spent fuel transportation system, and reopen the debate over shipping cask performance in severe accidents and acts of sabotage. This paper examines possible approaches to full-scale testing for enhancing public confidence in risk analyses, perception of risk, and acceptance of spent fuel shipments. The paper reviews the literature on public perception of spent nuclear fuel and nuclear waste transportation risks. We review and summarize opinion surveys sponsored by the State of Nevada over the past two decades, which show consistent patterns of concern among Nevada residents about health and safety impacts, and socioeconomic impacts such as reduced property values along likely transportation routes. We also review and summarize the large body of public opinion survey research on transportation concerns at regional and national levels. The paper reviews three past cask testing programs, the way in which these cask testing program results were portrayed in films and videos, and examines public and official responses to these three programs: the 1970's impact and fire testing of spent fuel truck casks at Sandia National

Integrated verification and testing system (IVTS) for HAL/S programs

Science.gov (United States)

Senn, E. H.; Ames, K. R.; Smith, K. A.

1983-01-01

The IVTS is a large software system designed to support user-controlled verification analysis and testing activities for programs written in the HAL/S language. The system is composed of a user interface and user command language, analysis tools and an organized data base of host system files. The analysis tools are of four major types: (1) static analysis, (2) symbolic execution, (3) dynamic analysis (testing), and (4) documentation enhancement. The IVTS requires a split HAL/S compiler, divided at the natural separation point between the parser/lexical analyzer phase and the target machine code generator phase. The IVTS uses the internal program form (HALMAT) between these two phases as primary input for the analysis tools. The dynamic analysis component requires some way to 'execute' the object HAL/S program. The execution medium may be an interpretive simulation or an actual host or target machine.

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

PWR Blowdown Heat Transfer Separate-Effects Program. Thermal-Hydraulic Test Facility experimental data report for test 166S

International Nuclear Information System (INIS)

Clemons, V.D.; White, M.D.; Hedrick, R.A.

1978-01-01

Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 166S, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system. Test 166S was conducted to obtain thermal-hydraulic and CHF information in THTF bundle 1 with an intact hot leg. The primary purpose of this report is to make the reduced instrument responses during tests 166S available. These are presented in graphical form in engineering units and have been analyzed only to the extent necessary to ensure reasonableness and consistency

Summary and recommendations of the NRC/INEL Activated Carbon Testing Program

International Nuclear Information System (INIS)

Scarpellino, C.D.; Sill, C.W.

1986-01-01

The Committee on Nuclear Air and Gas Treatment (CONAGT) of the American Society of Mechanical Engineers (ASME) sponsored an interlaboratory testing program, round-robin, of nuclear-grade activated carbon. The results of this round-robin revealed gross differences in penetration of radio-labeled methyl iodide as measured by the various laboratories when using Method A of the ASTM D-3803-79 Standard. These differences prompted the Nuclear Regulatory Commission (NRC) to establish the NRC/INEL Activated Carbon Testing Program to determine the causes of these discrepancies and to provide recommendations that could lead to an accurate and reliable testing procedure that would ensure an adequate method for assessing the capability of activated carbon to remove radioiodine from gas streams within commercial nuclear power plants. The NRC/INEL Activated Carbon Testing Program has conducted formal and informal interlaboratory comparisons to identify problems with the test method and its application and to assess the effectiveness of changes to procedures and equipment voluntarily implemented by commercial laboratories to mitigate the disparity of test results. The results of the first formal NRC/INEL Interlaboratory Comparison (IC) essentially verified the CONAGT round-robin results despite the use of a detailed test protocol. This data indicated that many of the participating laboratories probably had been operating outside the ASTM specifications for relative humidity (RH) and flow. In addition, this process provided information which was used to modify the testing protocol employed for the second NRC/INEL Interlaboratory Comparison (IC-2) to make it more rugged and reliable. These changes to the protocol together with the results of INEL sensitivity testing are the basis for the recommendations presented

Testing Algorithmic Skills in Traditional and Non-Traditional Programming Environments

Science.gov (United States)

Csernoch, Mária; Biró, Piroska; Máth, János; Abari, Kálmán

2015-01-01

The Testing Algorithmic and Application Skills (TAaAS) project was launched in the 2011/2012 academic year to test first year students of Informatics, focusing on their algorithmic skills in traditional and non-traditional programming environments, and on the transference of their knowledge of Informatics from secondary to tertiary education. The…

The BNL Accelerator Test Facility and experimental program

International Nuclear Information System (INIS)

Ben-Zvi, I.; State Univ. of New York, Stony Brook, NY

1992-01-01

The Accelerator Test Facility (ATF) at BNL is a users' facility for experiments in Accelerator and Beam Physics. The ATF provides high brightness electron beams and high-power laser pulses synchronized to the electron beam, suitable for studies of new methods of high-gradient acceleration and state-of-the-art Free-Electron Lasers. The electrons are produced by a laser photocathode rf gun and accelerated to 50 MeV by two traveling wave accelerator sections. The lasers include a 10 mJ, 10 ps ND:YAG laser and a 500 mJ, 10 to 100 ps C0 2 laser. A number of users from National Laboratories, universities and industry take part in experiments at the ATF. The experimental program includes various laser acceleration schemes, Free-Electron Laser experiments and a program on the development of high-brightness electron beams. The ATF's experimental program commenced in early 1991 at an energy of about 4 MeV. The full program, with 50 MeV and the high-power laser will begin operation this year

The BNL Accelerator Test Facility and experimental program

International Nuclear Information System (INIS)

Ben-Zvi, I.; State Univ. of New York, Stony Brook, NY

1991-01-01

The Accelerator Test Facility (ATF) at BNL is a users' facility for experiments in Accelerator and Beam Physics. The ATF provides high brightness electron beams and high power laser pulses synchronized to the electron beam, suitable for studies of new methods of high gradient acceleration and state of the art free electron lasers. The electrons are produced by a laser photocathode rf gun and accelerated to 50 to 100 MeV by two traveling wave accelerator sections. The lasers include a 10 mJ, 10 ps Nd:YAG laser and a 100 mJ, 10 ps CO 2 laser. A number of users from National Laboratories, universities and industry take part in experiments at the ATF. The experimental program includes various acceleration schemes, Free-Electron Laser experiments and a program on the development of high brightness electron beams. The AFT's experimental program commenced in early 1991 at an energy of about 4 MeV. The full program, with 50 MeV and the High power laser will begin operation this year. 28 refs., 4 figs

DOE standard: Filter test facility quality program plan

International Nuclear Information System (INIS)

1999-02-01

This standard was developed primarily for application in US Department of Energy programs. It contains specific direction for HEPA filter testing performed at a DOE-accepted HEPA Filter Test Facility (FTF). Beneficial comments (recommendations, additions, deletions) and any pertinent data that may improve this document should be sent to the Office of Nuclear Safety Policy and Standards (EH-31), US Department of Energy, Washington, DC 20585, by letter or by using the self-addressed Document Improvement Proposal form (DOE F 1300.3) appearing at the end of this document

Optimized FFTF Acceptance Test Program covering Phases III, IV, and V

International Nuclear Information System (INIS)

Wykoff, W.R.; Jones, D.H.

1977-03-01

A detailed review of Phases III, IV, and V of the FFTF Acceptance Test Program has been completed. The purpose of this review was to formulate that test sequence which not only meets requirements for safe, reliable and useful operation of the plant, but also results in the earliest prudent demonstration of full-power performance. A test sequence based on the underlying assumption that sodium flows into the secondary sodium storage tank (T-44) no later than August 31, 1978, is described in detail. A time-scale which allows extra time to put systems and equipment into operation the first time, debugging, and learning how to operate most effectively has been superimposed on the test sequence. Time is not included for major equipment malfunctions. This test plan provides the basis for coordinating the many and varied activities and interfaces necessary for successful and timely execution of the FFTF Acceptance Test Program. In this report, the need dates have been identified for presently scheduled test articles and standard core components

Software Review: A program for testing capture-recapture data for closure

Science.gov (United States)

Stanley, Thomas R.; Richards, Jon D.

2005-01-01

Capture-recapture methods are widely used to estimate population parameters of free-ranging animals. Closed-population capture-recapture models, which assume there are no additions to or losses from the population over the period of study (i.e., the closure assumption), are preferred for population estimation over the open-population models, which do not assume closure, because heterogeneity in detection probabilities can be accounted for and this improves estimates. In this paper we introduce CloseTest, a new Microsoft® Windows-based program that computes the Otis et al. (1978) and Stanley and Burnham (1999) closure tests for capture-recapture data sets. Information on CloseTest features and where to obtain the program are provided.

Nuclear waste transportation package testing: A review of selected programs in the United States and abroad

International Nuclear Information System (INIS)

Snedeker, D.F.

1990-12-01

This report provides an overview of some recent nuclear waste transportation package development programs. This information is intended to aid the State of Nevada in its review of US Department of Energy (DOE) nuclear waste transportation programs. This report addresses cask testing programs in the United Kingdom and selected 1/4 and full scale testing in the US. Facilities that can provide cask testing services, both in the US and to a limited extent abroad, are identified. The costs for different type test programs are identified as a means to estimate costs for future test programs. Not addressed is the public impact such testing might have in providing an increased sense of safety or confidence. The British test program was apparently quite successful in demonstrating safety to the public at the time. There is no US test effort that is similar in scope for direct comparison. Also addressed are lessons learned from testing programs and areas that may merit possible future integrated examination. Areas that may require further examination are both technical and institutional. This report provides information which, when combined with other sources of information will enable the State of Nevada to assess the following areas: feasibility of full scale testing; costs of full scale tests; potential benefits of testing; limits that full scale testing impose; and disadvantages of emphasis on testing vs analytical solutions. This assessment will then allow the state to comment on DOE Office of Civilian Radioactive Waste Management (OCRWM) plans for the development and licensing of new shipping cask designs. These plans currently expect contractors to perform engineering testing for materials development, quarter scale model testing to validate analytical assessments and full scale prototype testing of operational features. DOE currently plans no full scale or extra-regulatory destructive testing to aid in cask licensing. 1 tab

Implementing a routine, voluntary HIV testing program in a Massachusetts county prison.

Science.gov (United States)

Liddicoat, Rebecca V; Zheng, Hui; Internicola, Jeanne; Werner, Barbara G; Kazianis, Arthur; Golan, Yoav; Rubinstein, Eric P; Freedberg, Kenneth A; Walensky, Rochelle P

2006-11-01

Although U.S. prison inmates have higher rates of HIV infection than the general population, most inmates are not routinely tested for HIV infection at prison entry. The study objective was to implement a routine, voluntary HIV testing program in a Massachusetts county prison. During admission, inmates were given group HIV pre-test counseling and were subsequently offered private HIV testing. This intervention was compared to a control period during which HIV testing was provided only upon inmate or physician request. Between November 2004 and April 2005, 1,004 inmates met inclusion criteria and were offered routine, voluntary HIV testing. Of these, 734 (73.1%) accepted, 2 (0.3%) were HIV-infected, and 457 (45.5%) had been tested for HIV in the previous year. The testing rate of 73.1% was significantly increased from the rate of 18.0% (318 of 1,723) during the control period (pprison setting. Careful attention should be paid to prevent redundancy of testing efforts in the prison population. Implementing a routine HIV testing program among prison inmates greatly increased testing rates compared to on-request testing.

Handbook for Classroom Testing in Peace Corps Language Programs. Manual T0068.

Science.gov (United States)

Anderson, Neil J.

This manual provides instructors in Peace Corps language training programs with information about two kinds of classroom testing: formative, ongoing testing and summative testing that occurs at the end of an instructional period. The first of the manual's four chapters on the purposes of language testing, discusses language testing within a…

Technical resolution of Generic Safety Issue A-29

International Nuclear Information System (INIS)

1989-09-01

This report summarizes key technical findings related to Generic Safety Issue A-29, ''Nuclear Power Plant Design for Reduction of Vulnerability to Industrial Sabotage.'' The findings in this report deal with (1) a historical review of reported sabotage-related events at nuclear facilities, (2) NRC physical security requirements, (3) industry measures to prevent/mitigate sabotage, (4) design and procedural approaches that could be used to deter sabotage, (5) current NRC and industry initiatives aimed at personnel screening and selection, and (6) design considerations applicable to Advanced Light Water Reactors (ALWRs). The results reveal that insider sabotage at operating nuclear plants has not been a significant problem in the United States to date and that there are no singular design modifications or procedures that by themselves would completely eliminate or mitigate the threat of insider sabotage. Rather, it will take a combination of systematic and focused improvements in the three areas of reliable personnel, effective design features, and plant procedures developed to provide a strategy to deal with prevention of insider sabotage and to be able to mitigate adverse actions. 24 refs., 2 figs., 5 tabs

Ground test program for a full-size solar dynamic heat receiver

Science.gov (United States)

Sedgwick, L. M.; Kaufmann, K. J.; Mclallin, K. L.; Kerslake, T. W.

1991-01-01

Test hardware, facilities, and procedures were developed to conduct ground testing of a full-size, solar dynamic heat receiver in a partially simulated, low earth orbit environment. The heat receiver was designed to supply 102 kW of thermal energy to a helium and xenon gas mixture continuously over a 94 minute orbit, including up to 36 minutes of eclipse. The purpose of the test program was to quantify the receiver thermodynamic performance, its operating temperatures, and thermal response to changes in environmental and power module interface boundary conditions. The heat receiver was tested in a vacuum chamber using liquid nitrogen cold shrouds and an aperture cold plate. Special test equipment was designed to provide the required ranges in interface boundary conditions that typify those expected or required for operation as part of the solar dynamic power module on the Space Station Freedom. The support hardware includes an infrared quartz lamp heater with 30 independently controllable zones and a closed-Brayton cycle engine simulator to circulate and condition the helium-xenon gas mixture. The test article, test support hardware, facilities, and instrumentation developed to conduct the ground test program are all described.

77 FR 48527 - National Customs Automation Program (NCAP) Test Concerning Automated Commercial Environment (ACE...

Science.gov (United States)

2012-08-14

... National Customs Automation Program (NCAP) test concerning the simplified entry functionality in the... DEPARTMENT OF HOMELAND SECURITY U.S. Customs and Border Protection National Customs Automation Program (NCAP) Test Concerning Automated Commercial Environment (ACE) Simplified Entry: Modification of...

MAVL wastes containers functional demonstration and associated tests program

International Nuclear Information System (INIS)

Templier, J.C.

2002-01-01

In the framework of studies on the MAVL wastes, the CEA develops containers for middle time wastes storage. This program aims to realize a ''B wastes containers'' demonstrator. A demonstrator is a container, parts of a container or samples which must validate the tests. This document presents the state of the study in the following three chapters: functions description, base data and design choices; presentation of the functional demonstrators; demonstration tests description. (A.L.B.)

Space station environmental control and life support systems test bed program - an overview

Science.gov (United States)

Behrend, Albert F.

As the National Aeronautics and Space Administration (NASA) begins to intensify activities for development of the Space Station, decisions must be made concerning the technical state of the art that will be baselined for the initial Space Station system. These decisions are important because significant potential exists for enhancing system performance and for reducing life-cycle costs. However, intelligent decisions cannot be made without an adequate assessment of new and ready technologies, i.e., technologies which are sufficiently mature to allow predevelopment demonstrations to prove their application feasibility and to quantify the risk associated with their development. Therefore, the NASA has implemented a technology development program which includes the establishment of generic test bed capabilities in which these new technologies and approaches can be tested at the prototype level. One major Space Station subsystem discipline in which this program has been implemented is the environmental control and life support system (ECLSS). Previous manned space programs such as Gemini, Apollo, and Space Shuttle have relied heavily on consumables to provide environmental control and life support services. However, with the advent of a long-duration Space Station, consumables must be reduced within technological limits to minimize Space Station resupply penalties and operational costs. The use of advanced environmental control and life support approaches involving regenerative processes offers the best solution for significant consumables reduction while also providing system evolutionary growth capability. Consequently, the demonstration of these "new technologies" as viable options for inclusion in the baseline that will be available to support a Space Station initial operational capability in the early 1990's becomes of paramount importance. The mechanism by which the maturity of these new regenerative life support technologies will be demonstrated is the Space

77 FR 49063 - Energy Conservation Program: Test Procedures for Residential Dishwashers and Cooking Products

Science.gov (United States)

2012-08-15

... Energy Conservation Program: Test Procedures for Residential Dishwashers and Cooking Products; Proposed...-AC01 Energy Conservation Program: Test Procedures for Residential Dishwashers and Cooking Products... procedures for both dishwashers and conventional cooking products for the measurement of energy use in fan...

Test program for NIS calibration to reactor thermal output in HTTR

International Nuclear Information System (INIS)

Nakagawa, Shigeaki; Shinozaki, Masayuki; Tachibana, Yukio; Kunitomi, Kazuhiko

2000-03-01

Rise-to-power test program for reactor thermal output measurement has been established to calibrate a neutron instrumentation system taking account of the characteristics of the High Temperature Engineering Test Reactor (HTTR). An error of reactor thermal output measurement was evaluated taking account of a configuration of instrumentation system. And the expected dispersion of measurement in the full power operation was evaluated from non-nuclear heat-up of primary coolant up to 213degC. From the evaluation, it was found that an error of reactor thermal output measurement would be less than ±2.0% at the rated power. This report presents the detailed program of rise-to-power test for reactor thermal output measurement and discusses its measurement error. (author)

Plutonium immobilization project development and testing quality assurance program description - February 1999

International Nuclear Information System (INIS)

MacLean, L. M.; Ziemba, J.

1999-01-01

Lawrence Livermore National Laboratory Immobilization Development and Testing organization (LLNL ID and T) is a Participant in the Plutonium Immobilization Project (PIP). The LLNL D and T has lead responsibilities for form characterization and qualification, ceramic form development, process/equipment development with plutonium, and process systems testing and validation for both conversion and immobilization. This work must be performed in accordance with the graded approach of a Quality Assurance (QA) Program. A QA Program has been developed at LLNL to meet the requirements of the DOE/MD Quality Assurance Requirements. The LLNL QA Program consists of a Quality Assurance Program Description (QAPD) and Quality Implementing Procedures. These documents interface and are a subset of the overall PIP QA Program Documents. The PIP QA Program is described in the PIP ID and T QA Plan, PIP QAPD, and QA Procedures. Other Participant Organizations also must document and describe their PIP compliant QA Programs in a QAPD and implementing procedures. The purpose of this LLNL QAPD is to describe the organization, management processes, QA Controls for Grading, functional responsibilities, levels of authority, and interfaces for those managing, performing, and assessing the adequacy of work

Modern multithreading implementing, testing, and debugging multithreaded Java and C++/Pthreads/Win32 programs

CERN Document Server

Carver, Richard H

2005-01-01

Master the essentials of concurrent programming,including testing and debuggingThis textbook examines languages and libraries for multithreaded programming. Readers learn how to create threads in Java and C++, and develop essential concurrent programming and problem-solving skills. Moreover, the textbook sets itself apart from other comparable works by helping readers to become proficient in key testing and debugging techniques. Among the topics covered, readers are introduced to the relevant aspects of Java, the POSIX Pthreads library, and the Windows Win32 Applications Programming Interface.

78 FR 44142 - Modification of Two National Customs Automation Program (NCAP) Tests Concerning Automated...

Science.gov (United States)

2013-07-23

... Customs Automation Program (NCAP) Tests Concerning Automated Commercial Environment (ACE) Document Image... (CBP's) plan to modify the National Customs Automation Program (NCAP) tests concerning document imaging... entry process by reducing the number of data elements required to obtain release for cargo transported...

Sensory submodalities testing in neurolinguistic programming, part of mental training

Directory of Open Access Journals (Sweden)

Vlad Teodor GROSU

2017-03-01

Full Text Available Introduction: this study is part of a larger work, which involves increasing sporting performance by applying mental training techniques – special techniques of neurolinguistic programming. In this case we will discuss some aspects of the test application Jacobson S. (2011. Purpose of study and hypothesis: In neurolinguistic programming (NLP we have studied the relationship between sensory submodalities, in accordance with the Jacobson test (2011. We wanted to check the degree of significance of the mean difference parameters studied and if the materiality result falls within the objective parameters. If ideomotor representations of athletes are completed with multiple sensations of all sensory submodalities such as visual, auditory, kinesthetic, olfactory and gustatory, the possibility of applying the techniques of NLP (neurolinguistic programming will have more effective results. Methods and material: two records were made by using two tests, test1 and test2 on master students of the University “Babes-Bolyai” Cluj-Napoca, from FEFS from APS department (training and sports performance. The statistical indicators were calculated on elements of descriptive statistics and the data is presented using indicators of centrality, location and distribution. Statistical analysis of non-parametric Wilcoxon test was used for sample pairs (data uneven distribution/rank. Materiality tests used was α=0.05 (5%, α=0.01 (1% or α=0.001. Results and deliberations: to detect the correlation between the two variables we used the Spearman rank correlation coefficient (ρ. Statistical analysis was performed using the correlation coefficients Colton’s rule. It was found that no statistically significant differences were observed (p>0.05 in the statistical analysis of sample pairs Jacobson test values (times T1-T2. This is a result of the short timeframe – just one month – for objectives reasons. However, many of them appear in a good and a very good

Physical Education Experimental Program to Test the Effect on Perceived Competence

OpenAIRE

Edin Brankovic; Muriz Hadzikadunic

2017-01-01

The first purpose of this study was to test effect of multidisciplinary and holistic experimental program (EP) in physical education program effect on the soul need perceived competence. The second purpose of this study was to analyse the relationship between attitudes of perceived competence in the experimental group before and after the application of program, mostly due the theoretical reason that perceived competence is predictor of Flow. The data was collected from 74 students of the 8th...

75 FR 26183 - Procedures for Transportation Workplace Drug and Alcohol Testing Programs

Science.gov (United States)

2010-05-11

... 2105-AE01 Procedures for Transportation Workplace Drug and Alcohol Testing Programs AGENCY: Office of...: For program issues, Bohdan Baczara, Office of Drug and Alcohol Policy and Compliance, 1200 New Jersey... of Federal Regulations, as follows: [[Page 26184

Testing and development of electric vehicle batteries for EPRI Electric Transportation Program

Science.gov (United States)

1985-11-01

Argonne National Laboratory conducted an electric-vehicle battery testing and development program for the Electric Power Research Institute. As part of this program, eighteen battery modules previously developed by Johnson Controls, Inc. were tested. This type of battery (EV-2300 - an improved state-of-the-art lead-acid battery) was designed specifically for improved performance, range, and life in electric vehicles. In order to obtain necessary performance data, the batteries were tested under various duty cycles typical of normal service. This program, supported by the Electric Power Research Institute, consisted of three tasks: determination of the effect of cycle life vs peak power and rest period, determination of the impact of charge method on cycle life, and evaluation of the EV-2300 battery system. Two supporting studies were also carried out: one on thermal management of electric-vehicle batteries and one on enhanced utilization of active material in lead-acid batteries.

Test program element II blanket and shield thermal-hydraulic and thermomechanical testing, experimental facility survey

Energy Technology Data Exchange (ETDEWEB)

Ware, A.G.; Longhurst, G.R.

1981-12-01

This report presents results of a survey conducted by EG and G Idaho to determine facilities available to conduct thermal-hydraulic and thermomechanical testing for the Department of Energy Office of Fusion Energy First Wall/Blanket/Shield Engineering Test Program. In response to EG and G queries, twelve organizations (in addition to EG and G and General Atomic) expressed interest in providing experimental facilities. A variety of methods of supplying heat is available.

Test program element II blanket and shield thermal-hydraulic and thermomechanical testing, experimental facility survey

International Nuclear Information System (INIS)

Ware, A.G.; Longhurst, G.R.

1981-12-01

This report presents results of a survey conducted by EG and G Idaho to determine facilities available to conduct thermal-hydraulic and thermomechanical testing for the Department of Energy Office of Fusion Energy First Wall/Blanket/Shield Engineering Test Program. In response to EG and G queries, twelve organizations (in addition to EG and G and General Atomic) expressed interest in providing experimental facilities. A variety of methods of supplying heat is available

The US Army Foreign Comparative Test fuel cell program

Science.gov (United States)

Bostic, Elizabeth; Sifer, Nicholas; Bolton, Christopher; Ritter, Uli; Dubois, Terry

The US Army RDECOM initiated a Foreign Comparative Test (FCT) Program to acquire lightweight, high-energy dense fuel cell systems from across the globe for evaluation as portable power sources in military applications. Five foreign companies, including NovArs, Smart Fuel Cell, Intelligent Energy, Ballard Power Systems, and Hydrogenics, Inc., were awarded competitive contracts under the RDECOM effort. This paper will report on the status of the program as well as the experimental results obtained from one of the units. The US Army has interests in evaluating and deploying a variety of fuel cell systems, where these systems show added value when compared to current power sources in use. For low-power applications, fuel cells utilizing high-energy dense fuels offer significant weight savings over current battery technologies. This helps reduce the load a solider must carry for longer missions. For high-power applications, the low operating signatures (acoustic and thermal) of fuel cell systems make them ideal power generators in stealth operations. Recent testing has been completed on the Smart Fuel Cell A25 system that was procured through the FCT program. The "A-25" is a direct methanol fuel cell hybrid and was evaluated as a potential candidate for soldier and sensor power applications.

Field Test of Advanced Duct-Sealing Technologies Within the Weatherization Assistance Program

Energy Technology Data Exchange (ETDEWEB)

Ternes, MP

2001-12-05

A field test of an aerosol-spray duct-sealing technology and a conventional, best-practice approach was performed in 80 homes to determine the efficacy and programmatic needs of the duct-sealing technologies as applied in the U.S. Department of Energy Weatherization Assistance Program. The field test was performed in five states: Iowa, Virginia, Washington, West Virginia, and Wyoming. The study found that, compared with the best-practice approach, the aerosol-spray technology is 50% more effective at sealing duct leaks and can potentially reduce labor time and costs for duct sealing by 70%, or almost 4 crew-hours. Further study to encourage and promote use of the aerosol-spray technology within the Weatherization Assistance Program is recommended. A pilot test of full production weatherization programs using the aerosol-spray technology is recommended to develop approaches for integrating this technology with other energy conservation measures and minimizing impacts on weatherization agency logistics. In order to allow or improve adoption of the aerosol spray technology within the Weatherization Assistance Program, issues must be addressed concerning equipment costs, use of the technology under franchise arrangements with Aeroseal, Inc. (the holders of an exclusive license to use this technology), software used to control the equipment, safety, and training. Application testing of the aerosol-spray technology in mobile homes is also recommended.

76 FR 34246 - Automated Commercial Environment (ACE); Announcement of National Customs Automation Program Test...

Science.gov (United States)

2011-06-13

... Environment (ACE); Announcement of National Customs Automation Program Test of Automated Procedures for In... Customs Automation Program (NCAP) test relating to highway movements of commercial goods that are transported in-bond through the United States from one point in Canada to another point in Canada. The NCAP...

A quality assurance program for nuclear power reactor materials tests at the Ford nuclear reactor

International Nuclear Information System (INIS)

Burn, R.R.

1989-01-01

The University of Michigan Nuclear Reactor Laboratory Quality Assurance Program has been established to assure that materials testing services provided to electric utilities produce accurate results in accordance with industry standards, sound engineering practice, and customer requirements. The program was prepared to comply with applicable requirements of 10CFR50, Appendix B, of the Code of Federal Regulations and a standard of the American National Standards Institute (ANSI), N45.2. The paper discusses the quality assurance program applicability, organization, qualification and training of personnel, material identification and control, examination and testing, measuring and test equipment, nonconforming test equipment, records, audits, and distribution

78 FR 4015 - Energy Conservation Program: Test Procedures for Microwave Ovens

Science.gov (United States)

2013-01-18

... Conservation Program: Test Procedures for Microwave Ovens AGENCY: Office of Energy Efficiency and Renewable... microwave ovens. That SNOPR proposed amendments to the DOE test procedure to incorporate provisions from the... energy use of products that combine a microwave oven with other appliance functionality, as well as minor...

Risk Management Program Application for the Component Test Capability

International Nuclear Information System (INIS)

Stephanie L. Austad; Jeffrey D. Bryan

2009-01-01

This paper documents the application of the risk management program requirements to Component Test Capability (CTC) Project activities for each CTC alternative. In particular, DOE O 413.3A, 'Program and Project Management for the Acquisition of Capital Assets,' and DOE G 413.3-7, 'Risk Management Guide for Project Management,' will apply in the event that Alternative 4, Single, Standalone Component Test Facility (CTF), is selected and approved. As such, it is advisable to begin planning to meet the associated Department of Energy (DOE) requirements and guidance as early in the acquisition process as practicable. This white paper is intended to assist in this planning and to support associated decision-making activities. Nontechnical risks associated with each alternative will be identified to support the Next Generation Nuclear Plant (NGNP) CTC alternatives analysis. Technical risks are assumed to be addressed through the Technology Development Risk Management modeling process and are inherent to the alternatives

The RERTR [Reduced Enrichment Research and Test Reactor] program:

International Nuclear Information System (INIS)

Travelli, A.

1987-01-01

The progress of the Reduced Enrichment Research and Test Reactor (RERTR) program is described. After a brief summary of the results which the RERTR program, in collaboration with its many international partners, had achieved by the end of 1986, the activities, results and new developments which ocurred in 1987 are reviewed. Irradiation of the second miniplate series, concentrating on U 3 Si 2 -Al and U 3 Si-Al fuels was completed and postirradiation examinations were performed on many of its miniplates. The whole-core ORR demonstration with U 3 Si 2 -Al fuel at 4.8 g U/cm 3 was completed at the end of March with excellent results and with 29 elements estimated to have reached at least 40 % average burnup. Good progress was made in the area of LEU usage for the production of fission 99 Mo, and in the coordination of safety evaluations related to LEU conversions of U.S. university reactors. Planned activities include testing and demonstrating advanced fuels intended to allow use of reduced enrichment uranium in very-high-performance reactors. Two candidate fuels are U 3 Si-Al with 19.75 % enrichment and U 3 Si 2 -Al with 45 % enrichment. Demonstration of these fuels will include irradiation of full-size elements and, possibly, a full-core demonstration. Achievement of the final program goals is still projected for 1990. This progress could not have been possible without the close international cooperation which has existed from the beginning, and which is essential to the ultimate success of the RERTR program. (Author)

Optimized periodic verification testing blended risk and performance-based MOV inservice test program an application of ASME code case OMN-1

Energy Technology Data Exchange (ETDEWEB)

Sellers, C.; Fleming, K.; Bidwell, D.; Forbes, P. [and others

1996-12-01

This paper presents an application of ASME Code Case OMN-1 to the GL 89-10 Program at the South Texas Project Electric Generating Station (STPEGS). Code Case OMN-1 provides guidance for a performance-based MOV inservice test program that can be used for periodic verification testing and allows consideration of risk insights. Blended probabilistic and deterministic evaluation techniques were used to establish inservice test strategies including both test methods and test frequency. Described in the paper are the methods and criteria for establishing MOV safety significance based on the STPEGS probabilistic safety assessment, deterministic considerations of MOV performance characteristics and performance margins, the expert panel evaluation process, and the development of inservice test strategies. Test strategies include a mix of dynamic and static testing as well as MOV exercising.

Optimized periodic verification testing blended risk and performance-based MOV inservice test program an application of ASME code case OMN-1

International Nuclear Information System (INIS)

Sellers, C.; Fleming, K.; Bidwell, D.; Forbes, P.

1996-01-01

This paper presents an application of ASME Code Case OMN-1 to the GL 89-10 Program at the South Texas Project Electric Generating Station (STPEGS). Code Case OMN-1 provides guidance for a performance-based MOV inservice test program that can be used for periodic verification testing and allows consideration of risk insights. Blended probabilistic and deterministic evaluation techniques were used to establish inservice test strategies including both test methods and test frequency. Described in the paper are the methods and criteria for establishing MOV safety significance based on the STPEGS probabilistic safety assessment, deterministic considerations of MOV performance characteristics and performance margins, the expert panel evaluation process, and the development of inservice test strategies. Test strategies include a mix of dynamic and static testing as well as MOV exercising

Review of present groundwater monitoring programs at the Nevada Test Site

International Nuclear Information System (INIS)

Hershey, R.L.; Gillespie, D.

1993-09-01

Groundwater monitoring at the Nevada Test Site (NTS) is conducted to detect the presence of radionuclides produced by underground nuclear testing and to verify the quality and safety of groundwater supplies as required by the State of Nevada and federal regulations, and by U.S. Department of Energy (DOE) Orders. Groundwater is monitored at water-supply wells and at other boreholes and wells not specifically designed or located for traditional groundwater monitoring objectives. Different groundwater monitoring programs at the NTS are conducted by several DOE Nevada Operations Office (DOE/NV) contractors. Presently, these individual groundwater monitoring programs have not been assessed or administered under a comprehensive planning approach. Redundancy exists among the programs in both the sampling locations and the constituents analyzed. Also, sampling for certain radionuclides is conducted more frequently than required. The purpose of this report is to review the existing NTS groundwater monitoring programs and make recommendations for modifying the programs so a coordinated, streamlined, and comprehensive monitoring effort may be achieved by DOE/NV. This review will be accomplished in several steps. These include: summarizing the present knowledge of the hydrogeology of the NTS and the potential radionuclide source areas for groundwater contamination; reviewing the existing groundwater monitoring programs at the NTS; examining the rationale for monitoring and the constituents analyzed; reviewing the analytical methods used to quantify tritium activity; discussing monitoring network design criteria; and synthesizing the information presented and making recommendations based on the synthesis. This scope of work was requested by the DOE/NV Hydrologic Resources Management Program (HRMP) and satisfies the 1993 (fiscal year) HRMP Groundwater Monitoring Program Review task

Tuberculosis Infection in Urban Adolescents: Results of a School-Based Testing Program.

Science.gov (United States)

Barry, M. Anita; And Others

1990-01-01

Discusses a tuberculosis skin testing program introduced for seventh and tenth grade students in Boston (Massachusetts) public schools. Positivity rate was significantly higher in tenth grade students. Among those testing positive, the majority were born outside the United States. Results suggest that testing may identify a significant number of…

NRC review of passive reactor design certification testing programs: Overview, progress, and regulatory perspective

Energy Technology Data Exchange (ETDEWEB)

Levin, A.E.

1995-09-01

New reactor designs, employing passive safety systems, are currently under development by reactor vendors for certification under the U.S. Nuclear Regulatory Commission`s (NRC`s) design certification rule. The vendors have established testing programs to support the certification of the passive designs, to meet regulatory requirements for demonstration of passive safety system performance. The NRC has, therefore, developed a process for the review of the vendors` testing programs and for incorporation of the results of those reviews into the safety evaluations for the passive plants. This paper discusses progress in the test program reviews, and also addresses unique regulatory aspects of those reviews.

78 FR 12259 - Unmanned Aircraft System Test Site Program

Science.gov (United States)

2013-02-22

... addressing potential UAS privacy concerns, as set out herein, contact Gregory C. Carter, Office of the Chief... address privacy concerns relating to the operation of the test site program, the FAA intends to include in... among policymakers, privacy advocates, and the industry regarding broader questions concerning the use...

JOYO modification program for demonstration tests of FBR innovative technology development

International Nuclear Information System (INIS)

Yoshimi, H.; Hachiya, Y.

1990-01-01

A plan is under way at PNC to modify the experimental fast reactor JOYO. The project is called MARK-III (MK-III) program. The purpose of MK-III is to expand the function of JOYO, and to make it possible to receive demonstration tests of new or high level technologies for FBR development. The MK-III program consists of two main modifications: conversion to a highly efficient irradiation facility; and a modification for demonstration testing of new technologies and concepts that have a high potential to reduce FBR plant construction cost, to evaluate plant reliability and to improve plant safety. These modifications are scheduled to start in 1991

FY11 Facility Assessment Study for Aeronautics Test Program

Science.gov (United States)

Loboda, John A.; Sydnor, George H.

2013-01-01

This paper presents the approach and results for the Aeronautics Test Program (ATP) FY11 Facility Assessment Project. ATP commissioned assessments in FY07 and FY11 to aid in the understanding of the current condition and reliability of its facilities and their ability to meet current and future (five year horizon) test requirements. The principle output of the assessment was a database of facility unique, prioritized investments projects with budgetary cost estimates. This database was also used to identify trends for the condition of facility systems.

Model design for Large-Scale Seismic Test Program at Hualien, Taiwan

International Nuclear Information System (INIS)

Tang, H.T.; Graves, H.L.; Chen, P.C.

1991-01-01

The Large-Scale Seismic Test (LSST) Program at Hualien, Taiwan, is a follow-on to the soil-structure interaction (SSI) experiments at Lotung, Taiwan. The planned SSI studies will be performed at a stiff soil site in Hualien, Taiwan, that historically has had slightly more destructive earthquakes in the past than Lotung. The LSST is a joint effort among many interested parties. Electric Power Research Institute (EPRI) and Taipower are the organizers of the program and have the lead in planning and managing the program. Other organizations participating in the LSST program are US Nuclear Regulatory Commission (NRC), the Central Research Institute of Electric Power Industry (CRIEPI), the Tokyo Electric Power Company (TEPCO), the Commissariat A L'Energie Atomique (CEA), Electricite de France (EdF) and Framatome. The LSST was initiated in January 1990, and is envisioned to be five years in duration. Based on the assumption of stiff soil and confirmed by soil boring and geophysical results the test model was designed to provide data needed for SSI studies covering: free-field input, nonlinear soil response, non-rigid body SSI, torsional response, kinematic interaction, spatial incoherency and other effects. Taipower had the lead in design of the test model and received significant input from other LSST members. Questions raised by LSST members were on embedment effects, model stiffness, base shear, and openings for equipment. This paper describes progress in site preparation, design and construction of the model and development of an instrumentation plan

78 FR 7460 - Stakeholder Meeting on the Nationally Recognized Testing Laboratory Program

Science.gov (United States)

2013-02-01

...] Stakeholder Meeting on the Nationally Recognized Testing Laboratory Program AGENCY: Occupational Safety and Health Administration (OSHA), Labor. ACTION: Notice of stakeholder meeting. SUMMARY: OSHA invites interested parties to attend an informal stakeholder meeting concerning Nationally Recognized Testing...

Physical protection

International Nuclear Information System (INIS)

Myre, W.C.; DeMontmollin, J.M.

1989-01-01

Serious concern about physical protection of nuclear facilities began around 1972. R and D was initiated at Sandia National Laboratories which had developed techniques to protect weapons for many years. Special vehicles, convoy procedures, and a communications system previously developed for weapons shipments were improved and extended for shipments of other sensitive materials. Barriers, perimeter alarms, portal and internal control systems were developed, tested, and published in handbooks and presented at symposia. Training programs were initiated for U.S. and foreign personnel. Containment and surveillance techniques were developed for the IAEA. Presently emphasis is on computer security, active barriers, and techniques to prevent theft or sabotage by ''insiders''

History of physical security R and D

International Nuclear Information System (INIS)

Myre, W.C.; De Montmollin, J.M.

1987-01-01

Serious concern about physical protection of nuclear facilities began around 1972. R and D was initiated at Sandia National Laboratory which had developed techniques to protect weapons for many years. Special vehicles, convoy procedures, and a communications system previously developed for weapons shipments were improved and extended for shipments of other sensitive materials. Barriers, perimeter alarms, portal and internal control systems were developed, tested, and published in handbooks and presented at symposia. Training programs were initiated for U.S. and foreign personnel. Containment and surveillance techniques were developed for the IAEA. Presently emphasis is on computer security, active barriers, and techniques to prevent theft or sabotage by ''insiders''

Unit and integration testing of Lustre programs: a case study from the nuclear industry

International Nuclear Information System (INIS)

Thevenod-Fosse, P.

1998-01-01

LUSTRE belongs to the class of synchronous data flow languages which have been designed for programming reactive and real-time systems having safety-critical requirements. It is implemented in the SCADE tool. SCADE is a software development environment for real-time systems which consists of a graphical and textual editor, and a C code generator. In previous work, a testing approach specific to LUSTRE programs has been defined, which may be applied at either the unit or integration testing levels of a gradual testing process. The paper reports on an industrial case study we have performed to exemplify the feasibility of the testing strategy. The software module, called SRIC (Source Range Instrumentation channel), was developed by SCHNEIDER ELECTRIC in the SCADE environment. SRIC is extracted from a monitoring software system of a nuclear reactor: it approximates 2600 lines of C code automatically generated by SCADE. Section 2 outlines the testing strategy. Then, Section 3 presents the results related to the program SRIC, for which four testing levels were defined (unit testing followed by three successive integration testing levels). First conclusions and direction for future work are proposed in Section 4. (author)

Oregon state university's advanced plant experiment (APEX) AP1000 integral facility test program

International Nuclear Information System (INIS)

Reyes, J.N.; Groome, J.T.; Woods, B.G.; Young, E.; Abel, K.; Wu, Q.

2005-01-01

Oregon State University (OSU) has recently completed a three year study of the thermal hydraulic behavior of the Westinghouse AP1000 passive safety systems. Eleven Design Basis Accident (DBA) scenarios, sponsored by the U.S. Department of Energy (DOE) with technical support from Westinghouse Electric, were simulated in OSU's Advanced Plant Experiment (APEX)-1000. The OSU test program was conducted within the purview of the requirements of 10CFR50 Appendix B, NQA-1 and 10 CFR 21 and the test data was used to provide benchmarks for computer codes used in the final design approval of the AP1000. In addition to the DOE certification testing, OSU conducted eleven confirmatory tests for the U.S. Nuclear Regulatory Commission. This paper presents the test program objectives, a description of the APEX-1000 test facility and an overview of the test matrix that was conducted in support of plant certification. (authors)

U.S. advanced accelerator applications program: plans to develop and test waste transmutation technologies

International Nuclear Information System (INIS)

Van Tuyle, G.; Bennett, D.; Arthur, E.; Cappiello, M.; Finck, P.; Hill, D.; Herczeg, J.; Goldner, F.

2001-01-01

The primary mission of the U.S. Advanced Accelerator Applications (AAA) Program is to establish a national nuclear technology research capability that can demonstrate accelerator-based transmutation of waste and conduct transmutation research while at the same time providing a capability for the production of tritium if required. The AAA Program was created during fiscal year 2001 from the Accelerator Transmutation of Waste (ATW) Program and the Accelerator Production of Tritium (APT) Project. This paper describes the new AAA Program, as well as its two major components: development and testing of waste transmutation technologies and construction of an integrated accelerator-driven test facility (ADTF). (author)

41 CFR 300-80.4 - How many test programs may be authorized by GSA throughout the government?

Science.gov (United States)

2010-07-01

... 41 Public Contracts and Property Management 4 2010-07-01 2010-07-01 false How many test programs may be authorized by GSA throughout the government? 300-80.4 Section 300-80.4 Public Contracts and... TEST PROGRAMS § 300-80.4 How many test programs may be authorized by GSA throughout the government? No...

Evaluation of a Positive Youth Development Program Based on the Repertory Grid Test

Directory of Open Access Journals (Sweden)

Daniel T. L. Shek

2012-01-01

Full Text Available The repertory grid test, based on personal construct psychology, was used to evaluate the effectiveness of Project P.A.T.H.S. (Positive Adolescent Training through Holistic Social Programmes in Hong Kong. One hundred and four program participants (n=104 were randomly invited to complete a repertory grid based on personal construct theory in order to provide both quantitative and qualitative data for measuring self-identity changes after joining the program. Findings generally showed that the participants perceived that they understood themselves better and had stronger resilience after joining the program. Participants also saw themselves as closer to their ideal selves and other positive role figures (but farther away from a loser after joining the program. This study provides additional support for the effectiveness of the Tier 1 Program of Project P.A.T.H.S. in the Chinese context. This study also shows that the repertory grid test is a useful evaluation method to measure self-identity changes in participants in positive youth development programs.

EBR-2 [Experimental Breeder Reactor-2], IFR [Integral Fast Reactor] prototype testing programs

International Nuclear Information System (INIS)

Lehto, W.K.; Sackett, J.I.; Lindsay, R.W.; Planchon, H.P.; Lambert, J.D.B.

1990-01-01

The Experimental Breeder Reactor-2 (EBR-2) is a sodium cooled power reactor supplying about 20 MWe to the Idaho National Engineering Laboratory (INEL) grid and, in addition, is the key component in the development of the Integral Fast Reactor (IFR). EBR-2's testing capability is extensive and has seen four major phases: (1) demonstration of LMFBR power plant feasibility, (2) irradiation testing for fuel and material development. (3) testing the off-normal performance of fuel and plant systems and (4) operation as the IFR prototype, developing and demonstrating the IFR technology associated with fuel and plant design. Specific programs being carried out in support of the IFR include advanced fuels and materials development and component testing. This paper discusses EBR-2 as the IFR prototype and the associated testing programs. 29 refs

Meta-Analysis of Data from the Submarine Ventilation Doctrine Test Program

National Research Council Canada - National Science Library

Hoover, J

1998-01-01

.... The Submarine Ventilation Doctrine Test Program was developed to address submarine-specific issues regarding the use of ventilation systems to control smoke and heat movement, maintain habitability...

Results of the motor-operated valve engineering and testing program

International Nuclear Information System (INIS)

Black, B.R.

1994-01-01

The Texas Utilities Electric Company (TU Electric) motor-operated valve (MOV) program for implementing the recommendations of Generic Letter 89-10 has typically included the following: refurbishing each actuator, verifying each actuator's as-built configuration, testing each actuator's motor on a dynamometer, testing each actuator's torque spring pack (which is used to control the torque developed), testing each fully refurbished and reassembled actuator on a torque test stand, and testing as many MOVs as practicable both without fluid flow through the valve and with the maximum test conditions reasonably achievable (static and differential pressures (DP) conditions, respectively). Test data are acquired at 1,000 samples per second for stem thrust, stem torque, stem position, actuator compensator spring pack deflection, actuator torque spring pack deflection, motor current, motor voltage, motor three-phase power, valve upstream pressure, and valve downstream pressure, wherever practicable

77 FR 28673 - Energy Conservation Program for Consumer Products: Test Procedures for Residential Furnace Fans

Science.gov (United States)

2012-05-15

... multipliers based on climate, consumer behavior assumptions, and product characteristics (e.g., multi-stage or... Conservation Program for Consumer Products: Test Procedures for Residential Furnace Fans; Proposed Rule #0;#0... Conservation Program for Consumer Products: Test Procedures for Residential Furnace Fans AGENCY: Office of...

An overview of the Nuclear Electric Propulsion Space Test Program (NEPSTP) satellite

International Nuclear Information System (INIS)

Voss, S.S.; Reynolds, E.L.

1994-01-01

Early in 1992 the idea of purchasing a Russian designed and fabricated space reactor power system and integrating it with a US designed satellite went from fiction to reality with the purchase of the first two Topaz II reactors by the Strategic Defense Initiative Organization (now the Ballistic Missile Defense Organization (BMDO)). The New Mexico Alliance was formed to establish a ground test facility in which to perform nonnuclear systems testing of the Topaz II, and to evaluate the Topaz II system for flight testing with respect to safety, performance, and operability. In conjunction, SDIO requested that the Applied Physics Laboratory in Laurel, MD propose a mission and design a satellite in which the Topaz II could be used as the power source. The outcome of these two activities was the design of the Nuclear Electric Propulsion Space Test Program (NEPSTP) satellite which combines a modified Russian Topaz II power system with a US designed satellite to achieve a specified mission. Due to funding reduction within the SDIO, the Topaz II flight program was postponed indefinitely at the end of Fiscal year 1993. The purpose of this paper is to present an overview of the NEPSTP mission and the satellite design at the time the flight program ended

76 FR 47178 - Energy Efficiency Program: Test Procedure for Lighting Systems (Luminaires)

Science.gov (United States)

2011-08-04

... DEPARTMENT OF ENERGY [Docket Number EERE-2011-BT-TP-0041] RIN 1904-AC50 Energy Efficiency Program: Test Procedure for Lighting Systems (Luminaires) AGENCY: Office of Energy Efficiency and Renewable... (``DOE'' or the ``Department'') is currently evaluating energy efficiency test procedures for luminaires...

Iterative Evaluation in a Mobile Counseling and Testing Program to Reach People of Color at Risk for HIV--New Strategies Improve Program Acceptability, Effectiveness, and Evaluation Capabilities

Science.gov (United States)

Spielberg, Freya; Kurth, Ann; Reidy, William; McKnight, Teka; Dikobe, Wame; Wilson, Charles

2011-01-01

This article highlights findings from an evaluation that explored the impact of mobile versus clinic-based testing, rapid versus central-lab based testing, incentives for testing, and the use of a computer counseling program to guide counseling and automate evaluation in a mobile program reaching people of color at risk for HIV. The program's…

A systematic method for identifying vital areas at complex nuclear facilities.

Energy Technology Data Exchange (ETDEWEB)

Beck, David Franklin; Hockert, John

2005-05-01

Identifying the areas to be protected is an important part of the development of measures for physical protection against sabotage at complex nuclear facilities. In June 1999, the International Atomic Energy Agency published INFCIRC/225/Rev.4, 'The Physical Protection of Nuclear Material and Nuclear Facilities.' This guidance recommends that 'Safety specialists, in close cooperation with physical protection specialists, should evaluate the consequences of malevolent acts, considered in the context of the State's design basis threat, to identify nuclear material, or the minimum complement of equipment, systems or devices to be protected against sabotage.' This report presents a structured, transparent approach for identifying the areas that contain this minimum complement of equipment, systems, and devices to be protected against sabotage that is applicable to complex nuclear facilities. The method builds upon safety analyses to develop sabotage fault trees that reflect sabotage scenarios that could cause unacceptable radiological consequences. The sabotage actions represented in the fault trees are linked to the areas from which they can be accomplished. The fault tree is then transformed (by negation) into its dual, the protection location tree, which reflects the sabotage actions that must be prevented in order to prevent unacceptable radiological consequences. The minimum path sets of this fault tree dual yield, through the area linkage, sets of areas, each of which contains nuclear material, or a minimum complement of equipment, systems or devices that, if protected, will prevent sabotage. This method also provides guidance for the selection of the minimum path set that permits optimization of the trade-offs among physical protection effectiveness, safety impact, cost and operational impact.

75 FR 8526 - Procedures for Transportation Workplace Drug and Alcohol Testing Programs

Science.gov (United States)

2010-02-25

... 2105-AD64 Procedures for Transportation Workplace Drug and Alcohol Testing Programs AGENCY: Office of... required method. However, in response to comments requesting additional flexibility in testing methods, the... may increase flexibility and lower costs for employers who choose to use them over more expensive...

PWR Users Group 10 CFR 61 Waste Form Requirements Compliance Test Program

International Nuclear Information System (INIS)

Rosenlof, R.C.

1985-01-01

In January of 1984, a PWR Users Group was formed to initiate a 10 CFR 61 Waste Form Requirements Compliance Test Program on a shared cost basis. The original Radwaste Solidification Systems sold by ATCOR ENGINEERED SYSTEMS, INC. to the utilities were required to produce a free-standing monolith with no free water. None of the other requirements of 10 CFR 61 had to be met. Current regulations, however, have substantially expanded the scope of the waste form acceptance criteria. These new criteria required that generators of radioactive waste demonstrate the ability to produce waste forms which meet certain chemical and physical requirements. This paper will present the test program used and the results obtained to insure 10 CFR 61 compliance of the three (3) typical waste streams generated by the ATCOR PWR Users Group's plants. The primary objective of the PWR Users Group was not to maximize waste loading within the masonry cement solidification media, but to insure that the users Radwaste Solidification System is capable of producing waste forms which meet the waste form criteria of 10 CFR 61. A description of the laboratory small sample certification program and the actual full scale pilot plant verification approach used is included in this paper. Also included is a discussion of the development of a Process Control Program to ensure the reproducibility of the test results with actual waste

Hydrologic resources management program and underground test area operable unit fy 1997

Energy Technology Data Exchange (ETDEWEB)

Smith, D. F., LLNL

1998-05-01

This report present the results of FY 1997 technical studies conducted by the Lawrence Livermore National Laboratory (LLNL) as part of the Hydrology and Radionuclide Migration Program (HRMP) and Underground Test Area Operable Unit (UGTA). The HRMP is sponsored by the US Department of Energy to assess the environmental (radiochemical and hydrologic) consequences of underground nuclear weapons testing at the Nevada Test Site.

US DOE Regional Test Centers Program - 2016 Annual Report.

Energy Technology Data Exchange (ETDEWEB)

Stein, Joshua [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-05-01

The US Department of Energy’s Regional Test Center (RTC) program provides outdoor validation and bankability data for innovative solar technologies at five sites across the US representing a range of climate conditions. Data helps get new technologies to market faster and improves US industry competitiveness. Managed by Sandia National Laboratories and the National Renewable Energy Laboratory (NREL), the RTC program partners with US manufacturers of photovoltaic (PV) technologies, including modules, inverters, and balance-of-system equipment. The study is collaborative, with manufacturers (also known as RTC industry partners) and the national labs working together on a system design and validation strategy that meets a clearly defined set of performance and reliability objectives.

Evaluating the Navy’s Enlisted Accessions Testing Program Based on Future Talent Needs

Science.gov (United States)

2017-03-01

NAVY’S ENLISTED ACCESSIONS TESTING PROGRAM BASED ON FUTURE TALENT NEEDS by Shereka F. Riley March 2017 Thesis Advisor: Joseph Sullivan Co...REPORT TYPE AND DATES COVERED Master’s thesis 4. TITLE AND SUBTITLE EVALUATING THE NAVY’S ENLISTED ACCESSIONS TESTING PROGRAM BASED ON FUTURE TALENT ...public release. Distribution is unlimited. 12b. DISTRIBUTION CODE 13. ABSTRACT (maximum 200 words) In recent years, non-defense related industries

Cargo container inspection test program at ARPA's Nonintrusive Inspection Technology Testbed

Science.gov (United States)

Volberding, Roy W.; Khan, Siraj M.

1994-10-01

An x-ray-based cargo inspection system test program is being conducted at the Advanced Research Project Agency (ARPA)-sponsored Nonintrusive Inspection Technology Testbed (NITT) located in the Port of Tacoma, Washington. The test program seeks to determine the performance that can be expected from a dual, high-energy x-ray cargo inspection system when inspecting ISO cargo containers. This paper describes an intensive, three-month, system test involving two independent test groups, one representing the criminal smuggling element and the other representing the law enforcement community. The first group, the `Red Team', prepares ISO containers for inspection at an off-site facility. An algorithm randomly selects and indicates the positions and preparation of cargoes within a container. The prepared container is dispatched to the NITT for inspection by the `Blue Team'. After in-gate processing, it is queued for examination. The Blue Team inspects the container and decides whether or not to pass the container. The shipment undergoes out-gate processing and returns to the Red Team. The results of the inspection are recorded for subsequent analysis. The test process, including its governing protocol, the cargoes, container preparation, the examination and results available at the time of submission are presented.

ITERATIVE EVALUATION IN A MOBILE COUNSELING AND TESTING PROGRAM TO REACH PEOPLE OF COLOR AT RISK FOR HIV—NEW STRATEGIES IMPROVE PROGRAM ACCEPTABILITY, EFFECTIVENESS, AND EVALUATION CAPABILITIES

Science.gov (United States)

Spielberg, Freya; Kurth, Ann; Reidy, William; McKnight, Teka; Dikobe, Wame; Wilson, Charles

2016-01-01

This article highlights findings from an evaluation that explored the impact of mobile versus clinic-based testing, rapid versus central-lab based testing, incentives for testing, and the use of a computer counseling program to guide counseling and automate evaluation in a mobile program reaching people of color at risk for HIV. The program’s results show that an increased focus on mobile outreach using rapid testing, incentives and health information technology tools may improve program acceptability, quality, productivity and timeliness of reports. This article describes program design decisions based on continuous quality assessment efforts. It also examines the impact of the Computer Assessment and Risk Reduction Education computer tool on HIV testing rates, staff perception of counseling quality, program productivity, and on the timeliness of evaluation reports. The article concludes with a discussion of implications for programmatic responses to the Centers for Disease Control and Prevention’s HIV testing recommendations. PMID:21689041

Creating a test blueprint for a progress testing program: A paired-comparisons approach.

Science.gov (United States)

von Bergmann, HsingChi; Childs, Ruth A

2018-03-01

Creating a new testing program requires the development of a test blueprint that will determine how the items on each test form are distributed across possible content areas and practice domains. To achieve validity, categories of a blueprint are typically based on the judgments of content experts. How experts judgments are elicited and combined is important to the quality of resulting test blueprints. Content experts in dentistry participated in a day-long faculty-wide workshop to discuss, refine, and confirm the categories and their relative weights. After reaching agreement on categories and their definitions, experts judged the relative importance between category pairs, registering their judgments anonymously using iClicker, an audience response system. Judgments were combined in two ways: a simple calculation that could be performed during the workshop and a multidimensional scaling of the judgments performed later. Content experts were able to produce a set of relative weights using this approach. The multidimensional scaling yielded a three-dimensional model with the potential to provide deeper insights into the basis of the experts' judgments. The approach developed and demonstrated in this study can be applied across academic disciplines to elicit and combine content experts judgments for the development of test blueprints.

Growth in Means-Tested Programs and Tax Credits for Low-Income Households

Science.gov (United States)

Carrington, William; Dahl, Molly; Falk, Justin

2013-01-01

The federal government devotes roughly one-sixth of its spending to 10 major means-tested programs and tax credits, which provide cash payments or assistance in obtaining health care, food, housing, or education to people with relatively low income or few assets. Those programs and credits consist of the following: (1) Medicaid; (2) the low-income…

Meta-Analysis of Data from the Submarine Ventilation Doctrine Test Program

National Research Council Canada - National Science Library

Hoover, J

1998-01-01

... in critical spaces or provide safe ingresslegress routes. This program sponsored six test series between January 1995 and August 1996 and made specific recommendations for the use of ventilation during submarine firefighting...

HIV Testing Among Young People Aged 16-24 in South Africa: Impact of Mass Media Communication Programs.

Science.gov (United States)

Do, Mai; Figueroa, Maria Elena; Lawrence Kincaid, D

2016-09-01

Knowing one's serostatus is critical in the HIV prevention, care and treatment continuum. This study examines the impact of communication programs on HIV testing in South Africa. Data came from 2204 young men and women aged 16-24 who reported to be sexually active in a population based survey. Structural equation modeling was used to test the directions and causal pathways between communication program exposure, HIV testing discussion, and having a test in the last 12 months. Bivariate and multivariate probit regressions provided evidence of exogeneity of communication exposure and the two HIV-related outcomes. One in three sampled individuals had been tested in the last 12 months. Communication program exposure only had an indirect effect on getting tested by encouraging young people to talk about testing. The study suggests that communication programs may create an environment that supports open HIV-related discussions and may have a long-term impact on behavior change.

Validation of Linguistic and Communicative Oral Language Tests for Spanish-English Bilingual Programs.

Science.gov (United States)

Politzer, Robert L.; And Others

1983-01-01

The development, administration, and scoring of a communicative test and its validation with tests of linguistic and sociolinguistic competence in English and Spanish are reported. Correlation with measures of home language use and school achievement are also presented, and issues of test validation for bilingual programs are discussed. (MSE)

Estimation of an Examinee's Ability in the Web-Based Computerized Adaptive Testing Program IRT-CAT

Directory of Open Access Journals (Sweden)

Yoon-Hwan Lee

2006-11-01

Full Text Available We developed a program to estimate an examinee's ability in order to provide freely available access to a web-based computerized adaptive testing (CAT program. We used PHP and Java Script as the program languages, PostgresSQL as the database management system on an Apache web server and Linux as the operating system. A system which allows for user input and searching within inputted items and creates tests was constructed. We performed an ability estimation on each test based on a Rasch model and 2- or 3-parametric logistic models. Our system provides an algorithm for a web-based CAT, replacing previous personal computer-based ones, and makes it possible to estimate an examinee?占퐏 ability immediately at the end of test.

The Italian pilot external quality assessment program for cystic fibrosis sweat test.

Science.gov (United States)

Salvatore, Marco; Floridia, Giovanna; Amato, Annalisa; Censi, Federica; Carta, Claudio; de Stefano, Maria Chiara; Ferrari, Gianluca; Tosto, Fabrizio; Capoluongo, Ettore; Caruso, Ubaldo; Castaldo, Giuseppe; Cirilli, Natalia; Corbetta, Carlo; Padoan, Rita; Raia, Valeria; Taruscio, Domenica

2016-05-01

Sweat chloride test is the gold standard test for cystic fibrosis (CF) diagnosis. In 2014 the Istituto Superiore di Sanità established the Italian pilot external quality assessment program for CF sweat test (IEQA-ST). Ten laboratories, included among the 33 Italian CF Referral Centers, were selected and enrolled on the basis of their attitude to perform sweat test (ST) analysis by using methods recommended by the Italian Guidelines. They received three different sweat-like samples (normal, borderline and pathologic chloride concentration), with mock clinical indications, for analysis according to routine procedures. Assessment, performed by a panel of experts, covered analytical performance, interpretation and reporting of results; categories of "poor" and "satisfactory" performance were not defined. All data were managed through a web utility. The program identified important areas of interest and, in some case, of concern. It is important to underline that results are referred to a small proportion, i.e. about 30%, of Italian laboratories performing CF ST in the context of the Referral Centers. Data collected highlight the importance of participation in EQA programs as it may improve laboratory/clinical performance; our study represents a model for the setting up of a large-scale EQA scheme for ST. Copyright © 2016 The Canadian Society of Clinical Chemists. Published by Elsevier Inc. All rights reserved.

Present status of ESNIT (energy selective neutron irradiation test facility) program

International Nuclear Information System (INIS)

Noda, K.; Ohno, H.; Sugimoto, M.; Kato, Y.; Matsuo, H.; Watanabe, K.; Kikuchi, T.; Sawai, T.; Usui, T.; Oyama, Y.; Kondo, T.

1994-01-01

The present status of technical studies of a high energy neutron irradiation facility, ESNIT (energy selective neutron irradiation test facility), is summarized. Technological survey and feasibility studies of ESNIT have continued since 1988. The results of technical studies of the accelerator, the target and the experimental systems in ESNIT program were reviewed by an International Advisory Committee in February 1993. Recommendations for future R and D on ESNIT program are also summarized in this paper. ((orig.))

STECH, 3(3), S/NO 12, SEPTEMBER, 2014

African Journals Online (AJOL)

DR Nneka

2014-09-12

Sep 12, 2014 ... spillage on physical and chemical properties of the soils. Soil samples ... the result from the t-test analysis showed t value of 4.863, indicating ... corrosion of pipes, over pressure, malfunctioning of equipments, sabotage and.

Heavy Section Steel Technology Program. Part II. Intermediate vessel testing

International Nuclear Information System (INIS)

Whitman, G.D.

1975-01-01

The testing of the intermediate pressure vessels is a major activity under the Heavy Section Steel Technology Program. A primary objective of these tests is to develop or verify methods of fracture prediction, through the testing of selected structures and materials, in order that a valid basis can be established for evaluating the serviceability and safety of light-water reactor pressure vessels. These vessel tests were planned with sufficiently specific objectives that substantial quantitative weight could be given to the results. Each set of testing conditions was chosen so as to provide specific data by which analytical methods of predicting flaw growth, and in some cases crack arrest, could be evaluated. Every practical effort was made to assure that results would be relevant to some aspect of real reactor pressure vessel performance through careful control of material properties, selection of test temperatures, and design of prepared flaws. 5 references

Operational-safety advantages of LMFBR's: the EBR-II experience and testing program

International Nuclear Information System (INIS)

Sackett, J.I.; Lindsay, R.W.; Golden, G.H.

1982-01-01

LMFBR's contain many inherent characteristics that simplify control and improve operating safety and reliability. The EBR-II design is such that good advantage was taken of these characteristics, resulting in a vary favorable operating history and allowing for a program of off-normal testing to further demonstrate the safe response of LMFBR's to upsets. The experience already gained, and that expected from the future testing program, will contribute to further development of design and safety criteria for LMFBR's. Inherently safe characteristics are emphasized and include natural convective flow for decay heat removal, minimal need for emergency power and a large negative reactivity feedback coefficient. These characteristics at EBR-II allow for ready application of computer diagnosis and control to demonstrate their effectiveness in response to simulated plant accidents. This latter testing objective is an important part in improvements in the man-machine interface

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

International Nuclear Information System (INIS)

1980-06-01

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

Radiation damage calculations for the APT materials test program

International Nuclear Information System (INIS)

Corzine, R.K.; Wechsler, M.S.; Dudziak, D.J.; Ferguson, P.D.; James, M.R.

1999-01-01

A materials irradiation was performed at the Los Alamos Neutron Science Center (LANSCE) in the fall of 1996 and spring of 1997 in support of the Accelerator Production of Tritium (APT) program. Testing of the irradiated materials is underway. In the proposed APT design, materials in the target and blanket are to be exposed to protons and neutrons over a wide range of energies. The irradiation and testing program was undertaken to enlarge the very limited direct knowledge presently available of the effects of medium-energy protons (∼1 GeV) on the properties of engineering materials. APT candidate materials were placed in or near the LANSCE accelerator 800-MeV, 1-mA proton beam and received roughly the same proton current density in the center of the beam as would be the case for the APT facility. As a result, the proton fluences achieved in the irradiation were expected to approach the APT prototypic full-power-year values. To predict accurately the performance of materials in APT, radiation damage parameters for the materials experiment must be determined. By modeling the experiment, calculations for atomic displacement, helium and hydrogen cross sections and for proton and neutron fluences were done for representative samples in the 17A, 18A, and 18C areas. The LAHET code system (LCS) was used to model the irradiation program, LAHET 2.82 within LCS transports protons > 1 MeV, and neutrons >20 MeV. A modified version of MCNP for use in LCS, HMCNP 4A, was employed to tally neutrons of energies <20 MeV

Status and update of the National Ignition Facility radiation effects testing program

International Nuclear Information System (INIS)

Davis, J F; Serduke, F J; Wuest, C R.

1998-01-01

We are progressing in our efforts to make the National Ignition Facility (NIF) available to the nation as a radiation effects simulator to support the Services needs for nuclear hardness and survivability testing and validation. Details of our program were summarized in a paper presented at the 1998 HEART Conference [1]. This paper describes recent activities and updates plans for NIF radiation effects testing. research. Radiation Effects Testing

DYNAMIC PROGRAMMING APPROACH TO TESTING RESOURCE ALLOCATION PROBLEM FOR MODULAR SOFTWARE

Directory of Open Access Journals (Sweden)

P.K. Kapur

2003-02-01

Full Text Available Testing phase of a software begins with module testing. During this period modules are tested independently to remove maximum possible number of faults within a specified time limit or testing resource budget. This gives rise to some interesting optimization problems, which are discussed in this paper. Two Optimization models are proposed for optimal allocation of testing resources among the modules of a Software. In the first model, we maximize the total fault removal, subject to budgetary Constraint. In the second model, additional constraint representing aspiration level for fault removals for each module of the software is added. These models are solved using dynamic programming technique. The methods have been illustrated through numerical examples.

78 FR 63516 - Initial Test Program of Emergency Core Cooling Systems for New Boiling-Water Reactors

Science.gov (United States)

2013-10-24

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0134] Initial Test Program of Emergency Core Cooling....79.1, ``Initial Test Program of Emergency Core Cooling Systems for New Boiling-Water Reactors.'' This... emergency core cooling systems (ECCSs) for boiling- water reactors (BWRs) whose licenses are issued after...

A comparative evaluation of the process of developing and implementing an emergency department HIV testing program

Directory of Open Access Journals (Sweden)

Weiser Sheri

2011-03-01

Full Text Available Abstract Background The 2006 Centers for Disease Control and Prevention (CDC HIV testing guidelines recommend screening for HIV infection in all healthcare settings, including the emergency department (ED. In urban areas with a high background prevalence of HIV, the ED has become an increasingly important site for identifying HIV infection. However, this public health policy has been operationalized using different models. We sought to describe the development and implementation of HIV testing programs in three EDs, assess factors shaping the adoption and evolution of specific program elements, and identify barriers and facilitators to testing. Methods We performed a qualitative evaluation using in-depth interviews with fifteen 'key informants' involved in the development and implementation of HIV testing in three urban EDs serving sizable racial/ethnic minority and socioeconomically disadvantaged populations. Testing program HIV prevalence ranged from 0.4% to 3.0%. Results Three testing models were identified, reflecting differences in the use of existing ED staff to offer and perform the test and disclose results. Factors influencing the adoption of a particular model included: whether program developers were ED providers, HIV providers, or both; whether programs took a targeted or non-targeted approach to patient selection; and the extent to which linkage to care was viewed as the responsibility of the ED. A common barrier was discomfort among ED providers about disclosing a positive HIV test result. Common facilitators were a commitment to underserved populations, the perception that testing was an opportunity to re-engage previously HIV-infected patients in care, and the support and resources offered by the medical setting for HIV-infected patients. Conclusions ED HIV testing is occurring under a range of models that emerge from local realities and are tailored to institutional strengths to optimize implementation and overcome provider

Overview of the 2006-2008 JOGMEC/NRCan/Aurora Mallik Gas Hydrate Production Test Program

Science.gov (United States)

Yamamoto, K.; Dallimore, S. R.

2008-12-01

During the winters of 2007 and 2008 the Japan Oil, Gas and Metals National Corporation (JOGMEC) and Natural Resources Canada (NRCan), with Aurora Research Institute as the operator, carried out an on-shore gas hydrate production test program at the Mallik site, Mackenzie Delta, Northwest Territories, Canada. The prime objective of the program was to verify the feasibility of depressurization technique by drawing down the formation pressure across a 12m perforated gas hydrate bearing section. This project was the second full scale production test at this site following the 2002 Japex/JNOC/GSC et al Mallik research program in which seven participants organizatinos from five countries undertook a thermal test using hot water circulation Field work in 2007 was devoted to establishing a production test well, installing monitoring devices outside of casing, conducting base line geophysical studies and undertaking a short test to gain practical experience prior to longer term testing planned for 2008 . Hydrate-dissociated gas was produced to surface by depressurization achieved by lowering the fluid level with a dowhole pump. However, the operation was terminated 60 hours after the start of the pumping mainly due to sand production problems. In spite of the short period (12.5 hours of ellapsed pumping time), at least 830m3 of the gas was produced and accumulated in the borehole. Sand screens were installed across the perforated interval at the bottom hole for the 2008 program to overcome operational problems encountered in 2007 and achieve sustainable gas production. Stable bottom hole flowing pressures were successfully achieved during a 6 day test with continuous pump operation. Sustained gas production was achieved with rates between 2000- 4000m3/day and cummulative gas volume in the surface of approximately 13,000m3. Temperature and pressure data measured at the bottom hole and gas and water production rates gave positive evidence for the high efficiency of gas

A Meta-Analysis of Empirically Tested School-Based Dating Violence Prevention Programs

Directory of Open Access Journals (Sweden)

Sarah R. Edwards

2014-05-01

Full Text Available Teen dating violence prevention programs implemented in schools and empirically tested were subjected to meta-analysis. Eight studies met criteria for inclusion, consisting of both within and between designs. Overall, the weighted mean effect size (ES across studies was significant, ESr = .11; 95% confidence interval (CI = [.08, .15], p < .0001, showing an overall positive effect of the studied prevention programs. However, 25% of the studies showed an effect in the negative direction, meaning students appeared to be more supportive of dating violence after participating in a dating violence prevention program. This heightens the need for thorough program evaluation as well as the need for decision makers to have access to data about the effectiveness of programs they are considering implementing. Further implications of the results and recommendations for future research are discussed.

Employee assistance programs, drug testing, and workplace injury.

Science.gov (United States)

Waehrer, Geetha M; Miller, Ted R; Hendrie, Delia; Galvin, Deborah M

2016-06-01

Little is known about the effects of employee assistance programs (EAPs) on occupational injuries. Multivariate regressions probed a unique data set that linked establishment information about workplace anti-drug programs in 1988 with occupational injury rates for 1405 establishments. EAPs were associated with a significant reduction in both no-lost-work and lost-work injuries, especially in the manufacturing and transportation, communication and public utilities industries (TCPU). Lost-work injuries were more responsive to specific EAP characteristics, with lower rates associated with EAPs staffed by company employees (most likely onsite). Telephone hotline services were associated with reduced rates of lost-work injuries in manufacturing and TCPU. Drug testing was associated with reductions in the rate of minor injuries with no lost work, but had no significant relationship with lost-work injuries. This associational study suggests that EAPs, especially ones that are company-staffed and ones that include telephone hotlines, may prevent workplace injuries. Copyright © 2016. Published by Elsevier Ltd.

Progress of the RERTR [Reduced Enrichment Research and Test Reactor] Program in 1989

International Nuclear Information System (INIS)

Travelli, A.

1989-01-01

The progress of the Reduced Enrichment Research and Test Reactor (RERTR) Program is described. After a brief summary of the results which the RERTR Program, in collaboration with its many international partners, had achieved by the end of 1988, the major events, findings, and activities of 1989 are reviewed. The scope of the RERTR Program activities was curtailed, in 1989, by an unexpected legislative restriction which limited the ability of the Arms Control and Disarmament Agency to adequately fund the program. Nevertheless, the thrust of the major planned program activities was maintained, and meaningful results were obtained in several areas of great significance for future work. 15 refs., 12 figs

Comparison of Statistical Methods for Detector Testing Programs

Energy Technology Data Exchange (ETDEWEB)

Rennie, John Alan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Abhold, Mark [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-10-14

A typical goal for any detector testing program is to ascertain not only the performance of the detector systems under test, but also the confidence that systems accepted using that testing program’s acceptance criteria will exceed a minimum acceptable performance (which is usually expressed as the minimum acceptable success probability, p). A similar problem often arises in statistics, where we would like to ascertain the fraction, p, of a population of items that possess a property that may take one of two possible values. Typically, the problem is approached by drawing a fixed sample of size n, with the number of items out of n that possess the desired property, x, being termed successes. The sample mean gives an estimate of the population mean p ≈ x/n, although usually it is desirable to accompany such an estimate with a statement concerning the range within which p may fall and the confidence associated with that range. Procedures for establishing such ranges and confidence limits are described in detail by Clopper, Brown, and Agresti for two-sided symmetric confidence intervals.

Access to Adequate Healthcare for Hmong Women: A Patient Navigation Program to Increase Pap Test Screening

Directory of Open Access Journals (Sweden)

Moon S. Chen, Jr

2010-01-01

Full Text Available This paper describes the development and implementation of a Hmong Cervical Cancer Intervention Program utilizing a patient navigation model to raise cervical cancer awareness for Hmong women through educational workshops and to assist Hmong women in obtaining a Pap test. Out of 402 women who participated in a baseline survey, the Patient Navigation Program was able to enroll 109 participants who had not had a Pap test in the past 3 years and had never had a Pap test. Through utilization of outreach, an awareness campaign and patient navigation support, at least 38 percent of 109 participants obtained a Pap test. Overall, 21 workshops and 43 outreach activities were conducted by the Hmong Women’s Heritage Association, leading to 63 percent of those enrolled in the Patient Navigation Program who could be contacted to obtain a Pap test.

Do School-Based Tutoring Programs Significantly Improve Student Performance on Standardized Tests?

Science.gov (United States)

Rothman, Terri; Henderson, Mary

2011-01-01

This study used a pre-post, nonequivalent control group design to examine the impact of an in-district, after-school tutoring program on eighth grade students' standardized test scores in language arts and mathematics. Students who had scored in the near-passing range on either the language arts or mathematics aspect of a standardized test at the…

The passive seismic aftershock Monitoring system: testing program and preliminary results

International Nuclear Information System (INIS)

Mokhtari, M.

2005-01-01

The paper is dedicated to testing program (phase of the passive seismic aftershock monitoring system with RefTek equipment (Refraction Technology, Inc., USA) for On-Site Inspection purposes that was carried out near Vienna International Centre in 2000. Equipment and applied software are described. Testing results were analyzed; in particular, least needs in maintenance personnel during operation. Development perspectives of passive seismic aftershock monitoring system for On-Site Inspection have been discussed. (author)

76 FR 65631 - Energy Conservation Program: Test Procedures for Microwave Ovens

Science.gov (United States)

2011-10-24

... Conservation Program: Test Procedures for Microwave Ovens AGENCY: Office of Energy Efficiency and Renewable... residential microwave ovens. DOE specifically is seeking information, data, and comments regarding representative and repeatable methods for measuring the energy use of microwave-only ovens and combination...

Introduction to an open source internet-based testing program for medical student examinations.

Science.gov (United States)

Lee, Yoon-Hwan

2009-12-20

The author developed a freely available open source internet-based testing program for medical examination. PHP and Java script were used as the programming language and postgreSQL as the database management system on an Apache web server and Linux operating system. The system approach was that a super user inputs the items, each school administrator inputs the examinees' information, and examinees access the system. The examinee's score is displayed immediately after examination with item analysis. The set-up of the system beginning with installation is described. This may help medical professors to easily adopt an internet-based testing system for medical education.

Cycle life test. Evaluation program for secondary spacecraft cells. [performance tests on silver zinc batteries, silver cadmium batteries, and nickel cadmium batteries

Science.gov (United States)

Harkness, J. D.

1976-01-01

Considerable research is being done to find more efficient and reliable means of starting electrical energy for orbiting satellites. Rechargeable cells offer one such means. A test program is described which has been established in order to further the evaluation of certain types of cells and to obtain performance and failure data as an aid to their continued improvement. The purpose of the program is to determine the cycling performance capabilities of packs of cells under different load and temperature conditions. The various kinds of cells tested were nickel-cadmium, silver-cadmium, and silver-zinc sealed cells. A summary of the results of the life cycling program is given in this report.

Mobile Energy Laboratory energy-efficiency testing programs. Semiannual report, April 1, 1991--September 30, 1991

Energy Technology Data Exchange (ETDEWEB)

Parker, G. B.; Currie, J. W.

1992-03-01

This report summarizes energy-efficiency testing activities applying the Mobile Energy Laboratory (MEL) testing capabilities during the third and fourth quarters of fiscal year (FY) 1991. The MELs, developed by the US Department of Energy (DOE) Federal Energy Management Program (FEMP), are administered by Pacific Northwest Laboratory (PNL) and the Naval Energy and Environmental Support Activity (NEESA) for energy testing and energy conservation program support functions at federal facilities. The using agencies principally fund MEL applications, while DOE/FEMP funds program administration and capability enhancement activities. This report fulfills the requirements established in Section 8 of the MEL Use Plan (PNL-6861) for semi-annual reporting on energy-efficiency testing activities using the MEL capabilities. The MEL Use Committee, formally established in 1989, developed the MEL Use Plan and meets semi-annually to establish priorities for energy-efficient testing applications using the MEL capabilities. The MEL Use Committee is composed of one representative each of the US Department of Energy, US Army, US Air Force, US Navy, and other federal agencies.

A digital fly-by-wire technology development program using an F-8C test aircraft

Science.gov (United States)

Jarvis, C. R.

1974-01-01

A digital fly-by-wire flight control system has been installed in an F-8C test airplane and has undergone extensive ground and flight testing as part of an overall program to develop digital fly-by-wire technology. This is the first airplane to fly with a digital fly-by-wire system as its primary means of control and with no mechanical reversion capability. Forty-two test flights were made for a total flight time of 57 hours. Six pilots participated in the evaluation. This paper presents an overview of the digital fly-by-wire program and discusses some of the flight-test results.

LMFBR. Off normal, transient test facilities and programs in the USA

International Nuclear Information System (INIS)

Herbst, R.J.

1985-01-01

The United States fast breeder reactor development program has included operational transient analyses and experiments to verify the predicted performance of core components. Operational transient testing has focused on off-normal operation during Plant Protection System terminated transient-overpower events. In-pile and out-of-pile tests have been used to simulate predicted thermal and mechanical strain cycles and measure component response. The spectrum of reactivity ramp rates investigated in TOP tests has recently been expanded to include rates of less than $0.1/s. These slow ramp rate studies are being done in cooperation with the Japanese. The US has also cooperated with the UK in the transient testing of Prototype Fast Reactor fuel pins

Plutonium immobilization project development and testing technical project office quality assurance program description

International Nuclear Information System (INIS)

Gould, T.H.; MacLean, L.M.; Ziemba, J.M.

1999-01-01

The Plutonium Immobilization Project (PIP) is one of several fissile materials disposition projects managed by the Department of Energy (DOE) Office of Fissile Materials Disposition (OFMD). The PIP is expected to evolve from the current Development and Testing (D and T) effort, to design, to construction, and finally to operations. Overall management and technical management of the D and T effort resides at the Lead Laboratory, Lawrence Livermore National Laboratory (LLNL), through the LLNL Manager, Fissile Materials Disposition Program (FMDP). Day to day project activities are managed by the D and T Technical Project Office (TPO), which reports to the LLNL Manager, FMDP. The D and T TPO consists of the Technical Manager, the TPO Quality Assurance (QA) Program Manager, and TPO Planning and Support Staff. This Quality Assurance Program Description (QAPD) defines the QA policies and controls that will be implemented by these TPO personnel in their management of D and T activities. This QAPD is consistent with and responsive to the Department of Energy Fissile Materials Disposition Program Quality Assurance Requirements Document (FMDP QARD). As the Project and upper level requirement's documents evolve, this QAPD will be updated as necessary to accurately define and describe the QA Program and Management of the PIP. The TPO has a policy that all development and testing activities be planned, performed and assessed in accordance with its customer's requirements, needs and expectations, and with a commitment to excellence and continuous improvement. The TPO QAPD describes implementation requirements which, when completed, will ensure that the project development and testing activities conform to the appropriate QA requirements. For the program to be effective, the TPO QA Program Manager will ensure that each site participating in D and T activities has developed a QAPD, which meets the customer's requirements, and has a designated quality leader in place. These customer

An Interactive Method to Solve Infeasibility in Linear Programming Test Assembling Models

Science.gov (United States)

Huitzing, Hiddo A.

2004-01-01

In optimal assembly of tests from item banks, linear programming (LP) models have proved to be very useful. Assembly by hand has become nearly impossible, but these LP techniques are able to find the best solutions, given the demands and needs of the test to be assembled and the specifics of the item bank from which it is assembled. However,…

Safety properties test data selection from an algebraic model of Lustre programs; Selection de tests de proprietes de surete a partir d'une modelisation algebrique de programmes lustre

Energy Technology Data Exchange (ETDEWEB)

Hsiao, N.Ch

1995-07-01

In the context to validate an industrial software, which is a set of reactive programs, we are confronted with the safety properties verification problem. This thesis reports an experience in which our goal is to generate the test data satisfying a safety property. The software to be validated is designed with the SAGA tool, in which a view can be regarded as a program of a programming language called LUSTRE. We adapt a test data generation tool called LOFT to this kind of programs. In this way, we consider the functional testing method on which the LOFT tool is based. Given any LUSTRE program, we try to give it an algebraic model because LOFT treats algebraic specifications. So, our task consists In defining a formal framework in which any LUSTRE program can be translated into a LOFT module: based on an operational semantics of the LUSTRE language, the flow types 'T-flow' are specified with the constructive algebraic formalism, then implemented in a LOFT modules base. Next, in a test selection process assisted by LOFT, a safety property Is expressed by an equation to join other control hypotheses, and to guide the test data selection. Some concrete test data set are generated in this way on some significant examples. This experience confirm the feasibility of formal method on test data selection for the reactive programs. (author)

Seismic II over I Drop Test Program results and interpretation

International Nuclear Information System (INIS)

Thomas, B.

1993-03-01

The consequences of non-seismically qualified (Category 2) objects falling and striking essential seismically qualified (Category 1) objects has always been a significant, yet analytically difficult problem, particularly in evaluating the potential damage to equipment that may result from earthquakes. Analytical solutions for impact problems are conservative and available for mostly simple configurations. In a nuclear facility, the open-quotes sourcesclose quotes and open-quotes targetsclose quotes requiring evaluation are frequently irregular in shape and configuration, making calculations and computer modeling difficult. Few industry or regulatory rules are available on this topic even though it is a source of considerable construction upgrade costs. A drop test program was recently conducted to develop a more accurate understanding of the consequences of seismic interactions. The resulting data can be used as a means to improve the judgment of seismic qualification engineers performing interaction evaluations and to develop realistic design criteria for seismic interactions. Impact tests on various combinations of sources and targets commonly found in one Savannah River Site (SRS) nuclear facility were performed by dropping the sources from various heights onto the targets. This report summarizes results of the Drop Test Program. Force and acceleration time history data are presented as well as general observations on the overall ruggedness of various targets when subjected to impacts from different types of sources

Seismic II over I Drop Test Program results and interpretation

Energy Technology Data Exchange (ETDEWEB)

Thomas, B.

1993-03-01

The consequences of non-seismically qualified (Category 2) objects falling and striking essential seismically qualified (Category 1) objects has always been a significant, yet analytically difficult problem, particularly in evaluating the potential damage to equipment that may result from earthquakes. Analytical solutions for impact problems are conservative and available for mostly simple configurations. In a nuclear facility, the {open_quotes}sources{close_quotes} and {open_quotes}targets{close_quotes} requiring evaluation are frequently irregular in shape and configuration, making calculations and computer modeling difficult. Few industry or regulatory rules are available on this topic even though it is a source of considerable construction upgrade costs. A drop test program was recently conducted to develop a more accurate understanding of the consequences of seismic interactions. The resulting data can be used as a means to improve the judgment of seismic qualification engineers performing interaction evaluations and to develop realistic design criteria for seismic interactions. Impact tests on various combinations of sources and targets commonly found in one Savannah River Site (SRS) nuclear facility were performed by dropping the sources from various heights onto the targets. This report summarizes results of the Drop Test Program. Force and acceleration time history data are presented as well as general observations on the overall ruggedness of various targets when subjected to impacts from different types of sources.

Seismic II over I Drop Test Program results and interpretation

Energy Technology Data Exchange (ETDEWEB)

Thomas, B.

1993-03-01

The consequences of non-seismically qualified (Category 2) objects falling and striking essential seismically qualified (Category 1) objects has always been a significant, yet analytically difficult problem, particularly in evaluating the potential damage to equipment that may result from earthquakes. Analytical solutions for impact problems are conservative and available for mostly simple configurations. In a nuclear facility, the [open quotes]sources[close quotes] and [open quotes]targets[close quotes] requiring evaluation are frequently irregular in shape and configuration, making calculations and computer modeling difficult. Few industry or regulatory rules are available on this topic even though it is a source of considerable construction upgrade costs. A drop test program was recently conducted to develop a more accurate understanding of the consequences of seismic interactions. The resulting data can be used as a means to improve the judgment of seismic qualification engineers performing interaction evaluations and to develop realistic design criteria for seismic interactions. Impact tests on various combinations of sources and targets commonly found in one Savannah River Site (SRS) nuclear facility were performed by dropping the sources from various heights onto the targets. This report summarizes results of the Drop Test Program. Force and acceleration time history data are presented as well as general observations on the overall ruggedness of various targets when subjected to impacts from different types of sources.

Canister disposition plan for the DWPF Startup Test Program

International Nuclear Information System (INIS)

Harbour, J.R.; Payne, C.H.

1990-01-01

This report details the disposition of canisters and the canistered waste forms produced during the DWPF Startup Test Program. The six melter campaigns (DWPF Startup Tests FA-13, WP-14, WP-15, WP-16, WP-17, and FA-18) will produce 126 canistered waste forms. In addition, up to 20 additional canistered waste forms may be produced from glass poured during the transition between campaigns. In particular, this canister disposition plan (1) assigns (by alpha-numeric code) a specific canister to each location in the six campaign sequences, (2) describes the method of access for glass sampling on each canistered waste form, (3) describes the nature of the specific tests which will be carried out, (4) details which tests will be carried out on each canistered waste form, (5) provides the sequence of these tests for each canistered waste form, and (6) assigns a storage location for each canistered waste form. The tests are designed to provide evidence, as detailed in the Waste Form Compliance Plan (WCP 1 ), that the DWPF product will comply with the Waste Acceptance Product Specifications (WAPS 2 ). The WAPS must be met before the canistered waste form is accepted by DOE for ultimate disposal at the Federal Repository. The results of these tests will be included in the Waste Form Qualification Report (WQR)

The initial criticality and nuclear commissioning test program at HANARO

Energy Technology Data Exchange (ETDEWEB)

Lee, Choong-Sung; Seo, Chul-Gyo; Jun, Byung-Jin [Korea Atomic Energy Research Institute, Dukjin-Dong 150, Yusung-Ku, Taejon, 305-353 (Korea, Republic of)

1995-07-01

The construction of the Korea Multipurpose Research Reactor - HANARO of 3MW, developed by Korea Atomic Energy Research Institute, was completed at the beginning of this year. The first fuel loading began on February 2 1995, and initial criticality was achieved on February 8, when the core had four 18-element assemblies and thirteen 36-element assemblies. The critical control rod position was 600.8 mm which represents excess reactivity of 0.71 $. Currently the nuclear commissioning test is on going under the zero power range. This paper describes the initial criticality approach of the HANARO, and its nuclear commissioning test program. (author)

NDE Technology Development Program for Non-Visual Volumetric Inspection Technology; Sensor Effectiveness Testing Report

Energy Technology Data Exchange (ETDEWEB)

Moran, Traci L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Larche, Michael R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Denslow, Kayte M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Glass, Samuel W. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2017-08-31

The Pacific Northwest National Laboratory (PNNL) located in Richland, Washington, hosted and administered Sensor Effectiveness Testing that allowed four different participants to demonstrate the NDE volumetric inspection technologies that were previously demonstrated during the Technology Screening session. This document provides a Sensor Effectiveness Testing report for the final part of Phase I of a three-phase NDE Technology Development Program designed to identify and mature a system or set of non-visual volumetric NDE technologies for Hanford DST primary liner bottom inspection. Phase I of the program will baseline the performance of current or emerging non-visual volumetric NDE technologies for their ability to detect and characterize primary liner bottom flaws, and identify candidate technologies for adaptation and maturation for Phase II of the program.

77 FR 11367 - Defense Federal Acquisition Regulation Supplement; Extension of the Test Program for Negotiation...

Science.gov (United States)

2012-02-24

...DoD is issuing a final rule amending the Defense Federal Acquisition Regulation Supplement to extend the program period for the DoD Test Program for Negotiation of Comprehensive Small Business Subcontracting Plans.

Introduction to an Open Source Internet-Based Testing Program for Medical Student Examinations

Directory of Open Access Journals (Sweden)

Yoon-Hwan Lee

2009-12-01

Full Text Available The author developed a freely available open source internet-based testing program for medical examination. PHP and Java script were used as the programming language and postgreSQL as the database management system on an Apache web server and Linux operating system. The system approach was that a super user inputs the items, each school administrator inputs the examinees’ information, and examinees access the system. The examinee’s score is displayed immediately after examination with item analysis. The set-up of the system beginning with installation is described. This may help medical professors to easily adopt an internet-based testing system for medical education.

Testing geopressured geothermal reservoirs in existing wells. Wells of Opportunity Program final contract report, 1980-1981

Energy Technology Data Exchange (ETDEWEB)

1982-01-01

The geopressured-geothermal candidates for the Wells of Opportunity program were located by the screening of published information on oil industry activity and through direct contact with the oil and gas operators. This process resulted in the recommendation to the DOE of 33 candidate wells for the program. Seven of the 33 recommended wells were accepted for testing. Of these seven wells, six were actually tested. The first well, the No. 1 Kennedy, was acquired but not tested. The seventh well, the No. 1 Godchaux, was abandoned due to mechanical problems during re-entry. The well search activities, which culminated in the acceptance by the DOE of 7 recommended wells, were substantial. A total of 90,270 well reports were reviewed, leading to 1990 wells selected for thorough geological analysis. All of the reservoirs tested in this program have been restricted by one or more faults or permeability barriers. A comprehensive discussion of test results is presented.

Assessment of the response of spent fuel transports to malevolent acts

International Nuclear Information System (INIS)

Sandoval, R.P.

1983-01-01

This paper describes the results of a program conducted at Sandia National Laboratories (SNL) for the US Department of Energy to provide an experimental data base for more accurately assessing the radiological consequences from a hypothetical sabotage attack on a spent fuel shipping cask. The primary objectives of the program were limited to: (1) evaluating the effectiveness of selected high explosive devices (HED) in breaching full-size spent fuel casks, (2) quantifying and characterizing relevant aerosol properties of the released fuel, and (3) using the resulting experimental data to evaluate the radiological health consequences resulting from a hypothetical sabotage attack on a spent fuel shipping cask in a densely populated area. Subscale and full-scale experiments in conjunction with an analytical modeling study were performed to meet the programmatic objectives. The data from this program indicate that the Urban Studies greatly overestimated the impact of malevolent acts directed at spent fuel casks in urban environs. From that standpoint this work could be the basis of additional regulatory revisions of the NRC physical protection requirements. In a larger sense this work can also be the basis of more credible worst case analyses since it defines the actual result of an event which is well beyond any expectations of cask failures in accident environments. 5 references

Building Of Training Program Of Non-Destructive Testing For Concrete Structures (Part 1: Radiographic testing; Ultrasonic pulse velocity measurement; Nuclear moisture-density gauge)

International Nuclear Information System (INIS)

Nguyen Le Son; Phan Chanh Vu; Pham The Hung; Vu Huy Thuc

2007-01-01

Non-destructive testing methods (NDT) have been identified as a strong candidate for remote sensing of concrete structures over recent years. This has accelerated the powerful development of the NDT techniques in Vietnam. Hence, there is an urgent need to promote the awareness of NDT methods which could give an improved estimate of the condition concrete. Building of training program of non-destructive testing for concrete structures is a necessary duty, in aiming to build a unified training program, possibly satisfying the requirements on training as well as researching. Under the framework of the basic VAEC project (CS/07/02-03), a training program for the first 03 NDT methods: 1. Radiographic testing; 2. Ultrasonic pulse velocity measurement; 3. Nuclear moisture- density gauge was prepared. The main products of this project include: 1. Set out 03 training notes for 03 methods; 2. Set out the practical exercises to train for 03 methods; 3. Editing a set of examination questions in aiming to familiarize with various questions in 03 trained methods; 4. Fabricating practical test specimens to demonstrate for 03 techniques. (author)

The automated testing system of programs with the graphic user interface within the context of educational process

OpenAIRE

Sychev, O.; Kiryushkin, A.

2009-01-01

The paper describes the problems of automation of educational process at the course "Programming on high level language. Algorithmic languages". Complexities of testing of programs with the user interface are marked. Existing analogues was considered. Methods of automation of student's jobs testing are offered.

48 CFR 252.219-7004 - Small business subcontracting plan (test program).

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Small business... AND CONTRACT CLAUSES Text of Provisions And Clauses 252.219-7004 Small business subcontracting plan (test program). As prescribed in 219.708(b)(1)(B), use the following clause: Small Business...

Animal investigation program 1980 annual report: Nevada Test Site and vicinity

International Nuclear Information System (INIS)

Smith, D.D.; Bernhardt, D.E.; Giles, K.R.

1982-07-01

This report summarizes the data collected through the Animal Investigation Program during 1980. A major goal of the Program is to assess the radionuclide burden in the tissues of wild and domesticated animals around the Nevada Test Site and to detect pathological effects resulting from the burdens. Other than naturally occurring potassium-40, gamma emitting radionuclides were detected infrequently. Strontium-90 and plutonium concentrations in tissues from deer, cattle, and desert bighorn sheep were similar to those found in samples collected during recent years. Lesions found in necropsied animals were similar to those found in animals from other areas of the U.S. and would not be attributable to ionizing radiation exposure. The report also describes other activities of the program, including the deer migration study and census

Cover gas seals: FFTF-LMFBR seal test program

International Nuclear Information System (INIS)

Kurzeka, W.; Oliva, R.; Welch, T.S.; Shimazaki, T.

1974-01-01

The objectives of this program are to: (1) conduct static and dynamic tests to demonstrate or determine the mechanical performance of full-size (cross section) FFTF fuel transfer machine and reactor vessel head seals intended for use in a sodium vapor-inert gas environment, (2) demonstrate that these FFTF seals or new seal configurations provide acceptable fission product and cover gas retention capabilities at Clinch River Breeder Reactor Plant (CRBRP) operating environmental conditions other than radiation, and (3) develop improved seals and seal technology for the CRBRP to support the national objective to reduce all atmospheric contaminations to low levels

Status of the Virginia Power/DOE Cooperative Cask Testing/Demonstration Program: A video presentation

International Nuclear Information System (INIS)

McKinnon, M.A.; Creer, J.M.; Collantes, C.E.

1990-01-01

This paper is documentation of a video presentation and provides a brief summary of the Virginia power/US Department of Energy Cooperative Cask Testing/Demonstration Program. The program consists of two phases. The first phase has been completed and involved the unlicensed performance testing (heat transfer and shielding) of three metal spent fuel storage casks at the federally owned Idaho National Engineering Laboratory. The second phase is ongoing and consists of licensed demonstrations of standard casks from two different vendors and of one or two enhanced capacity casks. 6 refs., 1 tab

General-Purpose Heat Source Development: Safety Test Program. Postimpact evaluation, Design Iteration Test 3

International Nuclear Information System (INIS)

Schonfeld, F.W.; George, T.G.

1984-07-01

The General-Purpose Heat Source(GPHS) provides power for space missions by transmitting the heat of 238 PuO 2 decay to thermoelectric elements. Because of the inevitable return of certain aborted missions, the heat source must be designed and constructed to survive both re-entry and Earth impact. The Design Iteration Test (DIT) series is part of an ongoing test program. In the third test (DIT-3), a full GPHS module was impacted at 58 m/s and 930 0 C. The module impacted the target at an angle of 30 0 to the pole of the large faces. The four capsules used in DIT-3 survived impact with minimal deformation; no internal cracks other than in the regions indicated by Savannah River Plant (SRP) preimpact nondestructive testing were observed in any of the capsules. The 30 0 impact orientation used in DIT-3 was considerably less severe than the flat-on impact utilized in DIT-1 and DIT-2. The four capsules used in DIT-1 survived, while two of the capsules used in DIT-2 breached; a small quantity (approx. = 50 μg) of 238 PuO 2 was released from the capsules breached in the DIT-2 impact. All of the capsules used in DIT-1 and DIT-2 were severely deformed and contained large internal cracks. Postimpact analyses of the DIT-3 test components are described, with emphasis on weld structure and the behavior of defects identified by SRP nondestructive testing

Full-scale Mark II CRT program: dynamic response evaluation test of pressure transducers

International Nuclear Information System (INIS)

Kukita, Yutaka; Namatame, Ken; Takeshita, Isao; Shiba, Masayoshi

1982-12-01

A dynamic response evaluation test of pressure transducers was conducted in support of the JAERI Full-Scale Mark II CRT (Containment Response Test) Program. The test results indicated that certain of the cavity-type transducers used in the early blowdown test had undesirable response characteristics. The transducer mounting scheme was modified to avoid trapping of air bubbles in the pressure transmission tubing attached to the transducers. The dynamic response of the modified transducers was acceptable within the frequency range of 200 Hz. (author)

HIV testing uptake and prevalence among adolescents and adults in a large home-based HIV testing program in Western Kenya.

Science.gov (United States)

Wachira, Juddy; Ndege, Samson; Koech, Julius; Vreeman, Rachel C; Ayuo, Paul; Braitstein, Paula

2014-02-01

To describe HIV testing uptake and prevalence among adolescents and adults in a home-based HIV counseling and testing program in western Kenya. Since 2007, the Academic Model Providing Access to Healthcare program has implemented home-based HIV counseling and testing on a large scale. All individuals aged ≥13 years were eligible for testing. Data from 5 of 8 catchments were included in this analysis. We used descriptive statistics and multivariate logistic regression to examine testing uptake and HIV prevalence among adolescents (13-18 years), younger adults (19-24 years), and older adults (≥25 years). There were 154,463 individuals eligible for analyses as follows: 22% adolescents, 19% younger adults, and 59% older adults. Overall mean age was 32.8 years and 56% were female. HIV testing was high (96%) across the following 3 groups: 99% in adolescents, 98% in younger adults, and 94% in older adults (P < 0.001). HIV prevalence was higher (11.0%) among older adults compared with younger adults (4.8%) and adolescents (0.8%) (P < 0.001). Those who had ever previously tested for HIV were less likely to accept HIV testing (adjusted odds ratio: 0.06, 95% confidence interval: 0.05 to 0.07) but more likely to newly test HIV positive (adjusted odds ratio: 1.30, 95% confidence interval: 1.21 to 1.40). Age group differences were evident in the sociodemographic and socioeconomic factors associated with testing uptake and HIV prevalence, particularly, gender, relationship status, and HIV testing history. Sociodemographic and socioeconomic factors were independently associated with HIV testing and prevalence among the age groups. Community-based treatment and prevention strategies will need to consider these factors.

Summary of the Mol electrolysis cell test program in the CRL tritium laboratory

International Nuclear Information System (INIS)

Miller, J.M.; Keyes, R.J.

1996-01-01

The development of electrolysis technology for highly tritiated water at the Studiecentrum voor Kernenergie/Centre d'Etude de l'Energie Nucleaire (SCK/CEN), Mol, Belgium, focused on A Low Inventory Capillary Electrolyser (ALICE). The key characteristic of ALICE is its low liquid inventory, a key feature for the radio-toxicity of tritiated water. A program to test this electrolytic cell design with highly tritiated water in the Chalk River Tritium Laboratory was initiated in 1988 and extended through to early 1995. The activities conducted at CRL and associated with the experimental program-design, installation, licensing and commissioning activities- are described in this report along with the results of the test program conducted on the experimental system with non-tritiated heavy water. The installation in the CRL Tritium Laboratory consisted of three main sections: the electrolysis section, the tritium storage and supply section, and the recombination section. 16 figs., 2 tabs., 10 refs

Nevada Test Site Radiation Protection Program - Revision 1

International Nuclear Information System (INIS)

Nevada Test Site Radiological Control Managers' Council

2008-01-01

Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection,' establishes radiation protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of U.S. Department of Energy (DOE) activities. 10 CFR 835.101(a) mandates that DOE activities be conducted in compliance with a documented Radiation Protection Program (RPP) as approved by DOE. This document promulgates the RPP for the Nevada Test Site (NTS), related (on-site or off-site) U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) operations, and environmental restoration off-site projects. This NTS RPP promulgates the radiation protection standards, limits, and program requirements for occupational exposure to ionizing radiation resulting from NNSA/NSO activities at the NTS and other operational areas as stated in 10 CFR 835.1(a). NNSA/NSO activities (including design, construction, operation, and decommissioning) within the scope of this RPP may result in occupational exposures to radiation or radioactive material. Therefore, a system of control is implemented through specific references to the site-specific NV/YMP RCM. This system of control is intended to ensure that the following criteria are met: (1) occupational exposures are maintained as low as reasonably achievable (ALARA), (2) DOE's limiting values are not exceeded, (3) employees are aware of and are prepared to cope with emergency conditions, and (4) employees are not inadvertently exposed to radiation or radioactive material

Nevada Test Site Radiation Protection Program - Revision 1

Energy Technology Data Exchange (ETDEWEB)

Radiological Control Managers' Council

2008-06-01

Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection,' establishes radiation protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of U.S. Department of Energy (DOE) activities. 10 CFR 835.101(a) mandates that DOE activities be conducted in compliance with a documented Radiation Protection Program (RPP) as approved by DOE. This document promulgates the RPP for the Nevada Test Site (NTS), related (on-site or off-site) U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) operations, and environmental restoration off-site projects. This NTS RPP promulgates the radiation protection standards, limits, and program requirements for occupational exposure to ionizing radiation resulting from NNSA/NSO activities at the NTS and other operational areas as stated in 10 CFR 835.1(a). NNSA/NSO activities (including design, construction, operation, and decommissioning) within the scope of this RPP may result in occupational exposures to radiation or radioactive material. Therefore, a system of control is implemented through specific references to the site-specific NV/YMP RCM. This system of control is intended to ensure that the following criteria are met: (1) occupational exposures are maintained as low as reasonably achievable (ALARA), (2) DOE's limiting values are not exceeded, (3) employees are aware of and are prepared to cope with emergency conditions, and (4) employees are not inadvertently exposed to radiation or radioactive material.

Adaptation, testing and application of the two-dimensional FE computer program system for steam generator tube testing

International Nuclear Information System (INIS)

Betzold, K.

1987-01-01

The 2d-FE computing program system, taken over by EPRI, is used for the improvement of the eddy current test of steam generator heating tubes. The investigations focus on test tasks in the area of the tube plate and the scrap mark; among them: accumulation of mud in the cracking area and above the tube plate; circulating slots with and without accumulation of mud. The interaction of the factors of influence given by the test object and the parameters selectable by the tester as for example coil length and base space for absolute coils and differential coils as well as test frequencies are calculated and the form of the signal locus curves and the dynamic curves are listed in a sample catalogue. It is demonstrated with selected examples that the sample catalogue contributes to the test-specific design of the coil and to the choice of the test frequencies; interpretation of measured signals; deepening of the knowledge of the physical processe in eddy current tests. (orig./HP) [de

77 FR 74559 - Energy Conservation Program for Consumer Products: Test Procedures for Residential Water Heaters...

Science.gov (United States)

2012-12-17

... Conservation Program for Consumer Products: Test Procedures for Residential Water Heaters, Direct Heating... Energy (DOE) is amending its test procedures for residential water heaters, direct heating equipment (DHE... necessary for residential water heaters, because the existing test procedures for those products already...

76 FR 56347 - Energy Conservation Program for Consumer Products: Test Procedures for Residential Water Heaters...

Science.gov (United States)

2011-09-13

... Conservation Program for Consumer Products: Test Procedures for Residential Water Heaters, Direct Heating... proposed to amend, where appropriate, its test procedures for residential water heaters, direct heating... notes that the test procedure and metric for residential water heaters currently address and incorporate...

Testing New Programming Paradigms with NAS Parallel Benchmarks

Science.gov (United States)

Jin, H.; Frumkin, M.; Schultz, M.; Yan, J.

2000-01-01

Over the past decade, high performance computing has evolved rapidly, not only in hardware architectures but also with increasing complexity of real applications. Technologies have been developing to aim at scaling up to thousands of processors on both distributed and shared memory systems. Development of parallel programs on these computers is always a challenging task. Today, writing parallel programs with message passing (e.g. MPI) is the most popular way of achieving scalability and high performance. However, writing message passing programs is difficult and error prone. Recent years new effort has been made in defining new parallel programming paradigms. The best examples are: HPF (based on data parallelism) and OpenMP (based on shared memory parallelism). Both provide simple and clear extensions to sequential programs, thus greatly simplify the tedious tasks encountered in writing message passing programs. HPF is independent of memory hierarchy, however, due to the immaturity of compiler technology its performance is still questionable. Although use of parallel compiler directives is not new, OpenMP offers a portable solution in the shared-memory domain. Another important development involves the tremendous progress in the internet and its associated technology. Although still in its infancy, Java promisses portability in a heterogeneous environment and offers possibility to "compile once and run anywhere." In light of testing these new technologies, we implemented new parallel versions of the NAS Parallel Benchmarks (NPBs) with HPF and OpenMP directives, and extended the work with Java and Java-threads. The purpose of this study is to examine the effectiveness of alternative programming paradigms. NPBs consist of five kernels and three simulated applications that mimic the computation and data movement of large scale computational fluid dynamics (CFD) applications. We started with the serial version included in NPB2.3. Optimization of memory and cache usage

Dietary Interventions in Multiple Sclerosis: Development and Pilot-Testing of an Evidence Based Patient Education Program.

Science.gov (United States)

Riemann-Lorenz, Karin; Eilers, Marlene; von Geldern, Gloria; Schulz, Karl-Heinz; Köpke, Sascha; Heesen, Christoph

2016-01-01

Dietary factors have been discussed to influence risk or disease course of multiple sclerosis (MS). Specific diets are widely used among patients with MS. To design and pilot-test an evidence based patient education program on dietary factors in MS. We performed a systematic literature search on the effectiveness of dietary interventions in MS. A web-based survey among 337 patients with MS and 136 healthy controls assessed knowledge, dietary habits and information needs. An interactive group education program was developed and pilot-tested. Fifteen randomised-controlled trials (RCTs) were included in the systematic review. Quality of evidence was low and no clear benefit could be seen. Patients with MS significantly more often adhered to a `Mediterranean Diet`(29.7% versus 14.0%, ppilot test of our newly developed patient education program with 13 participants showed excellent comprehensibility and the MS-specific content was judged as very important. However, the poor evidence base for dietary approaches in MS was perceived disappointing. Development and pilot-testing of an evidence-based patient education program on nutrition and MS is feasible. Patient satisfaction with the program suffers from the lack of evidence. Further research should focus on generating evidence for the potential influence of lifestyle habits (diet, physical activity) on MS disease course thus meeting the needs of patients with MS.

75 FR 52892 - Energy Conservation Program for Consumer Products: Test Procedures for Residential Water Heaters...

Science.gov (United States)

2010-08-30

... ``Energy Conservation Program for Consumer Products Other Than Automobiles,'' including residential water... final rule revising energy conservation standards for residential water heaters, direct heating.... EERE-2009-BT-TP-0013] RIN 1904-AB95 Energy Conservation Program for Consumer Products: Test Procedures...

Coincident steam generator tube rupture and stuck-open safety relief valve carryover tests: MB-2 steam generator transient response test program

International Nuclear Information System (INIS)

Garbett, K.; Mendler, O.J.; Gardner, G.C.; Garnsey, R.; Young, M.Y.

1987-03-01

In PWR steam generator tube rupture (SGTR) faults, a direct pathway for the release of radioactive fission products can exist if there is a coincident stuck-open safety relief valve (SORV) or if the safety relief valve is cycled. In addition to the release of fission products from the bulk steam generator water by moisture carryover, there exists the possibility that some primary coolant may be released without having first mixed with the bulk water - a process called primary coolant bypassing. The MB-2 Phase II test program was designed specifically to identify the processes for droplet carryover during SGTR faults and to provide data of sufficient accuracy for use in developing physical models and computer codes to describe activity release. The test program consisted of sixteen separate tests designed to cover a range of steady-state and transient fault conditions. These included a full SGTR/SORV transient simulation, two SGTR overfill tests, ten steady-state SGTR tests at water levels ranging from very low levels in the bundle up to those when the dryer was flooded, and three moisture carryover tests without SGTR. In these tests the influence of break location and the effect of bypassing the dryer were also studied. In a final test the behavior with respect to aerosol particles in a dry steam generator, appropriate to a severe accident fault, was investigated

Water Quality: A Field-Based Quality Testing Program for Middle Schools and High Schools.

Science.gov (United States)

Massachusetts State Water Resources Authority, Boston.

This manual contains background information, lesson ideas, procedures, data collection and reporting forms, suggestions for interpreting results, and extension activities to complement a water quality field testing program. Information on testing water temperature, water pH, dissolved oxygen content, biochemical oxygen demand, nitrates, total…

Lawrence Livermore Laboratory's beryllium control program for high-explosive test firing bunkers and tables

International Nuclear Information System (INIS)

Johnson, J.S.

1980-01-01

This report on the control program to minimize beryllium levels in Laboratory workplaces includes an outline of beryllium surface, soil, and air levels and an 11-y summary of sampling results from two high-use, high-explosive test firing bunkers. These sampling data and other studies demonstrate that the beryllium control program is functioning effectively

Vehicle access and search training manual. Report for Oct 77-sep 79

International Nuclear Information System (INIS)

Obermiller, J.E.; Wait, H.J.

1979-11-01

This Vehicle Access and Search Training Manual is intended to assist NRC-licensed organizations and their security personnel in developing vehicle access, control and search operations necessary at nuclear fuel cycle facilities and at reactor facilities. The manual is based on security requirements prescribed by The Nuclear Regulatory Commission as contained in Title 10 of the Code of Federal Regulations, Part 73, 'Physical Protection of Plants and Materials.' As a condition of the licensing agreement, the licensee is required to maintain a physical protection system which includes a training program for security personnel. The manual includes lesson plans in (1) controlling vehicle entry and exit, (2) searching for contraband, and (3) protecting the facility from sabotage and/or theft of special nuclear materials. These training guidelines provide information and instruction for self-study, discussion and hands-on training. A job knowledge test reviews the entire training program

Conversion of research and test reactors to low enriched uranium fuel: technical overview and program status

International Nuclear Information System (INIS)

Roglans-Ribas, J.

2008-01-01

Many of the nuclear research and test reactors worldwide operate with high enriched uranium fuel. In response to worries over the potential use of HEU from research reactors in nuclear weapons, the U.S Department of Energy (DOE) initiated a program - the Reduced Enrichment for Research and Test Reactors (RERTR) - in 1978 to develop the technology necessary to reduce the use of HEU fuel by converting research reactors to low enriched uranium (LEU) fuel. The Reactor Conversion program is currently under the DOE's National Nuclear Security Administration's Global Threat Reduction Initiative (GTRI). 55 of the 129 reactors included in the scope have been already converted to LEU fuel or have shutdown prior to conversion. The major technical activities of the Conversion Program include: (1) the development of advanced LEU fuels; (2) conversion analysis and conversion support; and (3) technology development for the production of Molybdenum-99 (Mo 99 ) with LEU targets. The paper provides an overview of the status of the program, the technical challenges and accomplishments, and the role of international collaborations in the accomplishment of the Conversion Program objectives. Nuclear research and test reactors worldwide have been in operation for over 60 years. Many of these facilities operate with high enriched uranium fuel. In response to increased worries over the potential use of HEU from research reactors in the manufacturing of nuclear weapons, the U.S Department of Energy (DOE) initiated a program - the Reduced Enrichment for Research and Test Reactors (RERTR) - in 1978 to develop the technology necessary to reduce the use of HEU fuel in research reactors by converting them to low enriched uranium (LEU) fuel. The reactor conversion program was initially focused on U.S.-supplied reactors, but in the early 1990s it expanded and began to collaborate with Russian institutes with the objective of converting Russian supplied reactors to the use of LEU fuel.

Cost estimate for a proposed GDF Suez LNG testing program

Energy Technology Data Exchange (ETDEWEB)

Blanchat, Thomas K.; Brady, Patrick Dennis; Jernigan, Dann A.; Luketa, Anay Josephine; Nissen, Mark R.; Lopez, Carlos; Vermillion, Nancy; Hightower, Marion Michael

2014-02-01

At the request of GDF Suez, a Rough Order of Magnitude (ROM) cost estimate was prepared for the design, construction, testing, and data analysis for an experimental series of large-scale (Liquefied Natural Gas) LNG spills on land and water that would result in the largest pool fires and vapor dispersion events ever conducted. Due to the expected cost of this large, multi-year program, the authors utilized Sandia's structured cost estimating methodology. This methodology insures that the efforts identified can be performed for the cost proposed at a plus or minus 30 percent confidence. The scale of the LNG spill, fire, and vapor dispersion tests proposed by GDF could produce hazard distances and testing safety issues that need to be fully explored. Based on our evaluations, Sandia can utilize much of our existing fire testing infrastructure for the large fire tests and some small dispersion tests (with some modifications) in Albuquerque, but we propose to develop a new dispersion testing site at our remote test area in Nevada because of the large hazard distances. While this might impact some testing logistics, the safety aspects warrant this approach. In addition, we have included a proposal to study cryogenic liquid spills on water and subsequent vaporization in the presence of waves. Sandia is working with DOE on applications that provide infrastructure pertinent to wave production. We present an approach to conduct repeatable wave/spill interaction testing that could utilize such infrastructure.

EDISON-WMW: Exact Dynamic Programing Solution of the Wilcoxon–Mann–Whitney Test

Directory of Open Access Journals (Sweden)

Alexander Marx

2016-02-01

Full Text Available In many research disciplines, hypothesis tests are applied to evaluate whether findings are statistically significant or could be explained by chance. The Wilcoxon–Mann–Whitney (WMW test is among the most popular hypothesis tests in medicine and life science to analyze if two groups of samples are equally distributed. This nonparametric statistical homogeneity test is commonly applied in molecular diagnosis. Generally, the solution of the WMW test takes a high combinatorial effort for large sample cohorts containing a significant number of ties. Hence, P value is frequently approximated by a normal distribution. We developed EDISON-WMW, a new approach to calculate the exact permutation of the two-tailed unpaired WMW test without any corrections required and allowing for ties. The method relies on dynamic programing to solve the combinatorial problem of the WMW test efficiently. Beyond a straightforward implementation of the algorithm, we presented different optimization strategies and developed a parallel solution. Using our program, the exact P value for large cohorts containing more than 1000 samples with ties can be calculated within minutes. We demonstrate the performance of this novel approach on randomly-generated data, benchmark it against 13 other commonly-applied approaches and moreover evaluate molecular biomarkers for lung carcinoma and chronic obstructive pulmonary disease (COPD. We found that approximated P values were generally higher than the exact solution provided by EDISON-WMW. Importantly, the algorithm can also be applied to high-throughput omics datasets, where hundreds or thousands of features are included. To provide easy access to the multi-threaded version of EDISON-WMW, a web-based solution of our algorithm is freely available at http://www.ccb.uni-saarland.de/software/wtest/.

75 FR 42612 - Energy Conservation Program for Consumer Products: Test Procedure for Microwave Ovens

Science.gov (United States)

2010-07-22

... Conservation Program for Consumer Products: Test Procedure for Microwave Ovens AGENCY: Office of Energy... (NOPR) in which DOE proposed test procedures for microwave ovens under the Energy Policy and Conservation Act (EPCA) to measure standby mode and off mode power use by microwave ovens. To address issues...

Lawrence Livermore Laboratory's beryllium control program for high-explosive test firing bunkers and tables

International Nuclear Information System (INIS)

Johnson, J.S.

1978-01-01

This detailed report on Lawrence Livermore Laboratory's control program to minimize beryllium levels in Laboratory workplaces includes an outline of beryllium surface, soil, and air levels and an 11-y summary of sampling results from two high-use, high-explosive test firing bunkers. These sampling data and other studies demonstrate that the beryllium control program is funcioning effectively

Designing, testing, and implementing a sustainable nurse home visiting program: right@home.

Science.gov (United States)

Goldfeld, Sharon; Price, Anna; Kemp, Lynn

2018-05-01

Nurse home visiting (NHV) offers a potential platform to both address the factors that limit access to services for families experiencing adversity and provide effective interventions. Currently, the ability to examine program implementation is hampered by a lack of detailed description of actual, rather than expected, program development and delivery in published studies. Home visiting implementation remains a black box in relation to quality and sustainability. However, previous literature would suggest that efforts to both report and improve program implementation are vital for NHV to have population impact and policy sustainability. In this paper, we provide a case study of the design, testing, and implementation of the right@home program, an Australian NHV program and randomized controlled trial. We address existing gaps related to implementation of NHV programs by describing the processes used to develop the program to be trialed, summarizing its effectiveness, and detailing the quality processes and implementation evaluation. The weight of our evidence suggests that NHV can be a powerful and sustainable platform for addressing inequitable outcomes, particularly when the program focuses on parent engagement and partnership, delivers evidence-based strategies shown to improve outcomes, includes fidelity monitoring, and is adapted to and embedded within existing service delivery systems. © 2018 The Authors. Annals of the New York Academy of Sciences published by Wiley Periodicals, Inc. on behalf of The New York Academy of Sciences.

Licensee safeguards contingency plans

International Nuclear Information System (INIS)

Anon.

1978-01-01

The Nuclear Regulatory Commission is amending its regulations to require that licensees authorized to operate a nuclear reactor (other than certain research and test reactors), and those authorized to possess strategic quantities of plutonium, uranium-233, or uranium-235 develop and implement acceptable plans for responding to threats, thefts, and industrial sabotage of licensed nuclear materials and facilities. The plans will provide a structured, orderly, and timely response to safeguards contingencies and will be an important segment of NRC's contingency planning programs. Licensee safeguards contingency plans will result in organizing licensee's safeguards resources in such a way that, in the unlikely event of a safeguards contingency, the responding participants will be identified, their several responsibilities specified, and their responses coordinated

Intelligent Testing of Traffic Light Programs: Validation in Smart Mobility Scenarios

Directory of Open Access Journals (Sweden)

Javier Ferrer

2016-01-01

Full Text Available In smart cities, the use of intelligent automatic techniques to find efficient cycle programs of traffic lights is becoming an innovative front for traffic flow management. However, this automatic programming of traffic lights requires a validation process of the generated solutions, since they can affect the mobility (and security of millions of citizens. In this paper, we propose a validation strategy based on genetic algorithms and feature models for the automatic generation of different traffic scenarios checking the robustness of traffic light cycle programs. We have concentrated on an extensive urban area in the city of Malaga (in Spain, in which we validate a set of candidate cycle programs generated by means of four optimization algorithms: Particle Swarm Optimization for Traffic Lights, Differential Evolution for Traffic Lights, random search, and Sumo Cycle Program Generator. We can test the cycles of traffic lights considering the different states of the city, weather, congestion, driver expertise, vehicle’s features, and so forth, but prioritizing the most relevant scenarios among a large and varied set of them. The improvement achieved in solution quality is remarkable, especially for CO2 emissions, in which we have obtained a reduction of 126.99% compared with the experts’ solutions.

77 FR 73056 - Initial Test Programs for Water-Cooled Nuclear Power Plants

Science.gov (United States)

2012-12-07

... Plants AGENCY: Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for comment... (DG), DG-1259, ``Initial Test Programs for Water-Cooled Nuclear Power Plants.'' This guide describes... (ITPs) for light water cooled nuclear power plants. DATES: Submit comments by January 31, 2013. Comments...

Feasibility of an appliance energy testing and labeling program for Sri Lanka

Energy Technology Data Exchange (ETDEWEB)

Biermayer, Peter; Busch, John; Hakim, Sajid; Turiel, Issac; du Pont, Peter; Stone, Chris

2000-04-01

A feasibility study evaluated the costs and benefits of establishing a program for testing, labeling and setting minimum efficiency standards for appliances and lighting in Sri Lanka. The feasibility study included: refrigerators, air-conditioners, flourescent lighting (ballasts & CFls), ceiling fans, motors, and televisions.

PROGRAM ASTEC (ADVANCED SOLAR TURBO ELECTRIC CONCEPT). PART 1. CANDIDATE MATERIALS LABORATORY TESTS

Science.gov (United States)

A space power system of the type envisioned by the ASTEC program requires the development of a lightweight solar collector of high reflectance...capable of withstanding the space environment for an extended period. A survey of the environment of interest for ASTEC purposes revealed 4 potential...developed by the solar-collector industry for use in the ASTEC program, and to test the effects of space environment on these materials. Of 6 material

Risk evaluation for motor operated valves in an Inservice Testing Program at a PWR nuclear power plant in Taiwan

International Nuclear Information System (INIS)

Li, Y.C.; Chen, K.T.; Su, Y.L.; Ting, K.; Chien, F.T.; Li, G.D.; Huang, S.H.

2012-01-01

Safety related valves such as Motor Operated Valves (MOV), Air Operated Valves (AOV) or Check Valves (CV) play an important role in nuclear power plant. Functioning of these valves mainly aim at emergency reactivity control, post-accident residue heat removal, post-accident radioactivity removal and containment isolation when a design basis accident occurred. In order to maintain these valves under operable conditions, an Inservice Testing Program (IST) is defined for routine testing tasks based on the ASME Boiler and Pressure Vessel Code section XI code requirements. Risk based Inservice Testing Programs have been studied and developed extensively in the nuclear energy industry since the 1990s. Risk Based evaluations of IST can bring positive advantages to the licensee such as identifying the vulnerability of the system, reducing unnecessary testing burden, concentrating testing resources on the critical pass oriented valves and saving plant’s personnel dose exposure. This risk evaluation is incorporated with quantitative and qualitative analyses to the Motor Operated Valves under current Inservice Testing Program for PWR nuclear power plant in Taiwan. With the outcome of the risk classifications for the safety related MOVs through numerical or deterministic analyses, a risk based testing frequency relief is suggested to demonstrate the benefits received from the risk based Inservice Testing Program. The goal made of this study, it could be as a reference and cornerstone for the licensee to perform overall scope Risk-Informed Inservice Testing Program (RI-IST) evaluation by referring relevant methodologies established in this study.

Plutonium immobilization program - Cold pour Phase 1 test results

International Nuclear Information System (INIS)

Hamilton, L.

2000-01-01

The Plutonium Immobilization Project will disposition excess weapons grade plutonium. It uses the can-in-canister approach that involves placing plutonium-ceramic pucks in sealed cans that are then placed into Defense Waste Processing Facility canisters. These canisters are subsequently filled with high-level radioactive waste glass. This process puts the plutonium in a stable form and makes it unattractive for reuse. A cold (non-radioactive) glass pour program was performed to develop and verify the baseline design for the canister and internal hardware. This paper describes the Phase 1 scoping test results

Plutonium Immobilization Program - Cold pour Phase 1 test results

International Nuclear Information System (INIS)

Hamilton, L.

2000-01-01

The Plutonium Immobilization Project will disposition excess weapons grade plutonium. It uses the can-in-canister approach that involves placing plutonium-ceramic pucks in sealed cans that are then placed into Defense Waste Processing Facility canisters. These canisters are subsequently filled with high-level radioactive waste glass. This process puts the plutonium in a stable form and makes it unattractive for reuse. A cold (non-radioactive) glass pour program was performed to develop and verify the baseline design for the canister and internal hardware. This paper describes the Phase 1 scoping test results

76 FR 12825 - Energy Conservation Program for Consumer Products: Test Procedure for Microwave Ovens

Science.gov (United States)

2011-03-09

... Conservation Program for Consumer Products: Test Procedure for Microwave Ovens AGENCY: Office of Energy.... Department of Energy (DOE) is amending its test procedures for microwave ovens under the Energy Policy and Conservation Act (EPCA) to provide for the measurement of standby mode and off mode power use by microwave...

Implementation of a National Semen Testing and Counseling Program for Male Ebola Survivors - Liberia, 2015-2016.

Science.gov (United States)

Purpura, Lawrence J; Soka, Moses; Baller, April; White, Stephen; Rogers, Emerson; Choi, Mary J; Mahmoud, Nuha; Wasunna, Christine; Massaquoi, Moses; Vanderende, Kristin; Kollie, Jomah; Dweh, Straker; Bemah, Philip; Christie, Athalia; Ladele, Victor; Subah, Onyekachi; Pillai, Satish; Mugisha, Margaret; Kpaka, Jonathan; Nichol, Stuart; Ströher, Ute; Abad, Neetu; Mettee-Zarecki, Shauna; Bailey, Jeff A; Rollin, Pierre; Marston, Barbara; Nyenswah, Tolbert; Gasasira, Alex; Knust, Barbara; Williams, Desmond

2016-09-16

According to World Health Organization (WHO) data, the Ebola virus disease (Ebola) outbreak that began in West Africa in 2014 has resulted in 28,603 cases and 11,301 deaths (1). In March 2015, epidemiologic investigation and genetic sequencing in Liberia implicated sexual transmission from a male Ebola survivor, with Ebola virus detected by reverse transcription-polymerase chain reaction (RT-PCR) 199 days after symptom onset (2,3), far exceeding the 101 days reported from an earlier Ebola outbreak (4). In response, WHO released interim guidelines recommending that all male survivors, in addition to receiving condoms and sexual risk reduction counseling at discharge from an Ebola treatment unit (ETU), be offered semen testing for Ebola virus RNA by RT-PCR 3 months after disease onset, and every month thereafter until two consecutive semen specimens collected at least 1 week apart test negative for Ebola virus RNA (5). Male Ebola survivors should also receive counseling to promote safe sexual practices until their semen twice tests negative. When these recommendations were released, testing of semen was not widely available in Liberia. Challenges in establishing and operating the first nationwide semen testing and counseling program for male Ebola survivors included securing sufficient resources for the program, managing a public health semen testing program in the context of ongoing research studies that were also collecting and screening semen, identification of adequate numbers of trained counselors and appropriate health communication messages for the program, overcoming Ebola survivor-associated stigma, identification and recruitment of male Ebola survivors, and operation of mobile teams.

Hydrologic Resources Management Program and Underground Test Area Project FY2005 Progress Report

International Nuclear Information System (INIS)

Eaton, G F; Genetti, V; Hu, Q; Hudson, G B; Kersting, A B; Lindvall, R E; Moran, J E; Nimz, G J; Ramon, E C; Rose, T P; Shuller, L; Williams, R W; Zavarin, M; Zhao, P

2007-01-01

This report describes FY 2005 technical studies conducted by the Chemical Biology and Nuclear Science Division (CBND) at Lawrence Livermore National Laboratory (LLNL) in support of the Hydrologic Resources Management Program (HRMP) and the Underground Test Area Project (UGTA). These programs are administered by the U.S. Department of Energy, National Nuclear Security Administration, Nevada Site Office (NNSA/NSO) through the Defense Programs and Environmental Restoration Divisions, respectively. HRMP-sponsored work is directed toward the responsible management of the natural resources at the Nevada Test Site (NTS), enabling its continued use as a staging area for strategic operations in support of national security. UGTA-funded work emphasizes the development of an integrated set of groundwater flow and contaminant transport models to predict the extent of radionuclide migration from underground nuclear testing areas at the NTS. The report is organized on a topical basis and contains five chapters that highlight technical work products produced by CBND. However, it is important to recognize that most of this work involves collaborative partnerships with the other HRMP and UGTA contract organizations. These groups include the Energy and Environment Directorate at LLNL (LLNL-E and E), Los Alamos National Laboratory (LANL), the Desert Research Institute (DRI), the U.S. Geological Survey (USGS), Stoller-Navarro Joint Venture (SNJV), and Bechtel Nevada (BN)

NRC review of passive reactor design certification testing programs: Overview and regulatory perspective

International Nuclear Information System (INIS)

Levin, A.E.

1993-01-01

Reactor vendors are developing new designs for future deployment, including open-quotes passiveclose quotes light water reactors (LWRs), such as General Electric's (G.E.'s) simplified boiling water reactor (SBWR) and Westinghouse's AP600, which depend primarily on inherent processes, such as national convection and gravity feed, for safety injection and emergency core cooling. The U.S. Nuclear Regulatory Commission (NRC) has implemented a new process, certification of standardized reactor designs, for licensing these Plants. Part 52 of Title 10 of the Code of Federal Regulations (10CFR52) contains the requirements that vendors must meet for design certification. One important section, 10CFR52.47, reads open-quotes Certification of a standard design which . . . utilizes simplified, inherent, passive, or other innovative means to accomplish its safety functions will be granted only if: (1) The performance of each safety feature of the design has been demonstrated through either analysis, appropriate test programs, experience, or a combination thereof; (2) Interdependent effects among the safety features have been found acceptable by analysis, appropriate test programs, experience, or a combination thereof; and (3) Sufficient data exist on the safety features of the design to assess the analytical tools used for safety analyses. . . . The vendors have initiated programs to test innovative features of their designs and to develop data bases needed to validate their analytical codes, as required by the design certification rule. Accordingly, the NRC is reviewing and evaluating the vendors programs to ensure that they address adequately key issues concerning safety system performance. This paper provides an overview of the NRC's review process and regulatory perspective

Leach test methodology for the Waste/Rock Interactions Technology Program

International Nuclear Information System (INIS)

Bradley, D.J.; McVay, G.L.; Coles, D.G.

1980-05-01

Experimental leach studies in the WRIT Program have two primary functions. The first is to determine radionuclide release from waste forms in laboratory environments which attempt to simulate repository conditions. The second is to elucidate leach mechanisms which can ultimately be incorporated into nearfield transport models. The tests have been utilized to generate rates of removal of elements from various waste forms and to provide specimens for surface analysis. Correlation between constituents released to the solution and corresponding solid state profiles is invaluable in the development of a leach mechanism. Several tests methods are employed in our studies which simulate various proposed leach incident scenarios. Static tests include low temperature (below 100 0 C) and high temperature (above 100 0 C) hydrothermal tests. These tests reproduce nonflow or low-flow repository conditions and can be used to compare materials and leach solution effects. The dynamic tests include single-pass, continuous-flow(SPCF) and solution-change (IAA)-type tests in which the leach solutions are changed at specific time intervals. These tests simulate repository conditions of higher flow rates and can also be used to compare materials and leach solution effects under dynamic conditions. The modified IAEA test is somewhat simpler to use than the one-pass flow and gives adequate results for comparative purposes. The static leach test models the condition of near-zero flow in a repository and provides information on element readsorption and solubility limits. The SPCF test is used to study the effects of flowing solutions at velocities that may be anticipated for geologic groundwaters within breached repositories. These two testing methods, coupled with the use of autoclaves, constitute the current thrust of WRIT leach testing

78 FR 73702 - Federal Travel Regulation (FTR); Telework Travel Expenses Test Programs

Science.gov (United States)

2013-12-09

...; Docket Number 2013-0012, Sequence 1] RIN 3090-AJ23 Federal Travel Regulation (FTR); Telework Travel...). ACTION: Final rule. SUMMARY: GSA is amending the Federal Travel Regulation (FTR) to incorporate the Telework Enhancement Act of 2010, which establishes and authorizes telework travel expenses test programs...

75 FR 8528 - Procedures for Transportation Workplace Drug and Alcohol Testing Programs

Science.gov (United States)

2010-02-25

... OST 2105-AD84 Procedures for Transportation Workplace Drug and Alcohol Testing Programs AGENCY: Office... of small entities, for purposes of the Regulatory Flexibility Act. The Department makes these... necessary for the Department to conduct a regulatory evaluation or Regulatory Flexibility Analysis for this...

Selenide isotope generator for the Galileo Mission: SIG/Galileo hermetic receptable test program final report

International Nuclear Information System (INIS)

Roedel, S.

1979-06-01

The purpose of the receptacle test program was to test various types of hermetically sealed electrical receptacles and to select one model as the spaceflight hardware item for SIG/Galileo thermoelectric generators. The design goal of the program was to qualify a hermetic seal integrity of less than or equal to 1 x 10 -9 std cc He/sec -atm at 400 0 F (204 0 C) and verify a reliability of 0.95 at a 50% confidence level for a flight mission in excess of 7 years

Mixed waste chemical compatibility: A testing program for plastic packaging components

International Nuclear Information System (INIS)

Nigrey, P.J.

1995-01-01

The purpose of hazardous and radioactive materials packaging is to enable these materials to be transported without posing a threat to the health or property of the general public. To achieve this aim, regulations in the United States have been written establishing general design requirements for such packagings. While no regulations have been written specifically for mixed waste packaging, regulations for the constituents of mixed wastes, i.e., hazardous and radioactive substances, have been codified by the US Department of Transportation (DOT, 49 CFR 173) and the US Nuclear Regulatory Commission (NRC, 10 CFR 71). The design requirements for both hazardous [49 CFR 173.24 (e)(1)] and radioactive [49 CFR 173.412 (g)] materials packaging specify packaging compatibility, i.e., that the materials of the packaging at sign d any contents be chemically compatible with each other. Furthermore, Type A [49 CFR 173.412 (g)] and Type B (10 CFR 71.43) packaging design requirements stipulate that there be no significant chemical, galvanic, or other reaction between the materials and contents of the package. Based on these requirements, a Chemical Compatibility Testing Program was developed in the Transportation Systems Department at Sandia National Laboratories (SNL). The program attempts to assure any regulatory body that the issue of packaging material compatibility towards hazardous and radioactive materials has been addressed. This program has been described in considerable detail in an internal SNL document, the Chemical Compatibility Test Plan ampersand Procedure Report (Nigrey 1993)

An overview of environment Canada's National Incinerator Testing and Evaluation Program (NITEP)

International Nuclear Information System (INIS)

Finkelstein, A.

1991-01-01

In response to the many concerns associated with incineration, Environment Canada established the National Incineration Testing and evaluation Program (NITEP) in 1984. It's mission was to assess the incineration process as a means for disposal of MSW in Canada. The program primarily focused on the environment and health impacts of MSW incinerators by determining how design and operating conditions can be modified to reduce emissions of concern. In addition to developing better measuring and monitoring methods, supporting ash residue management research programs, NITEP established four major field projects to develop the data base necessary for national guidelines. This paper presents a brief overview of the most significant field program findings over the past six years and the rationale for the Canadian Council of Ministers of the Environment (CCME) Operating and Emissions Guidelines for MSW Incinerators published in June of 1989. In addition an overview of the ash work completed to date, and work still underway, will be presented

Nuclear thermal rocket nozzle testing and evaluation program

International Nuclear Information System (INIS)

Davidian, K.O.; Kacynski, K.J.

1993-01-01

Performance characteristics of the Nuclear Thermal Rocket can be enhanced through the use of unconventional nozzles as part of the propulsion system. In this report, the Nuclear Thermal Rocket nozzle testing and evaluation program being conducted at the NASA Lewis Research Center is outlined and the advantages of a plug nozzle are described. A facility description, experimental designs and schematics are given. Results of pretest performance analyses show that high nozzle performance can be attained despite substantial nozzle length reduction through the use of plug nozzles as compared to a convergent-divergent nozzle. Pretest measurement uncertainty analyses indicate that specific impulse values are expected to be within plus or minus 1.17%

Power Burst Facility severe-fuel-damage test program

International Nuclear Information System (INIS)

McCardell, R.K.; MacDonald, P.E.

1982-01-01

As a result of the Three Mile Island Unit 2 (TMI-2) accident, the United States Nuclear Regulatory Commission (USNRC) has initiated a severe fuel damage research program to investigate fuel rod and core response, and fission product and hydrogen release and transport during degraded core cooling accidents. This paper presents a discussion of the expected benefits of the PBF severe fuel damage tests to the nuclear industry, a description of the first five planned experiments, the results of pretest analysis performed to predict the fuel bundle heatup for the first two experiments, and a discussion of Phase II severe fuel damage experiments. Modifications to the fission product detection system envisioned for the later experiments are also described

Environmental Fatigue of Metallic Materials in Nuclear Power Plants - A Review of Korean Test Programs

Energy Technology Data Exchange (ETDEWEB)

Jang, Changheul; Jang, Hun; Hong, Jongdae [KAIST, Daejeon (Korea, Republic of); Cho, Hyunchul [Doosan Heavy Industry and Construction, Changwon (Korea, Republic of); Kim, Tae Soon; Lee, Jaegon [KHNP, Daejeon (Korea, Republic of)

2013-12-15

Environmental fatigue of the metallic components in light water reactors has been the subject of extensive research and regulatory interest in Korea and abroad. Especially, it was one of the key domestic issues for the license renewal of operating reactors and licensing of advanced reactors during the early 2000s. To deal with the environmental fatigue issue domestically, a systematic test program has been initiated and is still underway. The materials tested were SA508 Gr.1a low alloy steels, 316LN stainless steels, cast stainless steels, and an Alloy 690 and 52M weld. Through tests and subsequent analysis, the mechanisms of reduced low cycle fatigue life have been investigated for those alloys. In addition, the effects of temperature, dissolved oxygen level, and dissolved hydrogen level on low cycle fatigue behaviors have been investigated. In this paper, the test results and key analysis results are briefly summarized. Finally, an on-going test program for hot-bending of 347 stainless steel is introduced.

DENBRAN: A basic program for a significance test for multivariate normality of clusters from branching patterns in dendrograms

Science.gov (United States)

Sneath, P. H. A.

A BASIC program is presented for significance tests to determine whether a dendrogram is derived from clustering of points that belong to a single multivariate normal distribution. The significance tests are based on statistics of the Kolmogorov—Smirnov type, obtained by comparing the observed cumulative graph of branch levels with a graph for the hypothesis of multivariate normality. The program also permits testing whether the dendrogram could be from a cluster of lower dimensionality due to character correlations. The program makes provision for three similarity coefficients, (1) Euclidean distances, (2) squared Euclidean distances, and (3) Simple Matching Coefficients, and for five cluster methods (1) WPGMA, (2) UPGMA, (3) Single Linkage (or Minimum Spanning Trees), (4) Complete Linkage, and (5) Ward's Increase in Sums of Squares. The program is entitled DENBRAN.

75 FR 57555 - Energy Conservation Program for Consumer Products: Test Procedure for Residential Clothes Washers

Science.gov (United States)

2010-09-21

... technologies not covered by the current procedure; (2) more accurately reflect current consumer behavior and... Part II Department of Energy 10 CFR Part 430 Energy Conservation Program for Consumer Products... [Docket No. EERE-2010-BT-TP-0021] RIN 1904-AC08 Energy Conservation Program for Consumer Products: Test...

75 FR 57556 - Energy Conservation Program for Consumer Products: Test Procedure for Residential Clothes Washers

Science.gov (United States)

2010-09-21

... technologies not covered by the current procedure; (2) more accurately reflect current consumer behavior and... Part II Department of Energy 10 CFR Part 430 Energy Conservation Program for Consumer Products... [Docket No. EERE-2010-BT-TP-0021] RIN 1904-AC08 Energy Conservation Program for Consumer Products: Test...

Environmental test program for superconducting materials and devices. Mid-Term Report, May 1990 - Jun. 1991

International Nuclear Information System (INIS)

Haertling, G.; Randolph, H.; Hsi, Chi-Shiung; Verbelyi, D.

1991-07-01

This report is divided into two parts. The first dealing with work involved with Clemson University and the second with the results from Westinghouse/Savannah River. Both areas of work involved low noise, low thermal conductivity superconducting grounding links used in the NASA-sponsored Spectroscopy of the Atmosphere using Far Infrared Emission (SAFIRE) Project. Clemson prepared the links from YBa2Cu3O(7-x) superconductor tape that was mounted on a printed circuit board and encapsulated with epoxy resin. The Clemson program includes temperature vs. resistance, liquid nitrogen immersion, water immersion, thermal cycling, humidity, and radiation testing. The evaluation of the links under a long term environmental test program is described. The Savannah River program includes gamma irradiation, vibration, and long-term evaluation. The progress made in these evaluations is discussed

Gulf Coast geopressured-geothermal program summary report compilation. Volume 2-B: Resource description, program history, wells tested, university and company based research, site restoration