WorldWideScience

Sample records for verification program revision

  1. Engineering drawing field verification program. Revision 3

    International Nuclear Information System (INIS)

    Ulk, P.F.

    1994-01-01

    Safe, efficient operation of waste tank farm facilities is dependent in part upon the availability of accurate, up-to-date plant drawings. Accurate plant drawings are also required in support of facility upgrades and future engineering remediation projects. This supporting document establishes the procedure for performing a visual field verification of engineering drawings, the degree of visual observation being performed and documenting the results. A copy of the drawing attesting to the degree of visual observation will be paginated into the released Engineering Change Notice (ECN) documenting the field verification for future retrieval and reference. All waste tank farm essential and support drawings within the scope of this program will be converted from manual to computer aided drafting (CAD) drawings. A permanent reference to the field verification status will be placed along the right border of the CAD-converted drawing, referencing the revision level, at which the visual verification was performed and documented

  2. K Basins Field Verification Program

    International Nuclear Information System (INIS)

    Booth, H.W.

    1994-01-01

    The Field Verification Program establishes a uniform and systematic process to ensure that technical information depicted on selected engineering drawings accurately reflects the actual existing physical configuration. This document defines the Field Verification Program necessary to perform the field walkdown and inspection process that identifies the physical configuration of the systems required to support the mission objectives of K Basins. This program is intended to provide an accurate accounting of the actual field configuration by documenting the as-found information on a controlled drawing

  3. Towards automatic verification of ladder logic programs

    OpenAIRE

    Zoubek , Bohumir; Roussel , Jean-Marc; Kwiatkowska , Martha

    2003-01-01

    International audience; Control system programs are usually validated by testing prior to their deployment. Unfortunately, testing is not exhaustive and therefore it is possible that a program which passed all the required tests still contains errors. In this paper we apply techniques of automatic verification to a control program written in ladder logic. A model is constructed mechanically from the ladder logic program and subjected to automatic verification against requirements that include...

  4. Verification Testing of Air Pollution Control Technology Quality Management Plan Revision 2.3

    Science.gov (United States)

    The Air Pollution Control Technology Verification Center was established in 1995 as part of the EPA’s Environmental Technology Verification Program to accelerate the development and commercialization of improved environmental technologies’ performance.

  5. On the organisation of program verification competitions

    NARCIS (Netherlands)

    Huisman, Marieke; Klebanov, Vladimir; Monahan, Rosemary; Klebanov, Vladimir; Beckert, Bernhard; Biere, Armin; Sutcliffe, Geoff

    In this paper, we discuss the challenges that have to be addressed when organising program verification competitions. Our focus is on competitions for verification systems where the participants both formalise an informally stated requirement and (typically) provide some guidance for the tool to

  6. Finite Countermodel Based Verification for Program Transformation (A Case Study

    Directory of Open Access Journals (Sweden)

    Alexei P. Lisitsa

    2015-12-01

    Full Text Available Both automatic program verification and program transformation are based on program analysis. In the past decade a number of approaches using various automatic general-purpose program transformation techniques (partial deduction, specialization, supercompilation for verification of unreachability properties of computing systems were introduced and demonstrated. On the other hand, the semantics based unfold-fold program transformation methods pose themselves diverse kinds of reachability tasks and try to solve them, aiming at improving the semantics tree of the program being transformed. That means some general-purpose verification methods may be used for strengthening program transformation techniques. This paper considers the question how finite countermodels for safety verification method might be used in Turchin's supercompilation method. We extract a number of supercompilation sub-algorithms trying to solve reachability problems and demonstrate use of an external countermodel finder for solving some of the problems.

  7. FMEF Electrical single line diagram and panel schedule verification process

    International Nuclear Information System (INIS)

    Fong, S.K.

    1998-01-01

    Since the FMEF did not have a mission, a formal drawing verification program was not developed, however, a verification process on essential electrical single line drawings and panel schedules was established to benefit the operations lock and tag program and to enhance the electrical safety culture of the facility. The purpose of this document is to provide a basis by which future landlords and cognizant personnel can understand the degree of verification performed on the electrical single lines and panel schedules. It is the intent that this document be revised or replaced by a more formal requirements document if a mission is identified for the FMEF

  8. Solid waste operations complex engineering verification program plan

    International Nuclear Information System (INIS)

    Bergeson, C.L.

    1994-01-01

    This plan supersedes, but does not replace, the previous Waste Receiving and Processing/Solid Waste Engineering Development Program Plan. In doing this, it does not repeat the basic definitions of the various types or classes of development activities nor provide the rigorous written description of each facility and assign the equipment to development classes. The methodology described in the previous document is still valid and was used to determine the types of verification efforts required. This Engineering Verification Program Plan will be updated on a yearly basis. This EVPP provides programmatic definition of all engineering verification activities for the following SWOC projects: (1) Project W-026 - Waste Receiving and Processing Facility Module 1; (2) Project W-100 - Waste Receiving and Processing Facility Module 2A; (3) Project W-112 - Phase V Storage Facility; and (4) Project W-113 - Solid Waste Retrieval. No engineering verification activities are defined for Project W-112 as no verification work was identified. The Acceptance Test Procedures/Operational Test Procedures will be part of each project's Title III operation test efforts. The ATPs/OTPs are not covered by this EVPP

  9. Active sites environmental monitoring Program - Program Plan: Revision 2

    International Nuclear Information System (INIS)

    Morrissey, C.M.; Hicks, D.S.; Ashwood, T.L.; Cunningham, G.R.

    1994-05-01

    The Active Sites Environmental Monitoring Program (ASEMP), initiated in 1989, provides early detection and performance monitoring of active low-level-waste (LLW) and transuranic (TRU) waste facilities at Oak Ridge National Laboratory (ORNL). Several changes have recently occurred in regard to the sites that are currently used for waste storage and disposal. These changes require a second set of revisions to the ASEMP program plan. This document incorporates those revisions. This program plan presents the organization and procedures for monitoring the active sites. The program plan also provides internal reporting levels to guide the evaluation of monitoring results

  10. Protocol-Based Verification of Message-Passing Parallel Programs

    DEFF Research Database (Denmark)

    López-Acosta, Hugo-Andrés; Eduardo R. B. Marques, Eduardo R. B.; Martins, Francisco

    2015-01-01

    We present ParTypes, a type-based methodology for the verification of Message Passing Interface (MPI) programs written in the C programming language. The aim is to statically verify programs against protocol specifications, enforcing properties such as fidelity and absence of deadlocks. We develo...

  11. On Construction and Verification of PLC-Programs

    Directory of Open Access Journals (Sweden)

    E. V. Kuzmin

    2012-01-01

    Full Text Available We review some methods and approaches to programming discrete problems for Programmable Logic Controllers on the example of constructing PLC-programs for controling a code lock. For these approaches we evaluate the usability of the model checking method for the analysis of program correctness with respect to the automatic verification tool Cadence SMV. Some possible PLC-program vulnerabilities arising at a number approaches to programming of PLC are revealed.

  12. Formal verification of complex properties on PLC programs

    CERN Document Server

    Darvas, D; Voros, A; Bartha, T; Blanco Vinuela, E; Gonzalez Suarez, V M

    2014-01-01

    Formal verification has become a recommended practice in the safety-critical application areas. However, due to the complexity of practical control and safety systems, the state space explosion often prevents the use of formal analysis. In this paper we extend our former verification methodology with effective property preserving reduction techniques. For this purpose we developed general rule-based reductions and a customized version of the Cone of Influence (COI) reduction. Using these methods, the verification of complex requirements formalised with temporal logics (e.g. CTL, LTL) can be orders of magnitude faster. We use the NuSMV model checker on a real-life PLC program from CERN to demonstrate the performance of our reduction techniques.

  13. Cost-Effective CNC Part Program Verification Development for Laboratory Instruction.

    Science.gov (United States)

    Chen, Joseph C.; Chang, Ted C.

    2000-01-01

    Describes a computer numerical control program verification system that checks a part program before its execution. The system includes character recognition, word recognition, a fuzzy-nets system, and a tool path viewer. (SK)

  14. ENVIRONMENTAL TECHNOLOGY VERIFICATION (ETV) PROGRAM: GREEN BUILDING TECHNOLOGIES

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) Environmental Technology Verification (ETV) Program evaluates the performance of innovative air, water, pollution prevention and monitoring technologies that have the potential to improve human health and the environment. This techno...

  15. Effective verification of confidentiality for multi-threaded programs

    NARCIS (Netherlands)

    Ngo, Minh Tri; Stoelinga, Mariëlle Ida Antoinette; Huisman, Marieke

    2014-01-01

    This paper studies how confidentiality properties of multi-threaded programs can be verified efficiently by a combination of newly developed and existing model checking algorithms. In particular, we study the verification of scheduler-specific observational determinism (SSOD), a property that

  16. Belief Revision in the GOAL Agent Programming Language

    DEFF Research Database (Denmark)

    Spurkeland, Johannes Svante; Jensen, Andreas Schmidt; Villadsen, Jørgen

    2013-01-01

    Agents in a multiagent system may in many cases find themselves in situations where inconsistencies arise. In order to properly deal with these, a good belief revision procedure is required. This paper illustrates the usefulness of such a procedure: a certain belief revision algorithm is consider...... in order to deal with inconsistencies and, particularly, the issue of inconsistencies, and belief revision is examined in relation to the GOAL agent programming language....

  17. Verification of Java Programs using Symbolic Execution and Invariant Generation

    Science.gov (United States)

    Pasareanu, Corina; Visser, Willem

    2004-01-01

    Software verification is recognized as an important and difficult problem. We present a norel framework, based on symbolic execution, for the automated verification of software. The framework uses annotations in the form of method specifications an3 loop invariants. We present a novel iterative technique that uses invariant strengthening and approximation for discovering these loop invariants automatically. The technique handles different types of data (e.g. boolean and numeric constraints, dynamically allocated structures and arrays) and it allows for checking universally quantified formulas. Our framework is built on top of the Java PathFinder model checking toolset and it was used for the verification of several non-trivial Java programs.

  18. Revised inspection program for nuclear power plants

    International Nuclear Information System (INIS)

    1978-01-01

    The United States Nuclear Regulatory Commission (NRC) regulates nuclear power plants to assure adequate protection of the public and the environment from the dangers associated with nuclear materials. NRC fulfills this responsibility through comprehensive safety reviews of nuclear facilities, licensing of organizations that use nuclear materials, and continuing inspection. The NRC inspection program is currently conducted from the five regional offices in or near Philadelphia, Atlanta, Chicago, Dallas and San Francisco. Inspectors travel from the regional offices to nuclear power plants in various phases of construction, test and operation in order to conduct inspections. However, in June 1977 the Commission approved a revision to the inspection program that will include stationing inspectors at selected plants under construction and at all plants in operation. In addition, the revised program provides for appraising the performance of licensees on a national basis and involves more direct measurement and observation by NRC inspectors of work and tests in progress. The program also includes enhanced career management consisting of improved training and career development for inspectors and other professionals. The report was requested in the Conference Report on the NRC Authorization for Appropriations for Fiscal Year 1978. The report provides a discussion of the basis for both the current and revised inspection programs, describes these programs, and shows how the NRC inspection force will be trained and utilized. In addition, the report includes a discussion of the actions that will be taken to assure the objectivity of inspectors

  19. 77 FR 15273 - Oklahoma: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2012-03-15

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental... hazardous waste management program. We authorized the following revisions: Oklahoma received authorization... its program revision in accordance with 40 CFR 271.21. The Oklahoma Hazardous Waste Management Act...

  20. Assertion checking environment (ACE) for formal verification of C programs

    International Nuclear Information System (INIS)

    Sharma, Babita; Dhodapkar, S.D.; Ramesh, S.

    2003-01-01

    In this paper we describe an Assertion Checking Environment (ACE) for compositional verification of programs, which are written in an industrially sponsored safe subset of C programming language called MISRA C [Guidelines for the Use of the C Language in Vehicle Based Software, 1998]. The theory is based on Hoare logic [Commun. ACM 12 (1969) 576] and the C programs are verified using static assertion checking technique. First the functional specifications of the program, captured in the form of pre- and post-conditions for each C function, are derived from the specifications. These pre- and post-conditions are then introduced as assertions (also called annotations or formal comments) in the program code. The assertions are then proved formally using ACE and theorem proving tool called Stanford Temporal Prover [The Stanford Temporal Prover User's Manual, 1998]. ACE has been developed by us and consists mainly of a translator c2spl, a GUI and some utility programs. The technique and tools developed are targeted towards verification of real-time embedded software

  1. 78 FR 32161 - Oklahoma: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2013-05-29

    ... Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental Protection Agency (EPA... waste management program. We authorized the following revisions: Oklahoma received authorization for... authorization of its program revision in accordance with 40 CFR 271.21. The Oklahoma Hazardous Waste Management...

  2. VBMC: a formal verification tool for VHDL programs

    International Nuclear Information System (INIS)

    Ajith, K.J.; Bhattacharjee, A.K.

    2014-01-01

    The design of Control and Instrumentation (C and I) systems used in safety critical applications such as nuclear power plants involves partitioning of the overall system functionality into subparts and implementing each subpart in hardware and/or software as appropriate. With increasing use of programmable devices like FPGA, the hardware subsystems are often implemented in Hardware Description Languages (HDL) like VHDL. Since the functional bugs in such hardware subsystems used in safety critical C and I systems have disastrous consequences, it is important to use rigorous reasoning to verify the functionalities of the HDL models. This paper describes an indigenously developed software tool named VBMC (VHDL Bounded Model Checker) for mathematically proving/refuting functional properties of hardware designs described in VHDL. VBMC accepts hardware design as VHDL program file, functional property in PSL, and verification bound (number of cycles of operation) as inputs. It either reports that the design satisfies the functional property for the given verification bound or generates a counter example providing the reason of violation. In case of satisfaction, the proof holds good for the verification bound. VBMC has been used for the functional verification of FPGA based intelligent I/O boards developed at Reactor Control Division, BARC. (author)

  3. VBMC: a formal verification tool for VHDL program

    International Nuclear Information System (INIS)

    Ajith, K.J.; Bhattacharjee, A.K.

    2014-08-01

    The design of Control and Instrumentation (C and I) systems used in safety critical applications such as nuclear power plants involves partitioning of the overall system functionality into sub-parts and implementing each sub-part in hardware and/or software as appropriate. With increasing use of programmable devices like FPGA, the hardware subsystems are often implemented in Hardware Description Languages (HDL) like VHDL. Since the functional bugs in such hardware subsystems used in safety critical C and I systems have serious consequences, it is important to use rigorous reasoning to verify the functionalities of the HDL models. This report describes the design of a software tool named VBMC (VHDL Bounded Model Checker). The capability of this tool is in proving/refuting functional properties of hardware designs described in VHDL. VBMC accepts design as a VHDL program file, functional property in PSL, and verification bound (number of cycles of operation) as inputs. It either reports that the design satisfies the functional property for the given verification bound or generates a counterexample providing the reason of violation. In case of satisfaction, the proof holds good for the verification bound. VBMC has been used for the functional verification of FPGA based intelligent I/O boards developed at Reactor Control Division, BARC. (author)

  4. North Korea's nuclear weapons program:verification priorities and new challenges.

    Energy Technology Data Exchange (ETDEWEB)

    Moon, Duk-ho (Korean Consulate General in New York)

    2003-12-01

    A comprehensive settlement of the North Korean nuclear issue may involve military, economic, political, and diplomatic components, many of which will require verification to ensure reciprocal implementation. This paper sets out potential verification methodologies that might address a wide range of objectives. The inspection requirements set by the International Atomic Energy Agency form the foundation, first as defined at the time of the Agreed Framework in 1994, and now as modified by the events since revelation of the North Korean uranium enrichment program in October 2002. In addition, refreezing the reprocessing facility and 5 MWe reactor, taking possession of possible weapons components and destroying weaponization capabilities add many new verification tasks. The paper also considers several measures for the short-term freezing of the North's nuclear weapon program during the process of negotiations, should that process be protracted. New inspection technologies and monitoring tools are applicable to North Korean facilities and may offer improved approaches over those envisioned just a few years ago. These are noted, and potential bilateral and regional verification regimes are examined.

  5. 77 FR 47302 - South Dakota: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-08-08

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... EPA proposed to authorize South Dakota's State Hazardous waste management Program revisions published... to the hazardous waste program revisions submitted by South Dakota. The Agency published a Proposed...

  6. Systems analysis programs for Hands-on integrated reliability evaluations (SAPHIRE) Version 5.0: Verification and validation (V ampersand V) manual. Volume 9

    International Nuclear Information System (INIS)

    Jones, J.L.; Calley, M.B.; Capps, E.L.; Zeigler, S.L.; Galyean, W.J.; Novack, S.D.; Smith, C.L.; Wolfram, L.M.

    1995-03-01

    A verification and validation (V ampersand V) process has been performed for the System Analysis Programs for Hands-on Integrated Reliability Evaluation (SAPHIRE) Version 5.0. SAPHIRE is a set of four computer programs that NRC developed for performing probabilistic risk assessments. They allow an analyst to perform many of the functions necessary to create, quantify, and evaluate the risk associated with a facility or process being analyzed. The programs are Integrated Reliability and Risk Analysis System (IRRAS) System Analysis and Risk Assessment (SARA), Models And Results Database (MAR-D), and Fault tree, Event tree, and Piping and instrumentation diagram (FEP) graphical editor. Intent of this program is to perform a V ampersand V of successive versions of SAPHIRE. Previous efforts have been the V ampersand V of SAPHIRE Version 4.0. The SAPHIRE 5.0 V ampersand V plan is based on the SAPHIRE 4.0 V ampersand V plan with revisions to incorporate lessons learned from the previous effort. Also, the SAPHIRE 5.0 vital and nonvital test procedures are based on the test procedures from SAPHIRE 4.0 with revisions to include the new SAPHIRE 5.0 features as well as to incorporate lessons learned from the previous effort. Most results from the testing were acceptable; however, some discrepancies between expected code operation and actual code operation were identified. Modifications made to SAPHIRE are identified

  7. On Verification of PLC-Programs Written in the LD-Language

    Directory of Open Access Journals (Sweden)

    E. V. Kuzmin

    2012-01-01

    Full Text Available We discuss some questions connected with the construction of a technology of analysing correctness of Programmable Logic Controller programs. We consider an example of modeling and automated verification of PLC-programs written in the Ladder Diagram language (including timed function blocks of the IEC 61131-3 standard. We use the Cadence SMV for symbolic model checking. Program properties are written in the linear-time temporal logic LTL.

  8. Dynamic Frames Based Verification Method for Concurrent Java Programs

    NARCIS (Netherlands)

    Mostowski, Wojciech

    2016-01-01

    In this paper we discuss a verification method for concurrent Java programs based on the concept of dynamic frames. We build on our earlier work that proposes a new, symbolic permission system for concurrent reasoning and we provide the following new contributions. First, we describe our approach

  9. Practical Formal Verification of MPI and Thread Programs

    Science.gov (United States)

    Gopalakrishnan, Ganesh; Kirby, Robert M.

    Large-scale simulation codes in science and engineering are written using the Message Passing Interface (MPI). Shared memory threads are widely used directly, or to implement higher level programming abstractions. Traditional debugging methods for MPI or thread programs are incapable of providing useful formal guarantees about coverage. They get bogged down in the sheer number of interleavings (schedules), often missing shallow bugs. In this tutorial we will introduce two practical formal verification tools: ISP (for MPI C programs) and Inspect (for Pthread C programs). Unlike other formal verification tools, ISP and Inspect run directly on user source codes (much like a debugger). They pursue only the relevant set of process interleavings, using our own customized Dynamic Partial Order Reduction algorithms. For a given test harness, DPOR allows these tools to guarantee the absence of deadlocks, instrumented MPI object leaks and communication races (using ISP), and shared memory races (using Inspect). ISP and Inspect have been used to verify large pieces of code: in excess of 10,000 lines of MPI/C for ISP in under 5 seconds, and about 5,000 lines of Pthread/C code in a few hours (and much faster with the use of a cluster or by exploiting special cases such as symmetry) for Inspect. We will also demonstrate the Microsoft Visual Studio and Eclipse Parallel Tools Platform integrations of ISP (these will be available on the LiveCD).

  10. Nuclear Regulatory Commission Human Factors Program Plan. Revision 2

    International Nuclear Information System (INIS)

    1986-04-01

    This document is the Second Annual Revision to the NRC Human Factors Program Plan. The first edition was published in August 1983. Revision 1 was published in July of 1984. Purpose of the NRC Human Factors Program is to ensure that proper consideration is given to human factors in the design and operation of nuclear power plants. This document describes the plans of the Office of Nuclear Reactor Regulation to address high priority human factors concerns of importance to reactor safety in FY 1986 and FY 1987. Revision 2 of the plan incorporates recent Commission decisions and policies bearing on the human factors aspects of reactor safety regulation. With a few exceptions, the principal changes from prior editions reflect a shift from developing new requirements to staff evaluation of industry progress in resolving human factors issues. The plan addresses seven major program elements: (1) Training, (2) Licensing Examinations, (3) Procedures, (4) Man-Machine Interface, (5) Staffing and Qualifications, (6) Management and Organization, and (7) Human Performance

  11. Construction and Verification of PLC LD-programs by LTL-specification

    Directory of Open Access Journals (Sweden)

    E. V. Kuzmin

    2013-01-01

    Full Text Available An approach to construction and verification of PLC LD-programs for discrete problems is proposed. For the specification of the program behavior, we use the linear-time temporal logic LTL. Programming is carried out in the LD-language (Ladder Diagram according to an LTL-specification. The correctness analysis of an LTL-specification is carried out by the symbolic model checking tool Cadence SMV. A new approach to programming and verification of PLC LD-programs is shown by an example. For a discrete problem, we give a LD-program, its LTL-specification and an SMV-model. The purpose of the article is to describe an approach to programming PLC, which would provide a possibility of LD-program correctness analysis by the model checking method. Under the proposed approach, the change of the value of each program variable is described by a pair of LTL-formulas. The first LTL-formula describes situations which increase the value of the corresponding variable, the second LTL-formula specifies conditions leading to a decrease of the variable value. The LTL-formulas (used for speci- fication of the corresponding variable behavior are constructive in the sense that they construct the PLC-program (LD-program, which satisfies temporal properties expressed by these formulas. Thus, the programming of PLC is reduced to the construction of LTLspecification of the behavior of each program variable. In addition, an SMV-model of a PLC LD-program is constructed according to LTL-specification. Then, the SMV-model is analysed by the symbolic model checking tool Cadence SMV.

  12. 76 FR 62303 - California: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2011-10-07

    ... State Hazardous Waste Management Program Revision AGENCY: Environmental Protection Agency (EPA). ACTION... the revisions to California's hazardous waste management program shall be effective at 1 p.m. on... implement the RCRA hazardous waste management program. EPA granted authorization for changes to California's...

  13. 75 FR 918 - Oregon: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2010-01-07

    ... Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental Protection Agency (EPA... hazardous waste management program under the Resource Conservation and Recovery Act, as amended (RCRA). On... has decided that the revisions to the Oregon hazardous waste management program satisfy all of the...

  14. Proceedings Fifth International Workshop on Verification and Program Transformation

    OpenAIRE

    Lisitsa, Alexei; Nemytykh, Andrei P.; Proietti, Maurizio

    2017-01-01

    We extend a technique called Compiling Control. The technique transforms coroutining logic programs into logic programs that, when executed under the standard left-to-right selection rule (and not using any delay features) have the same computational behavior as the coroutining program. In recent work, we revised Compiling Control and reformulated it as an instance of Abstract Conjunctive Partial Deduction. This work was mostly focused on the program analysis performed in Compiling Control. I...

  15. Electric and hybrid vehicle self-certification and verification procedures: Market Demonstration Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-03-01

    The process by which a manufacturer of an electric or hybrid vehicle certifies that his vehicle meets the DOE Performance Standards for Demonstration is described. Such certification is required for any vehicles to be purchased under the Market Demonstration Program. It also explains the verification testing process followed by DOE for testing to verify compliance. Finally, the document outlines manufacturer responsibilities and presents procedures for recertification of vehicles that have failed verification testing.

  16. Nuclear test ban verification

    International Nuclear Information System (INIS)

    Chun, Kin-Yip

    1991-07-01

    This report describes verification and its rationale, the basic tasks of seismic verification, the physical basis for earthquake/explosion source discrimination and explosion yield determination, the technical problems pertaining to seismic monitoring of underground nuclear tests, the basic problem-solving strategy deployed by the forensic seismology resarch team at the University of Toronto, and the scientific significance of the team's research. The research carried out at the Univeristy of Toronto has two components: teleseismic verification using P wave recordings from the Yellowknife Seismic Array (YKA), and regional (close-in) verification using high-frequency L g and P n recordings from the Eastern Canada Telemetered Network. Major differences have been found in P was attenuation among the propagation paths connecting the YKA listening post with seven active nuclear explosion testing areas in the world. Significant revisions have been made to previously published P wave attenuation results, leading to more interpretable nuclear explosion source functions. (11 refs., 12 figs.)

  17. Verification of Imperative Programs by Constraint Logic Program Transformation

    Directory of Open Access Journals (Sweden)

    Emanuele De Angelis

    2013-09-01

    Full Text Available We present a method for verifying partial correctness properties of imperative programs that manipulate integers and arrays by using techniques based on the transformation of constraint logic programs (CLP. We use CLP as a metalanguage for representing imperative programs, their executions, and their properties. First, we encode the correctness of an imperative program, say prog, as the negation of a predicate 'incorrect' defined by a CLP program T. By construction, 'incorrect' holds in the least model of T if and only if the execution of prog from an initial configuration eventually halts in an error configuration. Then, we apply to program T a sequence of transformations that preserve its least model semantics. These transformations are based on well-known transformation rules, such as unfolding and folding, guided by suitable transformation strategies, such as specialization and generalization. The objective of the transformations is to derive a new CLP program TransfT where the predicate 'incorrect' is defined either by (i the fact 'incorrect.' (and in this case prog is not correct, or by (ii the empty set of clauses (and in this case prog is correct. In the case where we derive a CLP program such that neither (i nor (ii holds, we iterate the transformation. Since the problem is undecidable, this process may not terminate. We show through examples that our method can be applied in a rather systematic way, and is amenable to automation by transferring to the field of program verification many techniques developed in the field of program transformation.

  18. Revision 2 of the NPP Krsko Decommissioning Program Is Stalled

    International Nuclear Information System (INIS)

    Levanat, I.; Lokner, V.; Rapic, A.; Zeleznik, N.; Kralj, M.

    2012-01-01

    Revision 2 of the joint Slovenian-Croatian Program of NPP Krsko Decommissioning and SF andLILW Disposal was scheduled to be finished and formally approved by the end of 2009, in accordance with the bilateral Agreement on the NPP. Slightly behind the schedule, the Project team completed the entire document during spring of 2010, and in June 2010 drafted a proposal for a peer review of the Program by a dedicated IAEA expert mission. This procedure was agreed upon at the last session (May 2010) of the Intergovernmental Commission for implementation of the Agreement, when the Commission was acquainted with the five scenarios of the Revision 2 and with the estimates of their costs/financing. It was expected that the peer review would be performed soon, and that formal adoption of the Revision 2 would follow. Although in this process of approval some decisions remained to be made by the stakeholders, the Project team did select and recommend one scenario to be used for costing purposes, in order to ensure that most necessary corrections in Program financing would be timely adopted. However, the planned IAEA review was cancelled by the Advisory board, the body nominated by the Commission ''to supervise the activities and resolve the issues raised by the Project team''. By this cancellation, the process of Program revision was effectively stalled, because the Advisory board could not clearly define further course of action: differing views between the Slovenian and the Croatian part of the Advisory board appeared, in particular regarding the set of Program scenarios and regarding the appropriateness of the Revision 2 document for the IAEA review; nonetheless, the Advisory board sent to the Project team a compilation of requests to modify Revision 2 document. The Project team determined that some minor requests were easy to fulfill, but other modifications could only be carried out after changes in the boundary conditions (approved by the Commission), or changes in national

  19. 75 FR 48815 - Medicaid Program and Children's Health Insurance Program (CHIP); Revisions to the Medicaid...

    Science.gov (United States)

    2010-08-11

    ... Parts 431, 447, and 457 Medicaid Program and Children's Health Insurance Program (CHIP); Revisions to... 431, 447, and 457 [CMS-6150-F] RIN 0938-AP69 Medicaid Program and Children's Health Insurance Program... final rule implements provisions from the Children's Health Insurance Program Reauthorization Act of...

  20. 76 FR 18927 - Oklahoma: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2011-04-06

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental... hazardous waste management program. We authorized the following revisions: Oklahoma received authorization... accordance with 40 CFR 271.21. The Oklahoma Hazardous Waste Management Act (``OHWMA'') provides the ODEQ with...

  1. Transforming PLC Programs into Formal Models for Verification Purposes

    CERN Document Server

    Darvas, D; Blanco, E

    2013-01-01

    Most of CERN’s industrial installations rely on PLC-based (Programmable Logic Controller) control systems developed using the UNICOS framework. This framework contains common, reusable program modules and their correctness is a high priority. Testing is already applied to find errors, but this method has limitations. In this work an approach is proposed to transform automatically PLC programs into formal models, with the goal of applying formal verification to ensure their correctness. We target model checking which is a precise, mathematical-based method to check formalized requirements automatically against the system.

  2. Emergency Doses (ED) - Revision 3: A calculator code for environmental dose computations

    International Nuclear Information System (INIS)

    Rittmann, P.D.

    1990-12-01

    The calculator program ED (Emergency Doses) was developed from several HP-41CV calculator programs documented in the report Seven Health Physics Calculator Programs for the HP-41CV, RHO-HS-ST-5P (Rittman 1984). The program was developed to enable estimates of offsite impacts more rapidly and reliably than was possible with the software available for emergency response at that time. The ED - Revision 3, documented in this report, revises the inhalation dose model to match that of ICRP 30, and adds the simple estimates for air concentration downwind from a chemical release. In addition, the method for calculating the Pasquill dispersion parameters was revised to match the GENII code within the limitations of a hand-held calculator (e.g., plume rise and building wake effects are not included). The summary report generator for printed output, which had been present in the code from the original version, was eliminated in Revision 3 to make room for the dispersion model, the chemical release portion, and the methods of looping back to an input menu until there is no further no change. This program runs on the Hewlett-Packard programmable calculators known as the HP-41CV and the HP-41CX. The documentation for ED - Revision 3 includes a guide for users, sample problems, detailed verification tests and results, model descriptions, code description (with program listing), and independent peer review. This software is intended to be used by individuals with some training in the use of air transport models. There are some user inputs that require intelligent application of the model to the actual conditions of the accident. The results calculated using ED - Revision 3 are only correct to the extent allowed by the mathematical models. 9 refs., 36 tabs

  3. 78 FR 54200 - Virginia: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-09-03

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R03-RCRA-2012-0294; FRL-9900-37-Region3] Virginia: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... of revisions to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA...

  4. Revised experimental program on the nuclear ship 'Mutsu'

    International Nuclear Information System (INIS)

    Mori, Yuichi

    1985-01-01

    The experimental program on the nuclear ship ''Mutsu'' has been revised by the Government. And, the responsible organization for n. s. Mutsu was turned to Japan Atomic Energy Research Institute (JAERI) from Japan Nuclear-ship Development Agency. The revised, new experimental program is as follows. (1) Experimental navigation of n. s. Mutsu is made with the already loaded 1st reactor core for about one year. (2) The mooring port for n. s. Mutsu is in a minimum scale. (3) Upon termination of the experimental navigation, n. s. Mutsu is immediately decommissioned. (4) Power-up test and experimental navigation of n. s. Mutsu are made in fiscal 1989 to 1990. The policy of research and development with n. s. Mutsu and the works assigned to JAERI with n. s. Mutsu are described. (Mori, K.)

  5. Data verification and evaluation techniques for groundwater monitoring programs

    International Nuclear Information System (INIS)

    Mercier, T.M.; Turner, R.R.

    1990-12-01

    To ensure that data resulting from groundwater monitoring programs are of the quality required to fulfill program objectives, it is suggested that a program of data verification and evaluation be implemented. These procedures are meant to supplement and support the existing laboratory quality control/quality assurance programs by identifying aberrant data resulting from a variety of unforeseen circumstances: sampling problems, data transformations in the lab, data input at the lab, data transfer, end-user data input. Using common-sense principles, pattern recognition techniques, and hydrogeological principles, a computer program was written which scans the data for suspected abnormalities and produces a text file stating sample identifiers, the suspect data, and a statement of how the data has departed from the expected. The techniques described in this paper have been developed to support the Y-12 Plant Groundwater Protection Program Management Plan

  6. 75 FR 52976 - Issuance of Revised Users' Manual for Commission Mediation Program for Investigations Under...

    Science.gov (United States)

    2010-08-30

    ... INTERNATIONAL TRADE COMMISSION Issuance of Revised Users' Manual for Commission Mediation Program... 65615 (Nov. 8, 2008). The Commission has determined to issue a revised Users' Manual for its program for the mediation of investigations under section 337 of the Tariff Act of 1930. The revised Users' Manual...

  7. Dynamic Isotope Power System: technology verification phase, program plan, 1 October 1978

    International Nuclear Information System (INIS)

    1979-01-01

    The technology verification phase program plan of the Dynamic Isotope Power System (DIPS) project is presented. DIPS is a project to develop a 0.5 to 2.0 kW power system for spacecraft using an isotope heat source and a closed-cycle Rankine power-system with an organic working fluid. The technology verification phase's purposes are to increase the system efficiency to over 18%, to demonstrate system reliability, and to provide an estimate for flight test scheduling. Progress toward these goals is reported

  8. 76 FR 45253 - Public Water Supply Supervision Program; Program Revision for the State of Alaska

    Science.gov (United States)

    2011-07-28

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL-9444-8] Public Water Supply Supervision Program; Program... Water Supply Supervision Primacy Program. Alaska has adopted regulations analogous to the EPA's Ground Water Rule. The EPA has determined that these revisions are no less stringent than the corresponding...

  9. Revised GCFR safety program plan

    International Nuclear Information System (INIS)

    Kelley, A.P.; Boyack, B.E.; Torri, A.

    1980-05-01

    This paper presents a summary of the recently revised gas-cooled fast breeder reactor (GCFR) safety program plan. The activities under this plan are organized to support six lines of protection (LOPs) for protection of the public from postulated GCFR accidents. Each LOP provides an independent, sequential, quantifiable risk barrier between the public and the radiological hazards associated with postulated GCFR accidents. To implement a quantitative risk-based approach in identifying the important technology requirements for each LOP, frequency and consequence-limiting goals are allocated to each. To ensure that all necessary tasks are covered to achieve these goals, the program plan is broken into a work breakdown structure (WBS). Finally, the means by which the plan is being implemented are discussed

  10. 22 CFR 518.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-04-01

    ... GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 518.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or program as approved during the...

  11. ENVIRONMENTAL TECHNOLOGY VERIFICATION PROGRAM: PROTOCOL FOR THE VERIFICATION OF GROUTING MATERIALS FOR INFRASTRUCTURE REHABILITATION AT THE UNIVERSITY OF HOUSTON - CIGMAT

    Science.gov (United States)

    This protocol was developed under the Environmental Protection Agency's Environmental Technology Verification (ETV) Program, and is intended to be used as a guide in preparing laboratory test plans for the purpose of verifying the performance of grouting materials used for infra...

  12. SARP-II: Safeguards Accounting and Reports Program, Revised

    International Nuclear Information System (INIS)

    Kempf, C.R.

    1994-01-01

    A computer code, SARP (Safeguards Accounting and Reports Program) which will generate and maintain at-facility safeguards accounting records, and generate IAEA safeguards reports based on accounting data input by the user, was completed in 1990 by the Safeguards, Safety, and Nonproliferation Division (formerly the Technical Support Organization) at Brookhaven National Laboratory as a task under the US Program of Technical Support to IAEA safeguards. The code was based on a State System of Accounting for and Control of Nuclear Material (SSAC) for off-load refueled power reactor facilities, with model facility and safeguards accounting regime as described in IAEA Safeguards Publication STR-165. Since 1990, improvements in computing capabilities and comments and suggestions from users engendered revision of the original code. The result is an updated, revised version called SARP-II which is discussed in this report

  13. 34 CFR 74.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ... WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 74.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or program as approved during the award process. It may...

  14. DOE-EPRI distributed wind Turbine Verification Program (TVP III)

    Energy Technology Data Exchange (ETDEWEB)

    McGowin, C.; DeMeo, E. [Electric Power Research Institute, Palo Alto, CA (United States); Calvert, S. [Dept. of Energy, Washington, DC (United States)] [and others

    1997-12-31

    In 1992, the Electric Power Research Institute (EPRI) and the U.S. Department of Energy (DOE) initiated the Utility Wind Turbine Verification Program (TVP). The goal of the program is to evaluate prototype advanced wind turbines at several sites developed by U.S. electric utility companies. Two six MW wind projects have been installed under the TVP program by Central and South West Services in Fort Davis, Texas and Green Mountain Power Corporation in Searsburg, Vermont. In early 1997, DOE and EPRI selected five more utility projects to evaluate distributed wind generation using smaller {open_quotes}clusters{close_quotes} of wind turbines connected directly to the electricity distribution system. This paper presents an overview of the objectives, scope, and status of the EPRI-DOE TVP program and the existing and planned TVP projects.

  15. Waste Management Program management plan. Revision 1

    International Nuclear Information System (INIS)

    1997-02-01

    As the prime contractor to the Department of Energy Idaho Operations Office (DOE-ID), Lockheed Martin Idaho Technologies Company (LMITCO) provides comprehensive waste management services to all contractors at the Idaho National Engineering and Environmental Laboratory (INEEL) through the Waste Management (WM) Program. This Program Management Plan (PMP) provides an overview of the Waste Management Program objectives, organization and management practices, and scope of work. This document will be reviewed at least annually and updated as needed to address revisions to the Waste Management's objectives, organization and management practices, and scope of work. Waste Management Program is managed by LMITCO Waste Operations Directorate. The Waste Management Program manages transuranic, low-level, mixed low-level, hazardous, special-case, and industrial wastes generated at or transported to the INEEL

  16. Computer program user's manual for FIREFINDER digital topographic data verification library dubbing system

    Science.gov (United States)

    Ceres, M.; Heselton, L. R., III

    1981-11-01

    This manual describes the computer programs for the FIREFINDER Digital Topographic Data Verification-Library-Dubbing System (FFDTDVLDS), and will assist in the maintenance of these programs. The manual contains detailed flow diagrams and associated descriptions for each computer program routine and subroutine. Complete computer program listings are also included. This information should be used when changes are made in the computer programs. The operating system has been designed to minimize operator intervention.

  17. 200 area liquid effluent facility quality assurance program plan. Revision 1

    International Nuclear Information System (INIS)

    Sullivan, N.J.

    1995-01-01

    Direct revision of Supporting Document WHC-SD-LEF-QAPP-001, Rev. 0. 200 Area Liquid Effluent Facilities Quality Assurance Program Plan. Incorporates changes to references in tables. Revises test to incorporate WHC-SD-LEF-CSCM-001, Computer Software Configuration Management Plan for 200 East/West Liquid Effluent Facilities

  18. 340 and 310 drawing field verification

    International Nuclear Information System (INIS)

    Langdon, J.

    1996-01-01

    The purpose of the drawing field verification work plan is to provide reliable drawings for the 310 Treated Effluent Disposal Facility (TEDF) and 340 Waste Handling Facility (340 Facility). The initial scope of this work plan is to provide field verified and updated versions of all the 340 Facility essential drawings. This plan can also be used for field verification of any other drawings that the facility management directs to be so updated. Any drawings revised by this work plan will be issued in an AutoCAD format

  19. The NRC measurement verification program

    International Nuclear Information System (INIS)

    Pham, T.N.; Ong, L.D.Y.

    1995-01-01

    A perspective is presented on the US Nuclear Regulatory Commission (NRC) approach for effectively monitoring the measurement methods and directly testing the capability and performance of licensee measurement systems. A main objective in material control and accounting (MC and A) inspection activities is to assure the accuracy and precision of the accounting system and the absence of potential process anomalies through overall accountability. The primary means of verification remains the NRC random sampling during routine safeguards inspections. This involves the independent testing of licensee measurement performance with statistical sampling plans for physical inventories, item control, and auditing. A prospective cost-effective alternative overcheck is also discussed in terms of an externally coordinated sample exchange or ''round robin'' program among participating fuel cycle facilities in order to verify the quality of measurement systems, i.e., to assure that analytical measurement results are free of bias

  20. Empirical Tests and Preliminary Results with the Krakatoa Tool for Full Static Program Verification

    Directory of Open Access Journals (Sweden)

    Ramírez-de León Edgar Darío

    2014-10-01

    Full Text Available XJML (Ramírez et al., 2012 is a modular external platform for Verification and Validation of Java classes using the Java Modeling Language (JML through contracts written in XML. One problem faced in the XJML development was how to integrate Full Static Program Verification (FSPV. This paper presents the experiments and results that allowed us to define what tool to embed in XJML to execute FSPV.

  1. 78 FR 70255 - West Virginia: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-11-25

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R03-RCRA-2013-0571; FRL-9903-07-Region 3] West Virginia: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY... final authorization of revisions to its hazardous waste program under the Resource Conservation and...

  2. 77 FR 10373 - Greenhouse Gas Reporting Program: Electronics Manufacturing: Revisions to Heat Transfer Fluid...

    Science.gov (United States)

    2012-02-22

    ... Greenhouse Gas Reporting Program: Electronics Manufacturing: Revisions to Heat Transfer Fluid Provisions... technical revisions to the electronics manufacturing source category of the Greenhouse Gas Reporting Rule... final rule will also be available through the WWW on the EPA's Greenhouse Gas Reporting Program Web site...

  3. 40 CFR 30.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ... FEDERAL ASSISTANCE UNIFORM ADMINISTRATIVE REQUIREMENTS FOR GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 30.25 Revision of budget and program plans. (a) The budget plan is the financial...

  4. 45 CFR 74.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-10-01

    ... ADMINISTRATIVE REQUIREMENTS FOR AWARDS AND SUBAWARDS TO INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, OTHER NONPROFIT ORGANIZATIONS, AND COMMERCIAL ORGANIZATIONS Post-Award Requirements Financial and Program Management § 74.25 Revision of budget and program plans. (a) The budget plan is the financial expression of...

  5. Waste Management Program management plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-01

    As the prime contractor to the Department of Energy Idaho Operations Office (DOE-ID), Lockheed Martin Idaho Technologies Company (LMITCO) provides comprehensive waste management services to all contractors at the Idaho National Engineering and Environmental Laboratory (INEEL) through the Waste Management (WM) Program. This Program Management Plan (PMP) provides an overview of the Waste Management Program objectives, organization and management practices, and scope of work. This document will be reviewed at least annually and updated as needed to address revisions to the Waste Management`s objectives, organization and management practices, and scope of work. Waste Management Program is managed by LMITCO Waste Operations Directorate. The Waste Management Program manages transuranic, low-level, mixed low-level, hazardous, special-case, and industrial wastes generated at or transported to the INEEL.

  6. 20 CFR 435.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-04-01

    ... GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, OTHER NON-PROFIT ORGANIZATIONS, AND COMMERCIAL ORGANIZATIONS Post-Award Requirements Financial and Program Management § 435.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or...

  7. 38 CFR 49.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) UNIFORM ADMINISTRATIVE REQUIREMENTS FOR GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 49.25 Revision of budget and program plans. (a) The budget plan is the financial expression of...

  8. 45 CFR 2543.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-10-01

    ... AND COMMUNITY SERVICE GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 2543.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or...

  9. As-Built Verification Plan Spent Nuclear Fuel Canister Storage Building MCO Handling Machine

    International Nuclear Information System (INIS)

    SWENSON, C.E.

    2000-01-01

    This as-built verification plan outlines the methodology and responsibilities that will be implemented during the as-built field verification activity for the Canister Storage Building (CSB) MCO HANDLING MACHINE (MHM). This as-built verification plan covers THE ELECTRICAL PORTION of the CONSTRUCTION PERFORMED BY POWER CITY UNDER CONTRACT TO MOWAT. The as-built verifications will be performed in accordance Administrative Procedure AP 6-012-00, Spent Nuclear Fuel Project As-Built Verification Plan Development Process, revision I. The results of the verification walkdown will be documented in a verification walkdown completion package, approved by the Design Authority (DA), and maintained in the CSB project files

  10. Reliability program plan for the Kilowatt Isotope Power System (KIPS) technology verification phase

    International Nuclear Information System (INIS)

    1978-01-01

    Ths document is an integral part of the Kilowatt Isotope Power System (KIPS) Program Plan. This document defines the KIPS Reliability Program Plan for the Technology Verification Phase. This document delineates the reliability assurance tasks that are to be accomplished by Sundstrand and its suppliers during the design, fabrication and testing of the KIPS

  11. EQ3/6 software test and verification report 9/94

    International Nuclear Information System (INIS)

    Kishi, T.

    1996-02-01

    This document is the Software Test and Verification Report (STVR) for the EQ3/6 suite of codes as stipulated in the Individual Software Plan for Initial Qualification of EQ3/6 (ISP-NF-07, Revision 1, 11/25/92). The software codes, EQPT, EQ3NR, EQ6, and the software library EQLIB constitute the EQ3/6 software package. This software test and verification project for EQ3/6 was started under the requirements of the LLNL Yucca Mountain Project Software Quality Assurance Plan (SQAP), Revision 0, December 14, 1989, but QP 3.2, Revision 2, June 21, 1994 is now the operative controlling procedure. This is a ''V and V'' report in the language of QP 3.2, Revision 2. Because the author of this report does not have a background in geochemistry, other technical sources were consulted in order to acquire some familiarity with geochemisty, the terminology minology involved, and to review comparable computational methods especially, geochemical aqueous speciation-solubility calculations. The software for the EQ3/6 package consists of approximately 47,000 lines of FORTRAN77 source code and nine on platforms ranging from workstations to supercomputers. The physical control of EQ3/6 software package and documentation is on a SUN SPARC station. Walkthroughs of each principal software packages, EQPT, EQ3NR, and EQ6 were conducted in order to understand the computational procedures involved, to determine any commonality in procedures, and then to establish a plan for the test and verification of EQ3/6. It became evident that all three phases depended upon solving an n x n matrix by the Newton-Raphson Method. Thus, a great deal of emphasis on the test and verification of this procedure was carried out on the first code in the software package EQPT

  12. EQ3/6 software test and verification report 9/94

    Energy Technology Data Exchange (ETDEWEB)

    Kishi, T.

    1996-02-01

    This document is the Software Test and Verification Report (STVR) for the EQ3/6 suite of codes as stipulated in the Individual Software Plan for Initial Qualification of EQ3/6 (ISP-NF-07, Revision 1, 11/25/92). The software codes, EQPT, EQ3NR, EQ6, and the software library EQLIB constitute the EQ3/6 software package. This software test and verification project for EQ3/6 was started under the requirements of the LLNL Yucca Mountain Project Software Quality Assurance Plan (SQAP), Revision 0, December 14, 1989, but QP 3.2, Revision 2, June 21, 1994 is now the operative controlling procedure. This is a ``V and V`` report in the language of QP 3.2, Revision 2. Because the author of this report does not have a background in geochemistry, other technical sources were consulted in order to acquire some familiarity with geochemisty, the terminology minology involved, and to review comparable computational methods especially, geochemical aqueous speciation-solubility calculations. The software for the EQ3/6 package consists of approximately 47,000 lines of FORTRAN77 source code and nine on platforms ranging from workstations to supercomputers. The physical control of EQ3/6 software package and documentation is on a SUN SPARC station. Walkthroughs of each principal software packages, EQPT, EQ3NR, and EQ6 were conducted in order to understand the computational procedures involved, to determine any commonality in procedures, and then to establish a plan for the test and verification of EQ3/6. It became evident that all three phases depended upon solving an n x n matrix by the Newton-Raphson Method. Thus, a great deal of emphasis on the test and verification of this procedure was carried out on the first code in the software package EQPT.

  13. A Verification Logic for GOAL Agents

    Science.gov (United States)

    Hindriks, K. V.

    Although there has been a growing body of literature on verification of agents programs, it has been difficult to design a verification logic for agent programs that fully characterizes such programs and to connect agent programs to agent theory. The challenge is to define an agent programming language that defines a computational framework but also allows for a logical characterization useful for verification. The agent programming language GOAL has been originally designed to connect agent programming to agent theory and we present additional results here that GOAL agents can be fully represented by a logical theory. GOAL agents can thus be said to execute the corresponding logical theory.

  14. Program Verification with Monadic Second-Order Logic & Languages for Web Service Development

    DEFF Research Database (Denmark)

    Møller, Anders

    applications, this implementation forms the basis of a verification technique for imperative programs that perform data-type operations using pointers. To achieve this, the basic logic is extended with layers of language abstractions. Also, a language for expressing data structures and operations along...

  15. 22 CFR 145.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-04-01

    ... Section 145.25 Foreign Relations DEPARTMENT OF STATE CIVIL RIGHTS GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 145.25 Revision of budget and program plans. (a) The budget plan is the...

  16. 28 CFR 70.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ... REQUIREMENTS FOR GRANTS AND AGREEMENTS (INCLUDING SUBAWARDS) WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS AND OTHER NON-PROFIT ORGANIZATIONS Post-Award Requirements Financial and Program Management § 70.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or...

  17. 15 CFR 14.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-01-01

    ... ADMINISTRATIVE REQUIREMENTS FOR GRANTS AND AGREEMENTS WITH INSTITUTIONS OF HIGHER EDUCATION, HOSPITALS, OTHER NON-PROFIT, AND COMMERCIAL ORGANIZATIONS Post-Award Requirements Financial and Program Management § 14.25 Revision of budget and program plans. (a) The budget plan is the financial expression of the project or...

  18. Revised Severe Accident Research Program plan, FY 1990--1992

    International Nuclear Information System (INIS)

    1989-08-01

    For the past 10 years, since the Three Mile Island accident, the NRC has sponsored an active research program on light-water-reactor severe accidents as part of a multi-faceted approach to reactor safety. This report describes the revised Severe Accident Research Program (SARP) and how the revisions are designed to provide confirmatory information and technical support to the NRC staff in implementing the staff's Integration Plan for Closure of Severe Accident Issues as described in SECY-88-147. The revised SARP addresses both the near-term research directed at providing a technical basis upon which decisions on important containment performance issues can be made and the long-term research needed to confirm and refine our understanding of severe accidents. In developing this plan, the staff recognized that the overall goal is to reduce the uncertainties in the source term sufficiently to enable the staff to make regulatory decisions on severe accident issues. However, the staff also recognized that for some issues it may not be practical to attempt to further reduce uncertainties, and some regulatory decisions or conclusions will have to be made with full awareness of existing uncertainties. 2 figs., 1 tab

  19. 36 CFR 1210.25 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ... may, at its option, restrict the transfer of funds among direct cost categories or programs, functions... or the objective of the project or program (even if there is no associated budget revision requiring... funds allotted for training allowances (direct payment to trainees) to other categories of expense. (8...

  20. 76 FR 41186 - Salmonella Verification Sampling Program: Response to Comments on New Agency Policies and...

    Science.gov (United States)

    2011-07-13

    ... Service [Docket No. FSIS-2008-0008] Salmonella Verification Sampling Program: Response to Comments on New Agency Policies and Clarification of Timeline for the Salmonella Initiative Program (SIP) AGENCY: Food... Federal Register notice (73 FR 4767- 4774), which described upcoming policy changes in the FSIS Salmonella...

  1. WASTE CERTIFICATION PROGRAM PLAN - REVISION 7

    International Nuclear Information System (INIS)

    MORGAN, LK

    2002-01-01

    The primary changes that have been made to this revision reflect the relocation of the Waste Certification Official (WCO) organizationally from the Quality Services Division (QSD) into the Laboratory Waste Services (LWS) Organization. Additionally, the responsibilities for program oversight have been differentiated between the QSD and LWS. The intent of this effort is to ensure that those oversight functions, which properly belonged to the WCO, moved with that function; but retain an independent oversight function outside of the LWS Organization ensuring the potential for introduction of organizational bias, regarding programmatic and technical issues, is minimized. The Waste Certification Program (WCP) itself has been modified to allow the waste certification function to be performed by any of the personnel within the LWS Waste Acceptance/Certification functional area. However, a single individual may not perform both the technical waste acceptance review and the final certification review on the same 2109 data package. Those reviews must be performed by separate individuals in a peer review process. There will continue to be a designated WCO who will have lead programmatic responsibility for the WCP and will exercise overall program operational oversite as well as determine the overall requirements of the certification program. The quality assurance organization will perform independent, outside oversight to ensure that any organizational bias does not degrade the integrity of the waste certification process. The core elements of the previous WCP have been retained, however, the terms and process structure have been modified.. There are now two ''control points,'' (1) the data package enters the waste certification process with the signature of the Generator Interface/Generator Interface Equivalent (GI/GIE), (2) the package is ''certified'', thus exiting the process. The WCP contains three steps, (1) the technical review for waste acceptance, (2) a review of the

  2. 78 FR 25678 - Georgia: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-05-02

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... of changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA... Gwendolyn Gleaton, Permits and State Programs Section, RCRA Programs and Materials Management Branch, RCRA...

  3. 76 FR 6594 - Florida: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-02-07

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... of the changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA... and State Programs Section, RCRA Programs and Materials Management Branch, RCRA Division, U.S...

  4. 77 FR 60963 - Tennessee: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-10-05

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... of the changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA... Johnson, Permits and State Programs Section, RCRA Programs and Materials Management Branch, RCRA Division...

  5. 77 FR 24148 - Revision to the Hawaii State Implementation Plan, Minor New Source Review Program

    Science.gov (United States)

    2012-04-23

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 52 [EPA-R09-OAR-2012-0213; FRL-9661-6] Revision to the Hawaii State Implementation Plan, Minor New Source Review Program AGENCY: Environmental Protection Agency... final action to approve revisions to the Hawaii State Implementation Plan (SIP). These revisions would...

  6. Translation of PLC Programs to x86 for Simulation and Verification

    CERN Document Server

    Sallai, Gyula

    2017-01-01

    PLC programs are written in special languages, variants of the languages defined in the IEC 61131 standard. These programs cannot be directly executed on personal computers (on x86 architecture). To perform simulation of the PLC program or diagnostics during development, either a real PLC or a PLC simulator has to be used. However, these solutions are often inflexible and they do not provide appropriate performance. By generating x86-representations (semantically equivalent programs which can be executed on PCs, e.g. written in C, C++ or Java) of the PLC programs, some of these challenges could be met. PLCverif is a PLC program verification tool developed at CERN which includes a parser for Siemens PLC programs. In this work, we describe a code generator based on this parser of PLCverif. This work explores the possibilities and challenges of generating programs in widely-used general purpose languages from PLC programs, and provides a proof-of-concept code generation implementation. The presented solution dem...

  7. Verification and Planning Based on Coinductive Logic Programming

    Science.gov (United States)

    Bansal, Ajay; Min, Richard; Simon, Luke; Mallya, Ajay; Gupta, Gopal

    2008-01-01

    Coinduction is a powerful technique for reasoning about unfounded sets, unbounded structures, infinite automata, and interactive computations [6]. Where induction corresponds to least fixed point's semantics, coinduction corresponds to greatest fixed point semantics. Recently coinduction has been incorporated into logic programming and an elegant operational semantics developed for it [11, 12]. This operational semantics is the greatest fix point counterpart of SLD resolution (SLD resolution imparts operational semantics to least fix point based computations) and is termed co- SLD resolution. In co-SLD resolution, a predicate goal p( t) succeeds if it unifies with one of its ancestor calls. In addition, rational infinite terms are allowed as arguments of predicates. Infinite terms are represented as solutions to unification equations and the occurs check is omitted during the unification process. Coinductive Logic Programming (Co-LP) and Co-SLD resolution can be used to elegantly perform model checking and planning. A combined SLD and Co-SLD resolution based LP system forms the common basis for planning, scheduling, verification, model checking, and constraint solving [9, 4]. This is achieved by amalgamating SLD resolution, co-SLD resolution, and constraint logic programming [13] in a single logic programming system. Given that parallelism in logic programs can be implicitly exploited [8], complex, compute-intensive applications (planning, scheduling, model checking, etc.) can be executed in parallel on multi-core machines. Parallel execution can result in speed-ups as well as in larger instances of the problems being solved. In the remainder we elaborate on (i) how planning can be elegantly and efficiently performed under real-time constraints, (ii) how real-time systems can be elegantly and efficiently model- checked, as well as (iii) how hybrid systems can be verified in a combined system with both co-SLD and SLD resolution. Implementations of co-SLD resolution

  8. U.S. ENVIRONMENTAL PROTECTION AGENCY (EPA) ENVIRONMENTAL TECHNOLOGY VERIFICATION (ETV) PROGRAM: ARSENIC MONITORING TECHNOLOGIES

    Science.gov (United States)

    The U.S. Environmental Protection Agency Environmental Technology Verification (ETV) program evaluates the performance of innovative air, water, pollution prevention and monitoring technologies that have the potential to improve human health and the environment. This technology ...

  9. 75 FR 60398 - California: Proposed Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2010-09-30

    ...: Proposed Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental... its hazardous waste management program by November 1, 2010. ADDRESSES: Submit your comments... waste management program. EPA continues to have independent enforcement authority under RCRA sections...

  10. U.S. ENVIRONMENTAL PROTECTION AGENCY (EPA) ENVIRONMENTAL TECHNOLOGY VERIFICATION (ETV) PROGRAM: ARSENIC TREATMENT TECHNOLOGIES

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) Environmental Technology Verification (ETV) program evaluates the performance of innovative air, water, pollution prevention and monitoring technologies that have the potential to improve human health and the environment. This techn...

  11. 75 FR 69660 - Cross-Media Electronic Reporting Rule State Authorized Program Revision Approval: State of Hawaii

    Science.gov (United States)

    2010-11-15

    ... Authorized Program Revision Approval: State of Hawaii AGENCY: Environmental Protection Agency (EPA). ACTION... Reporting, of the State of Hawaii's request to revise certain of its EPA-authorized programs to allow... meet the applicable subpart D requirements. On February 16, 2010, the State of Hawaii Department of...

  12. 77 FR 65351 - Missouri: Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-10-26

    ...: Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental Protection Agency (EPA... Jackson-Johnson, Environmental Protection Agency, Waste Enforcement & Materials Management Branch, 11201... its hazardous waste program under the Resource Conservation and Recovery Act (RCRA). EPA proposes to...

  13. 76 FR 37021 - Louisiana: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2011-06-24

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental... implement its base Hazardous Waste Management Program. We granted authorization for changes to their program... opportunity to apply for final authorization to operate all aspects of their hazardous waste management...

  14. Modelling and Formal Verification of Timing Aspects in Large PLC Programs

    CERN Document Server

    Fernandez Adiego, B; Blanco Vinuela, E; Tournier, J-C; Gonzalez Suarez, V M; Blech, J O

    2014-01-01

    One of the main obstacle that prevents model checking from being widely used in industrial control systems is the complexity of building formal models out of PLC programs, especially when timing aspects need to be integrated. This paper brings an answer to this obstacle by proposing a methodology to model and verify timing aspects of PLC programs. Two approaches are proposed to allow the users to balance the trade-off between the complexity of the model, i.e. its number of states, and the set of specifications possible to be verified. A tool supporting the methodology which allows to produce models for different model checkers directly from PLC programs has been developed. Verification of timing aspects for real-life PLC programs are presented in this paper using NuSMV.

  15. Application of the SQUG-GIP to the seismic upgrade program of the Savannah River reactors

    International Nuclear Information System (INIS)

    Antaki, G.A.

    1991-01-01

    In August 1991, the Savannah River Site (SRS) seismic evaluation program using the Generic Implementation Procedure (GIP) celebrated its third anniversary-a respectable age for such a new methodology. During these three years, the GIP, developed for the commercial nuclear industry's Seismic Qualification Utility Group (SQUG), had evolved through Revision 01, Revision 1, Revision 2 and a Revision 2 open-quotes updateclose quotes which is currently in the works. This evolution is not surprising for such an important, and in many ways pioneering, document. The various revisions were anticipated at SRS, and the program adjusted accordingly. The verification of seismic adequacy of equipment at the SRS nuclear reactors has been outlined in previous publications. The purpose of this paper is to relate the more practical and managerial aspects of our relatively mature SQUG-GIP implementation program, which will hopefully prove useful to future users of the GIP. This report is divided into four sections, which follow the normal flow of work under GIP: (1) Program Prerequisites; (2) Definition of Scope; (3) Equipment Evaluations; and (4) Resolution of Outliers

  16. 77 FR 60919 - Tennessee: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-10-05

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental..., Division of Solid Waste Management, 5th Floor, L & C Tower, 401 Church Street, Nashville, Tennessee 37243... RCRA hazardous waste management program. We granted authorization for changes to Tennessee's program on...

  17. Verification of a Program for the Control of a Robotic Workcell with the Use of AR

    Directory of Open Access Journals (Sweden)

    Jozef Novak-Marcincin

    2012-08-01

    Full Text Available This paper contributes in the form of a theoretical discussion and also, by the presentation of a practical example, brings information about the utilization possibilities of elements of augmented reality for the creation of programs for the control of a robotic workplace and for their simulated verification. In the beginning it provides an overview of the current state in the area of robotic systems with the use of unreal objects and describes existing and assumed attitudes. The next part describes an experimental robotic workplace. Then it clarifies the realization of a new way of verification of the program for robotic workplace control and provides information about the possibilities for further development of created functioning concepts.

  18. 77 FR 61326 - Indiana: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2012-10-09

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental... RCRA hazardous waste management program. We granted authorization for changes to their program on... 202. Hazardous Waste Management July 30, 2003; 68 329 IAC 3.1-6-2(16); System; Identification and FR...

  19. Field Verification Program for Small Wind Turbines, Quartelry Report: 2nd Quarter, Issue No.1, October 2000

    Energy Technology Data Exchange (ETDEWEB)

    Tu, P.; Forsyth, T.

    2000-11-02

    The Field Verification Program for Small Wind Turbines quarterly report provides industry members with a description of the program, its mission, and purpose. It also provides a vehicle for participants to report performance data, activities, and issues during quarterly test periods.

  20. Nuclear Data Verification and Standardization

    Energy Technology Data Exchange (ETDEWEB)

    Karam, Lisa R.; Arif, Muhammad; Thompson, Alan K.

    2011-10-01

    The objective of this interagency program is to provide accurate neutron interaction verification and standardization data for the U.S. Department of Energy Division of Nuclear Physics programs which include astrophysics, radioactive beam studies, and heavy-ion reactions. The measurements made in this program are also useful to other programs that indirectly use the unique properties of the neutron for diagnostic and analytical purposes. These include homeland security, personnel health and safety, nuclear waste disposal, treaty verification, national defense, and nuclear based energy production. The work includes the verification of reference standard cross sections and related neutron data employing the unique facilities and capabilities at NIST and other laboratories as required; leadership and participation in international intercomparisons and collaborations; and the preservation of standard reference deposits. An essential element of the program is critical evaluation of neutron interaction data standards including international coordinations. Data testing of critical data for important applications is included. The program is jointly supported by the Department of Energy and the National Institute of Standards and Technology.

  1. 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.

  2. Spent Nuclear Fuel (SNF) Project Design Verification and Validation Process

    International Nuclear Information System (INIS)

    OLGUIN, L.J.

    2000-01-01

    This document provides a description of design verification and validation activities implemented by the Spent Nuclear Fuel (SNF) Project. During the execution of early design verification, a management assessment (Bergman, 1999) and external assessments on configuration management (Augustenburg, 1999) and testing (Loscoe, 2000) were conducted and identified potential uncertainties in the verification process. This led the SNF Chief Engineer to implement corrective actions to improve process and design products. This included Design Verification Reports (DVRs) for each subproject, validation assessments for testing, and verification of the safety function of systems and components identified in the Safety Equipment List to ensure that the design outputs were compliant with the SNF Technical Requirements. Although some activities are still in progress, the results of the DVR and associated validation assessments indicate that Project requirements for design verification are being effectively implemented. These results have been documented in subproject-specific technical documents (Table 2). Identified punch-list items are being dispositioned by the Project. As these remaining items are closed, the technical reports (Table 2) will be revised and reissued to document the results of this work

  3. REQUIREMENT VERIFICATION AND SYSTEMS ENGINEERING TECHNICAL REVIEW (SETR) ON A COMMERCIAL DERIVATIVE AIRCRAFT (CDA) PROGRAM

    Science.gov (United States)

    2017-09-01

    VERIFICATION AND SYSTEMS ENGINEERING TECHNICAL REVIEW (SETR) ON A COMMERCIAL DERIVATIVE AIRCRAFT (CDA) PROGRAM by Theresa L. Thomas September... ENGINEERING TECHNICAL REVIEW (SETR) ON A COMMERCIAL DERIVATIVE AIRCRAFT (CDA) PROGRAM 5. FUNDING NUMBERS 6. AUTHOR(S) Theresa L. Thomas 7...CODE 13. ABSTRACT (maximum 200 words) The Naval Air Systems Command (NAVAIR) systems engineering technical review (SETR) process does not

  4. 76 FR 6594 - North Carolina: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-02-07

    ... Carolina: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act... Section, RCRA Programs and Materials Management Branch, RCRA Division, U.S. Environmental Protection...

  5. HDM/PASCAL Verification System User's Manual

    Science.gov (United States)

    Hare, D.

    1983-01-01

    The HDM/Pascal verification system is a tool for proving the correctness of programs written in PASCAL and specified in the Hierarchical Development Methodology (HDM). This document assumes an understanding of PASCAL, HDM, program verification, and the STP system. The steps toward verification which this tool provides are parsing programs and specifications, checking the static semantics, and generating verification conditions. Some support functions are provided such as maintaining a data base, status management, and editing. The system runs under the TOPS-20 and TENEX operating systems and is written in INTERLISP. However, no knowledge is assumed of these operating systems or of INTERLISP. The system requires three executable files, HDMVCG, PARSE, and STP. Optionally, the editor EMACS should be on the system in order for the editor to work. The file HDMVCG is invoked to run the system. The files PARSE and STP are used as lower forks to perform the functions of parsing and proving.

  6. Verification Process of Behavioral Consistency between Design and Implementation programs of pSET using HW-CBMC

    International Nuclear Information System (INIS)

    Lee, Dong Ah; Lee, Jong Hoon; Yoo, Jun Beom

    2011-01-01

    Controllers in safety critical systems such as nuclear power plants often use Function Block Diagrams (FBDs) to design embedded software. The design is implemented using programming languages such as C to compile it into particular target hardware. The implementation must have the same behavior with the design and the behavior should be verified explicitly. For example, the pSET (POSAFE-Q Software Engineering Tool) is a loader software to program POSAFE-Q PLC (Programmable Logic Controller) and is developed as a part of the KNICS (Korea Nuclear Instrumentation and Control System R and D Center) project. It uses FBDs to design software of PLC, and generates ANSI-C code to compile it into specific machine code. To verify the equivalence between the FBDs and ANSI-C code, mathematical proof of code generator or a verification tools such as RETRANS can help guarantee the equivalence. Mathematical proof, however, has a weakness that requires high expenditure and repetitive fulfillment whenever the translator is modified. On the other hand, RETRANS reconstructs the generated source code without consideration of the generator. It has also a weakness that the reconstruction of generated code needs additional analysis This paper introduces verification process of behavioral consistency between design and its implementation of the pSET using the HW-CBMC. The HW-CBMC is a formal verification tool, verifying equivalence between hardware and software description. It requires two inputs for checking equivalence, Verilog for hard-ware and ANSI-C for software. In this approach, FBDs are translated into semantically equivalent Verilog pro-gram, and the HW-CBMC verifies equivalence between the Verilog program and the ANSI-C program which is generated from the FBDs

  7. Verification Process of Behavioral Consistency between Design and Implementation programs of pSET using HW-CBMC

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dong Ah; Lee, Jong Hoon; Yoo, Jun Beom [Konkuk University, Seoul (Korea, Republic of)

    2011-05-15

    Controllers in safety critical systems such as nuclear power plants often use Function Block Diagrams (FBDs) to design embedded software. The design is implemented using programming languages such as C to compile it into particular target hardware. The implementation must have the same behavior with the design and the behavior should be verified explicitly. For example, the pSET (POSAFE-Q Software Engineering Tool) is a loader software to program POSAFE-Q PLC (Programmable Logic Controller) and is developed as a part of the KNICS (Korea Nuclear Instrumentation and Control System R and D Center) project. It uses FBDs to design software of PLC, and generates ANSI-C code to compile it into specific machine code. To verify the equivalence between the FBDs and ANSI-C code, mathematical proof of code generator or a verification tools such as RETRANS can help guarantee the equivalence. Mathematical proof, however, has a weakness that requires high expenditure and repetitive fulfillment whenever the translator is modified. On the other hand, RETRANS reconstructs the generated source code without consideration of the generator. It has also a weakness that the reconstruction of generated code needs additional analysis This paper introduces verification process of behavioral consistency between design and its implementation of the pSET using the HW-CBMC. The HW-CBMC is a formal verification tool, verifying equivalence between hardware and software description. It requires two inputs for checking equivalence, Verilog for hard-ware and ANSI-C for software. In this approach, FBDs are translated into semantically equivalent Verilog pro-gram, and the HW-CBMC verifies equivalence between the Verilog program and the ANSI-C program which is generated from the FBDs

  8. Wind turbine power performance verification in complex terrain and wind farms

    DEFF Research Database (Denmark)

    Friis Pedersen, Troels; Gjerding, S.; Enevoldsen, P.

    2002-01-01

    is a power performance verification procedure for individual wind turbines. The third is a power performance measurement procedure of whole wind farms, and the fourth is a power performance measurement procedurefor non-grid (small) wind turbines. This report presents work that was made to support the basis......The IEC/EN 61400-12 Ed 1 standard for wind turbine power performance testing is being revised. The standard will be divided into four documents. The first one of these is more or less a revision of the existing document on power performance measurementson individual wind turbines. The second one...... then been investigated in more detail. The work has given rise to a range of conclusionsand recommendations regarding: guaranties on power curves in complex terrain; investors and bankers experience with verification of power curves; power performance in relation to regional correction curves for Denmark...

  9. Standard Verification System (SVS)

    Data.gov (United States)

    Social Security Administration — SVS is a mainframe program that accesses the NUMIDENT to perform SSN verifications. This program is called by SSA Internal applications to verify SSNs. There is also...

  10. 77 FR 15966 - Ohio: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2012-03-19

    ... Hazardous Waste Management Program Revision AGENCY: Environmental Protection Agency (EPA). ACTION: Final..., 1989 (54 FR 27170) to implement the RCRA hazardous waste management program. We granted authorization... Combustors; Final Rule, Checklist 198, February 14, 2002 (67 FR 6968); Hazardous Waste Management System...

  11. 76 FR 56708 - Ohio: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2011-09-14

    ... Hazardous Waste Management Program Revision AGENCY: Environmental Protection Agency (EPA). ACTION: Proposed..., 1989 (54 FR 27170) to implement the RCRA hazardous waste management program. We granted authorization... December 7, 2004. Waste Combustors; Final Rule; Checklist 198. Hazardous Waste Management March 13, 2002...

  12. 10 CFR 600.315 - Revision of budget and program plans.

    Science.gov (United States)

    2010-01-01

    ... revisions: (1) The transfer of funds among direct cost categories, functions, and activities for awards in... change in the scope or the objective of the project or program (even if there is no associated budget... accordance with the applicable costs principles for Federal funds and the requirements applicable to the...

  13. 77 FR 13200 - Texas: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2012-03-06

    ... Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental Protection Agency (EPA... December 26, 1984 (49 FR 48300), to implement its Base Hazardous Waste Management Program. This... Waste 53478, September Annotated Sections Management facilities. 8, 2005. 5.103 and 5.105 (Checklist 210...

  14. 77 FR 47797 - Arkansas: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-08-10

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R06-RCRA-2010-0307; FRL-9713-2] Arkansas: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  15. 76 FR 19004 - Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-04-06

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R06-RCRA-2010-0307; FRL-9290-9] Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  16. 78 FR 32223 - Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-05-29

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R06-RCRA-2012-0821; 9817-5] Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental Protection Agency (EPA... changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA). EPA...

  17. 77 FR 38566 - Louisiana: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-06-28

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA--R06-RCRA-2012-0367; FRL-9692-6] Louisiana: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  18. 78 FR 25579 - Georgia: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-05-02

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... adopted these requirements by reference at Georgia Hazardous Waste Management Rule 391-3-11-.07(1), EPA... authorization of changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA...

  19. 76 FR 37048 - Louisiana; Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-06-24

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R06-RCRA-2010-0307; FRL-9323-8] Louisiana; Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  20. 77 FR 15343 - Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-03-15

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R06-RCRA-2012-0054; FRL-9647-8] Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  1. 76 FR 6564 - Florida: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-02-07

    ... hazardous pharmaceutical waste to the list of wastes that may be managed under the Universal Waste rule...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  2. 32 CFR 34.15 - Revision of budget and program plans.

    Science.gov (United States)

    2010-07-01

    ... prior approvals are not required): (i) The transfer of funds among direct cost categories, functions and... or the objective of the project or program (even if there is no associated budget revision requiring... principles for Federal funds and recipients' cost share or match, in § 34.17 and § 34.13, respectively. (iv...

  3. 76 FR 69734 - Public Water System Supervision Program Revision for the State of New Mexico

    Science.gov (United States)

    2011-11-09

    ... Water System Supervision Program. New Mexico has adopted the Lead and Copper Rule Short Term Revisions... water. EPA has determined that this rule revision submitted by New Mexico is no less stringent than the... the following offices: New Mexico Environment Department, Drinking Water Bureau, 525 Camino De Los...

  4. Verification of RESRAD-build computer code, version 3.1

    International Nuclear Information System (INIS)

    2003-01-01

    RESRAD-BUILD is a computer model for analyzing the radiological doses resulting from the remediation and occupancy of buildings contaminated with radioactive material. It is part of a family of codes that includes RESRAD, RESRAD-CHEM, RESRAD-RECYCLE, RESRAD-BASELINE, and RESRAD-ECORISK. The RESRAD-BUILD models were developed and codified by Argonne National Laboratory (ANL); version 1.5 of the code and the user's manual were publicly released in 1994. The original version of the code was written for the Microsoft DOS operating system. However, subsequent versions of the code were written for the Microsoft Windows operating system. The purpose of the present verification task (which includes validation as defined in the standard) is to provide an independent review of the latest version of RESRAD-BUILD under the guidance provided by ANSI/ANS-10.4 for verification and validation of existing computer programs. This approach consists of a posteriori V and V review which takes advantage of available program development products as well as user experience. The purpose, as specified in ANSI/ANS-10.4, is to determine whether the program produces valid responses when used to analyze problems within a specific domain of applications, and to document the level of verification. The culmination of these efforts is the production of this formal Verification Report. The first step in performing the verification of an existing program was the preparation of a Verification Review Plan. The review plan consisted of identifying: Reason(s) why a posteriori verification is to be performed; Scope and objectives for the level of verification selected; Development products to be used for the review; Availability and use of user experience; and Actions to be taken to supplement missing or unavailable development products. The purpose, scope and objectives for the level of verification selected are described in this section of the Verification Report. The development products that were used

  5. Preparation of a program for the independent verification of the brachytherapy planning systems calculations

    International Nuclear Information System (INIS)

    V Carmona, V.; Perez-Calatayud, J.; Lliso, F.; Richart Sancho, J.; Ballester, F.; Pujades-Claumarchirant, M.C.; Munoz, M.

    2010-01-01

    In this work a program is presented that independently checks for each patient the treatment planning system calculations in low dose rate, high dose rate and pulsed dose rate brachytherapy. The treatment planning system output text files are automatically loaded in this program in order to get the source coordinates, the desired calculation point coordinates and the dwell times when it is the case. The source strength and the reference dates are introduced by the user. The program allows implementing the recommendations about independent verification of the clinical brachytherapy dosimetry in a simple and accurate way, in few minutes. (Author).

  6. A Practitioners Perspective on Verification

    Science.gov (United States)

    Steenburgh, R. A.

    2017-12-01

    NOAAs Space Weather Prediction Center offers a wide range of products and services to meet the needs of an equally wide range of customers. A robust verification program is essential to the informed use of model guidance and other tools by both forecasters and end users alike. In this talk, we present current SWPC practices and results, and examine emerging requirements and potential approaches to satisfy them. We explore the varying verification needs of forecasters and end users, as well as the role of subjective and objective verification. Finally, we describe a vehicle used in the meteorological community to unify approaches to model verification and facilitate intercomparison.

  7. Project W-320, WRSS PCP: Procedure implementation verification

    International Nuclear Information System (INIS)

    Bailey, J.W.

    1998-01-01

    This document provides verification that the methodology for the safe retrieval of high-heat waste from Tank 241-C-106 as specified in the WRSS Process Control Plan HNF-SD-PCP-013, Revision 1, has been adequately implemented into the Tank Waste Remediation System (TWRS) operational procedures. Tank 241-C-106 is listed on the High Heat Load Watch List

  8. 75 FR 50932 - Massachusetts: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2010-08-18

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental...-1990. FOR FURTHER INFORMATION CONTACT: Robin Biscaia, RCRA Waste Management Section, Office of Site... final [[Page 50933

  9. Automated Generation of Formal Models from ST Control Programs for Verification Purposes

    CERN Document Server

    Fernandez Adiego, B; Tournier, J-C; Blanco Vinuela, E; Blech, J-O; Gonzalez Suarez, V

    2014-01-01

    In large industrial control systems such as the ones installed at CERN, one of the main issues is the ability to verify the correct behaviour of the Programmable Logic Controller (PLC) programs. While manual and automated testing can achieve good results, some obvious problems remain unsolved such as the difficulty to check safety or liveness properties. This paper proposes a general methodology and a tool to verify PLC programs by automatically generating formal models for different model checkers out of ST code. The proposed methodology defines an automata-based formalism used as intermediate model (IM) to transform PLC programs written in ST language into different formal models for verification purposes. A tool based on Xtext has been implemented that automatically generates models for the NuSMV and UPPAAL model checkers and the BIP framework.

  10. In-core Instrument Subcritical Verification (INCISV) - Core Design Verification Method - 358

    International Nuclear Information System (INIS)

    Prible, M.C.; Heibel, M.D.; Conner, S.L.; Sebastiani, P.J.; Kistler, D.P.

    2010-01-01

    According to the standard on reload startup physics testing, ANSI/ANS 19.6.1, a plant must verify that the constructed core behaves sufficiently close to the designed core to confirm that the various safety analyses bound the actual behavior of the plant. A large portion of this verification must occur before the reactor operates at power. The INCISV Core Design Verification Method uses the unique characteristics of a Westinghouse Electric Company fixed in-core self powered detector design to perform core design verification after a core reload before power operation. A Vanadium self powered detector that spans the length of the active fuel region is capable of confirming the required core characteristics prior to power ascension; reactivity balance, shutdown margin, temperature coefficient and power distribution. Using a detector element that spans the length of the active fuel region inside the core provides a signal of total integrated flux. Measuring the integrated flux distributions and changes at various rodded conditions and plant temperatures, and comparing them to predicted flux levels, validates all core necessary core design characteristics. INCISV eliminates the dependence on various corrections and assumptions between the ex-core detectors and the core for traditional physics testing programs. This program also eliminates the need for special rod maneuvers which are infrequently performed by plant operators during typical core design verification testing and allows for safer startup activities. (authors)

  11. 78 FR 15299 - New York: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2013-03-11

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental... Waste program as addressed by the federal used oil management regulations that were published on..., New York Codes, Rules and Regulations (6 NYCRR), Volume A-2A, Hazardous Waste Management System...

  12. 75 FR 81187 - South Dakota: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2010-12-27

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental Protection Agency (EPA). ACTION: Proposed Rule. SUMMARY: The Solid Waste Disposal Act, as amended, commonly... Agency (EPA) to authorize states to operate their hazardous waste management programs in lieu of the...

  13. Civilian radioactive waste management program plan. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    This revision of the Civilian Radioactive Waste Management Program Plan describes the objectives of the Civilian Radioactive Waste management Program (Program) as prescribed by legislative mandate, and the technical achievements, schedule, and costs planned to complete these objectives. The Plan provides Program participants and stakeholders with an updated description of Program activities and milestones for fiscal years (FY) 1998 to 2003. It describes the steps the Program will undertake to provide a viability assessment of the Yucca Mountain site in 1998; prepare the Secretary of Energy`s site recommendation to the President in 2001, if the site is found to be suitable for development as a repository; and submit a license application to the Nuclear Regulatory Commission in 2002 for authorization to construct a repository. The Program`s ultimate challenge is to provide adequate assurance to society that an operating geologic repository at a specific site meets the required standards of safety. Chapter 1 describes the Program`s mission and vision, and summarizes the Program`s broad strategic objectives. Chapter 2 describes the Program`s approach to transform strategic objectives, strategies, and success measures to specific Program activities and milestones. Chapter 3 describes the activities and milestones currently projected by the Program for the next five years for the Yucca Mountain Site Characterization Project; the Waste Acceptance, Storage and Transportation Project; ad the Program Management Center. The appendices present information on the Nuclear Waste Policy Act of 1982, as amended, and the Energy Policy Act of 1992; the history of the Program; the Program`s organization chart; the Commission`s regulations, Disposal of High-Level Radioactive Wastes in geologic Repositories; and a glossary of terms.

  14. Numident Online Verification Utility (NOVU)

    Data.gov (United States)

    Social Security Administration — NOVU is a mainframe application that accesses the NUMIDENT to perform real-time SSN verifications. This program is called by other SSA online programs that serve as...

  15. Certainty in Stockpile Computing: Recommending a Verification and Validation Program for Scientific Software

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J.R.

    1998-11-01

    As computing assumes a more central role in managing the nuclear stockpile, the consequences of an erroneous computer simulation could be severe. Computational failures are common in other endeavors and have caused project failures, significant economic loss, and loss of life. This report examines the causes of software failure and proposes steps to mitigate them. A formal verification and validation program for scientific software is recommended and described.

  16. Verification and Optimization of a PLC Control Schedule

    NARCIS (Netherlands)

    Brinksma, Hendrik; Mader, Angelika H.; Havelund, K.; Penix, J.; Visser, W.

    We report on the use of the SPIN model checker for both the verification of a process control program and the derivation of optimal control schedules. This work was carried out as part of a case study for the EC VHS project (Verification of Hybrid Systems), in which the program for a Programmable

  17. 76 FR 6561 - North Carolina: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-02-07

    ... Carolina: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... December 31, 1984 (49 FR 48694) to implement its base hazardous waste management program. EPA granted... XV are from the North Carolina Hazardous Waste Management Rules 15A NCAC 13A, effective April 23...

  18. 78 FR 15338 - New York: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-03-11

    ... authorization of changes to its hazardous waste program under the Solid Waste Disposal Act, as amended, commonly... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R02-RCRA-2013-0144; FRL-9693-3] New York: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental...

  19. FY 1981 HTGR program summary-level program outline (revision 1/30/81)

    International Nuclear Information System (INIS)

    1981-01-01

    The objective of the DOE HTGR Program is the development of technology for the most important HTGR applications. Through this support, DOE seeks to encourage private sector initiatives which will lead to the development of commercially attractive HTGR applications that concurrently support national energy goals. Currently perceived as important to national energy goals are applications that primarily address the process heat market with a view toward reduction of national requirements for oil, natural gas and coal. A high priority during FY 1981, therefore, will be to further identify and define the details of the Technology Program so as to assure that it is both necessary and sufficient to provide the required support. In the establishment of a supportive Technology Program, key elements which will be addressed are as follows: studies will be conducted to further identify and characterize important unique HTGR applications and to evaluate their potential in the context of market opportunities, utility/user interest, and national objectives to develop new energy supply options; based upon the configurations and operating characteristics projected for selected applications, Technology Program requirements must be identified to support development, verification, and ultimately licensing of components and systems comprising the facilities of interest; and in the context of limited resources, sufficient analysis and evaluation must be accomplished so as to prioritize technology elements in accordance with appropriately developed criteria

  20. Civilian radioactive waste management program plan. Revision 2

    International Nuclear Information System (INIS)

    1998-07-01

    This revision of the Civilian Radioactive Waste Management Program Plan describes the objectives of the Civilian Radioactive Waste management Program (Program) as prescribed by legislative mandate, and the technical achievements, schedule, and costs planned to complete these objectives. The Plan provides Program participants and stakeholders with an updated description of Program activities and milestones for fiscal years (FY) 1998 to 2003. It describes the steps the Program will undertake to provide a viability assessment of the Yucca Mountain site in 1998; prepare the Secretary of Energy's site recommendation to the President in 2001, if the site is found to be suitable for development as a repository; and submit a license application to the Nuclear Regulatory Commission in 2002 for authorization to construct a repository. The Program's ultimate challenge is to provide adequate assurance to society that an operating geologic repository at a specific site meets the required standards of safety. Chapter 1 describes the Program's mission and vision, and summarizes the Program's broad strategic objectives. Chapter 2 describes the Program's approach to transform strategic objectives, strategies, and success measures to specific Program activities and milestones. Chapter 3 describes the activities and milestones currently projected by the Program for the next five years for the Yucca Mountain Site Characterization Project; the Waste Acceptance, Storage and Transportation Project; ad the Program Management Center. The appendices present information on the Nuclear Waste Policy Act of 1982, as amended, and the Energy Policy Act of 1992; the history of the Program; the Program's organization chart; the Commission's regulations, Disposal of High-Level Radioactive Wastes in geologic Repositories; and a glossary of terms

  1. Evaluation of the revised training program for senior control room staff: science fundamentals and equipment principles

    International Nuclear Information System (INIS)

    Jervis, R.E.; Evans, G.J.

    1996-10-01

    Canadian nuclear utilities have formed an Inter-Utility Working Group to revise their program for training nuclear generating station senior control room staff, namely Control Room Operators and Shift Supervisors, in Science Fundamentals and Equipment Principles. This report documents the findings of an external review of this revision process, addressing, amongst other topics, the process of revision undertaken by the Working Group, their outline of topics to be included, and, the pertinence and comprehensiveness of the detailed training objectives identified for two of the courses. The approach to revising the program being followed by the Working Group appears to be reasonable insomuch that some training needs have been identified and used to construct detailed sets of training objectives. However, as assessed by the consultants without full documentation being available, some important steps appear to have been missed. Specifically, much of the basis of the revision process has not been documented, neither has the approach selected for the revision process, nor has any justification for not performing a CANDU specific job and task analysis been offered. Furthermore, the Working Group has not yet proposed any criteria for evaluation of the program or provided any test items. As a result, the consultants have had to develop criteria for evaluation of the overall program and of individual courses. These criteria were applied in a more detailed review of the training objectives for two particular courses: Plant Chemistry, and Nuclear Physics and Reactor Theory. Many of the training objectives for these courses were found to be too qualitative or ones that require trainees to memorize blocks of information rather than develop in them an ability to arrive at conclusions about scientific phenomena using principles and reasoning. This assessment indicates that the training objectives are designed to achieve too low a level of cognition, inconsistent with developing an

  2. SU-E-T-455: Impact of Different Independent Dose Verification Software Programs for Secondary Check

    International Nuclear Information System (INIS)

    Itano, M; Yamazaki, T; Kosaka, M; Kobayashi, N; Yamashita, M; Ishibashi, S; Higuchi, Y; Tachibana, H

    2015-01-01

    Purpose: There have been many reports for different dose calculation algorithms for treatment planning system (TPS). Independent dose verification program (IndpPro) is essential to verify clinical plans from the TPS. However, the accuracy of different independent dose verification programs was not evident. We conducted a multi-institutional study to reveal the impact of different IndpPros using different TPSs. Methods: Three institutes participated in this study. They used two different IndpPros (RADCALC and Simple MU Analysis (SMU), which implemented the Clarkson algorithm. RADCALC needed the input of radiological path length (RPL) computed by the TPSs (Eclipse or Pinnacle3). SMU used CT images to compute the RPL independently from TPS). An ion-chamber measurement in water-equivalent phantom was performed to evaluate the accuracy of two IndpPros and the TPS in each institute. Next, the accuracy of dose calculation using the two IndpPros compared to TPS was assessed in clinical plan. Results: The accuracy of IndpPros and the TPSs in the homogenous phantom was +/−1% variation to the measurement. 1543 treatment fields were collected from the patients treated in the institutes. The RADCALC showed better accuracy (0.9 ± 2.2 %) than the SMU (1.7 ± 2.1 %). However, the accuracy was dependent on the TPS (Eclipse: 0.5%, Pinnacle3: 1.0%). The accuracy of RADCALC with Eclipse was similar to that of SMU in one of the institute. Conclusion: Depending on independent dose verification program, the accuracy shows systematic dose accuracy variation even though the measurement comparison showed a similar variation. The variation was affected by radiological path length calculation. IndpPro with Pinnacle3 has different variation because Pinnacle3 computed the RPL using physical density. Eclipse and SMU uses electron density, though

  3. Measurement and verification of low income energy efficiency programs in Brazil: Methodological challenges

    Energy Technology Data Exchange (ETDEWEB)

    Martino Jannuzzi, Gilberto De; Rodrigues da Silva, Ana Lucia; Melo, Conrado Augustus de; Paccola, Jose Angelo; Dourado Maia Gomes, Rodolfo (State Univ. of Campinas, International Energy Initiative (Brazil))

    2009-07-01

    Electric utilities in Brazil are investing about 80 million dollars annually in low-income energy efficiency programs, about half of their total compulsory investments in end-use efficiency programs under current regulation. Since 2007 the regulator has enforced the need to provide evaluation plans for the programs delivered. This paper presents the measurement and verification (MandV) methodology that has been developed to accommodate the characteristics of lighting and refrigerator programs that have been introduced in the Brazilian urban and peri-urban slums. A combination of household surveys, end-use measurements and metering at the transformers and grid levels were performed before and after the program implementation. The methodology has to accommodate the dynamics, housing, electrical wiring and connections of the population as well as their ability to pay for the electricity and program participation. Results obtained in slums in Rio de Janeiro are presented. Impacts of the programs were evaluated in energy terms to households and utilities. Feedback from the evaluations performed also permitted the improvement in the design of new programs for low-income households.

  4. 40 CFR 3.1000 - How does a state, tribe, or local government revise or modify its authorized program to allow...

    Science.gov (United States)

    2010-07-01

    ... government revise or modify its authorized program to allow electronic reporting? 3.1000 Section 3.1000... government revise or modify its authorized program to allow electronic reporting? (a) A state, tribe, or local government that receives or plans to begin receiving electronic documents in lieu of paper...

  5. ERD UMTRA Project quality assurance program plan, Revision 7

    International Nuclear Information System (INIS)

    1995-09-01

    This document is the revised Quality Assurance Program Plan (QAPP) dated September, 1995 for the Environmental Restoration Division (ERD) Uranium Mill Tailings Remedial Action Project (UMTRA). Quality Assurance requirements for the ERD UMTRA Project are based on the criteria outlined in DOE Order 5700.6C or applicable sections of 10 CFR 830.120. QA requirements contained in this QAPP shall apply to all personnel, processes, and activities, including planning, scheduling, and cost control, performed by the ERD UMTRA Project and its contractors

  6. Field Verification Program for Small Wind Turbines, Quarterly Report: 3rd Quarter, Issue No.2, July-September 2000

    Energy Technology Data Exchange (ETDEWEB)

    Cardinal. J.; Tu, P.

    2001-05-16

    This newsletter provides a brief overview of the Field Verification Program for Small Wind Turbines conducted out of the NWTC and a description of current activities. The newsletter also contains case studies of current projects.

  7. Computer Program of SIE ASME-NH (Revision 1.0) Code

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Gyeong Hoi; Lee, J. H

    2008-01-15

    In this report, the SIE ASME (Structural Integrity Evaluations by ASME-NH) (Revision 1.0), which has a computerized implementation of ASME Pressure Vessels and Piping Code Section III Subsection NH rules, is developed to apply to the next generation reactor design subjecting to the elevated temperature operations over 500 .deg. C and over 30 years design lifetime, and the user's manual for this program is described in detail.

  8. Computer Program of SIE ASME-NH (Revision 1.0) Code

    International Nuclear Information System (INIS)

    Koo, Gyeong Hoi; Lee, J. H.

    2008-01-01

    In this report, the SIE ASME (Structural Integrity Evaluations by ASME-NH) (Revision 1.0), which has a computerized implementation of ASME Pressure Vessels and Piping Code Section III Subsection NH rules, is developed to apply to the next generation reactor design subjecting to the elevated temperature operations over 500 .deg. C and over 30 years design lifetime, and the user's manual for this program is described in detail

  9. 76 FR 1431 - Public Water System Supervision Program Revision for the State of New Mexico

    Science.gov (United States)

    2011-01-10

    ... Public Water System Supervision Program. New Mexico has adopted the Ground Water Rule (GWR), the Long... the following offices: New Mexico Environment Department, Drinking Water Bureau, 525 Camino De Los... of New Mexico proposes to revise its approved Public Water System Supervision Primacy Program. This...

  10. Review of Evaluation, Measurement and Verification Approaches Used to Estimate the Load Impacts and Effectiveness of Energy Efficiency Programs

    Energy Technology Data Exchange (ETDEWEB)

    Messenger, Mike; Bharvirkar, Ranjit; Golemboski, Bill; Goldman, Charles A.; Schiller, Steven R.

    2010-04-14

    Public and private funding for end-use energy efficiency actions is expected to increase significantly in the United States over the next decade. For example, Barbose et al (2009) estimate that spending on ratepayer-funded energy efficiency programs in the U.S. could increase from $3.1 billion in 2008 to $7.5 and 12.4 billion by 2020 under their medium and high scenarios. This increase in spending could yield annual electric energy savings ranging from 0.58% - 0.93% of total U.S. retail sales in 2020, up from 0.34% of retail sales in 2008. Interest in and support for energy efficiency has broadened among national and state policymakers. Prominent examples include {approx}$18 billion in new funding for energy efficiency programs (e.g., State Energy Program, Weatherization, and Energy Efficiency and Conservation Block Grants) in the 2009 American Recovery and Reinvestment Act (ARRA). Increased funding for energy efficiency should result in more benefits as well as more scrutiny of these results. As energy efficiency becomes a more prominent component of the U.S. national energy strategy and policies, assessing the effectiveness and energy saving impacts of energy efficiency programs is likely to become increasingly important for policymakers and private and public funders of efficiency actions. Thus, it is critical that evaluation, measurement, and verification (EM&V) is carried out effectively and efficiently, which implies that: (1) Effective program evaluation, measurement, and verification (EM&V) methodologies and tools are available to key stakeholders (e.g., regulatory agencies, program administrators, consumers, and evaluation consultants); and (2) Capacity (people and infrastructure resources) is available to conduct EM&V activities and report results in ways that support program improvement and provide data that reliably compares achieved results against goals and similar programs in other jurisdictions (benchmarking). The National Action Plan for Energy

  11. Program plan for shipment, receipt, and storage of the TMI-2 core. Revision 1

    International Nuclear Information System (INIS)

    Quinn, G.J.; Reno, H.W.; Schmitt, R.C.

    1985-01-01

    This plan addresses the preparation and shipment of core debris from Three Mile Island Unit 2 (TMI-2) to the Idaho National Engineering Laboratory (INEL) and receipt and storage of that core debris. The Manager of the Nuclear Materials Evaluation Programs Division of EG and G Idaho, Inc. will manage two separate but integrated programs, one located at TMI (Part 1) and the other at INEL (Part 2). The Technical Integration Office (at TMI) is responsible for developing and implementing Part 1, TMI-2 Core Shipment Program. The Technical Support Branch (at INEL) is responsible for developing and implementing Part 2, TMI-2 Core Receipt and Storage. The plan described herein is a revision of a previous document entitled Plan for Shipment, Storage, and Examination of TMI-2 Fuel. This revision was required to delineate changes, primarily in Part 2, Core Activities Program, of the previous document. That part of the earlier document related to core examination was reidentified in mid-FY-1984 as a separate trackable entity entitled Core Sample Acquisition and Examination Project, which is not included here

  12. 75 FR 35720 - Massachusetts: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2010-06-23

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental...: Robin Biscaia, RCRA Waste Management Section, Office of Site Remediation and Restoration (OSRR 07-1... Courier: Deliver your comments to: Robin Biscaia, RCRA Waste Management Section, Office of Site...

  13. Hanford Site Groundwater Protection Management Program: Revision 1

    International Nuclear Information System (INIS)

    1993-11-01

    Groundwater protection is a national priority that is promulgated in a variety of environmental regulations at local, state, and federal levels. To effectively coordinate and ensure compliance with applicable regulations, the US Department of Energy has issued DOE Order 5400.1 (now under revision) that requires all US Department of Energy facilities to prepare separate groundwater protection program descriptions and plans. This document describes the Groundwater Protection Management Program for the Hanford Site located in the state of Washington. DOE Order 5400.1 specifies that the Groundwater Protection Management Program cover the following general topical areas: (1) documentation of the groundwater regime, (2) design and implementation of a groundwater monitoring program to support resource management and comply with applicable laws and regulations, (3) a management program for groundwater protection and remediation, (4) a summary and identification of areas that may be contaminated with hazardous waste, (5) strategies for controlling these sources, (6) a remedial action program, and (7) decontamination and decommissioning and related remedial action requirements. Many of the above elements are covered by existing programs at the Hanford Site; thus, one of the primary purposes of this document is to provide a framework for coordination of existing groundwater protection activities. Additionally, it describes how information needs are identified and can be incorporated into existing or proposed new programs. The Groundwater Protection Management Program provides the general scope, philosophy, and strategies for groundwater protection/management at the Hanford Site. Subtier documents provide the detailed plans for implementing groundwater-related activities and programs. Related schedule and budget information are provided in the 5-year plan for environmental restoration and waste management at the Hanford Site

  14. TWRS system drawings and field verification

    International Nuclear Information System (INIS)

    Shepard, D.G.

    1995-01-01

    The Configuration Management Program combines the TWRS Labeling and O and M drawing and drawing verification programs. The combined program will produce system drawings for systems that are normally operated or have maintenance performed on the system, label individual pieces of equipment for proper identification, even if system drawings are not warranted, and perform verification of drawings that are identified as essential in Tank Farm Essential Drawing Plans. During fiscal year 1994, work was begun to label Tank Farm components and provide user friendly system based drawings for Tank Waste Remediation System (TWRS) operations and maintenance. During the first half of fiscal 1995, the field verification program continued to convert TWRS drawings into CAD format and verify the accuracy based on visual inspections. During the remainder of fiscal year 1995 these efforts will be combined into a single program providing system based drawings and field verification of TWRS equipment and facilities. This combined program for TWRS will include all active systems for tank farms. Operations will determine the extent of drawing and labeling requirements for single shell tanks, i.e. the electrical distribution, HVAC, leak detection, and the radiation monitoring system. The tasks required to meet these objectives, include the following: identify system boundaries or scope for drawing being verified; label equipment/components in the process systems with a unique Equipment Identification Number (EIN) per the TWRS Data Standard; develop system drawings that are coordinated by ''smart'' drawing numbers and/or drawing references as identified on H-14-020000; develop a Master Equipment List (MEL) multi-user data base application which will contain key information about equipment identified in the field; and field verify and release TWRS Operation and Maintenance (O and M) drawings

  15. Integrated Verification Experiment data collected as part of the Los Alamos National Laboratory's Source Region Program

    Energy Technology Data Exchange (ETDEWEB)

    Whitaker, R.W.; Noel, S.D.

    1992-12-01

    The summary report by Tom Weaver gives the overall background for the series of IVE (Integrated Verification Experiment) experiments including information on the full set of measurements made. This appendix presents details of the infrasound data for the and discusses certain aspects of a few special experiments. Prior to FY90, the emphasis of the Infrasound Program was on underground nuclear test (UGT) detection and yield estimation. During this time the Infrasound Program was a separate program at Los Alamos, and it was suggested to DOE/OAC that a regional infrasound network be established around NTS. The IVE experiments took place in a time frame that allowed simultaneous testing of possible network sites and examination of propagation in different directions. Whenever possible, infrasound stations were combined with seismic stations so that a large number could be efficiently fielded. The regional infrasound network was not pursued by DOE, as world events began to change the direction of verification toward non-proliferation. Starting in FY90 the infrasound activity became part of the Source Region Program which has a goal of understanding how energy is transported from the UGT to a variety of measurement locations.

  16. Analysis and Transformation Tools for Constrained Horn Clause Verification

    DEFF Research Database (Denmark)

    Kafle, Bishoksan; Gallagher, John Patrick

    2014-01-01

    Several techniques and tools have been developed for verification of properties expressed as Horn clauses with constraints over a background theory (CHC). Current CHC verification tools implement intricate algorithms and are often limited to certain subclasses of CHC problems. Our aim in this work...... is to investigate the use of a combination of off-the-shelf techniques from the literature in analysis and transformation of Constraint Logic Programs (CLPs) to solve challenging CHC verification problems. We find that many problems can be solved using a combination of tools based on well-known techniques from...... abstract interpretation, semantics-preserving transformations, program specialisation and query-answer transformations. This gives insights into the design of automatic, more general CHC verification tools based on a library of components....

  17. Objective Oriented Design of System Thermal Hydraulic Analysis Program and Verification of Feasibility

    International Nuclear Information System (INIS)

    Chung, Bub Dong; Jeong, Jae Jun; Hwang, Moon Kyu

    2008-01-01

    The system safety analysis code, such as RELAP5, TRAC, CATHARE etc. have been developed based on Fortran language during the past few decades. Refactoring of conventional codes has been also performed to improve code readability and maintenance. TRACE, RELAP5-3D and MARS codes are examples of these activities. The codes were redesigned to have modular structures utilizing Fortran 90 features. However the programming paradigm in software technology has been changed to use objects oriented programming (OOP), which is based on several techniques, including encapsulation, modularity, polymorphism, and inheritance. It was not commonly used in mainstream software application development until the early 1990s. Many modern programming languages now support OOP. Although the recent Fortran language also support the OOP, it is considered to have limited functions compared to the modern software features. In this work, objective oriented program for system safety analysis code has been tried utilizing modern C language feature. The advantage of OOP has been discussed after verification of design feasibility

  18. 76 FR 28727 - Child Nutrition (CN) Labeling Program; Request for Extension and Revision of a Currently Approved...

    Science.gov (United States)

    2011-05-18

    ... (CN) Labeling Program; Request for Extension and Revision of a Currently Approved Information... INFORMATION: Title: Child Nutrition Labeling Program. OMB Number: 0581-0261 . Expiration Date of Approval: 3... collection. Abstract: The Child Nutrition (CN) Labeling Program is a voluntary technical assistance service...

  19. Field Verification Program for Small Wind Turbines: Quarterly Report for January-March 2001; 1st Quarter, Issue No.4

    Energy Technology Data Exchange (ETDEWEB)

    Forsyth, T.; Cardinal, J.

    2001-10-30

    This newsletter provides a brief overview of the Field Verification Program for Small Wind Turbines conducted out of the NWTC and a description of current activities. The newsletter also contains case studies of current projects.

  20. Field Verification Program for Small Wind Turbines: Quarterly Report for October-December 2000; 4th Quarter, Iss. No.3

    Energy Technology Data Exchange (ETDEWEB)

    Cardinal, J.

    2001-07-03

    This newsletter provides a brief overview of the Field Verification Program for Small Wind Turbines conducted out of the NWTC and a description of current activities. The newsletter also contains case studies of current projects.

  1. Formal verification of reactor process control software using assertion checking environment

    International Nuclear Information System (INIS)

    Sharma, Babita; Balaji, Sowmya; John, Ajith K.; Bhattacharjee, A.K.; Dhodapkar, S.D.

    2005-01-01

    Assertion Checking Environment (ACE) was developed in-house for carrying out formal (rigorous/ mathematical) functional verification of embedded software written in MISRA C. MISRA C is an industrially sponsored safe sub-set of C programming language and is well accepted in the automotive and aerospace industries. ACE uses static assertion checking technique for verification of MISRA C programs. First the functional specifications of the program are derived from the specifications in the form of pre- and post-conditions for each C function. These pre- and post-conditions are then introduced as assertions (formal comments) in the program code. The annotated C code is then formally verified using ACE. In this paper we present our experience of using ACE for the formal verification of process control software of a nuclear reactor. The Software Requirements Document (SRD) contained textual specifications of the process control software. The SRD was used by the designers to draw logic diagrams which were given as input to a code generator. The verification of the generated C code was done at 2 levels viz. (i) verification against specifications derived from logic diagrams, and (ii) verification against specifications derived from SRD. In this work we checked approximately 600 functional specifications of the software having roughly 15000 lines of code. (author)

  2. 77 FR 59311 - Federal Student Aid Programs (Student Assistance General Provisions, Federal Perkins Loan Program...

    Science.gov (United States)

    2012-09-27

    ... Colleague Letter GEN-04-03 (February 2004; revised November 2004). Verification of AGI and U.S. Income Tax... accept, in lieu of an income tax return for verification of AGI or income tax paid: A copy of IRS Form... or, for a self-employed individual, a statement signed by the individual certifying the amount of AGI...

  3. The revised program for measurements in intense operation mode according to AVV-IMIS

    International Nuclear Information System (INIS)

    Bieringer, J.; Wirth, E.; Buehling, A.; Mueller-Neumann, M.; Haase, G.; Heinrich, T.; Steinkopff, T.; Wiezorek, C.

    2007-01-01

    The monitoring program for measurements in intense operation mode has been revised recently by a working group at the Federal Ministry for Environment, Nature Conservation and Reactor Safety (BMU). The major issues of the revision are reported in this contribution. Measurements in intense operation must be appropriate for fast assessment of the radiological situation, for estimating the dose to the population and for decisions on countermeasures to minimize the dose. In order to meet these requirements the structure of the measurement program in intense operation mode was divided into three phases when different exposition paths are relevant: before and during dispersion of radioactive material, immediately after dispersion of radioactive material has ended and a late phase when contamination values have decreased in different environmental media. For each of these phases a special measurement program was defined that is tailored to achieve the above mentioned objectives. Minimum detectable activity concentrations were introduced similar to the measurement program in routine operation mode. They follow the intervention levels in the catalogue of countermeasures and maximum permitted values given by the European Union (EU) for food and animal feed. The minimum detectable activity concentrations were defined such that the detection of 1/10 of the intervention levels for countermeasures is ensured. (orig.)

  4. 76 FR 29805 - Submission for Review: Verification of Full-Time School Attendance, RI 25-49

    Science.gov (United States)

    2011-05-23

    ... other technological collection techniques or other forms of information technology, e.g., permitting... OFFICE OF PERSONNEL MANAGEMENT Submission for Review: Verification of Full-Time School Attendance... Federal agencies the opportunity to comment on a revised information collection request (ICR) 3206-0215...

  5. A Correctness Verification Technique for Commercial FPGA Synthesis Tools

    International Nuclear Information System (INIS)

    Kim, Eui Sub; Yoo, Jun Beom; Choi, Jong Gyun; Kim, Jang Yeol; Lee, Jang Soo

    2014-01-01

    Once the FPGA (Filed-Programmable Gate Array) designers designs Verilog programs, the commercial synthesis tools automatically translate the Verilog programs into EDIF programs so that the designers can have largely focused on HDL designs for correctness of functionality. Nuclear regulation authorities, however, require more considerate demonstration of the correctness and safety of mechanical synthesis processes of FPGA synthesis tools, even if the FPGA industry have acknowledged them empirically as correct and safe processes and tools. In order to assure of the safety, the industry standards for the safety of electronic/electrical devices, such as IEC 61508 and IEC 60880, recommend using the formal verification technique. There are several formal verification tools (i.e., 'FormalPro' 'Conformal' 'Formality' and so on) to verify the correctness of translation from Verilog into EDIF programs, but it is too expensive to use and hard to apply them to the works of 3rd-party developers. This paper proposes a formal verification technique which can contribute to the correctness demonstration in part. It formally checks the behavioral equivalence between Verilog and subsequently synthesized Net list with the VIS verification system. A Net list is an intermediate output of FPGA synthesis process, and EDIF is used as a standard format of Net lists. If the formal verification succeeds, then we can assure that the synthesis process from Verilog into Net list worked correctly at least for the Verilog used. In order to support the formal verification, we developed the mechanical translator 'EDIFtoBLIFMV,' which translates EDIF into BLIF-MV as an input front-end of VIS system, while preserving their behavior equivalence.. We performed the case study with an example of a preliminary version of RPS in a Korean nuclear power plant in order to provide the efficiency of the proposed formal verification technique and implemented translator. It

  6. A Correctness Verification Technique for Commercial FPGA Synthesis Tools

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Eui Sub; Yoo, Jun Beom [Konkuk University, Seoul (Korea, Republic of); Choi, Jong Gyun; Kim, Jang Yeol; Lee, Jang Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    Once the FPGA (Filed-Programmable Gate Array) designers designs Verilog programs, the commercial synthesis tools automatically translate the Verilog programs into EDIF programs so that the designers can have largely focused on HDL designs for correctness of functionality. Nuclear regulation authorities, however, require more considerate demonstration of the correctness and safety of mechanical synthesis processes of FPGA synthesis tools, even if the FPGA industry have acknowledged them empirically as correct and safe processes and tools. In order to assure of the safety, the industry standards for the safety of electronic/electrical devices, such as IEC 61508 and IEC 60880, recommend using the formal verification technique. There are several formal verification tools (i.e., 'FormalPro' 'Conformal' 'Formality' and so on) to verify the correctness of translation from Verilog into EDIF programs, but it is too expensive to use and hard to apply them to the works of 3rd-party developers. This paper proposes a formal verification technique which can contribute to the correctness demonstration in part. It formally checks the behavioral equivalence between Verilog and subsequently synthesized Net list with the VIS verification system. A Net list is an intermediate output of FPGA synthesis process, and EDIF is used as a standard format of Net lists. If the formal verification succeeds, then we can assure that the synthesis process from Verilog into Net list worked correctly at least for the Verilog used. In order to support the formal verification, we developed the mechanical translator 'EDIFtoBLIFMV,' which translates EDIF into BLIF-MV as an input front-end of VIS system, while preserving their behavior equivalence.. We performed the case study with an example of a preliminary version of RPS in a Korean nuclear power plant in order to provide the efficiency of the proposed formal verification technique and implemented translator. It

  7. Monitoring and verification R and D

    International Nuclear Information System (INIS)

    Pilat, Joseph F.; Budlong-Sylvester, Kory W.; Fearey, Bryan L.

    2011-01-01

    The 2010 Nuclear Posture Review (NPR) report outlined the Administration's approach to promoting the agenda put forward by President Obama in Prague on April 5, 2009. The NPR calls for a national monitoring and verification R and D program to meet future challenges arising from the Administration's nonproliferation, arms control and disarmament agenda. Verification of a follow-on to New START could have to address warheads and possibly components along with delivery capabilities. Deeper cuts and disarmament would need to address all of these elements along with nuclear weapon testing, nuclear material and weapon production facilities, virtual capabilities from old weapon and existing energy programs and undeclared capabilities. We only know how to address some elements of these challenges today, and the requirements may be more rigorous in the context of deeper cuts as well as disarmament. Moreover, there is a critical need for multiple options to sensitive problems and to address other challenges. There will be other verification challenges in a world of deeper cuts and disarmament, some of which we are already facing. At some point, if the reductions process is progressing, uncertainties about past nuclear materials and weapons production will have to be addressed. IAEA safeguards will need to continue to evolve to meet current and future challenges, and to take advantage of new technologies and approaches. Transparency/verification of nuclear and dual-use exports will also have to be addressed, and there will be a need to make nonproliferation measures more watertight and transparent. In this context, and recognizing we will face all of these challenges even if disarmament is not achieved, this paper will explore possible agreements and arrangements; verification challenges; gaps in monitoring and verification technologies and approaches; and the R and D required to address these gaps and other monitoring and verification challenges.

  8. Gamma-ray isotopic ratio measurements for the plutonium inventory verification program

    International Nuclear Information System (INIS)

    Lemming, J.F.; Haas, F.X.; Jarvis, J.Y.

    1976-01-01

    The Plutonium Inventory Verification Program at Mound Laboratory provides a nondestructive means of assaying bulk plutonium-bearing material. The assay is performed by combining the calorimetrically determined heat output of the sample and the relative abundances of the heat-producing isotopes. This report describes the method used for the nondestructive determination of plutonium-238, -240, -241 and americium-241 relative to plutonium-239 using gamma-ray spectroscopy for 93 percent plutonium-239 material. Comparison of chemical data on aliquots of samples to the nondestructive data shows accuracies of +-7 percent for 238 Pu/ 239 Pu, +-15 percent for 240 Pu/ 239 Pu, +- 3 percent for 241 Pu/ 239 Pu, and +-7 percent for 241 Am/ 239 Pu

  9. 78 FR 59661 - Revision of a Currently Approved Information Collection for the State Energy Program

    Science.gov (United States)

    2013-09-27

    ... the final version of the information collection request. The Department of Energy (DOE) invites public... information collection requests a revision and three-year extension of its State Energy Program, OMB Control...

  10. 78 FR 79654 - Vermont: Proposed Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-12-31

    ...] Vermont: Proposed Authorization of State Hazardous Waste Management Program Revisions AGENCY... Docket ID No. EPA-R01- RCRA-2013-0554, by mail to Sharon Leitch, RCRA Waste Management and UST Section..., RCRA Waste Management and UST Section, Office of Site Remediation and Restoration (OSRR07-1), US EPA...

  11. 7 CFR 272.11 - Systematic Alien Verification for Entitlements (SAVE) Program.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 4 2010-01-01 2010-01-01 false Systematic Alien Verification for Entitlements (SAVE... FOR PARTICIPATING STATE AGENCIES § 272.11 Systematic Alien Verification for Entitlements (SAVE... and Naturalization Service (INS), in order to verify the validity of documents provided by aliens...

  12. BAGHOUSE FILTRATION PRODUCTS VERIFICATION TESTING, HOW IT BENEFITS THE BOILER BAGHOUSE OPERATOR

    Science.gov (United States)

    The paper describes the Environmental Technology Verification (ETV) Program for baghouse filtration products developed by the Air Pollution Control Technology Verification Center, one of six Centers under the ETV Program, and discusses how it benefits boiler baghouse operators. A...

  13. ENVIRONMENTAL TECHNOLOGY VERIFICATION: TEST/QA PLAN FOR THE VERIFICATION TESTING OF SELECTIVE CATALYTIC REDUCTION CONTROL TECHNOLOGIES FOR HIGHWAY, NONROAD, AND STATIONARY USE DIESEL ENGINES

    Science.gov (United States)

    The U.S. Environmental Protection Agency established the Environmental Technology Verification Program to accelerate the development and commercialization of improved environmental technology through third party verification and reporting of product performance. Research Triangl...

  14. 75 FR 43478 - Rhode Island: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2010-07-26

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental.... Mail: Robin Biscaia, RCRA Waste Management Section, Office of Site Remediation and Restoration (OSRR 07... Delivery or Courier: Deliver your comments to: Robin Biscaia, RCRA Waste Management Section, Office of Site...

  15. 76 FR 31272 - Permanent Certification Program for Health Information Technology; Revisions to ONC-Approved...

    Science.gov (United States)

    2011-05-31

    ... Permanent Certification Program for Health Information Technology; Revisions to ONC-Approved Accreditor Processes AGENCY: Office of the National Coordinator for Health Information Technology (ONC), Department of... Coordinator for Health Information Technology (the National Coordinator) by section 3001(c)(5) of the Public...

  16. Wind turbine power performance verification in complex terrain and wind farms

    Energy Technology Data Exchange (ETDEWEB)

    Friis Pedersen, T.; Gjerding, S.; Ingham, P.; Enevoldsen, P.; Kjaer Hansen, J.; Kanstrup Joergensen, H.

    2002-04-01

    The IEC/EN 61400-12 Ed 1 standard for wind turbine power performance testing is being revised. The standard will be divided into four documents. The first one of these is more or less a revision of the existing document on power performance measurements on individual wind turbines. The second one is a power performance verification procedure for individual wind turbines. The third is a power performance measurement procedure of whole wind farms, and the fourth is a power performance measurement procedure for non-grid (small) wind turbines. This report presents work that was made to support the basis for this standardisation work. The work addressed experience from several national and international research projects and contractual and field experience gained within the wind energy community on this matter. The work was wide ranging and addressed 'grey' areas of knowledge regarding existing methodologies, which has then been investigated in more detail. The work has given rise to a range of conclusions and recommendations regarding: guaranties on power curves in complex terrain; investors and bankers experience with verification of power curves; power performance in relation to regional correction curves for Denmark; anemometry and the influence of inclined flow. (au)

  17. Removing Unnecessary Variables from Horn Clause Verification Conditions

    Directory of Open Access Journals (Sweden)

    Emanuele De Angelis

    2016-07-01

    Full Text Available Verification conditions (VCs are logical formulas whose satisfiability guarantees program correctness. We consider VCs in the form of constrained Horn clauses (CHC which are automatically generated from the encoding of (an interpreter of the operational semantics of the programming language. VCs are derived through program specialization based on the unfold/fold transformation rules and, as it often happens when specializing interpreters, they contain unnecessary variables, that is, variables which are not required for the correctness proofs of the programs under verification. In this paper we adapt to the CHC setting some of the techniques that were developed for removing unnecessary variables from logic programs, and we show that, in some cases, the application of these techniques increases the effectiveness of Horn clause solvers when proving program correctness.

  18. A static analysis tool set for assembler code verification

    International Nuclear Information System (INIS)

    Dhodapkar, S.D.; Bhattacharjee, A.K.; Sen, Gopa

    1991-01-01

    Software Verification and Validation (V and V) is an important step in assuring reliability and quality of the software. The verification of program source code forms an important part of the overall V and V activity. The static analysis tools described here are useful in verification of assembler code. The tool set consists of static analysers for Intel 8086 and Motorola 68000 assembly language programs. The analysers examine the program source code and generate information about control flow within the program modules, unreachable code, well-formation of modules, call dependency between modules etc. The analysis of loops detects unstructured loops and syntactically infinite loops. Software metrics relating to size and structural complexity are also computed. This report describes the salient features of the design, implementation and the user interface of the tool set. The outputs generated by the analyser are explained using examples taken from some projects analysed by this tool set. (author). 7 refs., 17 figs

  19. Systemverilog for verification a guide to learning the testbench language features

    CERN Document Server

    Spear, Chris

    2012-01-01

    Based on the highly successful second edition, this extended edition of SystemVerilog for Verification: A Guide to Learning the Testbench Language Features teaches all verification features of the SystemVerilog language, providing hundreds of examples to clearly explain the concepts and basic fundamentals. It contains materials for both the full-time verification engineer and the student learning this valuable skill. In the third edition, authors Chris Spear and Greg Tumbush start with how to verify a design, and then use that context to demonstrate the language features,  including the advantages and disadvantages of different styles, allowing readers to choose between alternatives. This textbook contains end-of-chapter exercises designed to enhance students’ understanding of the material. Other features of this revision include: New sections on static variables, print specifiers, and DPI from the 2009 IEEE language standard Descriptions of UVM features such as factories, the test registry, and the config...

  20. 76 FR 72636 - Permanent Certification Program for Health Information Technology; Revisions to ONC-Approved...

    Science.gov (United States)

    2011-11-25

    ... Permanent Certification Program for Health Information Technology; Revisions to ONC-Approved Accreditor Processes AGENCY: Office of the National Coordinator for Health Information Technology (ONC), Department of... Coordinator for Health Information Technology by section 3001(c)(5) of the Public Health Service Act (PHSA) as...

  1. Development of An Automatic Verification Program for Thermal-hydraulic System Codes

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J. Y.; Ahn, K. T.; Ko, S. H.; Kim, Y. S.; Kim, D. W. [Pusan National University, Busan (Korea, Republic of); Suh, J. S.; Cho, Y. S.; Jeong, J. J. [System Engineering and Technology Co., Daejeon (Korea, Republic of)

    2012-05-15

    As a project activity of the capstone design competitive exhibition, supported by the Education Center for Green Industry-friendly Fusion Technology (GIFT), we have developed a computer program which can automatically perform non-regression test, which is needed repeatedly during a developmental process of a thermal-hydraulic system code, such as the SPACE code. A non-regression test (NRT) is an approach to software testing. The purpose of the non-regression testing is to verify whether, after updating a given software application (in this case, the code), previous software functions have not been compromised. The goal is to prevent software regression, whereby adding new features results in software bugs. As the NRT is performed repeatedly, a lot of time and human resources will be needed during the development period of a code. It may cause development period delay. To reduce the cost and the human resources and to prevent wasting time, non-regression tests need to be automatized. As a tool to develop an automatic verification program, we have used Visual Basic for Application (VBA). VBA is an implementation of Microsoft's event-driven programming language Visual Basic 6 and its associated integrated development environment, which are built into most Microsoft Office applications (In this case, Excel)

  2. Development of An Automatic Verification Program for Thermal-hydraulic System Codes

    International Nuclear Information System (INIS)

    Lee, J. Y.; Ahn, K. T.; Ko, S. H.; Kim, Y. S.; Kim, D. W.; Suh, J. S.; Cho, Y. S.; Jeong, J. J.

    2012-01-01

    As a project activity of the capstone design competitive exhibition, supported by the Education Center for Green Industry-friendly Fusion Technology (GIFT), we have developed a computer program which can automatically perform non-regression test, which is needed repeatedly during a developmental process of a thermal-hydraulic system code, such as the SPACE code. A non-regression test (NRT) is an approach to software testing. The purpose of the non-regression testing is to verify whether, after updating a given software application (in this case, the code), previous software functions have not been compromised. The goal is to prevent software regression, whereby adding new features results in software bugs. As the NRT is performed repeatedly, a lot of time and human resources will be needed during the development period of a code. It may cause development period delay. To reduce the cost and the human resources and to prevent wasting time, non-regression tests need to be automatized. As a tool to develop an automatic verification program, we have used Visual Basic for Application (VBA). VBA is an implementation of Microsoft's event-driven programming language Visual Basic 6 and its associated integrated development environment, which are built into most Microsoft Office applications (In this case, Excel)

  3. SSME Alternate Turbopump Development Program: Design verification specification for high-pressure fuel turbopump

    Science.gov (United States)

    1989-01-01

    The design and verification requirements are defined which are appropriate to hardware at the detail, subassembly, component, and engine levels and to correlate these requirements to the development demonstrations which provides verification that design objectives are achieved. The high pressure fuel turbopump requirements verification matrix provides correlation between design requirements and the tests required to verify that the requirement have been met.

  4. Guidance document for revision of DOE Order 5820.2A, Radioactive Waste Technical Support Program. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Kudera, D.E.; McMurtrey, C.D.; Meagher, B.G.

    1993-04-01

    This document provides guidance for the revision of DOE Order 5820.2A, ``Radioactive Waste Management.`` Technical Working Groups have been established and are responsible for writing the revised order. The Technical Working Groups will use this document as a reference for polices and procedures that have been established for the revision process. The overall intent of this guidance is to outline how the order will be revised and how the revision process will be managed. In addition, this document outlines technical issues considered for inclusion by a Department of Energy Steering Committee.

  5. Free and Reduced-Price Meal Application and Income Verification Practices in School Nutrition Programs in the United States

    Science.gov (United States)

    Kwon, Junehee; Lee, Yee Ming; Park, Eunhye; Wang, Yujia; Rushing, Keith

    2017-01-01

    Purpose/Objectives: This study assessed current practices and attitudes of school nutrition program (SNP) management staff regarding free and reduced-price (F-RP) meal application and verification in SNPs. Methods: Stratified, randomly selected 1,500 SNP management staff in 14 states received a link to an online questionnaire and/or a printed…

  6. Integrated Java Bytecode Verification

    DEFF Research Database (Denmark)

    Gal, Andreas; Probst, Christian; Franz, Michael

    2005-01-01

    Existing Java verifiers perform an iterative data-flow analysis to discover the unambiguous type of values stored on the stack or in registers. Our novel verification algorithm uses abstract interpretation to obtain definition/use information for each register and stack location in the program...

  7. Independent verification in operations at nuclear power plants

    International Nuclear Information System (INIS)

    Donderi, D.C.; Smiley, A.; Ostry, D.J.; Moray, N.P.

    1995-09-01

    A critical review of approaches to independent verification in operations used in nuclear power plant quality assurance programs in other countries, was conducted for this study. This report identifies the uses of independent verification and provides an assessment of the effectiveness of the various approaches. The findings indicate that at Canadian nuclear power plants as much, if not more, independent verification is performed than at power plants in the other countries included in the study. Additional requirements in this area are not proposed for Canadian stations. (author)

  8. Revision 2 of the Program of NPP Krsko Decommissioning and SF and LILW Disposal

    International Nuclear Information System (INIS)

    Levanat, I.; Lokner, V.; Rapic, A.

    2010-01-01

    First joint Slovenian-Croatian Program of NPP Krsko Decommissioning and SF and LILW Disposal (DP) was completed in 2004 and formally adopted in 2005. As bilateral agreement on the NPP requires periodic revisions at least each 5 years, revision 2 of DP was started in September 2008, with the purpose to incorporate relevant developments since the 1st revision, to improve the level of details and reliability of DP, and to propose updated and more accurate cost estimates and appropriate financing models. In the first phase of the revision, new supporting studies for DP modules were prepared. Among these studies, the most demanding was the NPP Krsko specific Preliminary Decommissioning Plan (PDP), complying with the IAEA-recommended format, which included development of the NPP decommissioning inventory database. For upgrade of SF management, new and more detailed descriptions with improved cost estimates were prepared. Update of LILW disposal concept was based on new developments and projects prepared for the Slovenian repository. In the second phase of the revision, integrated DP scenarios were formulated and analyzed. They integrate NPP decommissioning together with RW and SF management/disposal into rationally inter-related sequences. Boundary conditions for this revision required: (a) that the reference scenario from the previous revision should be re-examined, with appropriate variations or new alternatives; (b) that the option of the NPP Krsko life extension should also be included; and (c) that the possibility of diverging interests of the contracting parties should also be analyzed (i.e. waste division and separate management). Finally, scenario evaluation is intended to compare the analyzed scenarios taking into account both their feasibility and estimated costs. It should provide the basis for determining future financing of DP, namely the annuities to be paid by the NPP Krsko owners into the national decommissioning funds.(author).

  9. A Formal Verification Method of Function Block Diagram

    International Nuclear Information System (INIS)

    Koh, Kwang Yong; Seong, Poong Hyun; Jee, Eun Kyoung; Jeon, Seung Jae; Park, Gee Yong; Kwon, Kee Choon

    2007-01-01

    Programmable Logic Controller (PLC), an industrial computer specialized for real-time applications, is widely used in diverse control systems in chemical processing plants, nuclear power plants or traffic control systems. As a PLC is often used to implement safety, critical embedded software, rigorous safety demonstration of PLC code is necessary. Function block diagram (FBD) is a standard application programming language for the PLC and currently being used in the development of a fully-digitalized reactor protection system (RPS), which is called the IDiPS, under the KNICS project. Therefore, verification issue of FBD programs is a pressing problem, and hence is of great importance. In this paper, we propose a formal verification method of FBD programs; we defined FBD programs formally in compliance with IEC 61131-3, and then translate the programs into Verilog model, and finally the model is verified using a model checker SMV. To demonstrate the feasibility and effective of this approach, we applied it to IDiPS which currently being developed under KNICS project. The remainder of this paper is organized as follows. Section 2 briefly describes Verilog and Cadence SMV. In Section 3, we introduce FBD2V which is a tool implemented to support the proposed FBD verification framework. A summary and conclusion are provided in Section 4

  10. Standard Verification System Lite (SVS Lite)

    Data.gov (United States)

    Social Security Administration — SVS Lite is a mainframe program used exclusively by the Office of Child Support Enforcement (OCSE) to perform batch SSN verifications. This process is exactly the...

  11. 16th edition IEE wiring regulations design and verification of electrical installations

    CERN Document Server

    Scaddan, Brian

    1995-01-01

    This book builds on the basic knowledge and techniques covered in 16th Edition IEE Wiring Regulations Explained and Illustrated, providing the information and revision materials needed for the City & Guilds 2400 (Design, Erection and Verification ofElectrical Installations) exam. All Qualifying Managers will be required to gain this qualification, and Brian Scaddan's book is the ideal text for all students undertaking C&G 2400 courses.

  12. The Learner Verification of Series r: The New Macmillan Reading Program; Highlights.

    Science.gov (United States)

    National Evaluation Systems, Inc., Amherst, MA.

    National Evaluation Systems, Inc., has developed curriculum evaluation techniques, in terms of learner verification, which may be used to help the curriculum-development efforts of publishing companies, state education departments, and universities. This document includes a summary of the learner-verification approach, with data collected about a…

  13. Revised Master Plan for the Hood River Production Program, Technical Report 2008.

    Energy Technology Data Exchange (ETDEWEB)

    Oregon Department of Fish and Wildlife; Confederated Tribes of the Warm Springs Reservation

    2008-04-28

    The Hood River Production Program (HRPP) is a Bonneville Power Administration (BPA) funded program initiated as a mitigation measure for Columbia River hydrosystem effects on anadromous fish. The HRPP began in the early 1990s with the release of spring Chinook and winter steelhead smolts into the basin. Prior to implementation, co-managers, including the Confederated Tribes of the Warm Springs Reservation and the Oregon Department of Fish and Wildlife drafted the Hood River Production Master Plan (O'Toole and ODFW 1991a; O'Toole and ODFW 1991b) and the Pelton Ladder Master Plan (Smith and CTWSR 1991). Both documents were completed in 1991 and subsequently approved by the Council in 1992 and authorized through a BPA-led Environmental Impact Statement in 1996. In 2003, a 10-year programmatic review was conducted for BPA-funded programs in the Hood River (Underwood et al. 2003). The primary objective of the HRPP Review (Review) was to determine if program goals were being met, and if modifications to program activities would be necessary in order to meet or revise program goals. In 2003, an agreement was signed between PacifiCorp and resource managers to remove the Powerdale Dam (RM 10) and associated adult trapping facility by 2010. The HRPP program has been dependant on the adult trap to collect broodstock for the hatchery programs; therefore, upon the dam's removal, some sort of replacement for the trap would be needed to continue the HRPP. At the same time the Hood River Subbasin Plan (Coccoli 2004) was being written and prompted the co-managers to considered future direction of the program. This included revising the numerical adult fish objectives based on the assimilated data and output from several models run on the Hood River system. In response to the Review as well as the Subbasin Plan, and intensive monitoring and evaluation of the current program, the HRPP co-managers determined the spring Chinook program was not achieving the HRPP

  14. 50 CFR 216.93 - Tracking and verification program.

    Science.gov (United States)

    2010-10-01

    .... purse seine fishing, processing, and marketing in the United States and abroad. Verification of tracking... the Agreement on the IDCP. (d) Tracking cannery operations. (1) Whenever a U.S. tuna canning company..., canning, sale, rejection, etc.). (4) During canning activities, non-dolphin-safe tuna may not be mixed in...

  15. Verification of structural analysis computer codes in nuclear engineering

    International Nuclear Information System (INIS)

    Zebeljan, Dj.; Cizelj, L.

    1990-01-01

    Sources of potential errors, which can take place during use of finite element method based computer programs, are described in the paper. The magnitude of errors was defined as acceptance criteria for those programs. Error sources are described as they are treated by 'National Agency for Finite Element Methods and Standards (NAFEMS)'. Specific verification examples are used from literature of Nuclear Regulatory Commission (NRC). Example of verification is made on PAFEC-FE computer code for seismic response analyses of piping systems by response spectrum method. (author)

  16. Fundamentals of successful monitoring, reporting, and verification under a cap-and-trade program

    Energy Technology Data Exchange (ETDEWEB)

    John Schakenbach; Robert Vollaro; Reynaldo Forte [U.S. Environmental Protection Agency, Office of Atmospheric Programs, Washington, DC (United States)

    2006-11-15

    The U.S. Environmental Protection Agency (EPA) developed and implemented the Acid Rain Program (ARP), and NOx Budget Trading Programs (NBTP) using several fundamental monitoring, reporting, and verification (MRV) elements: (1) compliance assurance through incentives and automatic penalties; (2) strong quality assurance (QA); (3) collaborative approach with a petition process; (4) standardized electronic reporting; (5) compliance flexibility for low-emitting sources; (6) complete emissions data record required; (7) centralized administration; (8) level playing field; (9) publicly available data; (10) performance-based approach; and (11) reducing conflicts of interest. Each of these elements is discussed in the context of the authors' experience under two U.S. cap-and-trade programs and their potential application to other cap and-trade programs. The U.S. Office of Management and Budget found that the Acid Rain Program has accounted for the largest quantified human health benefits of any federal regulatory program implemented in the last 10 yr, with annual benefits exceeding costs by {gt} 40 to 1. The authors believe that the elements described in this paper greatly contributed to this success. EPA has used the ARP fundamental elements as a model for other cap-and-trade programs, including the NBTP, which went into effect in 2003, and the recently published Clean Air Interstate Rule and Clean Air Mercury Rule. The authors believe that using these fundamental elements to develop and implement the MRV portion of their cap-and-trade programs has resulted in public confidence in the programs, highly accurate and complete emissions data, and a high compliance rate. 2 refs.

  17. Revised VESCAL: Vessel calibration data analysis program. Improvement of a model for non-linear parts of annular and slab tanks

    International Nuclear Information System (INIS)

    Yanagisawa, Hiroshi

    1995-05-01

    For the purpose of the nuclear material accountancy and control for NUCEF: the Nuclear Fuel Cycle Safety Engineering Research Facility, the vessel calibration data analysis program: VESCAL is revised, and a new model for non-linear parts of annular and slab tanks is added to the program. The new model has three unknown parameters, and liquid level is expressed as a square root function with respect to liquid volume. Using the new model, an accurate calibration function on the level and volume data for non-linear parts of annular and slab tanks can be obtained with the smaller number of unknown parameters, compared with a polynomial function model. As a result of benchmark tests for this revision, it was proved that numerical results computed with VESCAL well agreed with those by a statistical analysis program package which is widely used. In addition, the new model would be useful for carrying out data analyses on the vessel calibration at the other bulk handling facilities as well as at NUCEF. This paper describes summary of the program, computational methods and results of benchmark tests concerning this revision. (author)

  18. CASL Verification and Validation Plan

    Energy Technology Data Exchange (ETDEWEB)

    Mousseau, Vincent Andrew [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Dinh, Nam [North Carolina State Univ., Raleigh, NC (United States)

    2016-06-30

    This report documents the Consortium for Advanced Simulation of LWRs (CASL) verification and validation plan. The document builds upon input from CASL subject matter experts, most notably the CASL Challenge Problem Product Integrators, CASL Focus Area leaders, and CASL code development and assessment teams. This document will be a living document that will track progress on CASL to do verification and validation for both the CASL codes (including MPACT, CTF, BISON, MAMBA) and for the CASL challenge problems (CIPS, PCI, DNB). The CASL codes and the CASL challenge problems are at differing levels of maturity with respect to validation and verification. The gap analysis will summarize additional work that needs to be done. Additional VVUQ work will be done as resources permit. This report is prepared for the Department of Energy’s (DOE’s) CASL program in support of milestone CASL.P13.02.

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

    International Nuclear Information System (INIS)

    1983-10-01

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

  20. A transformation of SDL specifications : a step towards the verification

    NARCIS (Netherlands)

    Ioustinova, N.; Sidorova, N.; Bjorner, D.; Broy, M.; Zamulin, A.

    2001-01-01

    Industrial-size specifications/models (whose state space is often infinite) can not be model checked in a direct way— a verification model of a system is model checked instead. Program transformation is a way to build a finite-state verification model that can be submitted to a model checker.

  1. End-to-End Verification of Information-Flow Security for C and Assembly Programs

    Science.gov (United States)

    2016-04-01

    seL4 security verification [18] avoids this issue in the same way. In that work, the authors frame their solution as a restriction that disallows...identical: (σ, σ′1) ∈ TM ∧ (σ, σ′2) ∈ TM =⇒ Ol(σ′1) = Ol(σ′2) The successful security verifications of both seL4 and mCertiKOS provide reasonable...evidence that this restriction on specifications is not a major hindrance for usability. Unlike the seL4 verification, however, our framework runs into a

  2. Radiochemical verification and validation in the environmental data collection process

    International Nuclear Information System (INIS)

    Rosano-Reece, D.; Bottrell, D.; Bath, R.J.

    1994-01-01

    A credible and cost effective environmental data collection process should produce analytical data which meets regulatory and program specific requirements. Analytical data, which support the sampling and analysis activities at hazardous waste sites, undergo verification and independent validation before the data are submitted to regulators. Understanding the difference between verification and validation and their respective roles in the sampling and analysis process is critical to the effectiveness of a program. Verification is deciding whether the measurement data obtained are what was requested. The verification process determines whether all the requirements were met. Validation is more complicated than verification. It attempts to assess the impacts on data use, especially when requirements are not met. Validation becomes part of the decision-making process. Radiochemical data consists of a sample result with an associated error. Therefore, radiochemical validation is different and more quantitative than is currently possible for the validation of hazardous chemical data. Radiochemical data include both results and uncertainty that can be statistically compared to identify significance of differences in a more technically defensible manner. Radiochemical validation makes decisions about analyte identification, detection, and uncertainty for a batch of data. The process focuses on the variability of the data in the context of the decision to be made. The objectives of this paper are to present radiochemical verification and validation for environmental data and to distinguish the differences between the two operations

  3. MFTF sensor verification computer program

    International Nuclear Information System (INIS)

    Chow, H.K.

    1984-01-01

    The design, requirements document and implementation of the MFE Sensor Verification System were accomplished by the Measurement Engineering Section (MES), a group which provides instrumentation for the MFTF magnet diagnostics. The sensors, installed on and around the magnets and solenoids, housed in a vacuum chamber, will supply information about the temperature, strain, pressure, liquid helium level and magnet voltage to the facility operator for evaluation. As the sensors are installed, records must be maintained as to their initial resistance values. Also, as the work progresses, monthly checks will be made to insure continued sensor health. Finally, after the MFTF-B demonstration, yearly checks will be performed as well as checks of sensors as problem develops. The software to acquire and store the data was written by Harry Chow, Computations Department. The acquired data will be transferred to the MFE data base computer system

  4. Quantitative reactive modeling and verification.

    Science.gov (United States)

    Henzinger, Thomas A

    Formal verification aims to improve the quality of software by detecting errors before they do harm. At the basis of formal verification is the logical notion of correctness , which purports to capture whether or not a program behaves as desired. We suggest that the boolean partition of software into correct and incorrect programs falls short of the practical need to assess the behavior of software in a more nuanced fashion against multiple criteria. We therefore propose to introduce quantitative fitness measures for programs, specifically for measuring the function, performance, and robustness of reactive programs such as concurrent processes. This article describes the goals of the ERC Advanced Investigator Project QUAREM. The project aims to build and evaluate a theory of quantitative fitness measures for reactive models. Such a theory must strive to obtain quantitative generalizations of the paradigms that have been success stories in qualitative reactive modeling, such as compositionality, property-preserving abstraction and abstraction refinement, model checking, and synthesis. The theory will be evaluated not only in the context of software and hardware engineering, but also in the context of systems biology. In particular, we will use the quantitative reactive models and fitness measures developed in this project for testing hypotheses about the mechanisms behind data from biological experiments.

  5. DESIGN VERIFICATION REPORT SPENT NUCLEAR FUEL (SNF) PROJECT CANISTER STORAGE BUILDING (CSB)

    International Nuclear Information System (INIS)

    BAZINET, G.D.

    2003-01-01

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. Revision 1 documented verification actions that were pending at the time the initial report was prepared. Revision 3 of this document incorporates MCO Cover Cap Assembly welding verification activities. Verification activities for the installed and operational SSCs have been completed

  6. Automated Formal Verification for PLC Control Systems

    CERN Multimedia

    Fernández Adiego, Borja

    2014-01-01

    Programmable Logic Controllers (PLCs) are widely used devices used in industrial control systems. Ensuring that the PLC software is compliant with its specification is a challenging task. Formal verification has become a recommended practice to ensure the correctness of the safety-critical software. However, these techniques are still not widely applied in industry due to the complexity of building formal models, which represent the system and the formalization of requirement specifications. We propose a general methodology to perform automated model checking of complex properties expressed in temporal logics (e.g. CTL, LTL) on PLC programs. This methodology is based on an Intermediate Model (IM), meant to transform PLC programs written in any of the languages described in the IEC 61131-3 standard (ST, IL, etc.) to different modeling languages of verification tools. This approach has been applied to CERN PLC programs validating the methodology.

  7. Visualization of Instrumental Verification Information Details (VIVID) : code development, description, and usage.

    Energy Technology Data Exchange (ETDEWEB)

    Roy, Christopher John; Bainbridge, Bruce L.; Potter, Donald L.; Blottner, Frederick G.; Black, Amalia Rebecca

    2005-03-01

    The formulation, implementation and usage of a numerical solution verification code is described. This code uses the Richardson extrapolation procedure to estimate the order of accuracy and error of a computational program solution. It evaluates multiple solutions performed in numerical grid convergence studies to verify a numerical algorithm implementation. Analyses are performed on both structured and unstructured grid codes. Finite volume and finite element discretization programs are examined. Two and three-dimensional solutions are evaluated. Steady state and transient solution analysis capabilities are present in the verification code. Multiple input data bases are accepted. Benchmark options are included to allow for minimal solution validation capability as well as verification.

  8. 10 CFR 300.11 - Independent verification.

    Science.gov (United States)

    2010-01-01

    ... DEPARTMENT OF ENERGY CLIMATE CHANGE VOLUNTARY GREENHOUSE GAS REPORTING PROGRAM: GENERAL GUIDELINES § 300.11... managing an auditing or verification process, including the recruitment and allocation of other individual.... (c) Qualifications of organizations accrediting verifiers. Organizations that accredit individual...

  9. Verification of product design using regulation knowledge base and Web services

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ik June [KAERI, Daejeon (Korea, Republic of); Lee, Jae Chul; Mun Du Hwan [Kyungpook National University, Daegu (Korea, Republic of); Kim, Byung Chul [Dong-A University, Busan (Korea, Republic of); Hwang, Jin Sang [PartDB Co., Ltd., Daejeom (Korea, Republic of); Lim, Chae Ho [Korea Institute of Industrial Technology, Incheon (Korea, Republic of)

    2015-11-15

    Since product regulations contain important rules or codes that manufacturers must follow, automatic verification of product design with the regulations related to a product is necessary. For this, this study presents a new method for the verification of product design using regulation knowledge base and Web services. Regulation knowledge base consisting of product ontology and rules was built with a hybrid technique combining ontology and programming languages. Web service for design verification was developed ensuring the flexible extension of knowledge base. By virtue of two technical features, design verification is served to various products while the change of system architecture is minimized.

  10. Verification of product design using regulation knowledge base and Web services

    International Nuclear Information System (INIS)

    Kim, Ik June; Lee, Jae Chul; Mun Du Hwan; Kim, Byung Chul; Hwang, Jin Sang; Lim, Chae Ho

    2015-01-01

    Since product regulations contain important rules or codes that manufacturers must follow, automatic verification of product design with the regulations related to a product is necessary. For this, this study presents a new method for the verification of product design using regulation knowledge base and Web services. Regulation knowledge base consisting of product ontology and rules was built with a hybrid technique combining ontology and programming languages. Web service for design verification was developed ensuring the flexible extension of knowledge base. By virtue of two technical features, design verification is served to various products while the change of system architecture is minimized.

  11. A program for verification of phylogenetic network models.

    Science.gov (United States)

    Gunawan, Andreas D M; Lu, Bingxin; Zhang, Louxin

    2016-09-01

    Genetic material is transferred in a non-reproductive manner across species more frequently than commonly thought, particularly in the bacteria kingdom. On one hand, extant genomes are thus more properly considered as a fusion product of both reproductive and non-reproductive genetic transfers. This has motivated researchers to adopt phylogenetic networks to study genome evolution. On the other hand, a gene's evolution is usually tree-like and has been studied for over half a century. Accordingly, the relationships between phylogenetic trees and networks are the basis for the reconstruction and verification of phylogenetic networks. One important problem in verifying a network model is determining whether or not certain existing phylogenetic trees are displayed in a phylogenetic network. This problem is formally called the tree containment problem. It is NP-complete even for binary phylogenetic networks. We design an exponential time but efficient method for determining whether or not a phylogenetic tree is displayed in an arbitrary phylogenetic network. It is developed on the basis of the so-called reticulation-visible property of phylogenetic networks. A C-program is available for download on http://www.math.nus.edu.sg/∼matzlx/tcp_package matzlx@nus.edu.sg Supplementary data are available at Bioinformatics online. © The Author 2016. Published by Oxford University Press. All rights reserved. For Permissions, please e-mail: journals.permissions@oup.com.

  12. Ostomy Home Skills Program

    Medline Plus

    Full Text Available ... State Requirements Contact Online Education Accreditation, Verification, and Validation Accreditation, Verification, and Validation Programs Accreditation, Verification, and ...

  13. Computer-Assisted Program Reasoning Based on a Relational Semantics of Programs

    Directory of Open Access Journals (Sweden)

    Wolfgang Schreiner

    2012-02-01

    Full Text Available We present an approach to program reasoning which inserts between a program and its verification conditions an additional layer, the denotation of the program expressed in a declarative form. The program is first translated into its denotation from which subsequently the verification conditions are generated. However, even before (and independently of any verification attempt, one may investigate the denotation itself to get insight into the "semantic essence" of the program, in particular to see whether the denotation indeed gives reason to believe that the program has the expected behavior. Errors in the program and in the meta-information may thus be detected and fixed prior to actually performing the formal verification. More concretely, following the relational approach to program semantics, we model the effect of a program as a binary relation on program states. A formal calculus is devised to derive from a program a logic formula that describes this relation and is subject for inspection and manipulation. We have implemented this idea in a comprehensive form in the RISC ProgramExplorer, a new program reasoning environment for educational purposes which encompasses the previously developed RISC ProofNavigator as an interactive proving assistant.

  14. Nevada Test Site Radiological Control Manual. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2010-02-09

    This document supersedes DOE/NV/25946--801, “Nevada Test Site Radiological Control Manual,” Revision 0 issued in October 2009. Brief Description of Revision: A minor revision to correct oversights made during revision to incorporate the 10 CFR 835 Update; and for use as a reference document for Tenant Organization Radiological Protection Programs.

  15. Verification of data files of TREF-computer program; TREF-ohjelmiston ohjaustiedostojen soveltuvuustutkimus

    Energy Technology Data Exchange (ETDEWEB)

    Ruottu, S.; Halme, A.; Ruottu, A. [Einco Oy, Karhula (Finland)

    1996-12-01

    Originally the aim of Y43 project was to verify TREF data files for several different processes. However, it appeared that deficient or missing coordination between experimental and theoretical works made meaningful verifications impossible in some cases. Therefore verification calculations were focused on catalytic cracking reactor which was developed by Neste. The studied reactor consisted of prefluidisation and reaction zones. Verification calculations concentrated mainly on physical phenomena like vaporization near oil injection zone. The main steps of the cracking process can be described as follows oil (liquid) -> oil (gas) -> oil (catal) -> product (catal) + char (catal) -> product (gas). Catalytic nature of cracking reaction was accounted by defining the cracking pseudoreaction into catalyst phase. This simplified reaction model was valid only for vaporization zone. Applied fluid dynamic theory was based on the results of EINCO`s earlier LIEKKI-projects. (author)

  16. Packaged low-level waste verification system

    International Nuclear Information System (INIS)

    Tuite, K.T.; Winberg, M.; Flores, A.Y.; Killian, E.W.; McIsaac, C.V.

    1996-01-01

    Currently, states and low-level radioactive waste (LLW) disposal site operators have no method of independently verifying the radionuclide content of packaged LLW that arrive at disposal sites for disposal. At this time, disposal sites rely on LLW generator shipping manifests and accompanying records to insure that LLW received meets the waste acceptance criteria. An independent verification system would provide a method of checking generator LLW characterization methods and help ensure that LLW disposed of at disposal facilities meets requirements. The Mobile Low-Level Waste Verification System (MLLWVS) provides the equipment, software, and methods to enable the independent verification of LLW shipping records to insure that disposal site waste acceptance criteria are being met. The MLLWVS system was developed under a cost share subcontract between WMG, Inc., and Lockheed Martin Idaho Technologies through the Department of Energy's National Low-Level Waste Management Program at the Idaho National Engineering Laboratory (INEL)

  17. A Verification Framework for Agent Communication

    NARCIS (Netherlands)

    Eijk, R.M. van; Boer, F.S. de; Hoek, W. van der; Meyer, J-J.Ch.

    2003-01-01

    In this paper, we introduce a verification method for the correctness of multiagent systems as described in the framework of acpl (Agent Communication Programming Language). The computational model of acpl consists of an integration of the two different paradigms of ccp (Concurrent Constraint

  18. Analyzing personalized policies for online biometric verification.

    Science.gov (United States)

    Sadhwani, Apaar; Yang, Yan; Wein, Lawrence M

    2014-01-01

    Motivated by India's nationwide biometric program for social inclusion, we analyze verification (i.e., one-to-one matching) in the case where we possess similarity scores for 10 fingerprints and two irises between a resident's biometric images at enrollment and his biometric images during his first verification. At subsequent verifications, we allow individualized strategies based on these 12 scores: we acquire a subset of the 12 images, get new scores for this subset that quantify the similarity to the corresponding enrollment images, and use the likelihood ratio (i.e., the likelihood of observing these scores if the resident is genuine divided by the corresponding likelihood if the resident is an imposter) to decide whether a resident is genuine or an imposter. We also consider two-stage policies, where additional images are acquired in a second stage if the first-stage results are inconclusive. Using performance data from India's program, we develop a new probabilistic model for the joint distribution of the 12 similarity scores and find near-optimal individualized strategies that minimize the false reject rate (FRR) subject to constraints on the false accept rate (FAR) and mean verification delay for each resident. Our individualized policies achieve the same FRR as a policy that acquires (and optimally fuses) 12 biometrics for each resident, which represents a five (four, respectively) log reduction in FRR relative to fingerprint (iris, respectively) policies previously proposed for India's biometric program. The mean delay is [Formula: see text] sec for our proposed policy, compared to 30 sec for a policy that acquires one fingerprint and 107 sec for a policy that acquires all 12 biometrics. This policy acquires iris scans from 32-41% of residents (depending on the FAR) and acquires an average of 1.3 fingerprints per resident.

  19. Ostomy Home Skills Program

    Medline Plus

    Full Text Available ... Special Activities Resources Housing and Travel ... Contact Online Education Accreditation, Verification, and Validation Accreditation, Verification, and Validation Programs Accreditation, Verification, and ...

  20. Adapting Evidence-Based Prevention Approaches for Latino Adolescents: The Familia Adelante Program - Revised

    Directory of Open Access Journals (Sweden)

    Richard C. Cervantes

    2012-12-01

    Full Text Available Behavioral health is defined as the absence of mental illness or substance use problems and the presence of positive emotional well being. Although many U.S. Hispanic youth are at increased risk for substance abuse, suicidality, teen pregnancy, unsafe sexual practices and HIV, there exists a lack of available evidence-based practices for Hispanic youth which promotes behavioral health and HIV prevention. The objective of the current research was to adapt and revise the Familia Adelante (FA Program, a behavioral health, drug intervention and prevention program to incorporate an HIV prevention component. Through qualitative community based participatory methods, including an expert panel and members of the target population, the curriculum was redesigned to integrate effective HIV risk reduction strategies. The process of adapting the intervention is described in this paper, as well as recommendations for future research in program adaptation.

  1. The Effect of Mystery Shopper Reports on Age Verification for Tobacco Purchases

    Science.gov (United States)

    KREVOR, BRAD S.; PONICKI, WILLIAM R.; GRUBE, JOEL W.; DeJONG, WILLIAM

    2011-01-01

    Mystery shops (MS) involving attempted tobacco purchases by young buyers have been employed to monitor retail stores’ performance in refusing underage sales. Anecdotal evidence suggests that MS visits with immediate feedback to store personnel can improve age verification. This study investigated the impact of monthly and twice-monthly MS reports on age verification. Forty-five Walgreens stores were each visited 20 times by mystery shoppers. The stores were randomly assigned to one of three conditions. Control group stores received no feedback, whereas two treatment groups received feedback communications every visit (twice monthly) or every second visit (monthly) after baseline. Logit regression models tested whether each treatment group improved verification rates relative to the control group. Post-baseline verification rates were higher in both treatment groups than in the control group, but only the stores receiving monthly communications had a significantly greater improvement than control group stores. Verification rates increased significantly during the study period for all three groups, with delayed improvement among control group stores. Communication between managers regarding the MS program may account for the delayed age-verification improvements observed in the control group stores. Encouraging inter-store communication might extend the benefits of MS programs beyond those stores that receive this intervention. PMID:21541874

  2. DESIGN VERIFICATION REPORT SPENT NUCLEAR FUEL (SNF) PROJECT CANISTER STORAGE BUILDING (CSB)

    Energy Technology Data Exchange (ETDEWEB)

    BAZINET, G.D.

    2003-02-12

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. Revision 1 documented verification actions that were pending at the time the initial report was prepared. Revision 3 of this document incorporates MCO Cover Cap Assembly welding verification activities. Verification activities for the installed and operational SSCs have been completed.

  3. RISKIND verification and benchmark comparisons

    Energy Technology Data Exchange (ETDEWEB)

    Biwer, B.M.; Arnish, J.J.; Chen, S.Y.; Kamboj, S.

    1997-08-01

    This report presents verification calculations and benchmark comparisons for RISKIND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the population from exposures associated with the transportation of spent nuclear fuel and other radioactive materials. Spreadsheet calculations were performed to verify the proper operation of the major options and calculational steps in RISKIND. The program is unique in that it combines a variety of well-established models into a comprehensive treatment for assessing risks from the transportation of radioactive materials. Benchmark comparisons with other validated codes that incorporate similar models were also performed. For instance, the external gamma and neutron dose rate curves for a shipping package estimated by RISKIND were compared with those estimated by using the RADTRAN 4 code and NUREG-0170 methodology. Atmospheric dispersion of released material and dose estimates from the GENII and CAP88-PC codes. Verification results have shown the program to be performing its intended function correctly. The benchmark results indicate that the predictions made by RISKIND are within acceptable limits when compared with predictions from similar existing models.

  4. RISKIND verification and benchmark comparisons

    International Nuclear Information System (INIS)

    Biwer, B.M.; Arnish, J.J.; Chen, S.Y.; Kamboj, S.

    1997-08-01

    This report presents verification calculations and benchmark comparisons for RISKIND, a computer code designed to estimate potential radiological consequences and health risks to individuals and the population from exposures associated with the transportation of spent nuclear fuel and other radioactive materials. Spreadsheet calculations were performed to verify the proper operation of the major options and calculational steps in RISKIND. The program is unique in that it combines a variety of well-established models into a comprehensive treatment for assessing risks from the transportation of radioactive materials. Benchmark comparisons with other validated codes that incorporate similar models were also performed. For instance, the external gamma and neutron dose rate curves for a shipping package estimated by RISKIND were compared with those estimated by using the RADTRAN 4 code and NUREG-0170 methodology. Atmospheric dispersion of released material and dose estimates from the GENII and CAP88-PC codes. Verification results have shown the program to be performing its intended function correctly. The benchmark results indicate that the predictions made by RISKIND are within acceptable limits when compared with predictions from similar existing models

  5. Verification and the safeguards legacy

    International Nuclear Information System (INIS)

    Perricos, Demetrius

    2001-01-01

    A number of inspection or monitoring systems throughout the world over the last decades have been structured drawing upon the IAEA experience of setting up and operating its safeguards system. The first global verification system was born with the creation of the IAEA safeguards system, about 35 years ago. With the conclusion of the NPT in 1968, inspections were to be performed under safeguards agreements, concluded directly between the IAEA and non-nuclear weapon states parties to the Treaty. The IAEA developed the safeguards system within the limitations reflected in the Blue Book (INFCIRC 153), such as limitations of routine access by the inspectors to 'strategic points', including 'key measurement points', and the focusing of verification on declared nuclear material in declared installations. The system, based as it was on nuclear material accountancy. It was expected to detect a diversion of nuclear material with a high probability and within a given time and therefore determine also that there had been no diversion of nuclear material from peaceful purposes. The most vital element of any verification system is the inspector. Technology can assist but cannot replace the inspector in the field. Their experience, knowledge, intuition and initiative are invaluable factors contributing to the success of any inspection regime. The IAEA inspectors are however not part of an international police force that will intervene to prevent a violation taking place. To be credible they should be technically qualified with substantial experience in industry or in research and development before they are recruited. An extensive training program has to make sure that the inspectors retain their professional capabilities and that it provides them with new skills. Over the years, the inspectors and through them the safeguards verification system gained experience in: organization and management of large teams; examination of records and evaluation of material balances

  6. Environmental Technology Verification: Baghouse Filtration Products--TDC Filter Manufacturing, Inc., SB025 Filtration Media

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) has created the Environmental Technology Verification (ETV) Program to facilitate the deployment of innovative or improved environmental technologies through performance verification and dissemination of information. ETV seeks to ach...

  7. How Formal Dynamic Verification Tools Facilitate Novel Concurrency Visualizations

    Science.gov (United States)

    Aananthakrishnan, Sriram; Delisi, Michael; Vakkalanka, Sarvani; Vo, Anh; Gopalakrishnan, Ganesh; Kirby, Robert M.; Thakur, Rajeev

    With the exploding scale of concurrency, presenting valuable pieces of information collected by formal verification tools intuitively and graphically can greatly enhance concurrent system debugging. Traditional MPI program debuggers present trace views of MPI program executions. Such views are redundant, often containing equivalent traces that permute independent MPI calls. In our ISP formal dynamic verifier for MPI programs, we present a collection of alternate views made possible by the use of formal dynamic verification. Some of ISP’s views help pinpoint errors, some facilitate discerning errors by eliminating redundancy, while others help understand the program better by displaying concurrent even orderings that must be respected by all MPI implementations, in the form of completes-before graphs. In this paper, we describe ISP’s graphical user interface (GUI) capabilities in all these areas which are currently supported by a portable Java based GUI, a Microsoft Visual Studio GUI, and an Eclipse based GUI whose development is in progress.

  8. Advanced verification topics

    CERN Document Server

    Bhattacharya, Bishnupriya; Hall, Gary; Heaton, Nick; Kashai, Yaron; Khan Neyaz; Kirshenbaum, Zeev; Shneydor, Efrat

    2011-01-01

    The Accellera Universal Verification Methodology (UVM) standard is architected to scale, but verification is growing and in more than just the digital design dimension. It is growing in the SoC dimension to include low-power and mixed-signal and the system integration dimension to include multi-language support and acceleration. These items and others all contribute to the quality of the SOC so the Metric-Driven Verification (MDV) methodology is needed to unify it all into a coherent verification plan. This book is for verification engineers and managers familiar with the UVM and the benefits it brings to digital verification but who also need to tackle specialized tasks. It is also written for the SoC project manager that is tasked with building an efficient worldwide team. While the task continues to become more complex, Advanced Verification Topics describes methodologies outside of the Accellera UVM standard, but that build on it, to provide a way for SoC teams to stay productive and profitable.

  9. Source Code Verification for Embedded Systems using Prolog

    Directory of Open Access Journals (Sweden)

    Frank Flederer

    2017-01-01

    Full Text Available System relevant embedded software needs to be reliable and, therefore, well tested, especially for aerospace systems. A common technique to verify programs is the analysis of their abstract syntax tree (AST. Tree structures can be elegantly analyzed with the logic programming language Prolog. Moreover, Prolog offers further advantages for a thorough analysis: On the one hand, it natively provides versatile options to efficiently process tree or graph data structures. On the other hand, Prolog's non-determinism and backtracking eases tests of different variations of the program flow without big effort. A rule-based approach with Prolog allows to characterize the verification goals in a concise and declarative way. In this paper, we describe our approach to verify the source code of a flash file system with the help of Prolog. The flash file system is written in C++ and has been developed particularly for the use in satellites. We transform a given abstract syntax tree of C++ source code into Prolog facts and derive the call graph and the execution sequence (tree, which then are further tested against verification goals. The different program flow branching due to control structures is derived by backtracking as subtrees of the full execution sequence. Finally, these subtrees are verified in Prolog. We illustrate our approach with a case study, where we search for incorrect applications of semaphores in embedded software using the real-time operating system RODOS. We rely on computation tree logic (CTL and have designed an embedded domain specific language (DSL in Prolog to express the verification goals.

  10. CIT photoheliograph functional verification unit test program

    Science.gov (United States)

    1973-01-01

    Tests of the 2/3-meter photoheliograph functional verification unit FVU were performed with the FVU installed in its Big Bear Solar Observatory vacuum chamber. Interferometric tests were run both in Newtonian (f/3.85) and Gregorian (f/50) configurations. Tests were run in both configurations with optical axis horizontal, vertical, and at 45 deg to attempt to determine any gravity effects on the system. Gravity effects, if present, were masked by scatter in the data associated with the system wavefront error of 0.16 lambda rms ( = 6328A) apparently due to problems in the primary mirror. Tests showed that the redesigned secondary mirror assembly works well.

  11. International comparison of product certification and verification methods for appliances

    Energy Technology Data Exchange (ETDEWEB)

    Zhou, Nan [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Romankiewicz, John [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Fridley, David [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Zheng, Nina [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2012-06-01

    Enforcement of appliance standards and consumer trust in appliance labeling are important foundations of growing a more energy efficient economy. Product certification and verification increase compliance rates which in turn increase both energy savings and consumer trust. This paper will serve two purposes: 1) to review international practices for product certification and verification as they relate to the enforcement of standards and labeling programs in the U.S., E.U., Australia, Japan, Canada, and China; and 2) to make recommendations for China to implement improved certification processes related to their mandatory standards and labeling program such as to increase compliance rates and energy savings potential.

  12. International Comparison of Product Certification and Verification Methods for Appliances

    Energy Technology Data Exchange (ETDEWEB)

    Zhou, Nan [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Romankiewicz, John [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Fridley, David [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Zheng, Nina [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2012-06-01

    Enforcement of appliance standards and consumer trust in appliance labeling are important foundations of growing a more energy efficient economy. Product certification and verification increase compliance rates which in turn increase both energy savings and consumer trust. This paper will serve two purposes: 1) to review international practices for product certification and verification as they relate to the enforcement of standards and labeling programs in the U.S., E.U., Australia, Japan, Canada, and China; and 2) to make recommendations for China to implement improved certification processes related to their mandatory standards and labeling program such as to increase compliance rates and energy savings potential.

  13. Behavioral biometrics for verification and recognition of malicious software agents

    Science.gov (United States)

    Yampolskiy, Roman V.; Govindaraju, Venu

    2008-04-01

    Homeland security requires technologies capable of positive and reliable identification of humans for law enforcement, government, and commercial applications. As artificially intelligent agents improve in their abilities and become a part of our everyday life, the possibility of using such programs for undermining homeland security increases. Virtual assistants, shopping bots, and game playing programs are used daily by millions of people. We propose applying statistical behavior modeling techniques developed by us for recognition of humans to the identification and verification of intelligent and potentially malicious software agents. Our experimental results demonstrate feasibility of such methods for both artificial agent verification and even for recognition purposes.

  14. 77 FR 801 - National Vaccine Injury Compensation Program: Revised Amount of the Average Cost of a Health...

    Science.gov (United States)

    2012-01-06

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Health Resources and Services Administration National Vaccine Injury Compensation Program: Revised Amount of the Average Cost of a Health Insurance Policy The Health Resources and Services Administration (HRSA) is publishing an updated monetary amount of the average cost of a health insurance policy as it...

  15. Test-Retest Reliability of the Parent Behavior Importance Questionnaire-Revised and the Parent Behavior Frequency Questionnaire-Revised

    Science.gov (United States)

    Mowder, Barbara A.; Shamah, Renee

    2011-01-01

    This study evaluated the test-retest reliability of two parenting measures: the Parent Behavior Importance Questionnaire-Revised (PBIQ-R) and Parent Behavior Frequency Questionnaire-Revised (PBFQ-R). These self-report parenting behavior assessment measures may be utilized as pre- and post-parent education program measures, with parents as well as…

  16. Facility Decontamination and Decommissioning Program Surveillance and Maintenance Plan, Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Poderis, Reed J. [NSTec; King, Rebecca A. [NSTec

    2013-09-30

    This Surveillance and Maintenance (S&M) Plan describes the activities performed between deactivation and final decommissioning of the following facilities located on the Nevada National Security Site, as documented in the Federal Facility Agreement and Consent Order under the Industrial Sites program as decontamination and decommissioning sites: ? Engine Maintenance, Assembly, and Disassembly (EMAD) Facility: o EMAD Building (Building 25-3900) o Locomotive Storage Shed (Building 25-3901) ? Test Cell C (TCC) Facility: o Equipment Building (Building 25-3220) o Motor Drive Building (Building 25-3230) o Pump Shop (Building 25-3231) o Cryogenic Lab (Building 25-3232) o Ancillary Structures (e.g., dewars, water tower, piping, tanks) These facilities have been declared excess and are in various stages of deactivation (low-risk, long-term stewardship disposition state). This S&M Plan establishes and implements a solid, cost-effective, and balanced S&M program consistent with federal, state, and regulatory requirements. A graded approach is used to plan and conduct S&M activities. The goal is to maintain the facilities in a safe condition in a cost-effective manner until their final end state is achieved. This plan accomplishes the following: ? Establishes S&M objectives and framework ? Identifies programmatic guidance for S&M activities to be conducted by National Security Technologies, LLC, for the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) ? Provides present facility condition information and identifies hazards ? Identifies facility-specific S&M activities to be performed and their frequency ? Identifies regulatory drivers, NNSA/NFO policies and procedures, and best management practices that necessitate implementation of S&M activities ? Provides criteria and frequencies for revisions and updates ? Establishes the process for identifying and dispositioning a condition that has not been previously identified or

  17. Environmental Technology Verification Report - Electric Power and Heat Production Using Renewable Biogas at Patterson Farms

    Science.gov (United States)

    The U.S. EPA operates the Environmental Technology Verification program to facilitate the deployment of innovative technologies through performance verification and information dissemination. A technology area of interest is distributed electrical power generation, particularly w...

  18. FEFTRA {sup TM} verification. Update 2013

    Energy Technology Data Exchange (ETDEWEB)

    Loefman, J. [VTT Technical Research Centre of Finland, Espoo (Finland); Meszaros, F. [The Relief Lab., Harskut, (Hungary)

    2013-12-15

    FEFTRA is a finite element program package developed at VTT for the analyses of groundwater flow in Posiva's site evaluation programme that seeks a final repository for spent nuclear fuel in Finland. The code is capable of modelling steady-state or transient groundwater flow, solute transport and heat transfer as coupled or separate phenomena. Being a typical research tool used only by its developers, the FEFTRA code lacked long of a competent testing system and precise documentation of the verification of the code. In 2006 a project was launched, in which the objective was to reorganise all the material related to the existing verification cases and place them into the FEFTRA program path under the version-control system. The work also included development of a new testing system, which automatically calculates the selected cases, checks the new results against the old approved results and constructs a summary of the test run. All the existing cases were gathered together, checked and added into the new testing system. The documentation of each case was rewritten with the LATEX document preparation system and added into the testing system in a way that the whole test documentation (this report) could easily be generated in a postscript or pdf-format. The current report is the updated version of the verification report published in 2007. At the moment the report includes mainly the cases related to the testing of the primary result quantities (i.e. hydraulic head, pressure, salinity concentration, temperature). The selected cases, however, represent typical hydrological applications, in which the program package has been and will be employed in the Posiva's site evaluation programme, i.e. the simulations of groundwater flow, solute transport and heat transfer as separate or coupled phenomena. The comparison of the FEFTRA results to the analytical, semianalytical and/or other numerical solutions proves the capability of FEFTRA to simulate such problems

  19. Technical safety requirements control level verification

    International Nuclear Information System (INIS)

    STEWART, J.L.

    1999-01-01

    A Technical Safety Requirement (TSR) control level verification process was developed for the Tank Waste Remediation System (TWRS) TSRs at the Hanford Site in Richland, WA, at the direction of the US. Department of Energy, Richland Operations Office (RL). The objective of the effort was to develop a process to ensure that the TWRS TSR controls are designated and managed at the appropriate levels as Safety Limits (SLs), Limiting Control Settings (LCSs), Limiting Conditions for Operation (LCOs), Administrative Controls (ACs), or Design Features. The TSR control level verification process was developed and implemented by a team of contractor personnel with the participation of Fluor Daniel Hanford, Inc. (FDH), the Project Hanford Management Contract (PHMC) integrating contractor, and RL representatives. The team was composed of individuals with the following experience base: nuclear safety analysis; licensing; nuclear industry and DOE-complex TSR preparation/review experience; tank farm operations; FDH policy and compliance; and RL-TWRS oversight. Each TSR control level designation was completed utilizing TSR control logic diagrams and TSR criteria checklists based on DOE Orders, Standards, Contractor TSR policy, and other guidance. The control logic diagrams and criteria checklists were reviewed and modified by team members during team meetings. The TSR control level verification process was used to systematically evaluate 12 LCOs, 22 AC programs, and approximately 100 program key elements identified in the TWRS TSR document. The verification of each TSR control required a team consensus. Based on the results of the process, refinements were identified and the TWRS TSRs were modified as appropriate. A final report documenting key assumptions and the control level designation for each TSR control was prepared and is maintained on file for future reference. The results of the process were used as a reference in the RL review of the final TWRS TSRs and control suite. RL

  20. Current status of verification practices in clinical biochemistry in Spain.

    Science.gov (United States)

    Gómez-Rioja, Rubén; Alvarez, Virtudes; Ventura, Montserrat; Alsina, M Jesús; Barba, Núria; Cortés, Mariano; Llopis, María Antonia; Martínez, Cecilia; Ibarz, Mercè

    2013-09-01

    Verification uses logical algorithms to detect potential errors before laboratory results are released to the clinician. Even though verification is one of the main processes in all laboratories, there is a lack of standardization mainly in the algorithms used and the criteria and verification limits applied. A survey in clinical laboratories in Spain was conducted in order to assess the verification process, particularly the use of autoverification. Questionnaires were sent to the laboratories involved in the External Quality Assurance Program organized by the Spanish Society of Clinical Biochemistry and Molecular Pathology. Seven common biochemical parameters were included (glucose, cholesterol, triglycerides, creatinine, potassium, calcium, and alanine aminotransferase). Completed questionnaires were received from 85 laboratories. Nearly all the laboratories reported using the following seven verification criteria: internal quality control, instrument warnings, sample deterioration, reference limits, clinical data, concordance between parameters, and verification of results. The use of all verification criteria varied according to the type of verification (automatic, technical, or medical). Verification limits for these parameters are similar to biological reference ranges. Delta Check was used in 24% of laboratories. Most laboratories (64%) reported using autoverification systems. Autoverification use was related to laboratory size, ownership, and type of laboratory information system, but amount of use (percentage of test autoverified) was not related to laboratory size. A total of 36% of Spanish laboratories do not use autoverification, despite the general implementation of laboratory information systems, most of them, with autoverification ability. Criteria and rules for seven routine biochemical tests were obtained.

  1. Independent verification: operational phase liquid metal breeder reactors

    International Nuclear Information System (INIS)

    Bourne, P.B.

    1981-01-01

    The Fast Flux Test Facility (FFTF) recently achieved 100-percent power and now is in the initial stages of operation as a test reactor. An independent verification program has been established to assist in maintaining stable plant conditions, and to assure the safe operation of the reactor. Independent verification begins with the development of administrative procedures to control all other procedures and changes to the plant configurations. The technical content of the controlling procedures is subject to independent verification. The actual accomplishment of test procedures and operational maneuvers is witnessed by personnel not responsible for operating the plant. Off-normal events are analyzed, problem reports from other operating reactors are evaluated, and these results are used to improve on-line performance. Audits are used to confirm compliance with established practices and to identify areas where individual performance can be improved

  2. Reinforcing of QA/QC programs in radiotherapy departments in Croatia: Results of treatment planning system verification

    Energy Technology Data Exchange (ETDEWEB)

    Jurković, Slaven; Švabić, Manda; Diklić, Ana; Smilović Radojčić, Đeni; Dundara, Dea [Clinic for Radiotherapy and Oncology, Physics Division, University Hospital Rijeka, Rijeka (Croatia); Kasabašić, Mladen; Ivković, Ana [Department for Radiotherapy and Oncology, University Hospital Osijek, Osijek (Croatia); Faj, Dario, E-mail: dariofaj@mefos.hr [Department of Physics, School of Medicine, University of Osijek, Osijek (Croatia)

    2013-04-01

    Implementation of advanced techniques in clinical practice can greatly improve the outcome of radiation therapy, but it also makes the process much more complex with a lot of room for errors. An important part of the quality assurance program is verification of treatment planning system (TPS). Dosimetric verifications in anthropomorphic phantom were performed in 4 centers where new systems were installed. A total of 14 tests for 2 photon energies and multigrid superposition algorithms were conducted using the CMS XiO TPS. Evaluation criteria as specified in the International Atomic Energy Agency Technical Reports Series (IAEA TRS) 430 were employed. Results of measurements are grouped according to the placement of the measuring point and the beam energy. The majority of differences between calculated and measured doses in the water-equivalent part of the phantom were in tolerance. Significantly more out-of-tolerance values were observed in “nonwater-equivalent” parts of the phantom, especially for higher-energy photon beams. This survey was done as a part of continuous effort to build up awareness of quality assurance/quality control (QA/QC) importance in the Croatian radiotherapy community. Understanding the limitations of different parts of the various systems used in radiation therapy can systematically improve quality as well.

  3. 25 CFR 276.14 - Budget revision.

    Science.gov (United States)

    2010-04-01

    ... changes include: (1) The use of grantee funds in furtherance of program objectives over and above the... the objective of the grant-supported program. (2) The revision indicates the need for additional... programs, functions, and activities when budgeted separately for a grant, except that the Bureau shall...

  4. The joint verification experiments as a global non-proliferation exercise

    International Nuclear Information System (INIS)

    Shaner, J.W.

    1998-01-01

    This conference commemorates the 10th anniversary of the second of two Joint Verification Experiments conducted by the Soviet Union and the US. These two experiments, one at the Nevada test site in the US, and the second here at the Semipalatinsk test site were designed to test the verification of a nuclear testing treaty limiting the size underground explosions to 150 kilotons. By building trust and technical respect between the weapons scientists of the two most powerful adversaries, the Joint Verification Experiment (JVE) had the unanticipated result of initiating a suite of cooperative projects and programs aimed at reducing the Cold War threats and preventing the proliferation of weapons of mass destruction

  5. Verification and Validation for Flight-Critical Systems (VVFCS)

    Science.gov (United States)

    Graves, Sharon S.; Jacobsen, Robert A.

    2010-01-01

    On March 31, 2009 a Request for Information (RFI) was issued by NASA s Aviation Safety Program to gather input on the subject of Verification and Validation (V & V) of Flight-Critical Systems. The responses were provided to NASA on or before April 24, 2009. The RFI asked for comments in three topic areas: Modeling and Validation of New Concepts for Vehicles and Operations; Verification of Complex Integrated and Distributed Systems; and Software Safety Assurance. There were a total of 34 responses to the RFI, representing a cross-section of academic (26%), small & large industry (47%) and government agency (27%).

  6. The revision of the master's curiculm at Osaka Kyoiku University

    OpenAIRE

    赤松, 喜久; 伊藤, 敏雄

    2007-01-01

    The background covering the revision of the master's curriculum and a point concerning this revision in a teacher-training program at Osaka Kyoiku University are explained in this paper. Furthermore, future problems are organized and evaluated. The paper will help us to consider the revision of the curriculum expected as part of the master's course in a teacher's program. The number of required subjects is minimal so that a student may take more optional subjects to meet various needs. New su...

  7. Effective Analysis of C Programs by Rewriting Variability

    DEFF Research Database (Denmark)

    Iosif-Lazar, Alexandru Florin; Melo, Jean; Dimovski, Aleksandar

    2017-01-01

    and effective analysis and verification of real-world C program families. Importance. We report some interesting variability-related bugs that we discovered using various state-of-the-art single-program C verification tools, such as Frama-C, Clang, LLBMC.......Context. Variability-intensive programs (program families) appear in many application areas and for many reasons today. Different family members, called variants, are derived by switching statically configurable options (features) on and off, while reuse of the common code is maximized. Inquiry....... Verification of program families is challenging since the number of variants is exponential in the number of features. Existing single-program analysis and verification tools cannot be applied directly to program families, and designing and implementing the corresponding variability-aware versions is tedious...

  8. Independent verification in operations at nuclear power plants: Summaries of site visits

    International Nuclear Information System (INIS)

    Donderi, D.C.; Smiley, A.; Ostry, D.J.; Moray, N.P.

    1995-09-01

    A critical review of approaches to independent verification in operations used in nuclear power plant quality assurance programs in other countries was conducted and are detailed in volume 1. This paper is a compilation of the visits to nuclear power plant sites to study independent verification in operations at sites in Canada, USA, Japan, United Kingdom, France and Germany. 3 tabs., 22 figs

  9. Independent verification of the delivered dose in High-Dose Rate (HDR) brachytherapy

    International Nuclear Information System (INIS)

    Portillo, P.; Feld, D.; Kessler, J.

    2009-01-01

    An important aspect of a Quality Assurance program in Clinical Dosimetry is an independent verification of the dosimetric calculation done by the Treatment Planning System for each radiation treatment. The present paper is aimed at creating a spreadsheet for the verification of the dose recorded at a point of an implant with radioactive sources and HDR in gynecological injuries. An 192 Ir source automatic differed loading equipment, GammaMedplus model, Varian Medical System with HDR installed at the Angel H. Roffo Oncology Institute has been used. The planning system implemented for getting the dose distribution is the BraquiVision. The sources coordinates as well as those of the calculation point (Rectum) are entered into the Excel-devised verification program by assuming the existence of a point source in each one of the applicators' positions. Such calculation point has been selected as the rectum is an organ at risk, therefore determining the treatment planning. The dose verification is performed at points standing at a sources distance having at least twice the active length of such sources, so they may be regarded as point sources. Most of the sources used in HDR brachytherapy with 192 Ir have a 5 mm active length for all equipment brands. Consequently, the dose verification distance must be at least of 10 mm. (author)

  10. Research on non-uniform strain profile reconstruction along fiber Bragg grating via genetic programming algorithm and interrelated experimental verification

    Science.gov (United States)

    Zheng, Shijie; Zhang, Nan; Xia, Yanjun; Wang, Hongtao

    2014-03-01

    A new heuristic strategy for the non-uniform strain profile reconstruction along Fiber Bragg Gratings is proposed in this paper, which is based on the modified transfer matrix and Genetic Programming(GP) algorithm. The present method uses Genetic Programming to determine the applied strain field as a function of position along the fiber length. The structures that undergo adaptation in genetic programming are hierarchical structures which are different from that of conventional genetic algorithm operating on strings. GP regress the strain profile function which matches the 'measured' spectrum best and makes space resolution of strain reconstruction arbitrarily high, or even infinite. This paper also presents an experimental verification of the reconstruction of non-homogeneous strain fields using GP. The results are compared with numerical calculations of finite element method. Both the simulation examples and experimental results demonstrate that Genetic Programming can effectively reconstruct continuous profile expression along the whole FBG, and greatly improves its computational efficiency and accuracy.

  11. ENVIRONMENTAL TECHNOLOGY VERIFICATION REPORT: EXEL INDUSTRIAL AIRMIX SPRAY GUN

    Science.gov (United States)

    The Environmental Technology Verification Program has partnered with Concurrent Technologies Corp. to verify innovative coatings and coating equipment technologies for reducing air emissions. This report describes the performance of EXEL Industrial's Kremlin Airmix high transfer ...

  12. Multilateral disarmament verification

    International Nuclear Information System (INIS)

    Persbo, A.

    2013-01-01

    Non-governmental organisations, such as VERTIC (Verification Research, Training and Information Centre), can play an important role in the promotion of multilateral verification. Parties involved in negotiating nuclear arms accords are for the most part keen that such agreements include suitable and robust provisions for monitoring and verification. Generally progress in multilateral arms control verification is often painstakingly slow, but from time to time 'windows of opportunity' - that is, moments where ideas, technical feasibility and political interests are aligned at both domestic and international levels - may occur and we have to be ready, so the preparatory work is very important. In the context of nuclear disarmament, verification (whether bilateral or multilateral) entails an array of challenges, hurdles and potential pitfalls relating to national security, health, safety and even non-proliferation, so preparatory work is complex and time-greedy. A UK-Norway Initiative was established in order to investigate the role that a non-nuclear-weapon state such as Norway could potentially play in the field of nuclear arms control verification. (A.C.)

  13. Key Nuclear Verification Priorities: Safeguards and Beyond

    International Nuclear Information System (INIS)

    Carlson, J.

    2010-01-01

    traditional focus of safeguards is detection capability. Here, the greatest single priority is improving the capability to detect undeclared nuclear programs. Another key priority is greater efficiency in safeguards implementation, to meet an expanding workload. Other priorities include addressing innovative fuel cycle developments, and maintaining safeguards skills and knowledge. As important as these priorities are, it is essential to also address issues of confidence and deterrence. Failures in these areas will undermine the value of the safeguards system and constrain the development of future nuclear verification missions. This paper takes a broader view in discussing the key nuclear verification priorities. (author)

  14. Key Nuclear Verification Priorities - Safeguards and Beyond

    International Nuclear Information System (INIS)

    Carlson, J.

    2010-01-01

    traditional focus of safeguards is detection capability. Here, the greatest single priority is improving the capability to detect undeclared nuclear programs. Another key priority is greater efficiency in safeguards implementation, to meet an expanding workload. Other priorities include addressing innovative fuel cycle developments, and maintaining safeguards skills and knowledge. As important as these priorities are, it is essential to also address issues of confidence and deterrence. Failures in these areas will undermine the value of the safeguards system and constrain the development of future nuclear verification missions. This paper takes a broader view in discussing the key nuclear verification priorities. (author)

  15. Verification of business rules programs

    CERN Document Server

    Silva, Bruno Berstel-Da

    2013-01-01

    Rules represent a simplified means of programming, congruent with our understanding of human brain constructs. With the advent of business rules management systems, it has been possible to introduce rule-based programming to nonprogrammers, allowing them to map expert intent into code in applications such as fraud detection, financial transactions, healthcare, retail, and marketing. However, a remaining concern is the quality, safety, and reliability of the resulting programs.  This book is on business rules programs, that is, rule programs as handled in business rules management systems. Its

  16. SU-F-T-494: A Multi-Institutional Study of Independent Dose Verification Using Golden Beam Data

    Energy Technology Data Exchange (ETDEWEB)

    Itano, M; Yamazaki, T [Inagi Municipal Hospital, Inagi, Tokyo (Japan); Tachibana, R; Uchida, Y [National Cancer Center Hospital East, Kashiwa, Chiba (Japan); Yamashita, M [Kobe City Medical Center General Hospital, Kobe, Hyogo (Japan); Shimizu, H [Kitasato University Medical Center, Kitamoto, Saitama (Japan); Sugawara, Y; Kotabe, K [National Center for Global Health and Medicine, Shinjuku, Tokyo (Japan); Kamima, T [Cancer Institute Hospital Japanese Foundation for Cancer Research, Koto, Tokyo (Japan); Takahashi, R [Cancer Institute Hospital of Japanese Foundation for Cancer Research, Koto, Tokyo (Japan); Ishibashi, S [Sasebo City General Hospital, Sasebo, Nagasaki (Japan); Tachibana, H [National Cancer Center, Kashiwa, Chiba (Japan)

    2016-06-15

    Purpose: In general, beam data of individual linac is measured for independent dose verification software program and the verification is performed as a secondary check. In this study, independent dose verification using golden beam data was compared to that using individual linac’s beam data. Methods: Six institutions were participated and three different beam data were prepared. The one was individual measured data (Original Beam Data, OBD) .The others were generated by all measurements from same linac model (Model-GBD) and all linac models (All-GBD). The three different beam data were registered to the independent verification software program for each institute. Subsequently, patient’s plans in eight sites (brain, head and neck, lung, esophagus, breast, abdomen, pelvis and bone) were analyzed using the verification program to compare doses calculated using the three different beam data. Results: 1116 plans were collected from six institutes. Compared to using the OBD, the results shows the variation using the Model-GBD based calculation and the All-GBD was 0.0 ± 0.3% and 0.0 ± 0.6%, respectively. The maximum variations were 1.2% and 2.3%, respectively. The plans with the variation over 1% shows the reference points were located away from the central axis with/without physical wedge. Conclusion: The confidence limit (2SD) using the Model-GBD and the All-GBD was within 0.6% and 1.2%, respectively. Thus, the use of golden beam data may be feasible for independent verification. In addition to it, the verification using golden beam data provide quality assurance of planning from the view of audit. This research is partially supported by Japan Agency for Medical Research and Development(AMED)

  17. SU-F-T-494: A Multi-Institutional Study of Independent Dose Verification Using Golden Beam Data

    International Nuclear Information System (INIS)

    Itano, M; Yamazaki, T; Tachibana, R; Uchida, Y; Yamashita, M; Shimizu, H; Sugawara, Y; Kotabe, K; Kamima, T; Takahashi, R; Ishibashi, S; Tachibana, H

    2016-01-01

    Purpose: In general, beam data of individual linac is measured for independent dose verification software program and the verification is performed as a secondary check. In this study, independent dose verification using golden beam data was compared to that using individual linac’s beam data. Methods: Six institutions were participated and three different beam data were prepared. The one was individual measured data (Original Beam Data, OBD) .The others were generated by all measurements from same linac model (Model-GBD) and all linac models (All-GBD). The three different beam data were registered to the independent verification software program for each institute. Subsequently, patient’s plans in eight sites (brain, head and neck, lung, esophagus, breast, abdomen, pelvis and bone) were analyzed using the verification program to compare doses calculated using the three different beam data. Results: 1116 plans were collected from six institutes. Compared to using the OBD, the results shows the variation using the Model-GBD based calculation and the All-GBD was 0.0 ± 0.3% and 0.0 ± 0.6%, respectively. The maximum variations were 1.2% and 2.3%, respectively. The plans with the variation over 1% shows the reference points were located away from the central axis with/without physical wedge. Conclusion: The confidence limit (2SD) using the Model-GBD and the All-GBD was within 0.6% and 1.2%, respectively. Thus, the use of golden beam data may be feasible for independent verification. In addition to it, the verification using golden beam data provide quality assurance of planning from the view of audit. This research is partially supported by Japan Agency for Medical Research and Development(AMED)

  18. Technical safety requirements control level verification; TOPICAL

    International Nuclear Information System (INIS)

    STEWART, J.L.

    1999-01-01

    A Technical Safety Requirement (TSR) control level verification process was developed for the Tank Waste Remediation System (TWRS) TSRs at the Hanford Site in Richland, WA, at the direction of the US. Department of Energy, Richland Operations Office (RL). The objective of the effort was to develop a process to ensure that the TWRS TSR controls are designated and managed at the appropriate levels as Safety Limits (SLs), Limiting Control Settings (LCSs), Limiting Conditions for Operation (LCOs), Administrative Controls (ACs), or Design Features. The TSR control level verification process was developed and implemented by a team of contractor personnel with the participation of Fluor Daniel Hanford, Inc. (FDH), the Project Hanford Management Contract (PHMC) integrating contractor, and RL representatives. The team was composed of individuals with the following experience base: nuclear safety analysis; licensing; nuclear industry and DOE-complex TSR preparation/review experience; tank farm operations; FDH policy and compliance; and RL-TWRS oversight. Each TSR control level designation was completed utilizing TSR control logic diagrams and TSR criteria checklists based on DOE Orders, Standards, Contractor TSR policy, and other guidance. The control logic diagrams and criteria checklists were reviewed and modified by team members during team meetings. The TSR control level verification process was used to systematically evaluate 12 LCOs, 22 AC programs, and approximately 100 program key elements identified in the TWRS TSR document. The verification of each TSR control required a team consensus. Based on the results of the process, refinements were identified and the TWRS TSRs were modified as appropriate. A final report documenting key assumptions and the control level designation for each TSR control was prepared and is maintained on file for future reference. The results of the process were used as a reference in the RL review of the final TWRS TSRs and control suite. RL

  19. Embedded software verification and debugging

    CERN Document Server

    Winterholer, Markus

    2017-01-01

    This book provides comprehensive coverage of verification and debugging techniques for embedded software, which is frequently used in safety critical applications (e.g., automotive), where failures are unacceptable. Since the verification of complex systems needs to encompass the verification of both hardware and embedded software modules, this book focuses on verification and debugging approaches for embedded software with hardware dependencies. Coverage includes the entire flow of design, verification and debugging of embedded software and all key approaches to debugging, dynamic, static, and hybrid verification. This book discusses the current, industrial embedded software verification flow, as well as emerging trends with focus on formal and hybrid verification and debugging approaches. Includes in a single source the entire flow of design, verification and debugging of embedded software; Addresses the main techniques that are currently being used in the industry for assuring the quality of embedded softw...

  20. ENVIRONMENTAL TECHNOLOGY VERIFICATION REPORT - PORTABLE GAS CHROMATOGRAPH ELECTRONIC SENSOR TECHNOLOGY MODEL 4100

    Science.gov (United States)

    The U.S. Environmental Protection Agency, through the Environmental Technology Verification Program, is working to accelerate the acceptance and use of innovative technologies that improve the way the United States manages its environmental problems. As part of this program, the...

  1. Software verification for nuclear industry

    International Nuclear Information System (INIS)

    Wilburn, N.P.

    1985-08-01

    Why verification of software products throughout the software life cycle is necessary is considered. Concepts of verification, software verification planning, and some verification methodologies for products generated throughout the software life cycle are then discussed

  2. The design of verification regimes

    International Nuclear Information System (INIS)

    Gallagher, N.W.

    1991-01-01

    Verification of a nuclear agreement requires more than knowledge of relevant technologies and institutional arrangements. It also demands thorough understanding of the nature of verification and the politics of verification design. Arms control efforts have been stymied in the past because key players agreed to verification in principle, only to disagree radically over verification in practice. In this chapter, it is shown that the success and stability of arms control endeavors can be undermined by verification designs which promote unilateral rather than cooperative approaches to security, and which may reduce, rather than enhance, the security of both sides. Drawing on logical analysis and practical lessons from previous superpower verification experience, this chapter summarizes the logic and politics of verification and suggests implications for South Asia. The discussion begins by determining what properties all forms of verification have in common, regardless of the participants or the substance and form of their agreement. Viewing verification as the political process of making decisions regarding the occurrence of cooperation points to four critical components: (1) determination of principles, (2) information gathering, (3) analysis and (4) projection. It is shown that verification arrangements differ primarily in regards to how effectively and by whom these four stages are carried out

  3. US Nuclear Regulatory Commission Human Factors Program Plan. Revision 1

    International Nuclear Information System (INIS)

    1984-09-01

    The purpose of the NRC Human Factors Program Plan (NUREG-0985) is to ensure that proper consideration is given to human factors in the design, operation, and maintenance of nuclear facilities. This revised plan addresses nuclear power plants (NPPs) and describes (1) the technical assistance and research activities planned to provide the technical bases for the resolution of the remaining human factors related tasks described in NUREG-0660, THE NRC Action Plan developed as a result of the TMI-2 Accident, and NUREG-0737, Clarification of TMI Action Plan Requirements; (2) the additional human factors efforts identified during implementation of the Action Plan that should receive NRC attention; (3) conduct of developmental activities specified in NUREG-0985 during FY-83; and (4) the impact of Section 306 of the Nuclear Waste Policy Act of 1982, PL 97-425. The plan represents a systematic and comprehensive approach for addressing human factors concerns important to NPP safety in the FY-84 through FY-86 time frame

  4. Improved verification methods for safeguards verifications at enrichment plants

    International Nuclear Information System (INIS)

    Lebrun, A.; Kane, S. C.; Bourva, L.; Poirier, S.; Loghin, N. E.; Langlands, D.

    2009-01-01

    The International Atomic Energy Agency (IAEA) has initiated a coordinated research and development programme to improve its verification methods and equipment applicable to enrichment plants. The programme entails several individual projects to meet the objectives of the IAEA Safeguards Model Approach for Gas Centrifuge Enrichment Plants updated in 2006. Upgrades of verification methods to confirm the absence of HEU (highly enriched uranium) production have been initiated and, in particular, the Cascade Header Enrichment Monitor (CHEM) has been redesigned to reduce its weight and incorporate an electrically cooled germanium detector. Such detectors are also introduced to improve the attended verification of UF 6 cylinders for the verification of the material balance. Data sharing of authenticated operator weighing systems such as accountancy scales and process load cells is also investigated as a cost efficient and an effective safeguards measure combined with unannounced inspections, surveillance and non-destructive assay (NDA) measurement. (authors)

  5. Improved verification methods for safeguards verifications at enrichment plants

    Energy Technology Data Exchange (ETDEWEB)

    Lebrun, A.; Kane, S. C.; Bourva, L.; Poirier, S.; Loghin, N. E.; Langlands, D. [Department of Safeguards, International Atomic Energy Agency, Wagramer Strasse 5, A1400 Vienna (Austria)

    2009-07-01

    The International Atomic Energy Agency (IAEA) has initiated a coordinated research and development programme to improve its verification methods and equipment applicable to enrichment plants. The programme entails several individual projects to meet the objectives of the IAEA Safeguards Model Approach for Gas Centrifuge Enrichment Plants updated in 2006. Upgrades of verification methods to confirm the absence of HEU (highly enriched uranium) production have been initiated and, in particular, the Cascade Header Enrichment Monitor (CHEM) has been redesigned to reduce its weight and incorporate an electrically cooled germanium detector. Such detectors are also introduced to improve the attended verification of UF{sub 6} cylinders for the verification of the material balance. Data sharing of authenticated operator weighing systems such as accountancy scales and process load cells is also investigated as a cost efficient and an effective safeguards measure combined with unannounced inspections, surveillance and non-destructive assay (NDA) measurement. (authors)

  6. 78 FR 28812 - Energy Efficiency Program for Industrial Equipment: Petition of UL Verification Services Inc. for...

    Science.gov (United States)

    2013-05-16

    ... are engineers. UL today is comprised of five businesses, Product Safety, Verification Services, Life..., Director--Global Technical Research, UL Verification Services. Subscribed and sworn to before me this 20... (431.447(c)(4)) General Personnel Overview UL is a global independent safety science company with more...

  7. Graph-based specification and verification for aspect-oriented languages

    NARCIS (Netherlands)

    Staijen, T.

    2010-01-01

    Aspect-oriented software development aims at improving separation of concerns at all levels in the software development life-cycle, from architecture to code implementation. In this thesis we strive to develop verification methods specifically for aspect-oriented programming languages. For this

  8. 14 CFR 152.323 - Budget revision: Airport development.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Budget revision: Airport development. 152... TRANSPORTATION (CONTINUED) AIRPORTS AIRPORT AID PROGRAM Accounting and Reporting Requirements § 152.323 Budget... change in the budget estimates, the sponsor shall submit a request for budget revision on a form...

  9. Specification and Verification of Hybrid System

    International Nuclear Information System (INIS)

    Widjaja, Belawati H.

    1997-01-01

    Hybrid systems are reactive systems which intermix between two components, discrete components and continuous components. The continuous components are usually called plants, subject to disturbances which cause the state variables of the systems changing continuously by physical laws and/or by the control laws. The discrete components can be digital computers, sensor and actuators controlled by programs. These programs are designed to select, control and supervise the behavior of the continuous components. Specification and verification of hybrid systems has recently become an active area of research in both computer science and control engineering, many papers concerning hybrid system have been published. This paper gives a design methodology for hybrid systems as an example to the specification and verification of hybrid systems. The design methodology is based on the cooperation between two disciplines, control engineering and computer science. The methodology brings into the design of control loops and decision loops. The external behavior of control loops are specified in a notation which is understandable by the two disciplines. The design of control loops which employed theory of differential equation is done by control engineers, and its correctness is also guaranteed analytically or experimentally by control engineers. The decision loops are designed in computing science based on the specifications of control loops. The verification of systems requirements can be done by computing scientists using a formal reasoning mechanism. For illustrating the proposed design, a problem of balancing an inverted pendulum which is a popular experiment device in control theory is considered, and the Mean Value Calculus is chosen as a formal notation for specifying the control loops and designing the decision loops

  10. Physics Verification Overview

    Energy Technology Data Exchange (ETDEWEB)

    Doebling, Scott William [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-09-12

    The purpose of the verification project is to establish, through rigorous convergence analysis, that each ASC computational physics code correctly implements a set of physics models and algorithms (code verification); Evaluate and analyze the uncertainties of code outputs associated with the choice of temporal and spatial discretization (solution or calculation verification); and Develop and maintain the capability to expand and update these analyses on demand. This presentation describes project milestones.

  11. Monte Carlo simulations to replace film dosimetry in IMRT verification

    International Nuclear Information System (INIS)

    Goetzfried, Thomas; Trautwein, Marius; Koelbi, Oliver; Bogner, Ludwig; Rickhey, Mark

    2011-01-01

    Patient-specific verification of intensity-modulated radiation therapy (IMRT) plans can be done by dosimetric measurements or by independent dose or monitor unit calculations. The aim of this study was the clinical evaluation of IMRT verification based on a fast Monte Carlo (MC) program with regard to possible benefits compared to commonly used film dosimetry. 25 head-and-neck IMRT plans were recalculated by a pencil beam based treatment planning system (TPS) using an appropriate quality assurance (QA) phantom. All plans were verified both by film and diode dosimetry and compared to MC simulations. The irradiated films, the results of diode measurements and the computed dose distributions were evaluated, and the data were compared on the basis of gamma maps and dose-difference histograms. Average deviations in the high-dose region between diode measurements and point dose calculations performed with the TPS and MC program were 0.7 ± 2.7% and 1.2 ± 3.1%, respectively. For film measurements, the mean gamma values with 3% dose difference and 3 mm distance-to-agreement were 0.74 ± 0.28 (TPS as reference) with dose deviations up to 10%. Corresponding values were significantly reduced to 0.34 ± 0.09 for MC dose calculation. The total time needed for both verification procedures is comparable, however, by far less labor intensive in the case of MC simulations. The presented study showed that independent dose calculation verification of IMRT plans with a fast MC program has the potential to eclipse film dosimetry more and more in the near future. Thus, the linac-specific QA part will necessarily become more important. In combination with MC simulations and due to the simple set-up, point-dose measurements for dosimetric plausibility checks are recommended at least in the IMRT introduction phase. (orig.)

  12. Revised Methods for Characterizing Stream Habitat in the National Water-Quality Assessment Program

    Science.gov (United States)

    Fitzpatrick, Faith A.; Waite, Ian R.; D'Arconte, Patricia J.; Meador, Michael R.; Maupin, Molly A.; Gurtz, Martin E.

    1998-01-01

    Stream habitat is characterized in the U.S. Geological Survey's National Water-Quality Assessment (NAWQA) Program as part of an integrated physical, chemical, and biological assessment of the Nation's water quality. The goal of stream habitat characterization is to relate habitat to other physical, chemical, and biological factors that describe water-quality conditions. To accomplish this goal, environmental settings are described at sites selected for water-quality assessment. In addition, spatial and temporal patterns in habitat are examined at local, regional, and national scales. This habitat protocol contains updated methods for evaluating habitat in NAWQA Study Units. Revisions are based on lessons learned after 6 years of applying the original NAWQA habitat protocol to NAWQA Study Unit ecological surveys. Similar to the original protocol, these revised methods for evaluating stream habitat are based on a spatially hierarchical framework that incorporates habitat data at basin, segment, reach, and microhabitat scales. This framework provides a basis for national consistency in collection techniques while allowing flexibility in habitat assessment within individual Study Units. Procedures are described for collecting habitat data at basin and segment scales; these procedures include use of geographic information system data bases, topographic maps, and aerial photographs. Data collected at the reach scale include channel, bank, and riparian characteristics.

  13. Verification of EPA's " Preliminary remediation goals for radionuclides" (PRG) electronic calculator

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-03-29

    The U.S. Environmental Protection Agency (EPA) requested an external, independent verification study of their “Preliminary Remediation Goals for Radionuclides” (PRG) electronic calculator. The calculator provides information on establishing PRGs for radionuclides at Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) sites with radioactive contamination (Verification Study Charge, Background). These risk-based PRGs set concentration limits using carcinogenic toxicity values under specific exposure conditions (PRG User’s Guide, Section 1). The purpose of this verification study is to ascertain that the computer codes has no inherit numerical problems with obtaining solutions as well as to ensure that the equations are programmed correctly.

  14. TLM.open: a SystemC/TLM Frontend for the CADP Verification Toolbox

    Directory of Open Access Journals (Sweden)

    Claude Helmstetter

    2014-04-01

    Full Text Available SystemC/TLM models, which are C++ programs, allow the simulation of embedded software before hardware low-level descriptions are available and are used as golden models for hardware verification. The verification of the SystemC/TLM models is an important issue since an error in the model can mislead the system designers or reveal an error in the specifications. An open-source simulator for SystemC/TLM is provided but there are no tools for formal verification.In order to apply model checking to a SystemC/TLM model, a semantics for standard C++ code and for specific SystemC/TLM features must be provided. The usual approach relies on the translation of the SystemC/TLM code into a formal language for which a model checker is available.We propose another approach that suppresses the error-prone translation effort. Given a SystemC/TLM program, the transitions are obtained by executing the original code using g++ and an extended SystemC library, and we ask the user to provide additional functions to store the current model state. These additional functions generally represent less than 20% of the size of the original model, and allow it to apply all CADP verification tools to the SystemC/TLM model itself.

  15. 32 CFR 199.23 - Special Supplemental Food Program.

    Science.gov (United States)

    2010-07-01

    ... years of age; or (B) Incapable of self-support because of mental or physical incapacity and is in fact... prescribed by Domestic WIC programs, as required by 10 U.S.C. 1060a(c)(1)(B). (27) Verification. Verification... who presents a valid WIC Program Verification of Certification card, which is issued to participants...

  16. Integrating software testing and run-time checking in an assertion verification framework

    OpenAIRE

    Mera, E.; López García, Pedro; Hermenegildo, Manuel V.

    2009-01-01

    We have designed and implemented a framework that unifies unit testing and run-time verification (as well as static verification and static debugging). A key contribution of our approach is that a unified assertion language is used for all of these tasks. We first propose methods for compiling runtime checks for (parts of) assertions which cannot be verified at compile-time via program transformation. This transformation allows checking preconditions and postconditions, including conditional...

  17. Methods of Software Verification

    Directory of Open Access Journals (Sweden)

    R. E. Gurin

    2015-01-01

    Full Text Available This article is devoted to the problem of software verification (SW. Methods of software verification designed to check the software for compliance with the stated requirements such as correctness, system security and system adaptability to small changes in the environment, portability and compatibility, etc. These are various methods both by the operation process and by the way of achieving result. The article describes the static and dynamic methods of software verification and paid attention to the method of symbolic execution. In its review of static analysis are discussed and described the deductive method, and methods for testing the model. A relevant issue of the pros and cons of a particular method is emphasized. The article considers classification of test techniques for each method. In this paper we present and analyze the characteristics and mechanisms of the static analysis of dependencies, as well as their views, which can reduce the number of false positives in situations where the current state of the program combines two or more states obtained both in different paths of execution and in working with multiple object values. Dependences connect various types of software objects: single variables, the elements of composite variables (structure fields, array elements, the size of the heap areas, the length of lines, the number of initialized array elements in the verification code using static methods. The article pays attention to the identification of dependencies within the framework of the abstract interpretation, as well as gives an overview and analysis of the inference tools.Methods of dynamic analysis such as testing, monitoring and profiling are presented and analyzed. Also some kinds of tools are considered which can be applied to the software when using the methods of dynamic analysis. Based on the work a conclusion is drawn, which describes the most relevant problems of analysis techniques, methods of their solutions and

  18. ENVIRONMENTAL TECHNOLOGY VERIFICATION, TEST REPORT OF CONTROL OF BIOAEROSOLS IN HVAC SYSTEMS, COLUMBUS INDUSTRIES HIGH EFFICIENCY MINI PLEAT

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) has created the Environmental Technology Verification (ETV) Program to facilitate the deployment of innovative or improved environmental technologies through performance verification and dissemination of information. The goal of the...

  19. INPO JTA application: developing a competency-based training program

    International Nuclear Information System (INIS)

    Patrick, P.W.

    1985-01-01

    Developing a competency-based training program requires the support of a strong curriculum development program. The major thrust of Arkansas Power and Light Company's competency-based curriculum development program is the identification of competencies using position task analysis data, panels, and INPO JTA data. Eight steps in the curriculum development approach provide the logic and rationale of the process: (1) establish competencies, (2) conduct competency verification, (3) develop competency tests, (4) develop curriculum, (5) develop instructional media, (6) validate curriculum and conduct field testing, (7) perform training effectiveness evaluation, and (8) revise the curriculum as needed. The processes describe how INPO JTA's and NRC procedures are cross-referenced to show that standards and requirements imposed or sanctioned by NRC and INPO are met. The competency-based approach to curriculum and training development eliminates the traditional scatterload approach to training and focuses on training to the competency. The primary benefits of competency-based training include accountability, minimal job training to meet job or position requirements, and a process to document an individual's job proficiency

  20. 76 FR 1440 - Notice of Revised Child Outcomes Framework

    Science.gov (United States)

    2011-01-10

    ... Outcomes Framework, renamed The Head Start Child Development and Learning Framework: Promoting Positive Outcomes in Early Childhood Programs Serving Children 3-5 Years Old. The Framework was revised to give more... DEPARTMENT OF HEALTH AND HUMAN SERVICES Administration for Children and Families Notice of Revised...

  1. Software verification in on-line systems

    International Nuclear Information System (INIS)

    Ehrenberger, W.

    1980-01-01

    Operator assistance is more and more provided by computers. Computers contain programs, whose quality should be above a certain level, before they are allowed to be used in reactor control rooms. Several possibilities for gaining software reliability figures are discussed in this paper. By supervising the testing procedure of a program, one can estimate the number of remaining programming errors. Such an estimation, however, is not very accurate. With mathematical proving procedures one can gain some knowledge on program properties. Such proving procedures are important for the verification of general WHILE-loops, which tend to be error prone. The program analysis decomposes a program into its parts. First the program structure is made visible, which includes the data movements and the control flow. From this analysis test cases can be derived that lead to a complete test. Program analysis can be done by hand or automatically. A statistical program test normally requires a large number of test runs. This number is diminished if details concerning both the program to be tested or its use are known in advance. (orig.)

  2. Experimental verification of internal dosimetry calculations. Annual progress report

    International Nuclear Information System (INIS)

    1980-05-01

    During the past year a dosimetry research program has been established in the School of Nuclear Engineering at the Georgia Institute of Technology. The major objective of this program has been to provide research results upon which a useful internal dosimetry system could be based. The important application of this dosimetry system will be the experimental verification of internal dosimetry calculations such as those published by the MIRD Committee

  3. Clinical Skills Verification, Formative Feedback, and Psychiatry Residency Trainees

    Science.gov (United States)

    Dalack, Gregory W.; Jibson, Michael D.

    2012-01-01

    Objective: The authors describe the implementation of Clinical Skills Verification (CSV) in their program as an in-training assessment intended primarily to provide formative feedback to trainees, strengthen the supervisory experience, identify the need for remediation of interviewing skills, and secondarily to demonstrating resident competence…

  4. FMCT verification: Case studies

    International Nuclear Information System (INIS)

    Hui Zhang

    2001-01-01

    Full text: How to manage the trade-off between the need for transparency and the concern about the disclosure of sensitive information would be a key issue during the negotiations of FMCT verification provision. This paper will explore the general concerns on FMCT verification; and demonstrate what verification measures might be applied to those reprocessing and enrichment plants. A primary goal of an FMCT will be to have the five declared nuclear weapon states and the three that operate unsafeguarded nuclear facilities become parties. One focus in negotiating the FMCT will be verification. Appropriate verification measures should be applied in each case. Most importantly, FMCT verification would focus, in the first instance, on these states' fissile material production facilities. After the FMCT enters into force, all these facilities should be declared. Some would continue operating to produce civil nuclear power or to produce fissile material for non- explosive military uses. The verification measures necessary for these operating facilities would be essentially IAEA safeguards, as currently being applied to non-nuclear weapon states under the NPT. However, some production facilities would be declared and shut down. Thus, one important task of the FMCT verifications will be to confirm the status of these closed facilities. As case studies, this paper will focus on the verification of those shutdown facilities. The FMCT verification system for former military facilities would have to differ in some ways from traditional IAEA safeguards. For example, there could be concerns about the potential loss of sensitive information at these facilities or at collocated facilities. Eventually, some safeguards measures such as environmental sampling might be seen as too intrusive. Thus, effective but less intrusive verification measures may be needed. Some sensitive nuclear facilities would be subject for the first time to international inspections, which could raise concerns

  5. Medicare and Medicaid programs: Hospital Outpatient Prospective Payment and Ambulatory Surgical Center Payment Systems and Quality Reporting Programs; electronic reporting pilot; Inpatient Rehabilitation Facilities Quality Reporting Program; revision to Quality Improvement Organization regulations. Final rule with comment period.

    Science.gov (United States)

    2012-11-15

    This final rule with comment period revises the Medicare hospital outpatient prospective payment system (OPPS) and the Medicare ambulatory surgical center (ASC) payment system for CY 2013 to implement applicable statutory requirements and changes arising from our continuing experience with these systems. In this final rule with comment period, we describe the changes to the amounts and factors used to determine the payment rates for Medicare services paid under the OPPS and those paid under the ASC payment system. In addition, this final rule with comment period updates and refines the requirements for the Hospital Outpatient Quality Reporting (OQR) Program, the ASC Quality Reporting (ASCQR) Program, and the Inpatient Rehabilitation Facility (IRF) Quality Reporting Program. We are continuing the electronic reporting pilot for the Electronic Health Record (EHR) Incentive Program, and revising the various regulations governing Quality Improvement Organizations (QIOs), including the secure transmittal of electronic medical information, beneficiary complaint resolution and notification processes, and technical changes. The technical changes to the QIO regulations reflect CMS' commitment to the general principles of the President's Executive Order on Regulatory Reform, Executive Order 13563 (January 18, 2011).

  6. Inspector measurement verification activities

    International Nuclear Information System (INIS)

    George, R.S.; Crouch, R.

    e most difficult and complex activity facing a safeguards inspector involves the verification of measurements and the performance of the measurement system. Remeasurement is the key to measurement verification activities. Remeasurerements using the facility's measurement system provide the bulk of the data needed for determining the performance of the measurement system. Remeasurements by reference laboratories are also important for evaluation of the measurement system and determination of systematic errors. The use of these measurement verification activities in conjunction with accepted inventory verification practices provides a better basis for accepting or rejecting an inventory. (U.S.)

  7. Verification and disarmament

    Energy Technology Data Exchange (ETDEWEB)

    Blix, H. [IAEA, Vienna (Austria)

    1998-07-01

    The main features are described of the IAEA safeguards verification system that non-nuclear weapon states parties of the NPT are obliged to accept. Verification activities/problems in Iraq and North Korea are discussed.

  8. Verification and disarmament

    International Nuclear Information System (INIS)

    Blix, H.

    1998-01-01

    The main features are described of the IAEA safeguards verification system that non-nuclear weapon states parties of the NPT are obliged to accept. Verification activities/problems in Iraq and North Korea are discussed

  9. Game-based verification and synthesis

    DEFF Research Database (Denmark)

    Vester, Steen

    and the environment behaves. Synthesis of strategies in games can thus be used for automatic generation of correct-by-construction programs from specifications. We consider verification and synthesis problems for several well-known game-based models. This includes both model-checking problems and satisfiability...... can be extended to solve finitely-branching turn-based games more efficiently. Further, the novel concept of winning cores in parity games is introduced. We use this to develop a new polynomial-time under-approximation algorithm for solving parity games. Experimental results show that this algorithm...... corresponds directly to a program for the corresponding entity of the system. A strategy for a player which ensures that the player wins no matter how the other players behave then corresponds to a program ensuring that the specification of the entity is satisfied no matter how the other entities...

  10. Environmental Technology Verification Report: Taconic Energy, Inc. TEA Fuel Additive

    Science.gov (United States)

    The Greenhouse Gas Technology Center (GHG Center) is one of six verification organizations operating under EPA’s ETV program. One sector of significant interest to GHG Center stakeholders is transportation - particularly technologies that result in fuel economy improvements. Taco...

  11. Scientific Programming in Fortran

    Directory of Open Access Journals (Sweden)

    W. Van Snyder

    2007-01-01

    Full Text Available The Fortran programming language was designed by John Backus and his colleagues at IBM to reduce the cost of programming scientific applications. IBM delivered the first compiler for its model 704 in 1957. IBM's competitors soon offered incompatible versions. ANSI (ASA at the time developed a standard, largely based on IBM's Fortran IV in 1966. Revisions of the standard were produced in 1977, 1990, 1995 and 2003. Development of a revision, scheduled for 2008, is under way. Unlike most other programming languages, Fortran is periodically revised to keep pace with developments in language and processor design, while revisions largely preserve compatibility with previous versions. Throughout, the focus on scientific programming, and especially on efficient generated programs, has been maintained.

  12. Static and runtime verification, competitors or friends? : (Track summary)

    NARCIS (Netherlands)

    Tiziana, Margaria; Gurov, Dilian; Havelund, Klaus; Bernhard, Steffen; Huisman, Marieke; Monahan, Rosemary; Margaria, Tiziana; Steffen, Bernhard

    2016-01-01

    Over the last years, significant progress has been made both on static and runtime program verification techniques, focusing on increasing the quality of software. Within this track, we would like to investigate how we can leverage these techniques by combining them. Questions that will be addressed

  13. Test/QA Plan for Verification of Radio Frequency Identification (RFID) for Tracking Hazardous Waste Shipments across International Borders

    Science.gov (United States)

    The verification test will be conducted under the auspices of the U.S. Environmental Protection Agency (EPA) through the Environmental Technology Verification (ETV) Program. It will be performed by Battelle, which is managing the ETV Advanced Monitoring Systems (AMS) Center throu...

  14. ENVIRONMENTAL TECHNOLOGY VERIFICATION REPORT, ENVIRONMENTAL DECISION SUPPORT SOFTWARE, UNIVERSITY OF TENNESSEE RESEARCH CORPORATION, SPATIAL ANALYSIS AND DECISION ASSISTANCE (SADA)

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) has created the Environmental Technology Verification Program (ETV) to facilitate the deployment of innovative or improved environmental technologies through performance verification and dissemination of information. The goal of the...

  15. Verification and validation of control system software

    International Nuclear Information System (INIS)

    Munro, J.K. Jr.; Kisner, R.A.; Bhadtt, S.C.

    1991-01-01

    The following guidelines are proposed for verification and validation (V ampersand V) of nuclear power plant control system software: (a) use risk management to decide what and how much V ampersand V is needed; (b) classify each software application using a scheme that reflects what type and how much V ampersand V is needed; (c) maintain a set of reference documents with current information about each application; (d) use Program Inspection as the initial basic verification method; and (e) establish a deficiencies log for each software application. The following additional practices are strongly recommended: (a) use a computer-based configuration management system to track all aspects of development and maintenance; (b) establish reference baselines of the software, associated reference documents, and development tools at regular intervals during development; (c) use object-oriented design and programming to promote greater software reliability and reuse; (d) provide a copy of the software development environment as part of the package of deliverables; and (e) initiate an effort to use formal methods for preparation of Technical Specifications. The paper provides background information and reasons for the guidelines and recommendations. 3 figs., 3 tabs

  16. 75 FR 17253 - Revisions to the General Conformity Regulations

    Science.gov (United States)

    2010-04-05

    ... Part III Environmental Protection Agency 40 CFR Parts 51 and 93 Revisions to the General... under the minor source New Source Review (NSR) programs similar to the EPA's existing General Conformity... EPA is making two minor revisions to the definition. First, EPA is correcting the citation for the SIP...

  17. Automatic programming for critical applications

    Science.gov (United States)

    Loganantharaj, Raj L.

    1988-01-01

    The important phases of a software life cycle include verification and maintenance. Usually, the execution performance is an expected requirement in a software development process. Unfortunately, the verification and the maintenance of programs are the time consuming and the frustrating aspects of software engineering. The verification cannot be waived for the programs used for critical applications such as, military, space, and nuclear plants. As a consequence, synthesis of programs from specifications, an alternative way of developing correct programs, is becoming popular. The definition, or what is understood by automatic programming, has been changed with our expectations. At present, the goal of automatic programming is the automation of programming process. Specifically, it means the application of artificial intelligence to software engineering in order to define techniques and create environments that help in the creation of high level programs. The automatic programming process may be divided into two phases: the problem acquisition phase and the program synthesis phase. In the problem acquisition phase, an informal specification of the problem is transformed into an unambiguous specification while in the program synthesis phase such a specification is further transformed into a concrete, executable program.

  18. HDL to verification logic translator

    Science.gov (United States)

    Gambles, J. W.; Windley, P. J.

    1992-01-01

    The increasingly higher number of transistors possible in VLSI circuits compounds the difficulty in insuring correct designs. As the number of possible test cases required to exhaustively simulate a circuit design explodes, a better method is required to confirm the absence of design faults. Formal verification methods provide a way to prove, using logic, that a circuit structure correctly implements its specification. Before verification is accepted by VLSI design engineers, the stand alone verification tools that are in use in the research community must be integrated with the CAD tools used by the designers. One problem facing the acceptance of formal verification into circuit design methodology is that the structural circuit descriptions used by the designers are not appropriate for verification work and those required for verification lack some of the features needed for design. We offer a solution to this dilemma: an automatic translation from the designers' HDL models into definitions for the higher-ordered logic (HOL) verification system. The translated definitions become the low level basis of circuit verification which in turn increases the designer's confidence in the correctness of higher level behavioral models.

  19. 76 FR 32321 - Approval and Promulgation of Air Quality Implementation Plans; Pennsylvania; Revision to the...

    Science.gov (United States)

    2011-06-06

    ...) Program--Quality Assurance Protocol for the Safety Inspection Program in Non-I/M Counties AGENCY... approve revisions to the Pennsylvania State Implementation Plan (SIP). The revision consists of a change... prior SIP-approved I/M program to change the duration of the timing of quality assurance audits...

  20. Design verification for reactor head replacement

    International Nuclear Information System (INIS)

    Dwivedy, K.K.; Whitt, M.S.; Lee, R.

    2005-01-01

    This paper outlines the challenges of design verification for reactor head replacement for PWR plants and the program for qualification from the prospective of the utility design engineering group. This paper is based on the experience with the design confirmation of four reactor head replacements for two plants, and their interfacing components, parts, appurtenances, and support structures. The reactor head replacement falls under the jurisdiction of the applicable edition of the ASME Section XI code, with particular reference to repair/replacement activities. Under any repair/replacement activities, demands may be encountered in the development of program and plan for replacement due to the vintage of the original design/construction Code and the design reports governing the component qualifications. Because of the obvious importance of the reactor vessel, these challenges take on an added significance. Additional complexities are introduced to the project, when the replacement components are fabricated by vendors different from the original vendor. Specific attention is needed with respect to compatibility with the original design and construction of the part and interfacing components. The program for reactor head replacement requires evaluation of welding procedures, applicable examination, test, and acceptance criteria for material, welds, and the components. Also, the design needs to take into consideration the life of the replacement components with respect to the extended period of operation of the plant after license renewal and other plant improvements. Thus, the verification of acceptability of reactor head replacement provides challenges for development and maintenance of a program and plan, design specification, design report, manufacturer's data report and material certification, and a report of reconciliation. The technical need may also be compounded by other challenges such as widely scattered global activities and organizational barriers, which

  1. Runtime Verification of C Programs

    Science.gov (United States)

    Havelund, Klaus

    2008-01-01

    We present in this paper a framework, RMOR, for monitoring the execution of C programs against state machines, expressed in a textual (nongraphical) format in files separate from the program. The state machine language has been inspired by a graphical state machine language RCAT recently developed at the Jet Propulsion Laboratory, as an alternative to using Linear Temporal Logic (LTL) for requirements capture. Transitions between states are labeled with abstract event names and Boolean expressions over such. The abstract events are connected to code fragments using an aspect-oriented pointcut language similar to ASPECTJ's or ASPECTC's pointcut language. The system is implemented in the C analysis and transformation package CIL, and is programmed in OCAML, the implementation language of CIL. The work is closely related to the notion of stateful aspects within aspect-oriented programming, where pointcut languages are extended with temporal assertions over the execution trace.

  2. Migrant Education Administrative Handbook. Revised April 1973.

    Science.gov (United States)

    North Carolina State Dept. of Public Instruction, Raleigh. Div. of Compensatory Education.

    The revised handbook provides specific references to the legislation and the National Migrant Program Guidelines, while setting forth the administrative procedures required for migrant projects in North Carolina. Specific topics of discussion in migrant program administration cover Public Law 89-750, state and local educational agency…

  3. Packaged low-level waste verification system

    Energy Technology Data Exchange (ETDEWEB)

    Tuite, K.; Winberg, M.R.; McIsaac, C.V. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

    1995-12-31

    The Department of Energy through the National Low-Level Waste Management Program and WMG Inc. have entered into a joint development effort to design, build, and demonstrate the Packaged Low-Level Waste Verification System. Currently, states and low-level radioactive waste disposal site operators have no method to independently verify the radionuclide content of packaged low-level waste that arrives at disposal sites for disposition. At this time, the disposal site relies on the low-level waste generator shipping manifests and accompanying records to ensure that low-level waste received meets the site`s waste acceptance criteria. The subject invention provides the equipment, software, and methods to enable the independent verification of low-level waste shipping records to ensure that the site`s waste acceptance criteria are being met. The objective of the prototype system is to demonstrate a mobile system capable of independently verifying the content of packaged low-level waste.

  4. Guidance document for revision of DOE Order 5820.2A, Radioactive Waste Technical Support Program

    International Nuclear Information System (INIS)

    Kudera, D.E.; McMurtrey, C.D.; Meagher, B.G.

    1993-04-01

    This document provides guidance for the revision of DOE Order 5820.2A, ''Radioactive Waste Management.'' Technical Working Groups have been established and are responsible for writing the revised order. The Technical Working Groups will use this document as a reference for polices and procedures that have been established for the revision process. The overall intent of this guidance is to outline how the order will be revised and how the revision process will be managed. In addition, this document outlines technical issues considered for inclusion by a Department of Energy Steering Committee

  5. 45 CFR 63.19 - Budget revisions and minor deviations.

    Science.gov (United States)

    2010-10-01

    ... 45 Public Welfare 1 2010-10-01 2010-10-01 false Budget revisions and minor deviations. 63.19 Section 63.19 Public Welfare DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL ADMINISTRATION GRANT PROGRAMS... Budget revisions and minor deviations. Pursuant to § 74.102(d) of this title, paragraphs (b)(3) and (b)(4...

  6. Revision of the grandiosity dimension of the Dimensional Clinical Personality Inventory and verification of its psychometric properties

    Directory of Open Access Journals (Sweden)

    Lucas de Francisco Carvalho

    Full Text Available Abstract Introduction: Personality disorders are among the most common disorders seen in clinical psychology. However, in Brazil there are few instruments for assessing the pathological characteristics of personality. Objective: To revise the grandiosity dimension of the Brazilian Dimensional Clinical Personality Inventory (Inventário Dimensional Clínico da Personalidade [IDCP] and investigate its psychometric properties. Methods: A total of 225 people participated in this study. Their ages ranged from 18 to 66 years (mean [M] = 26.2, standard deviation [SD] = 8.1 and the majority were female (n = 162, 70.1%. The IDCP and the Brazilian versions of the Revised NEO Personality Inventory (NEO PI-R and the Personality Inventory for DSM-5 (PID-5 were administered to all participants. Results: A total of 285 new items were developed and content analysis was used to select 33 of these to comprise the final version destined for administration. The results of parallel analysis and factor analysis identified four interpretable factors. Internal consistency coefficients were deemed acceptable and varied from 0.73 to 0.84 for the factors. Additionally, the expected correlations between the IDCP Inventory and the other tests were observed. Conclusion: This study demonstrates the revised dimension's suitability for assessment of the pathological traits of narcissistic personality disorder.

  7. ENVIRONMENTAL TECHNOLOGY VERIFICATION--TEST REPORT OF MOBILE SOURCE EMISSION CONTROL DEVICES, CUMMINS EMISSION SOLUTIONS AND CUMMINS FILTRATION DIESEL OXIDATION CATALYST AND CLOSED CRANKCASE VENTILATION SYSTEM

    Science.gov (United States)

    The U.S. EPA has created the Environmental Technology Verification (ETV) Program. ETV seeks to provide high-quality, peer-reviewed data on technology performance. The Air Pollution Control Technology (APCT) Verification Center, a center under the ETV Program, is operated by Res...

  8. Likelihood-ratio-based biometric verification

    NARCIS (Netherlands)

    Bazen, A.M.; Veldhuis, Raymond N.J.

    2002-01-01

    This paper presents results on optimal similarity measures for biometric verification based on fixed-length feature vectors. First, we show that the verification of a single user is equivalent to the detection problem, which implies that for single-user verification the likelihood ratio is optimal.

  9. Likelihood Ratio-Based Biometric Verification

    NARCIS (Netherlands)

    Bazen, A.M.; Veldhuis, Raymond N.J.

    The paper presents results on optimal similarity measures for biometric verification based on fixed-length feature vectors. First, we show that the verification of a single user is equivalent to the detection problem, which implies that, for single-user verification, the likelihood ratio is optimal.

  10. Ostomy Home Skills Program

    Medline Plus

    Full Text Available ... Validation Programs Accreditation, Verification, and Validation Programs Accredited Education Institutes ... Entering Resident Readiness Assessment Evidence-Based Decisions in ...

  11. Software engineering and automatic continuous verification of scientific software

    Science.gov (United States)

    Piggott, M. D.; Hill, J.; Farrell, P. E.; Kramer, S. C.; Wilson, C. R.; Ham, D.; Gorman, G. J.; Bond, T.

    2011-12-01

    Software engineering of scientific code is challenging for a number of reasons including pressure to publish and a lack of awareness of the pitfalls of software engineering by scientists. The Applied Modelling and Computation Group at Imperial College is a diverse group of researchers that employ best practice software engineering methods whilst developing open source scientific software. Our main code is Fluidity - a multi-purpose computational fluid dynamics (CFD) code that can be used for a wide range of scientific applications from earth-scale mantle convection, through basin-scale ocean dynamics, to laboratory-scale classic CFD problems, and is coupled to a number of other codes including nuclear radiation and solid modelling. Our software development infrastructure consists of a number of free tools that could be employed by any group that develops scientific code and has been developed over a number of years with many lessons learnt. A single code base is developed by over 30 people for which we use bazaar for revision control, making good use of the strong branching and merging capabilities. Using features of Canonical's Launchpad platform, such as code review, blueprints for designing features and bug reporting gives the group, partners and other Fluidity uers an easy-to-use platform to collaborate and allows the induction of new members of the group into an environment where software development forms a central part of their work. The code repositoriy are coupled to an automated test and verification system which performs over 20,000 tests, including unit tests, short regression tests, code verification and large parallel tests. Included in these tests are build tests on HPC systems, including local and UK National HPC services. The testing of code in this manner leads to a continuous verification process; not a discrete event performed once development has ceased. Much of the code verification is done via the "gold standard" of comparisons to analytical

  12. Methods for implementing revisions to emergency operating procedures. Final report

    International Nuclear Information System (INIS)

    Myers, L.B.; Bell, A.J.

    1984-05-01

    In response to the Three Mile Island (TMI) accident, the US Nuclear Regulatory Commission (NRC) has published the TMI Action Plan. The TMI Action Plan Item I.C.1 called for the upgrading of Emergency Operating Procedures (EOPs) at nuclear power plants. The program developed from this Action Plan item has resulted in utility efforts to: (1) revise EOPs; (2) train personnel in the use of the EOPs; and (3) implement the revised EOPs. The NRC supported the study presented in this report to identify factors which influence the effectiveness of training and implementation of revised EOPs. The NRC's major concern was the possible effects of negative transfer of training. The report includes a summary of existing methods for implementing revisions to procedures based on interviews of plant personnel, a review of the training literature applicable to the effect of previously learned procedures on the learning of and performance with revised procedures (i.e., negative transfer) and recommendations of methods and schedules for implementing revised EOPs. While the study found that the concern over negative transfer of training was not as great as anticipated, several recommendations were made. These include: (1) overtraining of operators to reduce the effect of observed negative transfer; and (2) implementation of the revised EOPs as soon as possible after training to minimize the time operators must rely upon the old EOPs after having been trained on the revised EOPs. The results of the study should be useful both to the utilities and the NRC in the development and review of EOP implementation programs

  13. M&V Guidelines: Measurement and Verification for Performance-Based Contracts Version 4.0

    Energy Technology Data Exchange (ETDEWEB)

    None

    2015-11-02

    Document outlines the Federal Energy Management Program's standard procedures and guidelines for measurement and verification (M&V) for federal energy managers, procurement officials, and energy service providers.

  14. Probabilistic Requirements (Partial) Verification Methods Best Practices Improvement. Variables Acceptance Sampling Calculators: Derivations and Verification of Plans. Volume 1

    Science.gov (United States)

    Johnson, Kenneth L.; White, K, Preston, Jr.

    2012-01-01

    The NASA Engineering and Safety Center was requested to improve on the Best Practices document produced for the NESC assessment, Verification of Probabilistic Requirements for the Constellation Program, by giving a recommended procedure for using acceptance sampling by variables techniques. This recommended procedure would be used as an alternative to the potentially resource-intensive acceptance sampling by attributes method given in the document. This document contains the outcome of the assessment.

  15. 40 CFR 76.7 - Revised NOX emission limitations for Group 1, Phase II boilers.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Revised NOX emission limitations for Group 1, Phase II boilers. 76.7 Section 76.7 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) ACID RAIN NITROGEN OXIDES EMISSION REDUCTION PROGRAM § 76.7 Revised NOX...

  16. Scalable Techniques for Formal Verification

    CERN Document Server

    Ray, Sandip

    2010-01-01

    This book presents state-of-the-art approaches to formal verification techniques to seamlessly integrate different formal verification methods within a single logical foundation. It should benefit researchers and practitioners looking to get a broad overview of the spectrum of formal verification techniques, as well as approaches to combining such techniques within a single framework. Coverage includes a range of case studies showing how such combination is fruitful in developing a scalable verification methodology for industrial designs. This book outlines both theoretical and practical issue

  17. Verification of the network flow and transport/distributed velocity (NWFT/DVM) computer code

    International Nuclear Information System (INIS)

    Duda, L.E.

    1984-05-01

    The Network Flow and Transport/Distributed Velocity Method (NWFT/DVM) computer code was developed primarily to fulfill a need for a computationally efficient ground-water flow and contaminant transport capability for use in risk analyses where, quite frequently, large numbers of calculations are required. It is a semi-analytic, quasi-two-dimensional network code that simulates ground-water flow and the transport of dissolved species (radionuclides) in a saturated porous medium. The development of this code was carried out under a program funded by the US Nuclear Regulatory Commission (NRC) to develop a methodology for assessing the risk from disposal of radioactive wastes in deep geologic formations (FIN: A-1192 and A-1266). In support to the methodology development program, the NRC has funded a separate Maintenance of Computer Programs Project (FIN: A-1166) to ensure that the codes developed under A-1192 or A-1266 remain consistent with current operating systems, are as error-free as possible, and have up-to-date documentations for reference by the NRC staff. Part of this effort would include verification and validation tests to assure that a code correctly performs the operations specified and/or is representing the processes or system for which it is intended. This document contains four verification problems for the NWFT/DVM computer code. Two of these problems are analytical verifications of NWFT/DVM where results are compared to analytical solutions. The other two are code-to-code verifications where results from NWFT/DVM are compared to those of another computer code. In all cases NWFT/DVM showed good agreement with both the analytical solutions and the results from the other code

  18. TRU waste certification and TRUPACT-2 payload verification

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  19. Ostomy Home Skills Program

    Medline Plus

    Full Text Available ... Trauma Quality Programs National Trauma Data Bank Trauma Quality Improvement Program Mentoring for Excellence in Trauma Surgery Advanced Trauma Life Support Verification, Review, and Consultation Program for Hospitals ...

  20. 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.

  1. 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

  2. Probabilistic Programming : A True Verification Challenge

    NARCIS (Netherlands)

    Katoen, Joost P.; Finkbeiner, Bernd; Pu, Geguang; Zhang, Lijun

    2015-01-01

    Probabilistic programs [6] are sequential programs, written in languages like C, Java, Scala, or ML, with two added constructs: (1) the ability to draw values at random from probability distributions, and (2) the ability to condition values of variables in a program through observations. For a

  3. ENVIRONMENTAL TECHNOLOGY VERIFICATION REPORT: MOBILE SOURCE RETROFIT AIR POLLUTION CONTROL DEVICES: CLEAN CLEAR FUEL TECHNOLOGIES, INC.’S, UNIVERSAL FUEL CELL

    Science.gov (United States)

    The U.S. EPA's Office of Research and Development operates the Environmental Technology Verification (ETV) program to facilitate the deployment of innovative technologies through performance verification and information dissemination. Congress funds ETV in response to the belief ...

  4. Ostomy Home Skills Program

    Medline Plus

    Full Text Available ... Verification, Review, and Consultation Program for Hospitals Trauma Systems Consultation Program Trauma Education Achieving Zero Preventable Deaths Conference Publications and Posters ...

  5. Can self-verification strivings fully transcend the self-other barrier? Seeking verification of ingroup identities.

    Science.gov (United States)

    Gómez, Angel; Seyle, D Conor; Huici, Carmen; Swann, William B

    2009-12-01

    Recent research has demonstrated self-verification strivings in groups, such that people strive to verify collective identities, which are personal self-views (e.g., "sensitive") associated with group membership (e.g., "women"). Such demonstrations stop short of showing that the desire for self-verification can fully transcend the self-other barrier, as in people working to verify ingroup identities (e.g., "Americans are loud") even when such identities are not self-descriptive ("I am quiet and unassuming"). Five studies focus on such ingroup verification strivings. Results indicate that people prefer to interact with individuals who verify their ingroup identities over those who enhance these identities (Experiments 1-5). Strivings for ingroup identity verification were independent of the extent to which the identities were self-descriptive but were stronger among participants who were highly invested in their ingroup identities, as reflected in high certainty of these identities (Experiments 1-4) and high identification with the group (Experiments 1-5). In addition, whereas past demonstrations of self-verification strivings have been limited to efforts to verify the content of identities (Experiments 1 to 3), the findings also show that they strive to verify the valence of their identities (i.e., the extent to which the identities are valued; Experiments 4 and 5). Self-verification strivings, rather than self-enhancement strivings, appeared to motivate participants' strivings for ingroup identity verification. Links to collective self-verification strivings and social identity theory are discussed.

  6. Development and Implementation of Cgcre Accreditation Program for Greenhouse Gas Verification Bodies

    International Nuclear Information System (INIS)

    Fermam, Ricardo Kropf Santos; De Queiroz, Andrea Barroso Melo Monteiro

    2016-01-01

    An organizational innovation is defined as the implementation of a new organizational method in the firm's business practices, organization of your workplace or in its external relations. This work illustrates a Cgcre innovation, by presentation of the development process of greenhouse gases verification body in Brazil according to the Brazilian accreditation body, the General Coordination for Accreditation (Cgcre). (paper)

  7. 78 FR 54178 - Virginia: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-09-03

    ... XIX Academic Laboratories 73 FR 72912, 9 VAC Sec. Sec. 20- Generator Standards, Revision December 1... 17, 60-18, 20-60-261 A, Hazardous Constituents, 2010. 20-60-268 A. Revision Checklist 225. Academic... steps to eliminate drafting errors and ambiguity, minimize potential litigation, and provide a clear...

  8. Industrial hardware and software verification with ACL2.

    Science.gov (United States)

    Hunt, Warren A; Kaufmann, Matt; Moore, J Strother; Slobodova, Anna

    2017-10-13

    The ACL2 theorem prover has seen sustained industrial use since the mid-1990s. Companies that have used ACL2 regularly include AMD, Centaur Technology, IBM, Intel, Kestrel Institute, Motorola/Freescale, Oracle and Rockwell Collins. This paper introduces ACL2 and focuses on how and why ACL2 is used in industry. ACL2 is well-suited to its industrial application to numerous software and hardware systems, because it is an integrated programming/proof environment supporting a subset of the ANSI standard Common Lisp programming language. As a programming language ACL2 permits the coding of efficient and robust programs; as a prover ACL2 can be fully automatic but provides many features permitting domain-specific human-supplied guidance at various levels of abstraction. ACL2 specifications and models often serve as efficient execution engines for the modelled artefacts while permitting formal analysis and proof of properties. Crucially, ACL2 also provides support for the development and verification of other formal analysis tools. However, ACL2 did not find its way into industrial use merely because of its technical features. The core ACL2 user/development community has a shared vision of making mechanized verification routine when appropriate and has been committed to this vision for the quarter century since the Computational Logic, Inc., Verified Stack. The community has focused on demonstrating the viability of the tool by taking on industrial projects (often at the expense of not being able to publish much).This article is part of the themed issue 'Verified trustworthy software systems'. © 2017 The Author(s).

  9. DOE handbook: Integrated safety management systems (ISMS) verification. Team leader's handbook

    International Nuclear Information System (INIS)

    1999-06-01

    facilities, non-nuclear, or non-Defense Programs facilities. DOE line managers are encouraged to tailor the procedures described in this handbook for ISMS verifications for low risk facilities

  10. ENVIRONMENTAL TECHNOLOGY VERIFICATION REPORT, SHARPE MANUFACTURING TITANIUM T1-CG SPRAY GUN

    Science.gov (United States)

    Under EPA’s Environmental Technology Verification program, which provides objective and scientific third party analysis of new technology that can benefit the environment, the pollution prevention capabilities of a high transfer efficiency liquid spray gun was tested. This ...

  11. ENVIRONMENTAL TECHNOLOGY VERIFICATION REPORT, ANEST IWATA CORPORATION W400-LV SPRAY GUN

    Science.gov (United States)

    Under EPA’s Environmental Technology Verification program, which provides objective and scientific third party analysis of new technology that can benefit the environment, the pollution prevention capabilities of a high transfer efficiency liquid spray gun was tested. This ...

  12. Utterance Verification for Text-Dependent Speaker Recognition

    DEFF Research Database (Denmark)

    Kinnunen, Tomi; Sahidullah, Md; Kukanov, Ivan

    2016-01-01

    Text-dependent automatic speaker verification naturally calls for the simultaneous verification of speaker identity and spoken content. These two tasks can be achieved with automatic speaker verification (ASV) and utterance verification (UV) technologies. While both have been addressed previously...

  13. The new revision of NPP Krsko decommissioning, radioactive waste and spent fuel management program: analyses and results

    International Nuclear Information System (INIS)

    Zeleznik, Nadja; Kralj, Metka; Lokner, Vladimir; Levanat, Ivica; Rapic, Andrea; Mele, Irena

    2010-01-01

    The preparation of the new revision of the Decommissioning and Spent Fuel (SF) and Low and Intermediate level Waste (LILW) Disposal Program for the NPP Krsko (Program) started in September 2008 after the acceptance of the Term of Reference for the work by Intergovernmental Committee responsible for implementation of the Agreement between the governments of Slovenia and Croatia on the status and other legal issues related to investment, exploitation, and decommissioning of the Nuclear power plant Krsko. The responsible organizations, APO and ARAO together with NEK prepared all new technical and financial data and relevant inputs for the new revision in which several scenarios based on the accepted boundary conditions were investigated. The strategy of immediate dismantling was analyzed for planned and extended NPP life time together with linked radioactive waste and spent fuel management to calculate yearly annuity to be paid by the owners into the decommissioning funds in Slovenia and Croatia. The new Program incorporated among others new data on the LILW repository including the costs for siting, construction and operation of silos at the location Vrbina in Krsko municipality, the site specific Preliminary Decommissioning Plan for NPP Krsko which included besides dismantling and decontamination approaches also site specific activated and contaminated radioactive waste, and results from the referenced scenario for spent fuel disposal but at very early stage. Important inputs for calculations presented also new amounts of compensations to the local communities for different nuclear facilities which were taken from the supplemented Slovenian regulation and updated fiscal parameters (inflation, interest, discount factors) used in the financial model based on the current development in economical environment. From the obtained data the nominal and discounted costs for the whole nuclear program related to NPP Krsko which is jointly owned by Slovenia and Croatia have

  14. 78 FR 25013 - Medicare Program; Requirements for the Medicare Incentive Reward Program and Provider Enrollment

    Science.gov (United States)

    2013-04-29

    .... ACTION: Proposed rule. SUMMARY: This proposed rule would revise the Incentive Reward Program provisions... significant of these revisions include: changing the Incentive Reward Program potential reward amount for... related to the Incentive Reward Program. Frank Whelan, (410) 786-1302, for issues related to provider...

  15. Ostomy Home Skills Program

    Medline Plus

    Full Text Available ... in Trauma Surgery Advanced Trauma Life Support Verification, Review, and Consultation Program for Hospitals Trauma Systems Consultation Program Trauma Education Achieving Zero Preventable Deaths ...

  16. GENERIC VERIFICATION PROTOCOL FOR DETERMINATION OF EMISSIONS REDUCTIONS FROM SELECTIVE CATALYTIC REDUCTIONS CONTROL TECHNOLOGIES FOR HIGHWAY, NONROAD, AND STATIONARY USE DIESEL ENGINES

    Science.gov (United States)

    The protocol describes the Environmental Technology Verification (ETV) Program's considerations and requirements for verification of emissions reduction provided by selective catalytic reduction (SCR) technologies. The basis of the ETV will be comparison of the emissions and perf...

  17. ENVIRONMENTAL TECHNOLOGY VERIFICATION REPORT - BAGHOUSE FILTRATION PRODUCTS - TETRATEC PTFE TECHNOLOGIES TETRATEX 8005

    Science.gov (United States)

    Baghouse filtration products (BFPs) were evaluated by the Air Pollution Control Technology (APCT) pilot of the Environmental Technology Verification (ETV) Program. The performance factor verified was the mean outlet particle concentration for the filter fabric as a function of th...

  18. Re-evaluating your nuclear program needs: how to benefit from your vendor's Q.A. program

    International Nuclear Information System (INIS)

    Cocoros, A.E.

    1979-01-01

    The quality assurance component control and verification program to be presented provides a cost effective approach to monitoring and controlling the implementation of the design, fabrication, inspection and shipping plans of a supplier. It attempts to coordinate and integrate quality control and verification effort of a supplier with the control and verification effort of the purchaser to obtain a composite which accomplishes a total need. Based on the competency and capabilities of the supplier the purchaser can either maximize the effort the supplier performs or he must maximize his effort to obtain an optimum mix. The ultimate goal is to utilize the supplier's quality assurance program to the greatest benefit in assuring maximum quality

  19. Verification and validation of decision support software: Expert Choice{trademark} and PCM{trademark}

    Energy Technology Data Exchange (ETDEWEB)

    Nguyen, Q.H.; Martin, J.D.

    1994-11-04

    This report documents the verification and validation of two decision support programs: EXPERT CHOICE{trademark} and PCM{trademark}. Both programs use the Analytic Hierarchy Process (AHP) -- or pairwise comparison technique -- developed by Dr. Thomas L. Saaty. In order to provide an independent method for the validating the two programs, the pairwise comparison algorithm was developed for a standard mathematical program. A standard data set -- selecting a car to purchase -- was used with each of the three programs for validation. The results show that both commercial programs performed correctly.

  20. KNGR core proection calculator, software, verification and validation plan

    International Nuclear Information System (INIS)

    Kim, Jang Yeol; Park, Jong Kyun; Lee, Ki Young; Lee, Jang Soo; Cheon, Se Woo

    2001-05-01

    This document describes the Software Verification and Validation Plan(SVVP) Guidance to be used in reviewing the Software Program Manual(SPM) in Korean Next Generation Reactor(KNGR) projects. This document is intended for a verifier or reviewer who is involved with performing of software verification and validation task activity in KNGR projects. This document includeds the basic philosophy, performing V and V effort, software testing techniques, criteria of review and audit on the safety software V and V activity. Major review topics on safety software addresses three kinds of characteristics based on Standard Review Plan(SRP) Chapter 7, Branch Technical Position(BTP)-14 : management characteristics, implementation characteristics and resources characteristics when reviewing on SVVP. Based on major topics of this document, we have produced the evaluation items list such as checklist in Appendix A

  1. Automatic Verification of Railway Interlocking Systems: A Case Study

    DEFF Research Database (Denmark)

    Petersen, Jakob Lyng

    1998-01-01

    This paper presents experiences in applying formal verification to a large industrial piece of software. The are of application is railway interlocking systems. We try to prove requirements of the program controlling the Swedish railway Station Alingsås by using the decision procedure which...... express thoughts on what is needed in order to be able to successfully verify large real-life systems....

  2. Revision of ISO 15859 Aerospace Fluid Standards

    Science.gov (United States)

    Greene, Benjamin; McClure, Mark B.

    2012-01-01

    A detailed review of ISO 15859 "Space Systems - Fluid Characteristics, Sampling and Test Methods" was performed An approach to revising Parts 1-9 and 11-13 was developed and concurred by the NASA Technical Standards Program Office. The approach was to align them with the highest level source documents, and not to program-specific requirements. The updated documents were prepared and presented.

  3. Evaluating the Influence of the Revised Special Supplemental Nutrition Program for Women, Infants, and Children (WIC) Food Allocation Package on Healthy Food Availability, Accessibility, and Affordability in Texas.

    Science.gov (United States)

    Lu, Wenhua; McKyer, E Lisako J; Dowdy, Diane; Evans, Alexandra; Ory, Marcia; Hoelscher, Deanna M; Wang, Suojin; Miao, Jingang

    2016-02-01

    The Special Supplemental Nutrition Program for Women, Infants, and Children (WIC) was implemented to improve the health of pregnant women and children of low socioeconomic status. In 2009, the program was revised to provide a wider variety of healthy food choices (eg, fresh fruits, vegetables, and whole-grain items). The purpose of this study was to evaluate (1) the impact of the revised WIC Nutrition Program's food allocation package on the availability, accessibility, and affordability of healthy foods in WIC-authorized grocery stores in Texas; and (2) how the impact of the policy change differed by store types and between rural and urban regions. WIC-approved stores (n=105) across Texas were assessed using a validated instrument (88 items). Pre- (June-September 2009) and post-new WIC package implementation (June-September 2012) audits were conducted. Paired-sample t tests were conducted to compare the differences between pre- and post-implementation audits on shelf width and number of varieties (ie, availability), visibility (ie, accessibility), and inflation-adjusted price (ie, affordability). Across the 105 stores, post-implementation audits showed increased availability in terms of shelf space for most key healthy food options, including fruit (PFood visibility increased for fresh juices (Pfoods such as fruits (Pbread (Pbread (Pfood availability and visibility were observed in stores of different types and in different locations, although smaller or fewer effects were noted in small stores and stores in rural regions. Implementation of the revised WIC food package has generally improved availability and accessibility, but not affordability, of healthy foods in WIC-authorized stores in Texas. Future studies are needed to explore the impact of the revised program on healthy food option purchases and consumption patterns among Texas WIC participants. Copyright © 2016 Academy of Nutrition and Dietetics. Published by Elsevier Inc. All rights reserved.

  4. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    Energy Technology Data Exchange (ETDEWEB)

    BAZINET, G.D.

    2001-05-15

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. Revision 1 documented verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those requirements are noted in section 3

  5. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    Energy Technology Data Exchange (ETDEWEB)

    BAZINET, G.D.

    2000-11-03

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. The purpose of this revision is to document completion of verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those

  6. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    International Nuclear Information System (INIS)

    BAZINET, G.D.

    2001-01-01

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. Revision 1 documented verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those requirements are noted in section 3.1.5 and will be

  7. Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)

    International Nuclear Information System (INIS)

    BAZINET, G.D.

    2000-01-01

    The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. The purpose of this revision is to document completion of verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those requirements are noted

  8. Nuclear disarmament verification

    International Nuclear Information System (INIS)

    DeVolpi, A.

    1993-01-01

    Arms control treaties, unilateral actions, and cooperative activities -- reflecting the defusing of East-West tensions -- are causing nuclear weapons to be disarmed and dismantled worldwide. In order to provide for future reductions and to build confidence in the permanency of this disarmament, verification procedures and technologies would play an important role. This paper outlines arms-control objectives, treaty organization, and actions that could be undertaken. For the purposes of this Workshop on Verification, nuclear disarmament has been divided into five topical subareas: Converting nuclear-weapons production complexes, Eliminating and monitoring nuclear-weapons delivery systems, Disabling and destroying nuclear warheads, Demilitarizing or non-military utilization of special nuclear materials, and Inhibiting nuclear arms in non-nuclear-weapons states. This paper concludes with an overview of potential methods for verification

  9. Verification Account Management System (VAMS)

    Data.gov (United States)

    Social Security Administration — The Verification Account Management System (VAMS) is the centralized location for maintaining SSA's verification and data exchange accounts. VAMS account management...

  10. SU-F-T-268: A Feasibility Study of Independent Dose Verification for Vero4DRT

    International Nuclear Information System (INIS)

    Yamashita, M; Kokubo, M; Takahashi, R; Takayama, K; Tanabe, H; Sueoka, M; Okuuchi, N; Ishii, M; Iwamoto, Y; Tachibana, H

    2016-01-01

    Purpose: Vero4DRT (Mitsubishi Heavy Industries Ltd.) has been released for a few years. The treatment planning system (TPS) of Vero4DRT is dedicated, so the measurement is the only method of dose verification. There have been no reports of independent dose verification using Clarksonbased algorithm for Vero4DRT. An independent dose verification software program of the general-purpose linac using a modified Clarkson-based algorithm was modified for Vero4DRT. In this study, we evaluated the accuracy of independent dose verification program and the feasibility of the secondary check for Vero4DRT. Methods: iPlan (Brainlab AG) was used as the TPS. PencilBeam Convolution was used for dose calculation algorithm of IMRT and X-ray Voxel Monte Carlo was used for the others. Simple MU Analysis (SMU, Triangle Products, Japan) was used as the independent dose verification software program in which CT-based dose calculation was performed using a modified Clarkson-based algorithm. In this study, 120 patients’ treatment plans were collected in our institute. The treatments were performed using the conventional irradiation for lung and prostate, SBRT for lung and Step and shoot IMRT for prostate. Comparison in dose between the TPS and the SMU was done and confidence limits (CLs, Mean ± 2SD %) were compared to those from the general-purpose linac. Results: As the results of the CLs, the conventional irradiation (lung, prostate), SBRT (lung) and IMRT (prostate) show 2.2 ± 3.5% (CL of the general-purpose linac: 2.4 ± 5.3%), 1.1 ± 1.7% (−0.3 ± 2.0%), 4.8 ± 3.7% (5.4 ± 5.3%) and −0.5 ± 2.5% (−0.1 ± 3.6%), respectively. The CLs for Vero4DRT show similar results to that for the general-purpose linac. Conclusion: The independent dose verification for the new linac is clinically available as a secondary check and we performed the check with the similar tolerance level of the general-purpose linac. This research is partially supported by Japan Agency for Medical Research and

  11. SU-F-T-268: A Feasibility Study of Independent Dose Verification for Vero4DRT

    Energy Technology Data Exchange (ETDEWEB)

    Yamashita, M; Kokubo, M [Kobe City Medical Center General Hospital, Kobe, Hyogo (Japan); Institute of Biomedical Research and Innovation, Kobe, Hyogo (Japan); Takahashi, R [Cancer Institute Hospital of Japanese Foundation for Cancer Research, Koto, Tokyo (Japan); Takayama, K [Institute of Biomedical Research and Innovation, Kobe, Hyogo (Japan); Kobe City Medical Center General Hospital, Kobe, Hyogo (Japan); Tanabe, H; Sueoka, M; Okuuchi, N [Institute of Biomedical Research and Innovation, Kobe, Hyogo (Japan); Ishii, M; Iwamoto, Y [Kobe City Medical Center General Hospital, Kobe, Hyogo (Japan); Tachibana, H [National Cancer Center, Kashiwa, Chiba (Japan)

    2016-06-15

    Purpose: Vero4DRT (Mitsubishi Heavy Industries Ltd.) has been released for a few years. The treatment planning system (TPS) of Vero4DRT is dedicated, so the measurement is the only method of dose verification. There have been no reports of independent dose verification using Clarksonbased algorithm for Vero4DRT. An independent dose verification software program of the general-purpose linac using a modified Clarkson-based algorithm was modified for Vero4DRT. In this study, we evaluated the accuracy of independent dose verification program and the feasibility of the secondary check for Vero4DRT. Methods: iPlan (Brainlab AG) was used as the TPS. PencilBeam Convolution was used for dose calculation algorithm of IMRT and X-ray Voxel Monte Carlo was used for the others. Simple MU Analysis (SMU, Triangle Products, Japan) was used as the independent dose verification software program in which CT-based dose calculation was performed using a modified Clarkson-based algorithm. In this study, 120 patients’ treatment plans were collected in our institute. The treatments were performed using the conventional irradiation for lung and prostate, SBRT for lung and Step and shoot IMRT for prostate. Comparison in dose between the TPS and the SMU was done and confidence limits (CLs, Mean ± 2SD %) were compared to those from the general-purpose linac. Results: As the results of the CLs, the conventional irradiation (lung, prostate), SBRT (lung) and IMRT (prostate) show 2.2 ± 3.5% (CL of the general-purpose linac: 2.4 ± 5.3%), 1.1 ± 1.7% (−0.3 ± 2.0%), 4.8 ± 3.7% (5.4 ± 5.3%) and −0.5 ± 2.5% (−0.1 ± 3.6%), respectively. The CLs for Vero4DRT show similar results to that for the general-purpose linac. Conclusion: The independent dose verification for the new linac is clinically available as a secondary check and we performed the check with the similar tolerance level of the general-purpose linac. This research is partially supported by Japan Agency for Medical Research and

  12. VIPEX (Vital-area Identification Package EXpert) Software Verification and Validation

    International Nuclear Information System (INIS)

    Jung, Woo Sik; Suh, Jae Seung

    2010-06-01

    The purposes of this report are (1) to perform a Verification and Validation (V and V) test for the VIPEX(Vital-area Identification Package EXpert) software and (2) to improve a software quality through the V and V test. The VIPEX was developed in Korea Atomic Energy Research Institute (KAERI) for the Vital Area Identification (VAI) of nuclear power plants. The version of the VIPEX which was distributed is 3.2.0.0. The VIPEX was revised based on the first V and V test and the second V and V test was performed. We have performed the following tasks for the V and V test on Windows XP and VISTA operating systems: Ο Testing basic functions including fault tree editing Ο Testing all kind of functions Ο Research for update from Visual BASIC 6.0 to Visual BASIC 2008

  13. Commitment to COT verification improves patient outcomes and financial performance.

    Science.gov (United States)

    Maggio, Paul M; Brundage, Susan I; Hernandez-Boussard, Tina; Spain, David A

    2009-07-01

    After an unsuccessful American College of Surgery Committee on Trauma visit, our level I trauma center initiated an improvement program that included (1) hiring new personnel (trauma director and surgeons, nurse coordinator, orthopedic trauma surgeon, and registry staff), (2) correcting deficiencies in trauma quality assurance and process improvement programs, and (3) development of an outreach program. Subsequently, our trauma center had two successful verifications. We examined the longitudinal effects of these efforts on volume, patient outcomes and finances. The Trauma Registry was used to derive data for all trauma patients evaluated in the emergency department from 2001 to 2007. Clinical data analyzed included number of admissions, interfacility transfers, injury severity scores (ISS), length of stay, and mortality for 2001 to 2007. Financial performance was assessed for fiscal years 2001 to 2007. Data were divided into patients discharged from the emergency department and those admitted to the hospital. Admissions increased 30%, representing a 7.6% annual increase (p = 0.004), mostly due to a nearly fivefold increase in interfacility transfers. Severe trauma patients (ISS >24) increased 106% and mortality rate for ISS >24 decreased by 47% to almost half the average of the National Trauma Database. There was a 78% increase in revenue and a sustained increase in hospital profitability. A major hospital commitment to Committee on Trauma verification had several salient outcomes; increased admissions, interfacility transfers, and acuity. Despite more seriously injured patients, there has been a major, sustained reduction in mortality and a trend toward decreased intensive care unit length of stay. This resulted in a substantial increase in contribution to margin (CTM), net profit, and revenues. With a high level of commitment and favorable payer mix, trauma center verification improves outcomes for both patients and the hospital.

  14. Quantum money with classical verification

    Energy Technology Data Exchange (ETDEWEB)

    Gavinsky, Dmitry [NEC Laboratories America, Princeton, NJ (United States)

    2014-12-04

    We propose and construct a quantum money scheme that allows verification through classical communication with a bank. This is the first demonstration that a secure quantum money scheme exists that does not require quantum communication for coin verification. Our scheme is secure against adaptive adversaries - this property is not directly related to the possibility of classical verification, nevertheless none of the earlier quantum money constructions is known to possess it.

  15. Quantum money with classical verification

    International Nuclear Information System (INIS)

    Gavinsky, Dmitry

    2014-01-01

    We propose and construct a quantum money scheme that allows verification through classical communication with a bank. This is the first demonstration that a secure quantum money scheme exists that does not require quantum communication for coin verification. Our scheme is secure against adaptive adversaries - this property is not directly related to the possibility of classical verification, nevertheless none of the earlier quantum money constructions is known to possess it

  16. Development, Verification and Validation of Parallel, Scalable Volume of Fluid CFD Program for Propulsion Applications

    Science.gov (United States)

    West, Jeff; Yang, H. Q.

    2014-01-01

    There are many instances involving liquid/gas interfaces and their dynamics in the design of liquid engine powered rockets such as the Space Launch System (SLS). Some examples of these applications are: Propellant tank draining and slosh, subcritical condition injector analysis for gas generators, preburners and thrust chambers, water deluge mitigation for launch induced environments and even solid rocket motor liquid slag dynamics. Commercially available CFD programs simulating gas/liquid interfaces using the Volume of Fluid approach are currently limited in their parallel scalability. In 2010 for instance, an internal NASA/MSFC review of three commercial tools revealed that parallel scalability was seriously compromised at 8 cpus and no additional speedup was possible after 32 cpus. Other non-interface CFD applications at the time were demonstrating useful parallel scalability up to 4,096 processors or more. Based on this review, NASA/MSFC initiated an effort to implement a Volume of Fluid implementation within the unstructured mesh, pressure-based algorithm CFD program, Loci-STREAM. After verification was achieved by comparing results to the commercial CFD program CFD-Ace+, and validation by direct comparison with data, Loci-STREAM-VoF is now the production CFD tool for propellant slosh force and slosh damping rate simulations at NASA/MSFC. On these applications, good parallel scalability has been demonstrated for problems sizes of tens of millions of cells and thousands of cpu cores. Ongoing efforts are focused on the application of Loci-STREAM-VoF to predict the transient flow patterns of water on the SLS Mobile Launch Platform in order to support the phasing of water for launch environment mitigation so that vehicle determinantal effects are not realized.

  17. 78 FR 70225 - West Virginia: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-11-25

    ... 04. 45-25-1.1.a, 45-25- Trucks, Revision Checklist 1.5.a/Table 25-A, 205. Item 9. RCRA Cluster XV...- Pigments, and Food, Drug, and 70 FR 35032, 6/ 10.1. Cosmetic Colorants, Revision 16/05. Checklist 206...

  18. 40 CFR 131.20 - State review and revision of water quality standards.

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) WATER PROGRAMS WATER QUALITY STANDARDS Procedures for Review and Revision of Water Quality Standards § 131.20 State review and revision of water quality standards. (a) State review. The State shall... reviewing applicable water quality standards and, as appropriate, modifying and adopting standards. Any...

  19. Particularities of Verification Processes for Distributed Informatics Applications

    Directory of Open Access Journals (Sweden)

    Ion IVAN

    2013-01-01

    Full Text Available This paper presents distributed informatics applications and characteristics of their development cycle. It defines the concept of verification and there are identified the differences from software testing. Particularities of the software testing and software verification processes are described. The verification steps and necessary conditions are presented and there are established influence factors of quality verification. Software optimality verification is analyzed and some metrics are defined for the verification process.

  20. EPRI PWR primary water chemistry guidelines revision

    International Nuclear Information System (INIS)

    McElrath, Joel; Fruzzetti, Keith

    2014-01-01

    EPRI periodically updates the PWR Primary Water Chemistry Guidelines as new information becomes available and as required by NEI 97-06 (Steam Generator Program Guidelines) and NEI 03-08 (Guideline for the Management of Materials Issues). The last revision of the PWR water chemistry guidelines identified an optimum primary water chemistry program based on then-current understanding of research and field information. This new revision provides further details with regard to primary water stress corrosion cracking (PWSCC), fuel integrity, and shutdown dose rates. A committee of industry experts, including utility specialists, nuclear steam supply system (NSSS) and fuel vendor representatives, Institute of Nuclear Power Operations (INPO) representatives, consultants, and EPRI staff collaborated in reviewing the available data on primary water chemistry, reactor water coolant system materials issues, fuel integrity and performance issues, and radiation dose rate issues. From the data, the committee updated the water chemistry guidelines that all PWR nuclear plants should adopt. The committee revised guidance with regard to optimization to reflect industry experience gained since the publication of Revision 6. Among the changes, the technical information regarding the impact of zinc injection on PWSCC initiation and dose rate reduction has been updated to reflect the current level of knowledge within the industry. Similarly, industry experience with elevated lithium concentrations with regard to fuel performance and radiation dose rates has been updated to reflect data collected to date. Recognizing that each nuclear plant owner has a unique set of design, operating, and corporate concerns, the guidelines committee has retained a method for plant-specific optimization. Revision 7 of the Pressurized Water Reactor Primary Water Chemistry Guidelines provides guidance for PWR primary systems of all manufacture and design. The guidelines continue to emphasize plant

  1. What Is the Rerevision Rate After Revising a Hip Resurfacing Arthroplasty? Analysis From the AOANJRR.

    Science.gov (United States)

    Wong, James Min-Leong; Liu, Yen-Liang; Graves, Stephen; de Steiger, Richard

    2015-11-01

    More than 15,000 primary hip resurfacing arthroplasties have been recorded by the Australian Orthopaedic Association National Joint Replacement Registry (AOANJRR) with 884 primary procedures requiring revision for reasons other than infection, a cumulative percent revision rate at 12 years of 11%. However, few studies have reported the survivorship of these revision procedures. (1) What is the cumulative percent rerevision rate for revision procedures for failed hip resurfacings? (2) Is there a difference in rerevision rate among different types of revision or bearing surfaces? The AOANJRR collects data on all primary and revision hip joint arthroplasties performed in Australia and after verification against health department data, checking of unmatched procedures, and subsequent retrieval of unreported procedures is able to obtain an almost complete data set relating to hip arthroplasty in Australia. Revision procedures are linked to the known primary hip arthroplasty. There were 15,360 primary resurfacing hip arthroplasties recorded of which 884 had undergone revision and this was the cohort available to study. The types of revisions were acetabular only, femoral only, or revision of both acetabular and femoral components. With the exception of the acetabular-only revisions, all revisions converted hip resurfacing arthroplasties to conventional (stemmed) total hip arthroplasties (THAs). All initial revisions for infection were excluded. The survivorship of the different types of revisions and that of the different bearing surfaces used were estimated using the Kaplan-Meier method and compared using Cox proportional hazard models. Cumulative percent revision was calculated by determining the complement of the Kaplan-Meier survivorship function at that time multiplied by 100. Of the 884 revisions recorded, 102 underwent further revision, a cumulative percent rerevision at 10 years of 26% (95% confidence interval, 19.6-33.5). There was no difference in the rate of

  2. Preliminary Research on the Verification Task of North Korea's Plutonium Declaration

    International Nuclear Information System (INIS)

    Kim, Hyun Chul; Park, Il Jin

    2009-01-01

    The denuclearization of North Korea seems challenging. North Korea has recognized itself as a nuclear weapon state by carrying out two nuclear tests while many other nations including South Korea have opposed North Korea's nuclear proliferation. As a result of longstanding negotiations, North Korea provided nearly 19,000 pages of operation history of three Yongbyon nuclear facilities on May 8, 2008 and a 60-page declaration of its nuclear activities and programs on June 26, 2008. However, one should notice that declaration documents are by themselves meaningless without their verification. To completely dismantle North Korea's nuclear programs, the verification task based on its declaration documents should be performed very thoroughly, considering the possibility of the presence of the undeclared nuclear materials and facilities. The verification task of North Korea's nuclear declaration consists of many broad themes to deal with, such as the review of declaration documents, the interview with facility operators, the sampling in the field, the laboratory analysis of the sample, data interpretation, and so on. One of the important themes is to verify North Korea's declared plutonium stockpile by comparing the declaration documents with measurement data which can be obtained from the sampling in the field and laboratory analysis. To prepare for the possible future verification of the declared plutonium stockpile, it is meaningful to give a thought on what data can be compared and what samples need to be taken and analyzed. In this study, we focus on the data to be compared and samples to be taken and analyzed for the plutonium accounting, as a preliminary research. To give a quantitative example, the nuclear material of the most recent North Korea's spent fuel rods discharged from the 5 MWe reactor is analyzed. On June 13, 2009, North Korea declared that more than one-third of the spent fuel rods had been reprocessed

  3. EURATOM safeguards efforts in the development of spent fuel verification methods by non-destructive assay

    Energy Technology Data Exchange (ETDEWEB)

    Matloch, L.; Vaccaro, S.; Couland, M.; De Baere, P.; Schwalbach, P. [Euratom, Communaute europeenne de l' energie atomique - CEEA (European Commission (EC))

    2015-07-01

    The back end of the nuclear fuel cycle continues to develop. The European Commission, particularly the Nuclear Safeguards Directorate of the Directorate General for Energy, implements Euratom safeguards and needs to adapt to this situation. The verification methods for spent nuclear fuel, which EURATOM inspectors can use, require continuous improvement. Whereas the Euratom on-site laboratories provide accurate verification results for fuel undergoing reprocessing, the situation is different for spent fuel which is destined for final storage. In particular, new needs arise from the increasing number of cask loadings for interim dry storage and the advanced plans for the construction of encapsulation plants and geological repositories. Various scenarios present verification challenges. In this context, EURATOM Safeguards, often in cooperation with other stakeholders, is committed to further improvement of NDA methods for spent fuel verification. In this effort EURATOM plays various roles, ranging from definition of inspection needs to direct participation in development of measurement systems, including support of research in the framework of international agreements and via the EC Support Program to the IAEA. This paper presents recent progress in selected NDA methods. These methods have been conceived to satisfy different spent fuel verification needs, ranging from attribute testing to pin-level partial defect verification. (authors)

  4. Revision of Krsko NPP Quality Assurance Plan

    International Nuclear Information System (INIS)

    Biscan, R.; Fifnja, I.; Kavsek, D.

    2012-01-01

    International standards from nuclear power plant operation area are being frequently upgraded and revised in accordance with the continuous improvement philosophy. This philosophy applies also to the area of Quality Assurance, which has also undergone significant improvement since the early 1950s. Besides just nuclear industry, there are also other international quality standards that are being continuously developed and revised, bringing needs for upgrades also in the nuclear application. Since the beginning of Krsko NPP construction, the overall Quality Assurance program and its applicable procedures were in place to assure that all planned and systematic actions necessary to provide adequate confidence that an item or service will satisfy given requirements to quality, are in place. The overall requirements for quality as one of the major objectives for Krsko NPP operation are also set forth in the Updated Safety Analyses Report, the document that serves as a base for operating license. During more than 30 years of Krsko NPP operation, the quality requirements and related documents were revised and upgraded in several attempts. The latest revision 6 of QD-1, Quality Assurance Plan was issued during the year 2011. The bases for the revision were: Changes of the Slovenian regulatory requirements (ZVISJV, JV5, JV9?), Changes of Krsko NPP licensing documents (USAR section 13?), SNSA inspection requirements, Changes of international standards (IAEA, ISO?), Conclusions of first PSR, Implementation of ISO standards in Krsko NPP (ISO14001, ISO17025), Changes of plant procedures, etc. One of the most obvious changes was the enlargement of the QA Plan scope to cover interdisciplinary areas defined in the plant management program MD-1, such as Safety culture, Self-assessment, Human performance, Industrial Safety etc. The attachment of the QA Plan defining relationships between certain standards was also updated to provide matrix for better correlation of requirements of

  5. Image intelligence online consulting: A flexible and remote access to strategic information applied to verification of declaration

    International Nuclear Information System (INIS)

    Chassy, A.F. de; Denizot, L.

    2001-01-01

    Commercial satellite imagery is giving International Institutions specialized Information Departments access to a great source of valuable intelligence. High resolution and multiple sensors have also led to a growing complexity of interpretation that calls for a greater need of consulting, verification and training in the field in order to make it eligible as an operational source of verification. Responding to this need, Fleximage is extending its Image intelligence (IMINT) training program to include a fully operational and flexible online consulting and training program. Image Intelligence (IMINT) Online Program, a new approach to acquiring IMINT expertise, supported by Internet technologies, and managed by a professional team of experts and technical staff. Fleximage has developed a virtual learning environment on the Internet for acquiring IMINT expertise. Called the IMINT Online Program, this dynamic learning environment provides complete flexibility and personalization of the process for acquiring expertise. The IMINT online program includes two services: Online Consulting and Online Training. The Online Consulting service is designed for the technical staff of an organization who are already operational in the field of image intelligence. Online Consulting enables these staff members to acquire pertinent expertise online that can be directly applied to their professional activity, such as IAEA verification tasks. The Online Training service is designed for the technical staff of an organization who are relatively new to the field of image intelligence. These staff members need to build expertise within a formal training program. Online Training is a flexible and structured program for acquiring IMINT expertise online

  6. Verification of the MOTIF code version 3.0

    International Nuclear Information System (INIS)

    Chan, T.; Guvanasen, V.; Nakka, B.W.; Reid, J.A.K.; Scheier, N.W.; Stanchell, F.W.

    1996-12-01

    As part of the Canadian Nuclear Fuel Waste Management Program (CNFWMP), AECL has developed a three-dimensional finite-element code, MOTIF (Model Of Transport In Fractured/ porous media), for detailed modelling of groundwater flow, heat transport and solute transport in a fractured rock mass. The code solves the transient and steady-state equations of groundwater flow, solute (including one-species radionuclide) transport, and heat transport in variably saturated fractured/porous media. The initial development was completed in 1985 (Guvanasen 1985) and version 3.0 was completed in 1986. This version is documented in detail in Guvanasen and Chan (in preparation). This report describes a series of fourteen verification cases which has been used to test the numerical solution techniques and coding of MOTIF, as well as demonstrate some of the MOTIF analysis capabilities. For each case the MOTIF solution has been compared with a corresponding analytical or independently developed alternate numerical solution. Several of the verification cases were included in Level 1 of the International Hydrologic Code Intercomparison Project (HYDROCOIN). The MOTIF results for these cases were also described in the HYDROCOIN Secretariat's compilation and comparison of results submitted by the various project teams (Swedish Nuclear Power Inspectorate 1988). It is evident from the graphical comparisons presented that the MOTIF solutions for the fourteen verification cases are generally in excellent agreement with known analytical or numerical solutions obtained from independent sources. This series of verification studies has established the ability of the MOTIF finite-element code to accurately model the groundwater flow and solute and heat transport phenomena for which it is intended. (author). 20 refs., 14 tabs., 32 figs

  7. Java bytecode verification via static single assignment form

    DEFF Research Database (Denmark)

    Gal, Andreas; Probst, Christian W.; Franz, Michael

    2008-01-01

    Java Virtual Machines (JVMs) traditionally perform bytecode verification by way of an iterative data-flow analysis. Bytecode verification is necessary to ensure type safety because temporary variables in the JVM are not statically typed. We present an alternative verification mechanism that trans......Java Virtual Machines (JVMs) traditionally perform bytecode verification by way of an iterative data-flow analysis. Bytecode verification is necessary to ensure type safety because temporary variables in the JVM are not statically typed. We present an alternative verification mechanism...

  8. The art of multiprocessor programming

    CERN Document Server

    Herlihy, Maurice

    2012-01-01

    Revised and updated with improvements conceived in parallel programming courses, The Art of Multiprocessor Programming is an authoritative guide to multicore programming. It introduces a higher level set of software development skills than that needed for efficient single-core programming. This book provides comprehensive coverage of the new principles, algorithms, and tools necessary for effective multiprocessor programming. Students and professionals alike will benefit from thorough coverage of key multiprocessor programming issues. This revised edition incorporates much-demanded updates t

  9. SU-E-T-49: A Multi-Institutional Study of Independent Dose Verification for IMRT

    International Nuclear Information System (INIS)

    Baba, H; Tachibana, H; Kamima, T; Takahashi, R; Kawai, D; Sugawara, Y; Yamamoto, T; Sato, A; Yamashita, M

    2015-01-01

    Purpose: AAPM TG114 does not cover the independent verification for IMRT. We conducted a study of independent dose verification for IMRT in seven institutes to show the feasibility. Methods: 384 IMRT plans in the sites of prostate and head and neck (HN) were collected from the institutes, where the planning was performed using Eclipse and Pinnacle3 with the two techniques of step and shoot (S&S) and sliding window (SW). All of the institutes used a same independent dose verification software program (Simple MU Analysis: SMU, Triangle Product, Ishikawa, JP), which is Clarkson-based and CT images were used to compute radiological path length. An ion-chamber measurement in a water-equivalent slab phantom was performed to compare the doses computed using the TPS and an independent dose verification program. Additionally, the agreement in dose computed in patient CT images between using the TPS and using the SMU was assessed. The dose of the composite beams in the plan was evaluated. Results: The agreement between the measurement and the SMU were −2.3±1.9 % and −5.6±3.6 % for prostate and HN sites, respectively. The agreement between the TPSs and the SMU were −2.1±1.9 % and −3.0±3.7 for prostate and HN sites, respectively. There was a negative systematic difference with similar standard deviation and the difference was larger in the HN site. The S&S technique showed a statistically significant difference between the SW. Because the Clarkson-based method in the independent program underestimated (cannot consider) the dose under the MLC. Conclusion: The accuracy would be improved when the Clarkson-based algorithm should be modified for IMRT and the tolerance level would be within 5%

  10. Development of a Torque Sensor-Based Test Bed for Attitude Control System Verification and Validation

    Science.gov (United States)

    2017-12-30

    AFRL-RV-PS- AFRL-RV-PS- TR-2018-0008 TR-2018-0008 DEVELOPMENT OF A TORQUE SENSOR- BASED TEST BED FOR ATTITUDE CONTROL SYSTEM VERIFICATION AND...Sensor-Based Test Bed for Attitude Control System Verification & Validation 5a. CONTRACT NUMBER FA9453-15-1-0315 5b. GRANT NUMBER 5c. PROGRAM ELEMENT...NUMBER 62601F 6. AUTHOR(S) Norman Fitz-Coy 5d. PROJECT NUMBER 4846 5e. TASK NUMBER PPM00015968 5f. WORK UNIT NUMBER EF125135 7. PERFORMING

  11. ENVIRONMENTAL TECHNOLOGY VERIFICATION--TEST REPORT OF MOBILE SOURCE EMISSION CONTROL DEVICES, FLINT HILLS RESOURCES, LP, CCD15010 DIESEL FUEL FORMULATION WITH HITEC4121 ADDITIVE

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) has created the Environmental Technology Verification (ETV) Program to facilitate the deployment of innovative or improved environmental technologies through performance verification and dissemination of information. ETV seeks to ach...

  12. Formal verification of algorithms for critical systems

    Science.gov (United States)

    Rushby, John M.; Von Henke, Friedrich

    1993-01-01

    We describe our experience with formal, machine-checked verification of algorithms for critical applications, concentrating on a Byzantine fault-tolerant algorithm for synchronizing the clocks in the replicated computers of a digital flight control system. First, we explain the problems encountered in unsynchronized systems and the necessity, and criticality, of fault-tolerant synchronization. We give an overview of one such algorithm, and of the arguments for its correctness. Next, we describe a verification of the algorithm that we performed using our EHDM system for formal specification and verification. We indicate the errors we found in the published analysis of the algorithm, and other benefits that we derived from the verification. Based on our experience, we derive some key requirements for a formal specification and verification system adequate to the task of verifying algorithms of the type considered. Finally, we summarize our conclusions regarding the benefits of formal verification in this domain, and the capabilities required of verification systems in order to realize those benefits.

  13. Challenges for effective WMD verification

    International Nuclear Information System (INIS)

    Andemicael, B.

    2006-01-01

    Effective verification is crucial to the fulfillment of the objectives of any disarmament treaty, not least as regards the proliferation of weapons of mass destruction (WMD). The effectiveness of the verification package depends on a number of factors, some inherent in the agreed structure and others related to the type of responses demanded by emerging challenges. The verification systems of three global agencies-the IAEA, the Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO, currently the Preparatory Commission), and the Organization for the Prohibition of Chemical Weapons (OPCW)-share similarities in their broad objectives of confidence-building and deterrence by assuring members that rigorous verification would deter or otherwise detect non-compliance. Yet they are up against various constraints and other issues, both internal and external to the treaty regime. These constraints pose major challenges to the effectiveness and reliability of the verification operations. In the nuclear field, the IAEA safeguards process was the first to evolve incrementally from modest Statute beginnings to a robust verification system under the global Treaty on the Non-Proliferation of Nuclear Weapons (NPT). The nuclear non-proliferation regime is now being supplemented by a technology-intensive verification system of the nuclear test-ban treaty (CTBT), a product of over three decades of negotiation. However, there still remain fundamental gaps and loopholes in the regime as a whole, which tend to diminish the combined effectiveness of the IAEA and the CTBT verification capabilities. He three major problems are (a) the lack of universality of membership, essentially because of the absence of three nuclear weapon-capable States-India, Pakistan and Israel-from both the NPT and the CTBT, (b) the changes in US disarmament policy, especially in the nuclear field, and (c) the failure of the Conference on Disarmament to conclude a fissile material cut-off treaty. The world is

  14. Image intelligence online consulting: A flexible and remote access to strategic information applied to verification of declaration

    International Nuclear Information System (INIS)

    Chassy, A.F. de; Denizot, L.

    2001-01-01

    Commercial satellite imagery is giving International Institutions specialized Information Departments access to a great source of valuable intelligence. High resolution and multiple sensors have also led to a growing complexity of interpretation that calls for a greater need of consulting, verification and training in the field in order to make it eligible as an operational source of verification. Responding to this need, Fleximage is extending its Image Intelligence (IMINT) training program to include a fully operational and flexible online consulting and training program. Image Intelligence (IMINT) Online Program, a new approach to acquiring IMINT expertise, supported by Internet technologies, and managed by a professional team of experts and technical staff. Fleximage has developed a virtual learning environment on the Internet for acquiring IMINT expertise. Called the IMINT Online Program, this dynamic learning environment provides complete flexibility and personalization of the process for acquiring expertise. The IMINT online program includes two services: Online Consulting and Online Training. The Online Consulting service is designed for the technical staff of an organization who are already operational in the field of image intelligence. Online Consulting enables these staff members to acquire pertinent expertise online that can be directly applied to their professional activity, such as IAEA verification tasks. The IMINT virtual Consulting and Training services indicated above are made possible thanks to the latest in Internet-based technologies including: multimedia CD-ROM, Internet technologies, rich media content (Audio, Video and Flash), application sharing, platform Maintenance Tools, secured connections and authentication, knowledge database technologies. IMINT Online Program operates owing to: specialized experts in fields relating to IMINT. These experts carry out the tasks of consultants, coaches, occasional speakers, and course content designers

  15. Developing a NASA strategy for the verification of large space telescope observatories

    Science.gov (United States)

    Crooke, Julie A.; Gunderson, Johanna A.; Hagopian, John G.; Levine, Marie

    2006-06-01

    In July 2005, the Office of Program Analysis and Evaluation (PA&E) at NASA Headquarters was directed to develop a strategy for verification of the performance of large space telescope observatories, which occurs predominantly in a thermal vacuum test facility. A mission model of the expected astronomical observatory missions over the next 20 years was identified along with performance, facility and resource requirements. Ground testing versus alternatives was analyzed to determine the pros, cons and break points in the verification process. Existing facilities and their capabilities were examined across NASA, industry and other government agencies as well as the future demand for these facilities across NASA's Mission Directorates. Options were developed to meet the full suite of mission verification requirements, and performance, cost, risk and other analyses were performed. Findings and recommendations from the study were presented to the NASA Administrator and the NASA Strategic Management Council (SMC) in February 2006. This paper details the analysis, results, and findings from this study.

  16. Concepts of Model Verification and Validation

    International Nuclear Information System (INIS)

    Thacker, B.H.; Doebling, S.W.; Hemez, F.M.; Anderson, M.C.; Pepin, J.E.; Rodriguez, E.A.

    2004-01-01

    Model verification and validation (VandV) is an enabling methodology for the development of computational models that can be used to make engineering predictions with quantified confidence. Model VandV procedures are needed by government and industry to reduce the time, cost, and risk associated with full-scale testing of products, materials, and weapon systems. Quantifying the confidence and predictive accuracy of model calculations provides the decision-maker with the information necessary for making high-consequence decisions. The development of guidelines and procedures for conducting a model VandV program are currently being defined by a broad spectrum of researchers. This report reviews the concepts involved in such a program. Model VandV is a current topic of great interest to both government and industry. In response to a ban on the production of new strategic weapons and nuclear testing, the Department of Energy (DOE) initiated the Science-Based Stockpile Stewardship Program (SSP). An objective of the SSP is to maintain a high level of confidence in the safety, reliability, and performance of the existing nuclear weapons stockpile in the absence of nuclear testing. This objective has challenged the national laboratories to develop high-confidence tools and methods that can be used to provide credible models needed for stockpile certification via numerical simulation. There has been a significant increase in activity recently to define VandV methods and procedures. The U.S. Department of Defense (DoD) Modeling and Simulation Office (DMSO) is working to develop fundamental concepts and terminology for VandV applied to high-level systems such as ballistic missile defense and battle management simulations. The American Society of Mechanical Engineers (ASME) has recently formed a Standards Committee for the development of VandV procedures for computational solid mechanics models. The Defense Nuclear Facilities Safety Board (DNFSB) has been a proponent of model

  17. A Syntactic-Semantic Approach to Incremental Verification

    OpenAIRE

    Bianculli, Domenico; Filieri, Antonio; Ghezzi, Carlo; Mandrioli, Dino

    2013-01-01

    Software verification of evolving systems is challenging mainstream methodologies and tools. Formal verification techniques often conflict with the time constraints imposed by change management practices for evolving systems. Since changes in these systems are often local to restricted parts, an incremental verification approach could be beneficial. This paper introduces SiDECAR, a general framework for the definition of verification procedures, which are made incremental by the framework...

  18. A Scala DSL for RETE-Based Runtime Verification

    Science.gov (United States)

    Havelund, Klaus

    2013-01-01

    Runtime verification (RV) consists in part of checking execution traces against formalized specifications. Several systems have emerged, most of which support specification notations based on state machines, regular expressions, temporal logic, or grammars. The field of Artificial Intelligence (AI) has for an even longer period of time studied rule-based production systems, which at a closer look appear to be relevant for RV, although seemingly focused on slightly different application domains, such as for example business processes and expert systems. The core algorithm in many of these systems is the Rete algorithm. We have implemented a Rete-based runtime verification system, named LogFire (originally intended for offline log analysis but also applicable to online analysis), as an internal DSL in the Scala programming language, using Scala's support for defining DSLs. This combination appears attractive from a practical point of view. Our contribution is in part conceptual in arguing that such rule-based frameworks originating from AI may be suited for RV.

  19. Verification and validation benchmarks.

    Energy Technology Data Exchange (ETDEWEB)

    Oberkampf, William Louis; Trucano, Timothy Guy

    2007-02-01

    Verification and validation (V&V) are the primary means to assess the accuracy and reliability of computational simulations. V&V methods and procedures have fundamentally improved the credibility of simulations in several high-consequence fields, such as nuclear reactor safety, underground nuclear waste storage, and nuclear weapon safety. Although the terminology is not uniform across engineering disciplines, code verification deals with assessing the reliability of the software coding, and solution verification deals with assessing the numerical accuracy of the solution to a computational model. Validation addresses the physics modeling accuracy of a computational simulation by comparing the computational results with experimental data. Code verification benchmarks and validation benchmarks have been constructed for a number of years in every field of computational simulation. However, no comprehensive guidelines have been proposed for the construction and use of V&V benchmarks. For example, the field of nuclear reactor safety has not focused on code verification benchmarks, but it has placed great emphasis on developing validation benchmarks. Many of these validation benchmarks are closely related to the operations of actual reactors at near-safety-critical conditions, as opposed to being more fundamental-physics benchmarks. This paper presents recommendations for the effective design and use of code verification benchmarks based on manufactured solutions, classical analytical solutions, and highly accurate numerical solutions. In addition, this paper presents recommendations for the design and use of validation benchmarks, highlighting the careful design of building-block experiments, the estimation of experimental measurement uncertainty for both inputs and outputs to the code, validation metrics, and the role of model calibration in validation. It is argued that the understanding of predictive capability of a computational model is built on the level of

  20. Verification of Ceramic Structures

    Science.gov (United States)

    Behar-Lafenetre, Stephanie; Cornillon, Laurence; Rancurel, Michael; De Graaf, Dennis; Hartmann, Peter; Coe, Graham; Laine, Benoit

    2012-07-01

    In the framework of the “Mechanical Design and Verification Methodologies for Ceramic Structures” contract [1] awarded by ESA, Thales Alenia Space has investigated literature and practices in affiliated industries to propose a methodological guideline for verification of ceramic spacecraft and instrument structures. It has been written in order to be applicable to most types of ceramic or glass-ceramic materials - typically Cesic®, HBCesic®, Silicon Nitride, Silicon Carbide and ZERODUR®. The proposed guideline describes the activities to be performed at material level in order to cover all the specific aspects of ceramics (Weibull distribution, brittle behaviour, sub-critical crack growth). Elementary tests and their post-processing methods are described, and recommendations for optimization of the test plan are given in order to have a consistent database. The application of this method is shown on an example in a dedicated article [7]. Then the verification activities to be performed at system level are described. This includes classical verification activities based on relevant standard (ECSS Verification [4]), plus specific analytical, testing and inspection features. The analysis methodology takes into account the specific behaviour of ceramic materials, especially the statistical distribution of failures (Weibull) and the method to transfer it from elementary data to a full-scale structure. The demonstration of the efficiency of this method is described in a dedicated article [8]. The verification is completed by classical full-scale testing activities. Indications about proof testing, case of use and implementation are given and specific inspection and protection measures are described. These additional activities are necessary to ensure the required reliability. The aim of the guideline is to describe how to reach the same reliability level as for structures made of more classical materials (metals, composites).

  1. The Revised WIPP Passive Institutional Controls Program - A Conceptual Plan - 13145

    International Nuclear Information System (INIS)

    Patterson, Russ; Klein, Thomas; Van Luik, Abraham

    2013-01-01

    with the international guidance being developed. International guidance currently under development may suggest that the inter-generational equity principle strives to warn the future, however, in doing so not to unduly burden present generations. Building markers and monuments that are out of proportion to the risk being presented to the future is not in keeping with generational equity. With this in mind the DOE/CBFO is developing conceptual plans for re-evaluating and revising the current WIPP PIC's program. These conceptual plans will suggest scientific and technical work that must be completed to develop a 'new' PICs program that takes the best ideas of the present plan, blended with new ideas from the RK and M project, and proposed alternative permanent markers designs and materials in consideration. (authors)

  2. A strategy for automatically generating programs in the lucid programming language

    Science.gov (United States)

    Johnson, Sally C.

    1987-01-01

    A strategy for automatically generating and verifying simple computer programs is described. The programs are specified by a precondition and a postcondition in predicate calculus. The programs generated are in the Lucid programming language, a high-level, data-flow language known for its attractive mathematical properties and ease of program verification. The Lucid programming is described, and the automatic program generation strategy is described and applied to several example problems.

  3. Is flow verification necessary

    International Nuclear Information System (INIS)

    Beetle, T.M.

    1986-01-01

    Safeguards test statistics are used in an attempt to detect diversion of special nuclear material. Under assumptions concerning possible manipulation (falsification) of safeguards accounting data, the effects on the statistics due to diversion and data manipulation are described algebraically. A comprehensive set of statistics that is capable of detecting any diversion of material is defined in terms of the algebraic properties of the effects. When the assumptions exclude collusion between persons in two material balance areas, then three sets of accounting statistics are shown to be comprehensive. Two of the sets contain widely known accountancy statistics. One of them does not require physical flow verification - comparisons of operator and inspector data for receipts and shipments. The third set contains a single statistic which does not require physical flow verification. In addition to not requiring technically difficult and expensive flow verification, this single statistic has several advantages over other comprehensive sets of statistics. This algebraic approach as an alternative to flow verification for safeguards accountancy is discussed in this paper

  4. Revising Translations

    DEFF Research Database (Denmark)

    Rasmussen, Kirsten Wølch; Schjoldager, Anne

    2011-01-01

    The paper explains the theoretical background and findings of an empirical study of revision policies, using Denmark as a case in point. After an overview of important definitions, types and parameters, the paper explains the methods and data gathered from a questionnaire survey and an interview...... survey. Results clearly show that most translation companies regard both unilingual and comparative revisions as essential components of professional quality assurance. Data indicate that revision is rarely fully comparative, as the preferred procedure seems to be a unilingual revision followed by a more...... or less comparative rereading. Though questionnaire data seem to indicate that translation companies use linguistic correctness and presentation as the only revision parameters, interview data reveal that textual and communicative aspects are also considered. Generally speaking, revision is not carried...

  5. 78 FR 59982 - Revisions to Radiation Protection

    Science.gov (United States)

    2013-09-30

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0268] Revisions to Radiation Protection AGENCY: Nuclear..., ``Radiation Sources,'' Section 12.3 -12.4, ``Radiation Protection Design Features,'' and Section 12.5, ``Operational Radiation Protection Program.'' DATES: The effective date of this Standard Review Plan update is...

  6. Procedure generation and verification

    International Nuclear Information System (INIS)

    Sheely, W.F.

    1986-01-01

    The Department of Energy has used Artificial Intelligence of ''AI'' concepts to develop two powerful new computer-based techniques to enhance safety in nuclear applications. The Procedure Generation System, and the Procedure Verification System, can be adapted to other commercial applications, such as a manufacturing plant. The Procedure Generation System can create a procedure to deal with the off-normal condition. The operator can then take correct actions on the system in minimal time. The Verification System evaluates the logic of the Procedure Generator's conclusions. This evaluation uses logic techniques totally independent of the Procedure Generator. The rapid, accurate generation and verification of corrective procedures can greatly reduce the human error, possible in a complex (stressful/high stress) situation

  7. A Scalable Approach for Hardware Semiformal Verification

    OpenAIRE

    Grimm, Tomas; Lettnin, Djones; Hübner, Michael

    2018-01-01

    The current verification flow of complex systems uses different engines synergistically: virtual prototyping, formal verification, simulation, emulation and FPGA prototyping. However, none is able to verify a complete architecture. Furthermore, hybrid approaches aiming at complete verification use techniques that lower the overall complexity by increasing the abstraction level. This work focuses on the verification of complex systems at the RT level to handle the hardware peculiarities. Our r...

  8. Evaluation of verification methods for input-accountability measurements

    International Nuclear Information System (INIS)

    Maeck, W.J.

    1980-01-01

    As part of TASTEX related programs two independent methods have been evaluated for the purpose of providing verification of the amount of Pu charged to the head-end of a nuclear fuel processing plant. The first is the Pu/U (gravimetric method), TASTEX Task-L, and the second is the Tracer Method, designated Task-M. Summaries of the basic technology, results of various studies under actual plant conditions, future requirements, are given for each of the Tasks

  9. Survey on Offline Finger Print Verification System

    NARCIS (Netherlands)

    Suman, R.; Kaur, R.

    2012-01-01

    The fingerprint verification, means where "verification" implies a user matching a fingerprint against a single fingerprint associated with the identity that the user claims. Biometrics can be classified into two types Behavioral (signature verification, keystroke dynamics, etc.) And Physiological

  10. Verification of the cross-section and depletion chain processing module of DRAGON 3.06

    International Nuclear Information System (INIS)

    Chambon, R.; Marleau, G.; Zkiek, A.

    2008-01-01

    In this paper we present a verification of the module of the lattice code DRAGON 3.06 used for processing microscopic cross-section libraries, including their associated depletion chain. This verification is performed by reprogramming the capabilities of DRAGON in another language (MATLAB) and testing them on different problems typical of the CANDU reactor. The verification procedure consists in first programming MATLAB m-files to read the different cross section libraries in ASCII format and to compute the reference cross-sections and depletion chains. The same information is also recovered from the output files of DRAGON (using different m-files) and the resulting cross sections and depletion chain are compared with the reference library, the differences being evaluated and tabulated. The results show that the cross-section calculations and the depletion chains are correctly processed in version 3.06 of DRAGON. (author)

  11. Graphic Display Development Program. Volume II, Revision 0. Appendices

    International Nuclear Information System (INIS)

    1984-12-01

    The objective of this project is to demonstrate the feasibility and utility of developing a set of graphic displays to support symptom-based emergency operating procedures (EOPs). Development of generic graphic displays is based on Revision 3 of the symptomatic Emergency Procedure Guidelines (EPGs) prepared by the BWR Owners' Group (BWROG), and development of plant-specific graphic displays is based on a set of emergency operating procedures developed from these EPGs

  12. A Verification Method of Inter-Task Cooperation in Embedded Real-time Systems and its Evaluation

    Science.gov (United States)

    Yoshida, Toshio

    In software development process of embedded real-time systems, the design of the task cooperation process is very important. The cooperating process of such tasks is specified by task cooperation patterns. Adoption of unsuitable task cooperation patterns has fatal influence on system performance, quality, and extendibility. In order to prevent repetitive work caused by the shortage of task cooperation performance, it is necessary to verify task cooperation patterns in an early software development stage. However, it is very difficult to verify task cooperation patterns in an early software developing stage where task program codes are not completed yet. Therefore, we propose a verification method using task skeleton program codes and a real-time kernel that has a function of recording all events during software execution such as system calls issued by task program codes, external interrupts, and timer interrupt. In order to evaluate the proposed verification method, we applied it to the software development process of a mechatronics control system.

  13. Ostomy Home Skills Program

    Medline Plus

    Full Text Available ... About ACS NSQIP Join ACS NSQIP Now Collaboratives Hospital Compare Quality and Safety Conference Participant Use Data ... Life Support Verification, Review, and Consultation Program for Hospitals Trauma Systems Consultation Program Trauma Education Achieving Zero ...

  14. Revision total hip arthoplasty: factors associated with re-revision surgery.

    Science.gov (United States)

    Khatod, Monti; Cafri, Guy; Inacio, Maria C S; Schepps, Alan L; Paxton, Elizabeth W; Bini, Stefano A

    2015-03-04

    The survivorship of implants after revision total hip arthroplasty and risk factors associated with re-revision are not well defined. We evaluated the re-revision rate with use of the institutional total joint replacement registry. The purpose of this study was to determine patient, implant, and surgeon factors associated with re-revision total hip arthroplasty. A retrospective cohort study was conducted. The total joint replacement registry was used to identify patients who had undergone revision total hip arthroplasty for aseptic reasons from April 1, 2001, to December 31, 2010. The end point of interest was re-revision total hip arthroplasty. Risk factors evaluated for re-revision total hip arthroplasty included: patient risk factors (age, sex, body mass index, race, and general health status), implant risk factors (fixation type, bearing surface, femoral head size, and component replacement), and surgeon risk factors (volume and experience). A multivariable Cox proportional hazards model was used. Six hundred and twenty-nine revision total hip arthroplasties with sixty-three (10%) re-revisions were evaluated. The mean cohort age (and standard deviation) was 57.0 ± 12.4 years, the mean body mass index (and standard deviation) was 29.5 ± 6.1 kg/m(2), and most of the patients were women (64.5%) and white (81.9%) and had an American Society of Anesthesiologists score of associated with the risk of re-revision. For every ten-year increase in patient age, the hazard ratio for re-revision decreases by a factor of 0.72 (95% confidence interval, 0.58 to 0.90). For every five revision surgical procedures performed by a surgeon, the risk of revision decreases by a factor of 0.93 (95% confidence interval, 0.86 to 0.99). At the time of revision, a new or retained cemented femoral implant or all-cemented hip implant increases the risk of revision by a factor of 3.19 (95% confidence interval, 1.22 to 8.38) relative to a retained or new uncemented hip implant. A ceramic on a

  15. Development of independent MU/treatment time verification algorithm for non-IMRT treatment planning: A clinical experience

    Science.gov (United States)

    Tatli, Hamza; Yucel, Derya; Yilmaz, Sercan; Fayda, Merdan

    2018-02-01

    The aim of this study is to develop an algorithm for independent MU/treatment time (TT) verification for non-IMRT treatment plans, as a part of QA program to ensure treatment delivery accuracy. Two radiotherapy delivery units and their treatment planning systems (TPS) were commissioned in Liv Hospital Radiation Medicine Center, Tbilisi, Georgia. Beam data were collected according to vendors' collection guidelines, and AAPM reports recommendations, and processed by Microsoft Excel during in-house algorithm development. The algorithm is designed and optimized for calculating SSD and SAD treatment plans, based on AAPM TG114 dose calculation recommendations, coded and embedded in MS Excel spreadsheet, as a preliminary verification algorithm (VA). Treatment verification plans were created by TPSs based on IAEA TRS 430 recommendations, also calculated by VA, and point measurements were collected by solid water phantom, and compared. Study showed that, in-house VA can be used for non-IMRT plans MU/TT verifications.

  16. SU-E-T-50: A Multi-Institutional Study of Independent Dose Verification Software Program for Lung SBRT

    International Nuclear Information System (INIS)

    Kawai, D; Takahashi, R; Kamima, T; Baba, H; Yamamoto, T; Kubo, Y; Ishibashi, S; Higuchi, Y; Takahashi, H; Tachibana, H

    2015-01-01

    Purpose: The accuracy of dose distribution depends on treatment planning system especially in heterogeneity-region. The tolerance level (TL) of the secondary check using the independent dose verification may be variable in lung SBRT plans. We conducted a multi-institutional study to evaluate the tolerance level of lung SBRT plans shown in the AAPM TG114. Methods: Five institutes in Japan participated in this study. All of the institutes used a same independent dose verification software program (Simple MU Analysis: SMU, Triangle Product, Ishikawa, JP), which is Clarkson-based and CT images were used to compute radiological path length. Analytical Anisotropic Algorithm (AAA), Pencil Beam Convolution with modified Batho-method (PBC-B) and Adaptive Convolve (AC) were used for lung SBRT planning. A measurement using an ion-chamber was performed in a heterogeneous phantom to compare doses from the three different algorithms and the SMU to the measured dose. In addition to it, a retrospective analysis using clinical lung SBRT plans (547 beams from 77 patients) was conducted to evaluate the confidence limit (CL, Average±2SD) in dose between the three algorithms and the SMU. Results: Compared to the measurement, the AAA showed the larger systematic dose error of 2.9±3.2% than PBC-B and AC. The Clarkson-based SMU showed larger error of 5.8±3.8%. The CLs for clinical plans were 7.7±6.0 % (AAA), 5.3±3.3 % (AC), 5.7±3.4 % (PBC -B), respectively. Conclusion: The TLs from the CLs were evaluated. A Clarkson-based system shows a large systematic variation because of inhomogeneous correction. The AAA showed a significant variation. Thus, we must consider the difference of inhomogeneous correction as well as the dependence of dose calculation engine

  17. SU-E-T-50: A Multi-Institutional Study of Independent Dose Verification Software Program for Lung SBRT

    Energy Technology Data Exchange (ETDEWEB)

    Kawai, D [Kanagawa Cancer Center, Yokohama, Kanagawa-prefecture (Japan); Takahashi, R; Kamima, T [The Cancer Institute Hospital of JFCR, Koutou-ku, Tokyo (Japan); Baba, H [The National Cancer Center Hospital East, Kashiwa-city, Chiba prefecture (Japan); Yamamoto, T; Kubo, Y [Otemae Hospital, Chuou-ku, Osaka-city (Japan); Ishibashi, S; Higuchi, Y [Sasebo City General Hospital, Sasebo, Nagasaki (Japan); Takahashi, H [St Lukes International Hospital, Chuou-ku, Tokyo (Japan); Tachibana, H [National Cancer Center Hospital East, Kashiwa, Chiba (Japan)

    2015-06-15

    Purpose: The accuracy of dose distribution depends on treatment planning system especially in heterogeneity-region. The tolerance level (TL) of the secondary check using the independent dose verification may be variable in lung SBRT plans. We conducted a multi-institutional study to evaluate the tolerance level of lung SBRT plans shown in the AAPM TG114. Methods: Five institutes in Japan participated in this study. All of the institutes used a same independent dose verification software program (Simple MU Analysis: SMU, Triangle Product, Ishikawa, JP), which is Clarkson-based and CT images were used to compute radiological path length. Analytical Anisotropic Algorithm (AAA), Pencil Beam Convolution with modified Batho-method (PBC-B) and Adaptive Convolve (AC) were used for lung SBRT planning. A measurement using an ion-chamber was performed in a heterogeneous phantom to compare doses from the three different algorithms and the SMU to the measured dose. In addition to it, a retrospective analysis using clinical lung SBRT plans (547 beams from 77 patients) was conducted to evaluate the confidence limit (CL, Average±2SD) in dose between the three algorithms and the SMU. Results: Compared to the measurement, the AAA showed the larger systematic dose error of 2.9±3.2% than PBC-B and AC. The Clarkson-based SMU showed larger error of 5.8±3.8%. The CLs for clinical plans were 7.7±6.0 % (AAA), 5.3±3.3 % (AC), 5.7±3.4 % (PBC -B), respectively. Conclusion: The TLs from the CLs were evaluated. A Clarkson-based system shows a large systematic variation because of inhomogeneous correction. The AAA showed a significant variation. Thus, we must consider the difference of inhomogeneous correction as well as the dependence of dose calculation engine.

  18. Fingerprint verification prediction model in hand dermatitis.

    Science.gov (United States)

    Lee, Chew K; Chang, Choong C; Johor, Asmah; Othman, Puwira; Baba, Roshidah

    2015-07-01

    Hand dermatitis associated fingerprint changes is a significant problem and affects fingerprint verification processes. This study was done to develop a clinically useful prediction model for fingerprint verification in patients with hand dermatitis. A case-control study involving 100 patients with hand dermatitis. All patients verified their thumbprints against their identity card. Registered fingerprints were randomized into a model derivation and model validation group. Predictive model was derived using multiple logistic regression. Validation was done using the goodness-of-fit test. The fingerprint verification prediction model consists of a major criterion (fingerprint dystrophy area of ≥ 25%) and two minor criteria (long horizontal lines and long vertical lines). The presence of the major criterion predicts it will almost always fail verification, while presence of both minor criteria and presence of one minor criterion predict high and low risk of fingerprint verification failure, respectively. When none of the criteria are met, the fingerprint almost always passes the verification. The area under the receiver operating characteristic curve was 0.937, and the goodness-of-fit test showed agreement between the observed and expected number (P = 0.26). The derived fingerprint verification failure prediction model is validated and highly discriminatory in predicting risk of fingerprint verification in patients with hand dermatitis. © 2014 The International Society of Dermatology.

  19. Verification of RESRAD-RDD. (Version 2.01)

    Energy Technology Data Exchange (ETDEWEB)

    Cheng, Jing-Jy [Argonne National Lab. (ANL), Argonne, IL (United States); Flood, Paul E. [Argonne National Lab. (ANL), Argonne, IL (United States); LePoire, David [Argonne National Lab. (ANL), Argonne, IL (United States); Kamboj, Sunita [Argonne National Lab. (ANL), Argonne, IL (United States); Yu, Charley [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-09-01

    In this report, the results generated by RESRAD-RDD version 2.01 are compared with those produced by RESRAD-RDD version 1.7 for different scenarios with different sets of input parameters. RESRAD-RDD version 1.7 is spreadsheet-driven, performing calculations with Microsoft Excel spreadsheets. RESRAD-RDD version 2.01 revamped version 1.7 by using command-driven programs designed with Visual Basic.NET to direct calculations with data saved in Microsoft Access database, and re-facing the graphical user interface (GUI) to provide more flexibility and choices in guideline derivation. Because version 1.7 and version 2.01 perform the same calculations, the comparison of their results serves as verification of both versions. The verification covered calculation results for 11 radionuclides included in both versions: Am-241, Cf-252, Cm-244, Co-60, Cs-137, Ir-192, Po-210, Pu-238, Pu-239, Ra-226, and Sr-90. At first, all nuclidespecific data used in both versions were compared to ensure that they are identical. Then generic operational guidelines and measurement-based radiation doses or stay times associated with a specific operational guideline group were calculated with both versions using different sets of input parameters, and the results obtained with the same set of input parameters were compared. A total of 12 sets of input parameters were used for the verification, and the comparison was performed for each operational guideline group, from A to G, sequentially. The verification shows that RESRAD-RDD version 1.7 and RESRAD-RDD version 2.01 generate almost identical results; the slight differences could be attributed to differences in numerical precision with Microsoft Excel and Visual Basic.NET. RESRAD-RDD version 2.01 allows the selection of different units for use in reporting calculation results. The results of SI units were obtained and compared with the base results (in traditional units) used for comparison with version 1.7. The comparison shows that RESRAD

  20. 42 CFR 456.523 - Revised UR plan.

    Science.gov (United States)

    2010-10-01

    ... control over the utilization of services; and (2) Conducts reviews in a way that improves the quality of...) MEDICAL ASSISTANCE PROGRAMS UTILIZATION CONTROL Utilization Review Plans: FFP, Waivers, and Variances for Hospitals and Mental Hospitals Ur Plan: Remote Facility Variances from Time Requirements § 456.523 Revised...

  1. Test/QA Plan For Verification Of Anaerobic Digester For Energy Production And Pollution Prevention

    Science.gov (United States)

    The ETV-ESTE Program conducts third-party verification testing of commercially available technologies that improve the environmental conditions in the U.S. A stakeholder committee of buyers and users of such technologies guided the development of this test on anaerobic digesters...

  2. Statistical methods to correct for verification bias in diagnostic studies are inadequate when there are few false negatives: a simulation study

    Directory of Open Access Journals (Sweden)

    Vickers Andrew J

    2008-11-01

    Full Text Available Abstract Background A common feature of diagnostic research is that results for a diagnostic gold standard are available primarily for patients who are positive for the test under investigation. Data from such studies are subject to what has been termed "verification bias". We evaluated statistical methods for verification bias correction when there are few false negatives. Methods A simulation study was conducted of a screening study subject to verification bias. We compared estimates of the area-under-the-curve (AUC corrected for verification bias varying both the rate and mechanism of verification. Results In a single simulated data set, varying false negatives from 0 to 4 led to verification bias corrected AUCs ranging from 0.550 to 0.852. Excess variation associated with low numbers of false negatives was confirmed in simulation studies and by analyses of published studies that incorporated verification bias correction. The 2.5th – 97.5th centile range constituted as much as 60% of the possible range of AUCs for some simulations. Conclusion Screening programs are designed such that there are few false negatives. Standard statistical methods for verification bias correction are inadequate in this circumstance.

  3. Verification and validation benchmarks

    International Nuclear Information System (INIS)

    Oberkampf, William Louis; Trucano, Timothy Guy

    2007-01-01

    Verification and validation (V and V) are the primary means to assess the accuracy and reliability of computational simulations. V and V methods and procedures have fundamentally improved the credibility of simulations in several high-consequence fields, such as nuclear reactor safety, underground nuclear waste storage, and nuclear weapon safety. Although the terminology is not uniform across engineering disciplines, code verification deals with assessing the reliability of the software coding, and solution verification deals with assessing the numerical accuracy of the solution to a computational model. Validation addresses the physics modeling accuracy of a computational simulation by comparing the computational results with experimental data. Code verification benchmarks and validation benchmarks have been constructed for a number of years in every field of computational simulation. However, no comprehensive guidelines have been proposed for the construction and use of V and V benchmarks. For example, the field of nuclear reactor safety has not focused on code verification benchmarks, but it has placed great emphasis on developing validation benchmarks. Many of these validation benchmarks are closely related to the operations of actual reactors at near-safety-critical conditions, as opposed to being more fundamental-physics benchmarks. This paper presents recommendations for the effective design and use of code verification benchmarks based on manufactured solutions, classical analytical solutions, and highly accurate numerical solutions. In addition, this paper presents recommendations for the design and use of validation benchmarks, highlighting the careful design of building-block experiments, the estimation of experimental measurement uncertainty for both inputs and outputs to the code, validation metrics, and the role of model calibration in validation. It is argued that the understanding of predictive capability of a computational model is built on the

  4. Verification and validation benchmarks

    International Nuclear Information System (INIS)

    Oberkampf, William L.; Trucano, Timothy G.

    2008-01-01

    Verification and validation (V and V) are the primary means to assess the accuracy and reliability of computational simulations. V and V methods and procedures have fundamentally improved the credibility of simulations in several high-consequence fields, such as nuclear reactor safety, underground nuclear waste storage, and nuclear weapon safety. Although the terminology is not uniform across engineering disciplines, code verification deals with assessing the reliability of the software coding, and solution verification deals with assessing the numerical accuracy of the solution to a computational model. Validation addresses the physics modeling accuracy of a computational simulation by comparing the computational results with experimental data. Code verification benchmarks and validation benchmarks have been constructed for a number of years in every field of computational simulation. However, no comprehensive guidelines have been proposed for the construction and use of V and V benchmarks. For example, the field of nuclear reactor safety has not focused on code verification benchmarks, but it has placed great emphasis on developing validation benchmarks. Many of these validation benchmarks are closely related to the operations of actual reactors at near-safety-critical conditions, as opposed to being more fundamental-physics benchmarks. This paper presents recommendations for the effective design and use of code verification benchmarks based on manufactured solutions, classical analytical solutions, and highly accurate numerical solutions. In addition, this paper presents recommendations for the design and use of validation benchmarks, highlighting the careful design of building-block experiments, the estimation of experimental measurement uncertainty for both inputs and outputs to the code, validation metrics, and the role of model calibration in validation. It is argued that the understanding of predictive capability of a computational model is built on the

  5. PWR secondary water chemistry guidelines: Revision 3

    International Nuclear Information System (INIS)

    Lurie, S.; Bucci, G.; Johnson, L.; King, M.; Lamanna, L.; Morgan, E.; Bates, J.; Burns, R.; Eaker, R.; Ward, G.; Linnenbom, V.; Millet, P.; Paine, J.P.; Wood, C.J.; Gatten, T.; Meatheany, D.; Seager, J.; Thompson, R.; Brobst, G.; Connor, W.; Lewis, G.; Shirmer, R.; Gillen, J.; Kerns, M.; Jones, V.; Lappegaard, S.; Sawochka, S.; Smith, F.; Spires, D.; Pagan, S.; Gardner, J.; Polidoroff, T.; Lambert, S.; Dahl, B.; Hundley, F.; Miller, B.; Andersson, P.; Briden, D.; Fellers, B.; Harvey, S.; Polchow, J.; Rootham, M.; Fredrichs, T.; Flint, W.

    1993-05-01

    An effective, state-of-the art secondary water chemistry control program is essential to maximize the availability and operating life of major PWR components. Furthermore, the costs related to maintaining secondary water chemistry will likely be less than the repair or replacement of steam generators or large turbine rotors, with resulting outages taken into account. The revised PWR secondary water chemistry guidelines in this report represent the latest field and laboratory data on steam generator corrosion phenomena. This document supersedes Interim PWR Secondary Water Chemistry Recommendations for IGA/SCC Control (EPRI report TR-101230) as well as PWR Secondary Water Chemistry Guidelines--Revision 2 (NP-6239)

  6. Impact of the Revised Special Supplemental Nutrition Program for Women, Infants, and Children (WIC) Food Package Policy on Fruit and Vegetable Prices

    Science.gov (United States)

    Zenk, Shannon N.; Powell, Lisa M.; Odoms-Young, Angela M.; Krauss, Ramona; Fitzgibbon, Marian L.; Block, Daniel; Campbell, Richard T.

    2014-01-01

    Obesity is generally inversely related to income among women in the United States. Less access to healthy foods is one way lower income can influence dietary behaviors and body weight. Federal food assistance programs, such as the Special Supplemental Nutrition Program for Women, Infants, and Children (WIC), are an important source of healthy food for low-income populations. In 2009, as part of a nationwide policy revision, WIC added a fruit and vegetable (F/V) voucher to WIC food packages. This quasi-experimental study determined whether F/V prices at stores authorized to accept WIC (ie, WIC vendors) decreased after the policy revision in seven Illinois counties. It also examined cross-sectional F/V price variations by store type and neighborhood characteristics. Two pre-policy observations were conducted in 2008 and 2009; one post-policy observation was conducted in 2010. Small pre- to post-policy reductions in some F/V prices were found, particularly for canned fruit and frozen vegetables at small stores. Compared with chain supermarkets, mass merchandise stores had lower prices for fresh F/V and frozen F/V and small stores and non-chain supermarkets had higher canned and frozen F/V prices, but lower fresh F/V prices. Limited price differences were found across neighborhoods, although canned vegetables were more expensive in neighborhoods with higher concentrations of either Hispanics or blacks and fresh F/V prices were lower in neighborhoods with more Hispanics. Results suggest the WIC policy revision contributed to modest reductions in F/V prices. WIC participants’ purchasing power can differ depending on the type and neighborhood of the WIC vendor used. PMID:24183996

  7. Quantitative analysis of patient-specific dosimetric IMRT verification

    International Nuclear Information System (INIS)

    Budgell, G J; Perrin, B A; Mott, J H L; Fairfoul, J; Mackay, R I

    2005-01-01

    Patient-specific dosimetric verification methods for IMRT treatments are variable, time-consuming and frequently qualitative, preventing evidence-based reduction in the amount of verification performed. This paper addresses some of these issues by applying a quantitative analysis parameter to the dosimetric verification procedure. Film measurements in different planes were acquired for a series of ten IMRT prostate patients, analysed using the quantitative parameter, and compared to determine the most suitable verification plane. Film and ion chamber verification results for 61 patients were analysed to determine long-term accuracy, reproducibility and stability of the planning and delivery system. The reproducibility of the measurement and analysis system was also studied. The results show that verification results are strongly dependent on the plane chosen, with the coronal plane particularly insensitive to delivery error. Unexpectedly, no correlation could be found between the levels of error in different verification planes. Longer term verification results showed consistent patterns which suggest that the amount of patient-specific verification can be safely reduced, provided proper caution is exercised: an evidence-based model for such reduction is proposed. It is concluded that dose/distance to agreement (e.g., 3%/3 mm) should be used as a criterion of acceptability. Quantitative parameters calculated for a given criterion of acceptability should be adopted in conjunction with displays that show where discrepancies occur. Planning and delivery systems which cannot meet the required standards of accuracy, reproducibility and stability to reduce verification will not be accepted by the radiotherapy community

  8. A Verification Study on the Loop-Breaking Logic of FTREX

    International Nuclear Information System (INIS)

    Choi, Jong Soo

    2008-01-01

    The logical loop problem in fault tree analysis (FTA) has been solved by manually or automatically breaking their circular logics. The breaking of logical loops is one of uncertainty sources in fault tree analyses. A practical method which can verify fault tree analysis results was developed by Choi. The method has the capability to handle logical loop problems. It has been implemented in a FORTRAN program which is called VETA (Verification and Evaluation of fault Tree Analysis results) code. FTREX, a well-known fault tree quantifier developed by KAERI, has an automatic loop-breaking logic. In order to make certain of the correctness of the loop-breaking logic of FTREX, some typical trees with complex loops are developed and applied to this study. This paper presents some verification results of the loop-breaking logic tested by the VETA code

  9. Mathematical verification of a nuclear power plant protection system function with combined CPN and PVS

    International Nuclear Information System (INIS)

    Koo, Seo Ryong; Son, Han Seong; Seong, Poong Hyun

    1999-01-01

    In this work, an automatic software verification method for Nuclear Power Plant (NPP) protection system is developed. This method utilizes Colored Petri Net (CPN) for system modeling and Prototype Verification System (PVS) for mathematical verification. In order to help flow-through from modeling by CPN to mathematical proof by PVS, an information extractor from CPN models has been developed in this work. In order to convert the extracted information to the PVS specification language, a translator also has been developed. ML that is a higher-order functional language programs the information extractor and translator. This combined method has been applied to a protection system function of Wolsung NPP SDS2 (Steam Generator Low Level Trip). As a result of this application, we could prove completeness and consistency of the requirement logically. Through this work, in short, an axiom or lemma based-analysis method for CPN models is newly suggested in order to complement CPN analysis methods and a guideline for the use of formal methods is proposed in order to apply them to NPP software verification and validation. (author). 9 refs., 15 figs

  10. Post-silicon and runtime verification for modern processors

    CERN Document Server

    Wagner, Ilya

    2010-01-01

    The purpose of this book is to survey the state of the art and evolving directions in post-silicon and runtime verification. The authors start by giving an overview of the state of the art in verification, particularly current post-silicon methodologies in use in the industry, both for the domain of processor pipeline design and for memory subsystems. They then dive into the presentation of several new post-silicon verification solutions aimed at boosting the verification coverage of modern processors, dedicating several chapters to this topic. The presentation of runtime verification solution

  11. EPRI BWR Water Chemistry Guidelines Revision

    International Nuclear Information System (INIS)

    Garcia, Susan E.; Giannelli, Joseph F.

    2014-01-01

    BWRVIP-190: BWR Water Chemistry Guidelines – 2008 Revision has been revised. The revision committee consisted of U.S. and non-U.S. utilities (members of the BWR Vessel and Internals Protection (BWRVIP) Mitigation Committee), reactor system manufacturers, fuel suppliers, and EPRI and industry experts. The revised document, BWRVIP-190 Revision 1, was completely reformatted into two volumes, with a simplified presentation of water chemistry control, diagnostic and good practice parameters in Volume 1 and the technical bases in Volume 2, to facilitate use. The revision was developed in parallel and in coordination with preparation of the Fuel Reliability Guidelines Revision 1: BWR Fuel Cladding Crud and Corrosion. Guidance is included for plants operating under normal water chemistry (NWC), moderate hydrogen water chemistry (HWC-M), and noble metal application (GE-Hitachi NobleChem™) plus hydrogen injection. Volume 1 includes significant changes to BWR feedwater and reactor water chemistry control parameters to provide increased assurance of intergranular stress corrosion cracking (IGSCC) mitigation of reactor materials and fuel reliability during all plant conditions, including cold shutdown (≤200°F (93°C)), startup/hot standby (>200°F (93°C) and ≤ 10%) and power operation (>10% power). Action Level values for chloride and sulfate have been tightened to minimize environmentally assisted cracking (EAC) of all wetted surfaces, including those not protected by hydrogen injection, with or without noble metals. Chemistry control guidance has been enhanced to minimize shutdown radiation fields by clarifying targets for depleted zinc oxide (DZO) injection while meeting requirements for fuel reliability. Improved tabular presentations of parameter values explicitly indicate levels at which actions are to be taken and required sampling frequencies. Volume 2 provides the technical bases for BWR water chemistry control for control of EAC, flow accelerated corrosion

  12. Rule Systems for Runtime Verification: A Short Tutorial

    Science.gov (United States)

    Barringer, Howard; Havelund, Klaus; Rydeheard, David; Groce, Alex

    In this tutorial, we introduce two rule-based systems for on and off-line trace analysis, RuleR and LogScope. RuleR is a conditional rule-based system, which has a simple and easily implemented algorithm for effective runtime verification, and into which one can compile a wide range of temporal logics and other specification formalisms used for runtime verification. Specifications can be parameterized with data, or even with specifications, allowing for temporal logic combinators to be defined. We outline a number of simple syntactic extensions of core RuleR that can lead to further conciseness of specification but still enabling easy and efficient implementation. RuleR is implemented in Java and we will demonstrate its ease of use in monitoring Java programs. LogScope is a derivation of RuleR adding a simple very user-friendly temporal logic. It was developed in Python, specifically for supporting testing of spacecraft flight software for NASA’s next 2011 Mars mission MSL (Mars Science Laboratory). The system has been applied by test engineers to analysis of log files generated by running the flight software. Detailed logging is already part of the system design approach, and hence there is no added instrumentation overhead caused by this approach. While post-mortem log analysis prevents the autonomous reaction to problems possible with traditional runtime verification, it provides a powerful tool for test automation. A new system is being developed that integrates features from both RuleR and LogScope.

  13. Preparation of a program for the independent verification of the brachytherapy planning systems calculations; Confeccion de un programa para la verificacion independiente de los calculos de los sistemas de planificacion en braquiterapia

    Energy Technology Data Exchange (ETDEWEB)

    V Carmona, V.; Perez-Calatayud, J.; Lliso, F.; Richart Sancho, J.; Ballester, F.; Pujades-Claumarchirant, M.C.; Munoz, M.

    2010-07-01

    In this work a program is presented that independently checks for each patient the treatment planning system calculations in low dose rate, high dose rate and pulsed dose rate brachytherapy. The treatment planning system output text files are automatically loaded in this program in order to get the source coordinates, the desired calculation point coordinates and the dwell times when it is the case. The source strength and the reference dates are introduced by the user. The program allows implementing the recommendations about independent verification of the clinical brachytherapy dosimetry in a simple and accurate way, in few minutes. (Author).

  14. Apollo experience report: Guidance and control systems. Engineering simulation program

    Science.gov (United States)

    Gilbert, D. W.

    1973-01-01

    The Apollo Program experience from early 1962 to July 1969 with respect to the engineering-simulation support and the problems encountered is summarized in this report. Engineering simulation in support of the Apollo guidance and control system is discussed in terms of design analysis and verification, certification of hardware in closed-loop operation, verification of hardware/software compatibility, and verification of both software and procedures for each mission. The magnitude, time, and cost of the engineering simulations are described with respect to hardware availability, NASA and contractor facilities (for verification of the command module, the lunar module, and the primary guidance, navigation, and control system), and scheduling and planning considerations. Recommendations are made regarding implementation of similar, large-scale simulations for future programs.

  15. TRU waste certification and TRUPACT-II payload verification

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  16. 76 FR 50708 - Texas Regulatory Program

    Science.gov (United States)

    2011-08-16

    ..., renewals, and significant revisions. Texas intends to revise its program to improve operational efficiency. This document provides the times and locations that the Texas program and proposed amendments to that... business hours at the following location: Railroad Commission of Texas, 1701 North Congress Ave., Austin...

  17. Comparison between In-house developed and Diamond commercial software for patient specific independent monitor unit calculation and verification with heterogeneity corrections.

    Science.gov (United States)

    Kuppusamy, Vijayalakshmi; Nagarajan, Vivekanandan; Jeevanandam, Prakash; Murugan, Lavanya

    2016-02-01

    The study was aimed to compare two different monitor unit (MU) or dose verification software in volumetric modulated arc therapy (VMAT) using modified Clarkson's integration technique for 6 MV photons beams. In-house Excel Spreadsheet based monitor unit verification calculation (MUVC) program and PTW's DIAMOND secondary check software (SCS), version-6 were used as a secondary check to verify the monitor unit (MU) or dose calculated by treatment planning system (TPS). In this study 180 patients were grouped into 61 head and neck, 39 thorax and 80 pelvic sites. Verification plans are created using PTW OCTAVIUS-4D phantom and also measured using 729 detector chamber and array with isocentre as the suitable point of measurement for each field. In the analysis of 154 clinically approved VMAT plans with isocentre at a region above -350 HU, using heterogeneity corrections, In-house Spreadsheet based MUVC program and Diamond SCS showed good agreement TPS. The overall percentage average deviations for all sites were (-0.93% + 1.59%) and (1.37% + 2.72%) for In-house Excel Spreadsheet based MUVC program and Diamond SCS respectively. For 26 clinically approved VMAT plans with isocentre at a region below -350 HU showed higher variations for both In-house Spreadsheet based MUVC program and Diamond SCS. It can be concluded that for patient specific quality assurance (QA), the In-house Excel Spreadsheet based MUVC program and Diamond SCS can be used as a simple and fast accompanying to measurement based verification for plans with isocentre at a region above -350 HU. Copyright © 2016 Associazione Italiana di Fisica Medica. Published by Elsevier Ltd. All rights reserved.

  18. 77 FR 15024 - Privacy Act of 1974; Revised System of Records

    Science.gov (United States)

    2012-03-14

    ...-on capability for USDA applications, management of user credentials, and verification of identity... address: Program Manager--Identity and Access Management, 301 South Howes Street, Suite 309, Fort Collins... interests, identity theft or fraud, or harm to the security or integrity of this system or other systems or...

  19. ENVIRONMENTAL TECHNOLOGY VERIFICATION REPORT: NEW CONDENSATOR, INC.--THE CONDENSATOR DIESEL ENGINE RETROFIT CRANKCASE VENTILATION SYSTEM

    Science.gov (United States)

    EPA's Environmental Technology Verification Program has tested New Condensator Inc.'s Condensator Diesel Engine Retrofit Crankcase Ventilation System. Brake specific fuel consumption (BSFC), the ratio of engine fuel consumption to the engine power output, was evaluated for engine...

  20. ENVIRONMENTAL TECHNOLOGY VERIFICATION REPORT, GROUNDWATER SAMPLING TECHNOLOGIES, GEOPROBE INC., PNEUMATIC BLADDER PUMP GW 1400 SERIES

    Science.gov (United States)

    The U.S. Environmental Protection Agency (EPA) design efficient processes for conducting has created the Environmental Technology perfofl1lance tests of innovative technologies. Verification Program (E TV) to facilitate the deployment of innovative or improved environmental techn...

  1. RESRAD-BUILD verification

    International Nuclear Information System (INIS)

    Kamboj, S.; Yu, C.; Biwer, B. M.; Klett, T.

    2002-01-01

    The results generated by the RESRAD-BUILD code (version 3.0) were verified with hand or spreadsheet calculations using equations given in the RESRAD-BUILD manual for different pathways. For verification purposes, different radionuclides--H-3, C-14, Na-22, Al-26, Cl-36, Mn-54, Co-60, Au-195, Ra-226, Ra-228, Th-228, and U-238--were chosen to test all pathways and models. Tritium, Ra-226, and Th-228 were chosen because of the special tritium and radon models in the RESRAD-BUILD code. Other radionuclides were selected to represent a spectrum of radiation types and energies. Verification of the RESRAD-BUILD code was conducted with an initial check of all the input parameters for correctness against their original source documents. Verification of the calculations was performed external to the RESRAD-BUILD code with Microsoft Excel to verify all the major portions of the code. In some cases, RESRAD-BUILD results were compared with those of external codes, such as MCNP (Monte Carlo N-particle) and RESRAD. The verification was conducted on a step-by-step basis and used different test cases as templates. The following types of calculations were investigated: (1) source injection rate, (2) air concentration in the room, (3) air particulate deposition, (4) radon pathway model, (5) tritium model for volume source, (6) external exposure model, (7) different pathway doses, and (8) time dependence of dose. Some minor errors were identified in version 3.0; these errors have been corrected in later versions of the code. Some possible improvements in the code were also identified

  2. SPR Hydrostatic Column Model Verification and Validation.

    Energy Technology Data Exchange (ETDEWEB)

    Bettin, Giorgia [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lord, David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Rudeen, David Keith [Gram, Inc. Albuquerque, NM (United States)

    2015-10-01

    A Hydrostatic Column Model (HCM) was developed to help differentiate between normal "tight" well behavior and small-leak behavior under nitrogen for testing the pressure integrity of crude oil storage wells at the U.S. Strategic Petroleum Reserve. This effort was motivated by steady, yet distinct, pressure behavior of a series of Big Hill caverns that have been placed under nitrogen for extended period of time. This report describes the HCM model, its functional requirements, the model structure and the verification and validation process. Different modes of operation are also described, which illustrate how the software can be used to model extended nitrogen monitoring and Mechanical Integrity Tests by predicting wellhead pressures along with nitrogen interface movements. Model verification has shown that the program runs correctly and it is implemented as intended. The cavern BH101 long term nitrogen test was used to validate the model which showed very good agreement with measured data. This supports the claim that the model is, in fact, capturing the relevant physical phenomena and can be used to make accurate predictions of both wellhead pressure and interface movements.

  3. Spent fuel verification options for final repository safeguards in Finland. A study on verification methods, their feasibility and safety aspects

    International Nuclear Information System (INIS)

    Hautamaeki, J.; Tiitta, A.

    2000-12-01

    The verification possibilities of the spent fuel assemblies from the Olkiluoto and Loviisa NPPs and the fuel rods from the research reactor of VTT are contemplated in this report. The spent fuel assemblies have to be verified at the partial defect level before the final disposal into the geologic repository. The rods from the research reactor may be verified at the gross defect level. Developing a measurement system for partial defect verification is a complicated and time-consuming task. The Passive High Energy Gamma Emission Tomography and the Fork Detector combined with Gamma Spectrometry are the most potential measurement principles to be developed for this purpose. The whole verification process has to be planned to be as slick as possible. An early start in the planning of the verification and developing the measurement devices is important in order to enable a smooth integration of the verification measurements into the conditioning and disposal process. The IAEA and Euratom have not yet concluded the safeguards criteria for the final disposal. E.g. criteria connected to the selection of the best place to perform the verification. Measurements have not yet been concluded. Options for the verification places have been considered in this report. One option for a verification measurement place is the intermediate storage. The other option is the encapsulation plant. Crucial viewpoints are such as which one offers the best practical possibilities to perform the measurements effectively and which would be the better place in the safeguards point of view. Verification measurements may be needed both in the intermediate storages and in the encapsulation plant. In this report also the integrity of the fuel assemblies after wet intermediate storage period is assessed, because the assemblies have to stand the handling operations of the verification measurements. (orig.)

  4. 76 FR 26224 - Revisions to the California State Implementation Plan, Northern Sonoma County Air Pollution...

    Science.gov (United States)

    2011-05-06

    ...EPA is proposing to approve revisions to the Northern Sonoma County Air Pollution Control District (NSCAPCD) and Mendocino County Air Quality Management District (MCAQMD) portions of the California State Implementation Plan (SIP). Both districts are required under Part C of title I of the Clean Air Act (CAA) to adopt and implement SIP- approved Prevention of Significant Deterioration (PSD) permit programs. These proposed revisions update the definitions used in the districts' PSD permit programs.

  5. ENVIRONMENTAL TECHNOLOGY PROTOCOL VERIFICATION REPORT, EMISSIONS OF VOCS AND ALDEHYDES FROM COMMERCIAL FURNITURE (WITH APPENDICES)

    Science.gov (United States)

    As part of a U.S. Environmental Protection Agency Environmental Technology Verification program, the Research Triangle Institute (RTI) developed a test protocol for measuring volatile organic compounds and aldehydes in a large chamber. RTI convened stakeholders for the commercial...

  6. Revision Total Hip Arthoplasty: Factors Associated with Re-Revision Surgery

    OpenAIRE

    Khatod, M; Cafri, G; Inacio, MCS; Schepps, AL; Paxton, EW; Bini, SA

    2015-01-01

    The survivorship of implants after revision total hip arthroplasty and risk factors associated with re-revision are not well defined. We evaluated the re-revision rate with use of the institutional total joint replacement registry. The purpose of this study was to determine patient, implant, and surgeon factors associated with re-revision total hip arthroplasty.A retrospective cohort study was conducted. The total joint replacement registry was used to identify patients who had undergone revi...

  7. Finite element program ARKAS: verification for IAEA benchmark problem analysis on core-wide mechanical analysis of LMFBR cores

    International Nuclear Information System (INIS)

    Nakagawa, M.; Tsuboi, Y.

    1990-01-01

    ''ARKAS'' code verification, with the problems set in the International Working Group on Fast Reactors (IWGFR) Coordinated Research Programme (CRP) on the inter-comparison between liquid metal cooled fast breeder reactor (LMFBR) Core Mechanics Codes, is discussed. The CRP was co-ordinated by the IWGFR around problems set by Dr. R.G. Anderson (UKAEA) and arose from the IWGFR specialists' meeting on The Predictions and Experience of Core Distortion Behaviour (ref. 2). The problems for the verification (''code against code'') and validation (''code against experiment'') were set and calculated by eleven core mechanics codes from nine countries. All the problems have been completed and were solved with the core structural mechanics code ARKAS. Predictions by ARKAS agreed very well with other solutions for the well-defined verification problems. For the validation problems based on Japanese ex-reactor 2-D thermo-elastic experiments, the agreements between measured and calculated values were fairly good. This paper briefly describes the numerical model of the ARKAS code, and discusses some typical results. (author)

  8. Accelerating functional verification of an integrated circuit

    Science.gov (United States)

    Deindl, Michael; Ruedinger, Jeffrey Joseph; Zoellin, Christian G.

    2015-10-27

    Illustrative embodiments include a method, system, and computer program product for accelerating functional verification in simulation testing of an integrated circuit (IC). Using a processor and a memory, a serial operation is replaced with a direct register access operation, wherein the serial operation is configured to perform bit shifting operation using a register in a simulation of the IC. The serial operation is blocked from manipulating the register in the simulation of the IC. Using the register in the simulation of the IC, the direct register access operation is performed in place of the serial operation.

  9. 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)

  10. The Impact of the 2009 Special Supplemental Nutrition Program for Women, Infants, and Children Food Package Revisions on Participants: A Systematic Review.

    Science.gov (United States)

    Schultz, Daniel Joseph; Byker Shanks, Carmen; Houghtaling, Bailey

    2015-11-01

    For the first time since 1980, the US Department of Agriculture Food and Nutrition Service Special Supplemental Nutrition Program for Women, Infants, and Children (WIC) food package policies were revised in 2009 to meet the Institute of Medicine's nutrition recommendations. These changes included increases in fruits, vegetables, whole grains, and low-fat dairy to improve nutrition and health of WIC participants. Our systematic review of the literature assessed the influence that the 2009 WIC food package revisions have had on dietary intake, healthy food and beverage availability, and breastfeeding participation. The systematic review followed Preferred Reporting Items for Systematic Reviews and Meta-Analyses recommendations. Four electronic databases were searched between April 1 and 30, 2014, for peer-reviewed research. Two reviewers screened the articles, extracted the data, and established inter-rater reliability by discussing and resolving discrepancies. Twenty articles were included that met our inclusion criteria. Nine of the studies analyzed changes in dietary intake, eight examined changes in healthy food and beverage availability, and three evaluated breastfeeding participation exclusively. The review demonstrated an improved dietary intake and an increase in the availability of healthier foods and beverages in authorized WIC stores. The revised food package was also associated with improved dietary intake of WIC participants. Mixed results were demonstrated in regard to improved breastfeeding outcomes. Further research is needed to assess the influence of WIC 2009 food package revisions on breastfeeding outcomes and to make conclusions about broad nutrition-related implications. Copyright © 2015 Academy of Nutrition and Dietetics. Published by Elsevier Inc. All rights reserved.

  11. TEST DESIGN FOR ENVIRONMENTAL TECHNOLOGY VERIFICATION (ETV) OF ADD-ON NOX CONTROL UTILIZING OZONE INJECTION

    Science.gov (United States)

    The paper discusses the test design for environmental technology verification (ETV) of add-0n nitrogen oxides (NOx) control utilizing ozone injection. (NOTE: ETV is an EPA-established program to enhance domestic and international market acceptance of new or improved commercially...

  12. Ostomy Home Skills Program

    Medline Plus

    Full Text Available ... Life Support Verification, Review, and Consultation Program for Hospitals ... Injury Prevention and Control Quality and Safety Conference Quality and Safety Conference Quality ...

  13. An Implementation Guide for Intermodal Transportation Career Education. Revised Edition.

    Science.gov (United States)

    Associated Research Corp., South Miami, FL.

    One of a series devoted to career education in transportation, this teachers' guide, which is a revised edition of a guide issued in 1974, covers the planning, implementation, and evaluation of programs in transportation career education and provides forms to be used in these three processes. The most important principles in program planning are…

  14. SU-E-T-762: Toward Volume-Based Independent Dose Verification as Secondary Check

    International Nuclear Information System (INIS)

    Tachibana, H; Tachibana, R

    2015-01-01

    Purpose: Lung SBRT plan has been shifted to volume prescription technique. However, point dose agreement is still verified using independent dose verification at the secondary check. The volume dose verification is more affected by inhomogeneous correction rather than point dose verification currently used as the check. A feasibility study for volume dose verification was conducted in lung SBRT plan. Methods: Six SBRT plans were collected in our institute. Two dose distributions with / without inhomogeneous correction were generated using Adaptive Convolve (AC) in Pinnacle3. Simple MU Analysis (SMU, Triangle Product, Ishikawa, JP) was used as the independent dose verification software program, in which a modified Clarkson-based algorithm was implemented and radiological path length was computed using CT images independently to the treatment planning system. The agreement in point dose and mean dose between the AC with / without the correction and the SMU were assessed. Results: In the point dose evaluation for the center of the GTV, the difference shows the systematic shift (4.5% ± 1.9 %) in comparison of the AC with the inhomogeneous correction, on the other hands, there was good agreement of 0.2 ± 0.9% between the SMU and the AC without the correction. In the volume evaluation, there were significant differences in mean dose for not only PTV (14.2 ± 5.1 %) but also GTV (8.0 ± 5.1 %) compared to the AC with the correction. Without the correction, the SMU showed good agreement for GTV (1.5 ± 0.9%) as well as PTV (0.9% ± 1.0%). Conclusion: The volume evaluation for secondary check may be possible in homogenous region. However, the volume including the inhomogeneous media would make larger discrepancy. Dose calculation algorithm for independent verification needs to be modified to take into account the inhomogeneous correction

  15. Verification of safety critical software

    International Nuclear Information System (INIS)

    Son, Ki Chang; Chun, Chong Son; Lee, Byeong Joo; Lee, Soon Sung; Lee, Byung Chai

    1996-01-01

    To assure quality of safety critical software, software should be developed in accordance with software development procedures and rigorous software verification and validation should be performed. Software verification is the formal act of reviewing, testing of checking, and documenting whether software components comply with the specified requirements for a particular stage of the development phase[1]. New software verification methodology was developed and was applied to the Shutdown System No. 1 and 2 (SDS1,2) for Wolsung 2,3 and 4 nuclear power plants by Korea Atomic Energy Research Institute(KAERI) and Atomic Energy of Canada Limited(AECL) in order to satisfy new regulation requirements of Atomic Energy Control Boars(AECB). Software verification methodology applied to SDS1 for Wolsung 2,3 and 4 project will be described in this paper. Some errors were found by this methodology during the software development for SDS1 and were corrected by software designer. Outputs from Wolsung 2,3 and 4 project have demonstrated that the use of this methodology results in a high quality, cost-effective product. 15 refs., 6 figs. (author)

  16. Future of monitoring and verification

    International Nuclear Information System (INIS)

    Wagenmakers, H.

    1991-01-01

    The organized verification entrusted to IAEA for the implementation of the NPT, of the Treaty of Tlatelolco and of the Treaty of Rarotonga, reaches reasonable standards. The current dispute with the Democratic People's Republic of Korea about the conclusion of a safeguards agreement with IAEA, by its exceptional nature, underscores rather than undermines the positive judgement to be passed on IAEA's overall performance. The additional task given to the Director General of IAEA under Security Council resolution 687 (1991) regarding Iraq's nuclear-weapons-usable material is particularly challenging. For the purposes of this paper, verification is defined as the process for establishing whether the States parties are complying with an agreement. In the final stage verification may lead into consideration of how to respond to non-compliance. Monitoring is perceived as the first level in the verification system. It is one generic form of collecting information on objects, activities or events and it involves a variety of instruments ranging from communications satellites to television cameras or human inspectors. Monitoring may also be used as a confidence-building measure

  17. Impact of the revised Special Supplemental Nutrition Program for Women, Infants, and Children (WIC) food package policy on fruit and vegetable prices.

    Science.gov (United States)

    Zenk, Shannon N; Powell, Lisa M; Odoms-Young, Angela M; Krauss, Ramona; Fitzgibbon, Marian L; Block, Daniel; Campbell, Richard T

    2014-02-01

    Obesity is generally inversely related to income among women in the United States. Less access to healthy foods is one way lower income can influence dietary behaviors and body weight. Federal food assistance programs, such as the Special Supplemental Nutrition Program for Women, Infants, and Children (WIC), are an important source of healthy food for low-income populations. In 2009, as part of a nationwide policy revision, WIC added a fruit and vegetable (F/V) voucher to WIC food packages. This quasi-experimental study determined whether F/V prices at stores authorized to accept WIC (ie, WIC vendors) decreased after the policy revision in seven Illinois counties. It also examined cross-sectional F/V price variations by store type and neighborhood characteristics. Two pre-policy observations were conducted in 2008 and 2009; one post-policy observation was conducted in 2010. Small pre- to post-policy reductions in some F/V prices were found, particularly for canned fruit and frozen vegetables at small stores. Compared with chain supermarkets, mass merchandise stores had lower prices for fresh F/V and frozen F/V and small stores and non-chain supermarkets had higher canned and frozen F/V prices, but lower fresh F/V prices. Limited price differences were found across neighborhoods, although canned vegetables were more expensive in neighborhoods with higher concentrations of either Hispanics or blacks and fresh F/V prices were lower in neighborhoods with more Hispanics. Results suggest the WIC policy revision contributed to modest reductions in F/V prices. WIC participants' purchasing power can differ depending on the type and neighborhood of the WIC vendor used. Copyright © 2014 Academy of Nutrition and Dietetics. Published by Elsevier Inc. All rights reserved.

  18. Passive Tomography for Spent Fuel Verification: Analysis Framework and Instrument Design Study

    Energy Technology Data Exchange (ETDEWEB)

    White, Timothy A.; Svard, Staffan J.; Smith, Leon E.; Mozin, Vladimir V.; Jansson, Peter; Davour, Anna; Grape, Sophie; Trellue, H.; Deshmukh, Nikhil S.; Wittman, Richard S.; Honkamaa, Tapani; Vaccaro, Stefano; Ely, James

    2015-05-18

    The potential for gamma emission tomography (GET) to detect partial defects within a spent nuclear fuel assembly is being assessed through a collaboration of Support Programs to the International Atomic Energy Agency (IAEA). In the first phase of this study, two safeguards verification objectives have been identified. The first is the independent determination of the number of active pins that are present in the assembly, in the absence of a priori information. The second objective is to provide quantitative measures of pin-by-pin properties, e.g. activity of key isotopes or pin attributes such as cooling time and relative burnup, for the detection of anomalies and/or verification of operator-declared data. The efficacy of GET to meet these two verification objectives will be evaluated across a range of fuel types, burnups, and cooling times, and with a target interrogation time of less than 60 minutes. The evaluation of GET viability for safeguards applications is founded on a modelling and analysis framework applied to existing and emerging GET instrument designs. Monte Carlo models of different fuel types are used to produce simulated tomographer responses to large populations of “virtual” fuel assemblies. Instrument response data are processed by a variety of tomographic-reconstruction and image-processing methods, and scoring metrics specific to each of the verification objectives are defined and used to evaluate the performance of the methods. This paper will provide a description of the analysis framework and evaluation metrics, example performance-prediction results, and describe the design of a “universal” GET instrument intended to support the full range of verification scenarios envisioned by the IAEA.

  19. 76 FR 26192 - Revisions to the California State Implementation Plan, Northern Sonoma County Air Pollution...

    Science.gov (United States)

    2011-05-06

    ...EPA is taking direct final action to approve revisions to the Northern Sonoma County Air Pollution Control District (NSCAPCD) and Mendocino County Air Quality Management District (MCAQMD) portions of the California State Implementation Plan (SIP). Both districts are required under Part C of title I of the Clean Air Act (CAA) to adopt and implement SIP-approved Prevention of Significant Deterioration (PSD) permit programs. These revisions update the definitions used in the districts' PSD permit programs.

  20. Concepts for inventory verification in critical facilities

    International Nuclear Information System (INIS)

    Cobb, D.D.; Sapir, J.L.; Kern, E.A.; Dietz, R.J.

    1978-12-01

    Materials measurement and inventory verification concepts for safeguarding large critical facilities are presented. Inspection strategies and methods for applying international safeguards to such facilities are proposed. The conceptual approach to routine inventory verification includes frequent visits to the facility by one inspector, and the use of seals and nondestructive assay (NDA) measurements to verify the portion of the inventory maintained in vault storage. Periodic verification of the reactor inventory is accomplished by sampling and NDA measurement of in-core fuel elements combined with measurements of integral reactivity and related reactor parameters that are sensitive to the total fissile inventory. A combination of statistical sampling and NDA verification with measurements of reactor parameters is more effective than either technique used by itself. Special procedures for assessment and verification for abnormal safeguards conditions are also considered. When the inspection strategies and inventory verification methods are combined with strict containment and surveillance methods, they provide a high degree of assurance that any clandestine attempt to divert a significant quantity of fissile material from a critical facility inventory will be detected. Field testing of specific hardware systems and procedures to determine their sensitivity, reliability, and operational acceptability is recommended. 50 figures, 21 tables

  1. Verification and Examination Management of Complex Systems

    Directory of Open Access Journals (Sweden)

    Stian Ruud

    2014-10-01

    Full Text Available As ship systems become more complex, with an increasing number of safety-critical functions, many interconnected subsystems, tight integration to other systems, and a large amount of potential failure modes, several industry parties have identified the need for improved methods for managing the verification and examination efforts of such complex systems. Such needs are even more prominent now that the marine and offshore industries are targeting more activities and operations in the Arctic environment. In this paper, a set of requirements and a method for verification and examination management are proposed for allocating examination efforts to selected subsystems. The method is based on a definition of a verification risk function for a given system topology and given requirements. The marginal verification risks for the subsystems may then be evaluated, so that examination efforts for the subsystem can be allocated. Two cases of requirements and systems are used to demonstrate the proposed method. The method establishes a systematic relationship between the verification loss, the logic system topology, verification method performance, examination stop criterion, the required examination effort, and a proposed sequence of examinations to reach the examination stop criterion.

  2. Revised

    DEFF Research Database (Denmark)

    Johannsen, Vivian Kvist; Nord-Larsen, Thomas; Riis-Nielsen, Torben

    This report is a revised analysis of the Danish data on CO2 emissions from forest, afforestation and deforestation for the period 1990 - 2008 and a prognosis for the period until 2020. Revision have included measurements from 2009 in the estimations. The report is funded by the Ministry of Climate...

  3. Transition projects, Fiscal Year 1996: Multi-Year Program Plan (MYPP) for WBS 1.31, 7.1, and 6.13. Revision 1, Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Cartmell, D.B.

    1995-09-01

    Based on US Department of Energy (DOE), Richland Operations Office (RL) review, specific areas of Westinghouse Hanford Company (WHC), Transition Projects ``Draft`` Multi-Year Program Plan (MYPP) were revised in preparation for the RL approval ceremony on September 26, 1995. These changes were reviewed with the appropriate RL Project Manager. The changes have been incorporated to the MYPP electronic file, and hard copies replacing the ``Draft`` MYPP will be distributed after the formal signing. In addition to the comments received, a summary level schedule and outyear estimates for the K Basin deactivation beginning in FY 2001 have been included. The K Basin outyear waste data is nearing completion this week and will be incorporated. This exclusion was discussed with Mr. N.D. Moorer, RL, Facility Transition Program Support/Integration. The attached MYPP scope/schedule reflects the Integrated Target Case submitted in the April 1995 Activity Data Sheets (ADS) with the exception of B Plant and the Plutonium Finishing Plant (PFP). The 8 Plant assumption in FY 1997 reflects the planning case in the FY 1997 ADS with a shortfall of $5 million. PFP assumptions have been revised from the FY 1997 ADS based on the direction provided this past summer by DOE-Headquarters. This includes the acceleration of the polycube stabilization back to its originally planned completion date. Although the overall program repricing in FY 1996 allowed the scheduled acceleration to fall with the funding allocation, the FY 1997 total reflects a shortfall of $6 million.

  4. Transition projects, Fiscal Year 1996: Multi-Year Program Plan (MYPP) for WBS 1.31, 7.1, and 6.13. Revision 1, Volume 1

    International Nuclear Information System (INIS)

    Cartmell, D.B.

    1995-09-01

    Based on US Department of Energy (DOE), Richland Operations Office (RL) review, specific areas of Westinghouse Hanford Company (WHC), Transition Projects ''Draft'' Multi-Year Program Plan (MYPP) were revised in preparation for the RL approval ceremony on September 26, 1995. These changes were reviewed with the appropriate RL Project Manager. The changes have been incorporated to the MYPP electronic file, and hard copies replacing the ''Draft'' MYPP will be distributed after the formal signing. In addition to the comments received, a summary level schedule and outyear estimates for the K Basin deactivation beginning in FY 2001 have been included. The K Basin outyear waste data is nearing completion this week and will be incorporated. This exclusion was discussed with Mr. N.D. Moorer, RL, Facility Transition Program Support/Integration. The attached MYPP scope/schedule reflects the Integrated Target Case submitted in the April 1995 Activity Data Sheets (ADS) with the exception of B Plant and the Plutonium Finishing Plant (PFP). The 8 Plant assumption in FY 1997 reflects the planning case in the FY 1997 ADS with a shortfall of $5 million. PFP assumptions have been revised from the FY 1997 ADS based on the direction provided this past summer by DOE-Headquarters. This includes the acceleration of the polycube stabilization back to its originally planned completion date. Although the overall program repricing in FY 1996 allowed the scheduled acceleration to fall with the funding allocation, the FY 1997 total reflects a shortfall of $6 million

  5. A Methodology for Formal Hardware Verification, with Application to Microprocessors.

    Science.gov (United States)

    1993-08-29

    concurrent programming lan- guages. Proceedings of the NATO Advanced Study Institute on Logics and Models of Concurrent Systems ( Colle - sur - Loup , France, 8-19...restricted class of formu- las . Bose and Fisher [26] developed a symbolic model checker based on a Cosmos switch-level model. Their modeling approach...verification using SDVS-the method and a case study. 17th Anuual Microprogramming Workshop (New Orleans, LA , 30 October-2 November 1984). Published as

  6. Verification and validation of predictive computer programs describing the near and far-field chemistry of radioactive waste disposal systems

    International Nuclear Information System (INIS)

    Read, D.; Broyd, T.W.

    1988-01-01

    This paper provides an introduction to CHEMVAL, an international project concerned with establishing the applicability of chemical speciation and coupled transport models to the simulation of realistic waste disposal situations. The project aims to validate computer-based models quantitatively by comparison with laboratory and field experiments. Verification of the various computer programs employed by research organisations within the European Community is ensured through close inter-laboratory collaboration. The compilation and review of thermodynamic data forms an essential aspect of this work and has led to the production of an internally consistent standard CHEMVAL database. The sensitivity of results to variation in fundamental constants is being monitored at each stage of the project and, where feasible, complementary laboratory studies are used to improve the data set. Currently, thirteen organisations from five countries are participating in CHEMVAL which forms part of the Commission of European Communities' MIRAGE 2 programme of research. (orig.)

  7. Support of Construction and Verification of Out-of-Pile Fuel Assembly Test Facilities

    International Nuclear Information System (INIS)

    Park, Nam Gyu; Kim, K. T.; Park, J. K.

    2006-12-01

    Fuel assembly and components should be verified by the out-of-pile test facilities in order to load the developed fuel in reactor. Even though most of the component-wise tests have been performed using the facilities in land, the assembly-wise tests has been depended on the oversees' facility due to the lack of the facilities. KAERI started to construct the assembly-wise mechanical/hydraulic test facilities and KNF, as an end user, is supporting the mechanical/hydraulic test facility construction by using the technologies studied through the fuel development programs. The works performed are as follows: - Test assembly shipping container design and manufacturing support - Fuel handling tool design : Gripper, Upper and lower core simulators for assembly mechanical test facility, Internals for assembly hydraulic test facility - Manufacture of test specimens : skeleton and assembly for preliminary functional verification of assembly mechanical/hydraulic test facilities, two assemblies for the verification of assembly mechanical/hydraulic test facilities, Instrumented rod design and integrity evaluation - Verification of assembly mechanical/hydraulic test facilities : test data evaluation

  8. Support of Construction and Verification of Out-of-Pile Fuel Assembly Test Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Park, Nam Gyu; Kim, K. T.; Park, J. K. [KNF, Daejeon (Korea, Republic of)] (and others)

    2006-12-15

    Fuel assembly and components should be verified by the out-of-pile test facilities in order to load the developed fuel in reactor. Even though most of the component-wise tests have been performed using the facilities in land, the assembly-wise tests has been depended on the oversees' facility due to the lack of the facilities. KAERI started to construct the assembly-wise mechanical/hydraulic test facilities and KNF, as an end user, is supporting the mechanical/hydraulic test facility construction by using the technologies studied through the fuel development programs. The works performed are as follows: - Test assembly shipping container design and manufacturing support - Fuel handling tool design : Gripper, Upper and lower core simulators for assembly mechanical test facility, Internals for assembly hydraulic test facility - Manufacture of test specimens : skeleton and assembly for preliminary functional verification of assembly mechanical/hydraulic test facilities, two assemblies for the verification of assembly mechanical/hydraulic test facilities, Instrumented rod design and integrity evaluation - Verification of assembly mechanical/hydraulic test facilities : test data evaluation.

  9. 2009.3 Revision of the Evaluated Nuclear Data Library (ENDL2009.3)

    Energy Technology Data Exchange (ETDEWEB)

    Thompson, I. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Beck, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Descalle, M. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mattoon, C. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Jurgenson, E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-11-06

    LLNL's Computational Nuclear Data and Theory Group have created a 2009.3 revised release of the Evaluated Nuclear Data Library (ENDL2009.3). This library is designed to support LLNL's current and future nuclear data needs and will be employed in nuclear reactor, nuclear security and stockpile stewardship simulations with ASC codes. The ENDL2009 database was the most complete nuclear database for Monte Carlo and deterministic transport of neutrons and charged particles. It was assembled with strong support from the ASC PEM and Attribution programs, leveraged with support from Campaign 4 and the DOE/Office of Science's US Nuclear Data Program. This document lists the revisions and fixes made in a new release called ENDL2009.3, by com- paring with the existing data in the previous release ENDL2009.2. These changes are made in conjunction with the revisions for ENDL2011.3, so that both the .3 releases are as free as possible of known defects.

  10. 2011.2 Revision of the Evaluated Nuclear Data Library (ENDL2011.2)

    Energy Technology Data Exchange (ETDEWEB)

    Beck, B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Descalles, M. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Mattoon, C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Jurgenson, E. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Thompson, I. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-09-22

    LLNL's Computational Nuclear Physics Group and Nuclear Theory and Modeling Group have col- laborated to create the 2011.2 revised release of the Evaluated Nuclear Data Library (ENDL2011.2). ENDL2011.2 is designed to support LLNL's current and future nuclear data needs and will be em- ployed in nuclear reactor, nuclear security and stockpile stewardship simulations with ASC codes. This database is currently the most complete nuclear database for Monte Carlo and deterministic transport of neutrons and charged particles. This library was assembled with strong support from the ASC PEM and Attribution programs, leveraged with support from Campaign 4 and the DOE/O ce of Science's US Nuclear Data Program. This document lists the revisions made in ENDL2011.2 compared with the data existing in the original ENDL2011.0 release and the ENDL2011.1-rc4 re- lease candidate of April 2015. These changes are made in parallel with some similar revisions for ENDL2009.2.

  11. Questions and answers based on revised 10 CFR Part 20

    International Nuclear Information System (INIS)

    Borges, T.; Stafford, R.S.; Lu, P.Y.; Carter, D.

    1994-05-01

    NUREG/CR-6204 is a collection of questions and answers that were originally issued in seven sets and which pertain to revised 10 CFR Part 20. The questions came from both outside and within the NRC. The answers were compiled and provided by NRC staff within the offices of Nuclear Reactor Regulation, Nuclear Material Safety and Safeguards, Nuclear Regulatory Research, the Office of State Programs, and the five regional offices. Although all of the questions and answers have been reviewed by attorneys in the NRC Office of the General Counsel, they do not constitute official legal interpretations relevant to revised 10 CFR Part 20. The questions and answers do, however, reflect NRC staff decisions and technical options on aspects of the revised 10 CFR Part 20 regulatory requirements. This NUREG is being made available to encourage communication among the public, industry, and NRC staff concerning the major revisions of the NRC's standards for protection against radiation

  12. Face Verification for Mobile Personal Devices

    NARCIS (Netherlands)

    Tao, Q.

    2009-01-01

    In this thesis, we presented a detailed study of the face verification problem on the mobile device, covering every component of the system. The study includes face detection, registration, normalization, and verification. Furthermore, the information fusion problem is studied to verify face

  13. Gender Verification of Female Olympic Athletes.

    Science.gov (United States)

    Dickinson, Barry D.; Genel, Myron; Robinowitz, Carolyn B.; Turner, Patricia L.; Woods, Gary L.

    2002-01-01

    Gender verification of female athletes has long been criticized by geneticists, endocrinologists, and others in the medical community. Recently, the International Olympic Committee's Athletic Commission called for discontinuation of mandatory laboratory-based gender verification of female athletes. This article discusses normal sexual…

  14. An unattended verification station for UF6 cylinders: Field trial findings

    Science.gov (United States)

    Smith, L. E.; Miller, K. A.; McDonald, B. S.; Webster, J. B.; Zalavadia, M. A.; Garner, J. R.; Stewart, S. L.; Branney, S. J.; Todd, L. C.; Deshmukh, N. S.; Nordquist, H. A.; Kulisek, J. A.; Swinhoe, M. T.

    2017-12-01

    In recent years, the International Atomic Energy Agency (IAEA) has pursued innovative techniques and an integrated suite of safeguards measures to address the verification challenges posed by the front end of the nuclear fuel cycle. Among the unattended instruments currently being explored by the IAEA is an Unattended Cylinder Verification Station (UCVS), which could provide automated, independent verification of the declared relative enrichment, 235U mass, total uranium mass, and identification for all declared uranium hexafluoride cylinders in a facility (e.g., uranium enrichment plants and fuel fabrication plants). Under the auspices of the United States and European Commission Support Programs to the IAEA, a project was undertaken to assess the technical and practical viability of the UCVS concept. The first phase of the UCVS viability study was centered on a long-term field trial of a prototype UCVS system at a fuel fabrication facility. A key outcome of the study was a quantitative performance evaluation of two nondestructive assay (NDA) methods being considered for inclusion in a UCVS: Hybrid Enrichment Verification Array (HEVA), and Passive Neutron Enrichment Meter (PNEM). This paper provides a description of the UCVS prototype design and an overview of the long-term field trial. Analysis results and interpretation are presented with a focus on the performance of PNEM and HEVA for the assay of over 200 "typical" Type 30B cylinders, and the viability of an "NDA Fingerprint" concept as a high-fidelity means to periodically verify that material diversion has not occurred.

  15. 77 FR 50723 - Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety...

    Science.gov (United States)

    2012-08-22

    ... regulations with respect to software verification and auditing of digital computer software used in the safety... Standards and Records,'' which requires, in part, that a quality assurance program be established and implemented to provide adequate assurance that systems and components important to safety will satisfactorily...

  16. Model-Checking Real-Time Control Programs

    DEFF Research Database (Denmark)

    Iversen, T. K.; Kristoffersen, K. J.; Larsen, Kim Guldstrand

    2000-01-01

    In this paper, we present a method for automatic verification of real-time control programs running on LEGO(R) RCX(TM) bricks using the verification tool UPPALL. The control programs, consisting of a number of tasks running concurrently, are automatically translated into the mixed automata model...... of UPPAAL. The fixed scheduling algorithm used by the LEGO(R) RCX(TM) processor is modeled in UPPALL, and supply of similar (sufficient) timed automata models for the environment allows analysis of the overall real-time system using the tools of UPPALL. To illustrate our technique for sorting LEGO(R) bricks...

  17. Reload core safety verification

    International Nuclear Information System (INIS)

    Svetlik, M.; Minarcin, M.

    2003-01-01

    This paper presents a brief look at the process of reload core safety evaluation and verification in Slovak Republic. It gives an overview of experimental verification of selected nuclear parameters in the course of physics testing during reactor start-up. The comparison of IAEA recommendations and testing procedures at Slovak and European nuclear power plants of similar design is included. An introduction of two level criteria for evaluation of tests represents an effort to formulate the relation between safety evaluation and measured values (Authors)

  18. Validation of Embedded System Verification Models

    NARCIS (Netherlands)

    Marincic, J.; Mader, Angelika H.; Wieringa, Roelf J.

    The result of a model-based requirements verification shows that the model of a system satisfies (or not) formalised system requirements. The verification result is correct only if the model represents the system adequately. No matter what modelling technique we use, what precedes the model

  19. On Verification Modelling of Embedded Systems

    NARCIS (Netherlands)

    Brinksma, Hendrik; Mader, Angelika H.

    Computer-aided verification of embedded systems hinges on the availability of good verification models of the systems at hand. Such models must be much simpler than full design models or specifications to be of practical value, because of the unavoidable combinatorial complexities in the

  20. ENVIRONMENTAL TECHNOLOGY VERIFICATION REPORT, SWINE WASTE ELECTRIC POWER AND HEAT PRODUCTION--MARTIN MACHINERY INTERNAL COMBUSTION ENGINE

    Science.gov (United States)

    Under EPA’s Environmental Technology Verification program, which provides objective and scientific third party analysis of new technology that can benefit the environment, a combined heat and power system designed by Martin Machinery was evaluated. This paper provides test result...

  1. Compositional verification of real-time systems using Ecdar

    DEFF Research Database (Denmark)

    David, Alexandre; Larsen, Kim Guldstrand; Legay, Axel

    2012-01-01

    We present a specification theory for timed systems implemented in the Ecdar tool. We illustrate the operations of the specification theory on a running example, showing the models and verification checks. To demonstrate the power of the compositional verification, we perform an in depth case study...... of a leader election protocol; Modeling it in Ecdar as Timed input/output automata Specifications and performing both monolithic and compositional verification of two interesting properties on it. We compare the execution time of the compositional to the classical verification showing a huge difference...

  2. Disarmament Verification - the OPCW Experience

    International Nuclear Information System (INIS)

    Lodding, J.

    2010-01-01

    The Chemical Weapons Convention is the only multilateral treaty that bans completely an entire category of weapons of mass destruction under international verification arrangements. Possessor States, i.e. those that have chemical weapons stockpiles at the time of becoming party to the CWC, commit to destroying these. All States undertake never to acquire chemical weapons and not to help other States acquire such weapons. The CWC foresees time-bound chemical disarmament. The deadlines for destruction for early entrants to the CWC are provided in the treaty. For late entrants, the Conference of States Parties intervenes to set destruction deadlines. One of the unique features of the CWC is thus the regime for verifying destruction of chemical weapons. But how can you design a system for verification at military sites, while protecting military restricted information? What degree of assurance is considered sufficient in such circumstances? How do you divide the verification costs? How do you deal with production capability and initial declarations of existing stockpiles? The founders of the CWC had to address these and other challenges in designing the treaty. Further refinement of the verification system has followed since the treaty opened for signature in 1993 and since inspection work was initiated following entry-into-force of the treaty in 1997. Most of this work concerns destruction at the two large possessor States, Russia and the United States. Perhaps some of the lessons learned from the OPCW experience may be instructive in a future verification regime for nuclear weapons. (author)

  3. Verification of Chemical Weapons Destruction

    International Nuclear Information System (INIS)

    Lodding, J.

    2010-01-01

    The Chemical Weapons Convention is the only multilateral treaty that bans completely an entire category of weapons of mass destruction under international verification arrangements. Possessor States, i.e. those that have chemical weapons stockpiles at the time of becoming party to the CWC, commit to destroying these. All States undertake never to acquire chemical weapons and not to help other States acquire such weapons. The CWC foresees time-bound chemical disarmament. The deadlines for destruction for early entrants to the CWC are provided in the treaty. For late entrants, the Conference of States Parties intervenes to set destruction deadlines. One of the unique features of the CWC is thus the regime for verifying destruction of chemical weapons. But how can you design a system for verification at military sites, while protecting military restricted information? What degree of assurance is considered sufficient in such circumstances? How do you divide the verification costs? How do you deal with production capability and initial declarations of existing stockpiles? The founders of the CWC had to address these and other challenges in designing the treaty. Further refinement of the verification system has followed since the treaty opened for signature in 1993 and since inspection work was initiated following entry-into-force of the treaty in 1997. Most of this work concerns destruction at the two large possessor States, Russia and the United States. Perhaps some of the lessons learned from the OPCW experience may be instructive in a future verification regime for nuclear weapons. (author)

  4. Design verification of the CANFLEX fuel bundle - quality assurance requirements for mechanical flow testing

    International Nuclear Information System (INIS)

    Alavi, P.; Oldaker, I.E.; Chung, C.H.; Suk, H.C.

    1997-01-01

    As part of the design verification program for the new fuel bundle, a series of out-reactor tests was conducted on the CANFLEX 43-element fuel bundle design. These tests simulated current CANDU 6 reactor normal operating conditions of flow, temperature and pressure. This paper describes the Quality Assurance (QA) Program implemented for the tests that were run at the testing laboratories of Atomic Energy of Canada Limited (AECL) and Korea Atomic energy Research Institute (KAERI). (author)

  5. A Model for Collaborative Runtime Verification

    NARCIS (Netherlands)

    Testerink, Bas; Bulling, Nils; Dastani, Mehdi

    2015-01-01

    Runtime verification concerns checking whether a system execution satisfies a given property. In this paper we propose a model for collaborative runtime verification where a network of local monitors collaborates in order to verify properties of the system. A local monitor has only a local view on

  6. Burnup verification using the FORK measurement system

    International Nuclear Information System (INIS)

    Ewing, R.I.

    1994-01-01

    Verification measurements may be used to help ensure nuclear criticality safety when burnup credit is applied to spent fuel transport and storage systems. The FORK measurement system, designed at Los Alamos National Laboratory for the International Atomic Energy Agency safeguards program, has been used to verify reactor site records for burnup and cooling time for many years. The FORK system measures the passive neutron and gamma-ray emission from spent fuel assemblies while in the storage pool. This report deals with the application of the FORK system to burnup credit operations based on measurements performed on spent fuel assemblies at the Oconee Nuclear Station of Duke Power Company

  7. Self-verification and contextualized self-views.

    Science.gov (United States)

    Chen, Serena; English, Tammy; Peng, Kaiping

    2006-07-01

    Whereas most self-verification research has focused on people's desire to verify their global self-conceptions, the present studies examined self-verification with regard to contextualized selfviews-views of the self in particular situations and relationships. It was hypothesized that individuals whose core self-conceptions include contextualized self-views should seek to verify these self-views. In Study 1, the more individuals defined the self in dialectical terms, the more their judgments were biased in favor of verifying over nonverifying feedback about a negative, situation-specific self-view. In Study 2, consistent with research on gender differences in the importance of relationships to the self-concept, women but not men showed a similar bias toward feedback about a negative, relationship-specific self-view, a pattern not seen for global self-views. Together, the results support the notion that self-verification occurs for core self-conceptions, whatever form(s) they may take. Individual differences in self-verification and the nature of selfhood and authenticity are discussed.

  8. Technical specification optimization program - engineered safety features

    International Nuclear Information System (INIS)

    Andre, G.R.; Jansen, R.L.

    1986-01-01

    The Westinghouse Technical Specification Program (TOP) was designed to evaluate on a quantitative basis revisions to Nuclear Power Plant Technical Specifications. The revisions are directed at simplifying plant operation, and reducing unnecessary transients, shutdowns, and manpower requirements. In conjunction with the Westinghouse Owners Group, Westinghouse initiated a program to develop a methodology to justify Technical Specification revisions; particularly revisions related to testing and maintenance requirements on plant operation for instrumentation systems. The methodology was originally developed and applied to the reactor trip features of the reactor protection system (RPS). The current study further refined the methodology and applied it to the engineered safety features of the RPS

  9. Sumario de Reglamentos Revisados de Titulo I - Educacion Migrante (Summary of Revised Title I - Migrant Regulations).

    Science.gov (United States)

    Gonzalez, Ramon

    Extracted from the April 3, 1980 Federal Register, revisions of the Migrant Education regulations are synthesized in this Spanish-English booklet. Revised regulations address program planning and evaluation; needs assessment; identification and recruitment of migrant children; and special discretionary projects for the coordination of migrant…

  10. Verification Test Report for CFAST 3.1.6

    International Nuclear Information System (INIS)

    Vincent, A.M. III

    2002-01-01

    Fire is a significant hazard in most facilities that handle radioactive materials. The severity of fire varies with room arrangement, combustible loading, ventilation and protective system response. The complexity of even simple situations can be unwieldy to solve by hand calculations. Thus, computer simulation of the fire severity has become an important tool in characterizing fire risk. The Savannah River Site (SRS), a Department of Energy facility, has been using the Consolidated Model of Fire Growth and Smoke Transport (CFAST) software to complete such deterministic evaluations to better characterize the nuclear facility fire severity. To fully utilize CFAST at SRS it is necessary to demonstrate that CFAST produces valid analytic solutions over its range of use. This report describes the primary verification exercise that is required to establish that CFAST, and its user interface program FAST, produce valid analytic solutions. This verification exercise may be used to check the fu nctionality of FAST and as a training tool to familiarize users with the software. In addition, the report consolidates the lessons learned by the SRS staff in using FAST and CFAST as fire modeling tools

  11. Program Correctness, Verification and Testing for Exascale (Corvette)

    Energy Technology Data Exchange (ETDEWEB)

    Sen, Koushik [Univ. of California, Berkeley, CA (United States); Iancu, Costin [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Demmel, James W [UC Berkeley

    2018-01-26

    The goal of this project is to provide tools to assess the correctness of parallel programs written using hybrid parallelism. There is a dire lack of both theoretical and engineering know-how in the area of finding bugs in hybrid or large scale parallel programs, which our research aims to change. In the project we have demonstrated novel approaches in several areas: 1. Low overhead automated and precise detection of concurrency bugs at scale. 2. Using low overhead bug detection tools to guide speculative program transformations for performance. 3. Techniques to reduce the concurrency required to reproduce a bug using partial program restart/replay. 4. Techniques to provide reproducible execution of floating point programs. 5. Techniques for tuning the floating point precision used in codes.

  12. International Energy Agency Ocean Energy Systems Task 10 Wave Energy Converter Modeling Verification and Validation

    DEFF Research Database (Denmark)

    Wendt, Fabian F.; Yu, Yi-Hsiang; Nielsen, Kim

    2017-01-01

    This is the first joint reference paper for the Ocean Energy Systems (OES) Task 10 Wave Energy Converter modeling verification and validation group. The group is established under the OES Energy Technology Network program under the International Energy Agency. OES was founded in 2001 and Task 10 ...

  13. Clinical Skills Verification in General Psychiatry: Recommendations of the ABPN Task Force on Rater Training

    Science.gov (United States)

    Jibson, Michael D.; Broquet, Karen E.; Anzia, Joan Meyer; Beresin, Eugene V.; Hunt, Jeffrey I.; Kaye, David; Rao, Nyapati Raghu; Rostain, Anthony Leon; Sexson, Sandra B.; Summers, Richard F.

    2012-01-01

    Objective: The American Board of Psychiatry and Neurology (ABPN) announced in 2007 that general psychiatry training programs must conduct Clinical Skills Verification (CSV), consisting of observed clinical interviews and case presentations during residency, as one requirement to establish graduates' eligibility to sit for the written certification…

  14. Argonne Code Center: compilation of program abstracts

    Energy Technology Data Exchange (ETDEWEB)

    Butler, M.K.; DeBruler, M.; Edwards, H.S.

    1976-08-01

    This publication is the tenth supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the document are as follows: preface; history and acknowledgements; abstract format; recommended program package contents; program classification guide and thesaurus; and abstract collection. (RWR)

  15. Argonne Code Center: compilation of program abstracts

    International Nuclear Information System (INIS)

    Butler, M.K.; DeBruler, M.; Edwards, H.S.

    1976-08-01

    This publication is the tenth supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the document are as follows: preface; history and acknowledgements; abstract format; recommended program package contents; program classification guide and thesaurus; and abstract collection

  16. Safety assessment and verification for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2001-01-01

    This publication supports the Safety Requirements on the Safety of Nuclear Power Plants: Design. This Safety Guide was prepared on the basis of a systematic review of all the relevant publications including the Safety Fundamentals, Safety of Nuclear Power Plants: Design, current and ongoing revisions of other Safety Guides, INSAG reports and other publications that have addressed the safety of nuclear power plants. This Safety Guide also provides guidance for Contracting Parties to the Convention on Nuclear Safety in meeting their obligations under Article 14 on Assessment and Verification of Safety. The Safety Requirements publication entitled Safety of Nuclear Power Plants: Design states that a comprehensive safety assessment and an independent verification of the safety assessment shall be carried out before the design is submitted to the regulatory body. This publication provides guidance on how this requirement should be met. This Safety Guide provides recommendations to designers for carrying out a safety assessment during the initial design process and design modifications, as well as to the operating organization in carrying out independent verification of the safety assessment of new nuclear power plants with a new or already existing design. The recommendations for performing a safety assessment are suitable also as guidance for the safety review of an existing plant. The objective of reviewing existing plants against current standards and practices is to determine whether there are any deviations which would have an impact on plant safety. The methods and the recommendations of this Safety Guide can also be used by regulatory bodies for the conduct of the regulatory review and assessment. Although most recommendations of this Safety Guide are general and applicable to all types of nuclear reactors, some specific recommendations and examples apply mostly to water cooled reactors. Terms such as 'safety assessment', 'safety analysis' and 'independent

  17. 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

  18. ENVIRONMENTAL TECHNOLOGY VERIFICATION REPORT, SWINE WASTE ELECTRIC POWER AND HEAT PRODUCTION--CAPSTONE 30KW MICROTURBINE SYSTEM

    Science.gov (United States)

    Under EPA’s Environmental Technology Verification program, which provides objective and scientific third party analysis of new technology that can benefit the environment, a combined heat and power system was evaluated based on the Capstone 30kW Microturbine developed by Cain Ind...

  19. ANIMAL WASTE IMPACT ON SOURCE WATERSAIDED BY EPA/NSF ENVIRONMENTAL TECHNOLOGY VERIFICATION (ETV) SOURCE WATER PROTECTION PILOT

    Science.gov (United States)

    The Environmental Technology Verification Program (ETV) was established in 1995 by the U.S. Environmental Protection Agency to encourage the development and commercialization of new environmental technologies through third part testing and reporting of performance data. By ensur...

  20. Secure optical verification using dual phase-only correlation

    International Nuclear Information System (INIS)

    Liu, Wei; Liu, Shutian; Zhang, Yan; Xie, Zhenwei; Liu, Zhengjun

    2015-01-01

    We introduce a security-enhanced optical verification system using dual phase-only correlation based on a novel correlation algorithm. By employing a nonlinear encoding, the inherent locks of the verification system are obtained in real-valued random distributions, and the identity keys assigned to authorized users are designed as pure phases. The verification process is implemented in two-step correlation, so only authorized identity keys can output the discriminate auto-correlation and cross-correlation signals that satisfy the reset threshold values. Compared with the traditional phase-only-correlation-based verification systems, a higher security level against counterfeiting and collisions are obtained, which is demonstrated by cryptanalysis using known attacks, such as the known-plaintext attack and the chosen-plaintext attack. Optical experiments as well as necessary numerical simulations are carried out to support the proposed verification method. (paper)

  1. OpenMP 4.5 Validation and Verification Suite

    Energy Technology Data Exchange (ETDEWEB)

    2017-12-15

    OpenMP, a directive-based programming API, introduce directives for accelerator devices that programmers are starting to use more frequently in production codes. To make sure OpenMP directives work correctly across architectures, it is critical to have a mechanism that tests for an implementation's conformance to the OpenMP standard. This testing process can uncover ambiguities in the OpenMP specification, which helps compiler developers and users make a better use of the standard. We fill this gap through our validation and verification test suite that focuses on the offload directives available in OpenMP 4.5.

  2. Verification of DRAGON: the NXT tracking module

    International Nuclear Information System (INIS)

    Zkiek, A.; Marleau, G.

    2007-01-01

    The version of DRAGON-IST that has been verified for the calculation of the incremental cross sections associated with CANDU reactivity devices is version 3.04Bb that was released in 2001. Since then, various improvements were implemented in the code including the NXT: module that can track assemblies of clusters in 2-D and 3-D geometries. Here we will discuss the verification plan for the NXT: module of DRAGON, illustrate the verification procedure we selected and present our verification results. (author)

  3. The NASA Commercial Crew Program (CCP) Mission Assurance Process

    Science.gov (United States)

    Canfield, Amy

    2016-01-01

    In 2010, NASA established the Commercial Crew Program in order to provide human access to the International Space Station and low earth orbit via the commercial (non-governmental) sector. A particular challenge to NASA has been how to determine the commercial providers transportation system complies with Programmatic safety requirements. The process used in this determination is the Safety Technical Review Board which reviews and approves provider submitted Hazard Reports. One significant product of the review is a set of hazard control verifications. In past NASA programs, 100 percent of these safety critical verifications were typically confirmed by NASA. The traditional Safety and Mission Assurance (SMA) model does not support the nature of the Commercial Crew Program. To that end, NASA SMA is implementing a Risk Based Assurance (RBA) process to determine which hazard control verifications require NASA authentication. Additionally, a Shared Assurance Model is also being developed to efficiently use the available resources to execute the verifications. This paper will describe the evolution of the CCP Mission Assurance process from the beginning of the Program to its current incarnation. Topics to be covered include a short history of the CCP; the development of the Programmatic mission assurance requirements; the current safety review process; a description of the RBA process and its products and ending with a description of the Shared Assurance Model.

  4. Technical challenges for dismantlement verification

    International Nuclear Information System (INIS)

    Olinger, C.T.; Stanbro, W.D.; Johnston, R.G.; Nakhleh, C.W.; Dreicer, J.S.

    1997-01-01

    In preparation for future nuclear arms reduction treaties, including any potential successor treaties to START I and II, the authors have been examining possible methods for bilateral warhead dismantlement verification. Warhead dismantlement verification raises significant challenges in the political, legal, and technical arenas. This discussion will focus on the technical issues raised by warhead arms controls. Technical complications arise from several sources. These will be discussed under the headings of warhead authentication, chain-of-custody, dismantlement verification, non-nuclear component tracking, component monitoring, and irreversibility. The authors will discuss possible technical options to address these challenges as applied to a generic dismantlement and disposition process, in the process identifying limitations and vulnerabilities. They expect that these considerations will play a large role in any future arms reduction effort and, therefore, should be addressed in a timely fashion

  5. Safety Verification for Probabilistic Hybrid Systems

    DEFF Research Database (Denmark)

    Zhang, Lijun; She, Zhikun; Ratschan, Stefan

    2010-01-01

    The interplay of random phenomena and continuous real-time control deserves increased attention for instance in wireless sensing and control applications. Safety verification for such systems thus needs to consider probabilistic variations of systems with hybrid dynamics. In safety verification o...... on a number of case studies, tackled using a prototypical implementation....

  6. Feasibility of biochemical verification in a web-based smoking cessation study.

    Science.gov (United States)

    Cha, Sarah; Ganz, Ollie; Cohn, Amy M; Ehlke, Sarah J; Graham, Amanda L

    2017-10-01

    Cogent arguments have been made against the need for biochemical verification in population-based studies with low-demand characteristics. Despite this fact, studies involving digital interventions (low-demand) are often required in peer review to report biochemically verified abstinence. To address this discrepancy, we examined the feasibility and costs of biochemical verification in a web-based study conducted with a national sample. Participants were 600U.S. adult current smokers who registered on a web-based smoking cessation program and completed surveys at baseline and 3months. Saliva sampling kits were sent to participants who reported 7-day abstinence at 3months, and analyzed for cotinine. The response rate at 3-months was 41.2% (n=247): 93 participants reported 7-day abstinence (38%) and were mailed a saliva kit (71% returned). The discordance rate was 36.4%. Participants with discordant responses were more likely to report 3-month use of nicotine replacement therapy or e-cigarettes than those with concordant responses (79.2% vs. 45.2%, p=0.007). The total cost of saliva sampling was $8280 ($125/sample). Biochemical verification was both time- and cost-intensive, and yielded a relatively small number of samples due to low response rates and use of other nicotine products during the follow-up period. There was a high rate of discordance of self-reported abstinence and saliva testing. Costs for data collection may be prohibitive for studies with large sample sizes or limited budgets. Our findings echo previous statements that biochemical verification is not necessary in population-based studies, and add evidence specific to technology-based studies. Copyright © 2017 Elsevier Ltd. All rights reserved.

  7. H–J–B Equations of Optimal Consumption-Investment and Verification Theorems

    Energy Technology Data Exchange (ETDEWEB)

    Nagai, Hideo, E-mail: nagaih@kansai-u.ac.jp [Kansai University, Department of Mathematics, Faculty of Engineering Science (Japan)

    2015-04-15

    We consider a consumption-investment problem on infinite time horizon maximizing discounted expected HARA utility for a general incomplete market model. Based on dynamic programming approach we derive the relevant H–J–B equation and study the existence and uniqueness of the solution to the nonlinear partial differential equation. By using the smooth solution we construct the optimal consumption rate and portfolio strategy and then prove the verification theorems under certain general settings.

  8. H–J–B Equations of Optimal Consumption-Investment and Verification Theorems

    International Nuclear Information System (INIS)

    Nagai, Hideo

    2015-01-01

    We consider a consumption-investment problem on infinite time horizon maximizing discounted expected HARA utility for a general incomplete market model. Based on dynamic programming approach we derive the relevant H–J–B equation and study the existence and uniqueness of the solution to the nonlinear partial differential equation. By using the smooth solution we construct the optimal consumption rate and portfolio strategy and then prove the verification theorems under certain general settings

  9. SSN Verification Service

    Data.gov (United States)

    Social Security Administration — The SSN Verification Service is used by Java applications to execute the GUVERF02 service using the WebSphere/CICS Interface. It accepts several input data fields...

  10. Selection of 3013 containers for field surveillance: LA-14310, Revision 1

    International Nuclear Information System (INIS)

    Peppers, Larry; Kelly, Elizabeth; McClard, James; Friday, Gary; Venetz, Theodore; Stakebake, Jerry

    2009-01-01

    This document is the fifth in a series of reports that document the binning, statistical sampling, and sample selection of 3013 containers for field surveillance. 1,2,3,39 Revisions to binning assignments documented in this report are primarily a result of new prompt gamma data. This report also documents changes to the random sample specification resulting from these binning changes and identifies and provides the rationale for the engineering judgment sample items for Fiscal Year (FY) 2008 and 2009. This revision also updates the changes to the previous surveillance sample resulting from changes to the order that specific containers undergo surveillance. This report will continue to be reviewed regularly and revised as needed to meet the requirements of the surveillance program.

  11. Enhanced Verification Test Suite for Physics Simulation Codes

    Energy Technology Data Exchange (ETDEWEB)

    Kamm, J R; Brock, J S; Brandon, S T; Cotrell, D L; Johnson, B; Knupp, P; Rider, W; Trucano, T; Weirs, V G

    2008-10-10

    This document discusses problems with which to augment, in quantity and in quality, the existing tri-laboratory suite of verification problems used by Los Alamos National Laboratory (LANL), Lawrence Livermore National Laboratory (LLNL), and Sandia National Laboratories (SNL). The purpose of verification analysis is demonstrate whether the numerical results of the discretization algorithms in physics and engineering simulation codes provide correct solutions of the corresponding continuum equations. The key points of this document are: (1) Verification deals with mathematical correctness of the numerical algorithms in a code, while validation deals with physical correctness of a simulation in a regime of interest. This document is about verification. (2) The current seven-problem Tri-Laboratory Verification Test Suite, which has been used for approximately five years at the DOE WP laboratories, is limited. (3) Both the methodology for and technology used in verification analysis have evolved and been improved since the original test suite was proposed. (4) The proposed test problems are in three basic areas: (a) Hydrodynamics; (b) Transport processes; and (c) Dynamic strength-of-materials. (5) For several of the proposed problems we provide a 'strong sense verification benchmark', consisting of (i) a clear mathematical statement of the problem with sufficient information to run a computer simulation, (ii) an explanation of how the code result and benchmark solution are to be evaluated, and (iii) a description of the acceptance criterion for simulation code results. (6) It is proposed that the set of verification test problems with which any particular code be evaluated include some of the problems described in this document. Analysis of the proposed verification test problems constitutes part of a necessary--but not sufficient--step that builds confidence in physics and engineering simulation codes. More complicated test cases, including physics models of

  12. Verification of dosimetry planning in brachytherapy in format Dicom and EUD calculation of Risk in bodies

    International Nuclear Information System (INIS)

    Garcia Hernandez, M. J.; Sendon del Rio, J. R.; Ayala Lazaro, R.; Jimenez Rojas, M. R.; Gomez Cores, S.; Polo Cezon, R.; Lopez Bote, M. A.

    2013-01-01

    This work Describes a program that automates the verification of the schedules in brachytherapy (configuration and dosimetric treatment parameters) for sources of Ir-192 (mHDR v2) and Co-60 (Co0.A86) from the plan exported in DICOM format data. (Author)

  13. Lessons Learned From Microkernel Verification — Specification is the New Bottleneck

    Directory of Open Access Journals (Sweden)

    Thorsten Bormer

    2012-11-01

    Full Text Available Software verification tools have become a lot more powerful in recent years. Even verification of large, complex systems is feasible, as demonstrated in the L4.verified and Verisoft XT projects. Still, functional verification of large software systems is rare – for reasons beyond the large scale of verification effort needed due to the size alone. In this paper we report on lessons learned for verification of large software systems based on the experience gained in microkernel verification in the Verisoft XT project. We discuss a number of issues that impede widespread introduction of formal verification in the software life-cycle process.

  14. Advancing Disarmament Verification Tools: A Task for Europe?

    International Nuclear Information System (INIS)

    Göttsche, Malte; Kütt, Moritz; Neuneck, Götz; Niemeyer, Irmgard

    2015-01-01

    A number of scientific-technical activities have been carried out to establish more robust and irreversible disarmament verification schemes. Regardless of the actual path towards deeper reductions in nuclear arsenals or their total elimination in the future, disarmament verification will require new verification procedures and techniques. This paper discusses the information that would be required as a basis for building confidence in disarmament, how it could be principally verified and the role Europe could play. Various ongoing activities are presented that could be brought together to produce a more intensified research and development environment in Europe. The paper argues that if ‘effective multilateralism’ is the main goal of the European Union’s (EU) disarmament policy, EU efforts should be combined and strengthened to create a coordinated multilateral disarmament verification capacity in the EU and other European countries. The paper concludes with several recommendations that would have a significant impact on future developments. Among other things, the paper proposes a one-year review process that should include all relevant European actors. In the long run, an EU Centre for Disarmament Verification could be envisaged to optimize verification needs, technologies and procedures.

  15. The verification of DRAGON: progress and lessons learned

    International Nuclear Information System (INIS)

    Marleau, G.

    2002-01-01

    The general requirements for the verification of the legacy code DRAGON are somewhat different from those used for new codes. For example, the absence of a design manual for DRAGON makes it difficult to confirm that the each part of the code performs as required since these requirements are not explicitly spelled out for most of the DRAGON modules. In fact, this conformance of the code can only be assessed, in most cases, by making sure that the contents of the DRAGON data structures, which correspond to the output generated by a module of the code, contains the adequate information. It is also possible in some cases to use the self-verification options in DRAGON to perform additional verification or to evaluate, using an independent software, the performance of specific functions in the code. Here, we will describe the global verification process that was considered in order to bring DRAGON to an industry standard tool-set (IST) status. We will also discuss some of the lessons we learned in performing this verification and present some of the modification to DRAGON that were implemented as a consequence of this verification. (author)

  16. Simulation Environment Based on the Universal Verification Methodology

    CERN Document Server

    AUTHOR|(SzGeCERN)697338

    2017-01-01

    Universal Verification Methodology (UVM) is a standardized approach of verifying integrated circuit designs, targeting a Coverage-Driven Verification (CDV). It combines automatic test generation, self-checking testbenches, and coverage metrics to indicate progress in the design verification. The flow of the CDV differs from the traditional directed-testing approach. With the CDV, a testbench developer, by setting the verification goals, starts with an structured plan. Those goals are targeted further by a developed testbench, which generates legal stimuli and sends them to a device under test (DUT). The progress is measured by coverage monitors added to the simulation environment. In this way, the non-exercised functionality can be identified. Moreover, the additional scoreboards indicate undesired DUT behaviour. Such verification environments were developed for three recent ASIC and FPGA projects which have successfully implemented the new work-flow: (1) the CLICpix2 65 nm CMOS hybrid pixel readout ASIC desi...

  17. Argonne Code Center: compilation of program abstracts

    Energy Technology Data Exchange (ETDEWEB)

    Butler, M.K.; DeBruler, M.; Edwards, H.S.; Harrison, C. Jr.; Hughes, C.E.; Jorgensen, R.; Legan, M.; Menozzi, T.; Ranzini, L.; Strecok, A.J.

    1977-08-01

    This publication is the eleventh supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the complete document ANL-7411 are as follows: preface, history and acknowledgements, abstract format, recommended program package contents, program classification guide and thesaurus, and the abstract collection. (RWR)

  18. Argonne Code Center: compilation of program abstracts

    International Nuclear Information System (INIS)

    Butler, M.K.; DeBruler, M.; Edwards, H.S.; Harrison, C. Jr.; Hughes, C.E.; Jorgensen, R.; Legan, M.; Menozzi, T.; Ranzini, L.; Strecok, A.J.

    1977-08-01

    This publication is the eleventh supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the complete document ANL-7411 are as follows: preface, history and acknowledgements, abstract format, recommended program package contents, program classification guide and thesaurus, and the abstract collection

  19. Hierarchical Representation Learning for Kinship Verification.

    Science.gov (United States)

    Kohli, Naman; Vatsa, Mayank; Singh, Richa; Noore, Afzel; Majumdar, Angshul

    2017-01-01

    Kinship verification has a number of applications such as organizing large collections of images and recognizing resemblances among humans. In this paper, first, a human study is conducted to understand the capabilities of human mind and to identify the discriminatory areas of a face that facilitate kinship-cues. The visual stimuli presented to the participants determine their ability to recognize kin relationship using the whole face as well as specific facial regions. The effect of participant gender and age and kin-relation pair of the stimulus is analyzed using quantitative measures such as accuracy, discriminability index d' , and perceptual information entropy. Utilizing the information obtained from the human study, a hierarchical kinship verification via representation learning (KVRL) framework is utilized to learn the representation of different face regions in an unsupervised manner. We propose a novel approach for feature representation termed as filtered contractive deep belief networks (fcDBN). The proposed feature representation encodes relational information present in images using filters and contractive regularization penalty. A compact representation of facial images of kin is extracted as an output from the learned model and a multi-layer neural network is utilized to verify the kin accurately. A new WVU kinship database is created, which consists of multiple images per subject to facilitate kinship verification. The results show that the proposed deep learning framework (KVRL-fcDBN) yields the state-of-the-art kinship verification accuracy on the WVU kinship database and on four existing benchmark data sets. Furthermore, kinship information is used as a soft biometric modality to boost the performance of face verification via product of likelihood ratio and support vector machine based approaches. Using the proposed KVRL-fcDBN framework, an improvement of over 20% is observed in the performance of face verification.

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

    Science.gov (United States)

    2001-06-25

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