WorldWideScience

Sample records for psa advisory body

  1. Clinical impact of body mass index on prostate biopsy in patients with intermediate PSA levels

    International Nuclear Information System (INIS)

    Sekita, Nobuyuki; Chin, Kensei; Fujimura, Masaaki; Mikami, Kazuo; Suzuki, Hiroyoshi; Kamijima, Shuichi

    2008-01-01

    From April 2005 to September 2007, 480 patients underwent transrectal prostate biopsy at our institution. The clinical data including age, serum prostate specific antigen (PSA) level, prostate volume and body mass index (BMI) were obtained, and the cancer detection rates and pathological findings were evaluated in 305 cases with a PSA concentration of 4.0 to 10.0 ng/ml. Prostate volume was calculated from magnetic resonance imaging (MRI) findings. The 305 patients were categorized according to their BMI into three groups (normal, less than 22 kg/m 2 ; overweight, 22-25 kg/m 2 ; and obese, more than 25 kg/m 2 ). Cancer detection rates and histopathologic findings were compared between the groups. Multivariate logistic regression analysis was also performed. Prostate cancer was detected in 127 patients. No significant differences in BMI were observed between biopsy-positive and biopsy-negative cases (p=0.965), and the detection rates of prostate cancer observed in the three groups were not significantly different. There was a significant association between BMI and the findings of high Gleason score (more than 4+3) (p=0.048). BMI was not a contributory factor of prostate cancer detection for cases with intermediate PSA levels; however, patients with high BMI may have high-grade malignancy features. (author)

  2. COMPOSITION OF STAFF REVIEW ADVISORY BODIES - 2001

    CERN Multimedia

    Seamus Hegarty / HR; Tel. 74128

    2001-01-01

    For the present staff review, the advisory bodies set up to prepare recommendations are composed as follows : Senior Staff Advancement Committee (SSAC) David O. Williams/it (Convener) Cristoforo Benvenuti/est David Plane/ep Technical Engineers & Administrative Careers Committee (TEACC) Sverre Jarp/it (Chairman) Flemming Pedersen/ps Robin Lauckner/sl Christian Roche/ett Lars Leistam/est Dietrich Schinzel/ep Long-term contract Boards (LTCBs) LTCB 1 (Categories 2 & 5a) Tiziano Camporesi/ep [Convener] - Florence Ranjard/ep [Alternate] Jacques Gruber/ps - Peter Sievers/lhc [Alternate] Thomas Pettersson/est - Michel Mayoud/est [Alternate] Sue Foffano/as - Thierry Lagrange/spl [Alternate] Werner Zapf/hr (Secretary) LTCB 2 (Categories 3, 4, 5b & 5c) Véronique Paris/sl [Convener] - Fabien Perriollat/ps [Alternate] Mats Wilhelmsson/st - Véronique Fassnacht/tis [Alternate] Lucie Linssen/ep - Alfredo Placci/ep [Alternate] Patrick Geeraert/fi - John Cuthb...

  3. Composition of Staff Review Advisory Bodies - 2003

    CERN Multimedia

    2003-01-01

    For the present staff review, the advisory bodies set up to prepare recommendations are composed as follows : Senior Staff Advancement Committee (SSAC) David Plane/EP [Convener] Enrico Chiaveri/AB Peter Schmid/EP Technical Engineers & Administrative Careers Committee (TEACC) Robin Lauckner/AB [Chairman]Marcel Mottier/EST Michael Letheren/EP Louis Walckiers/AT Lucie Linssen/EP Mats Wilhelmsson/ST Long-term contract Boards (LTCBs) LTCB 1 (Categories 2 & 5a) Tiziano Camporesi/EP [Convener]Florence Ranjard/EP [Alternate] Roger Bailey/ABPeter Sievers/AT " " Doris Forkel-Wirth/TISPierre Ninin/ST " " Rob Rayson/HRMaarten Wilbers/DSU " " Seamus Hegarty/HR [Secretary] LTCB 2 (Categories 3, 4, 5b & 5c) Véronique Paris/AB [Convener]Fabien Perriollat/AB [Alternate] Christian Lasseur/ESTRamon Folch/EST " " Lucie Linssen/EP Alfredo Placci/EP " " Mats Møller/ASLaszlo Abel/SPL " " Seamus Hegarty/HR [Secretary] Human Resources Division Tel. 74128

  4. COMPOSITION OF STAFF REVIEW ADVISORY BODIES - 2002

    CERN Multimedia

    Human Resources Division

    2002-01-01

    For the present staff review, the advisory bodies set up to prepare recommendations are composed as follows: Senior Staff Advancement Committee (SSAC) Cristoforo BENVENUTI/EST [Convener] David PLANE/EP Peter SCHMID/EP Technical Engineers & Administrative Careers Committee (TEACC) Robin LAUCKNER/SL [Chairman] Flemming PEDERSEN/PS Lucie LINSSEN/EP Dietrich SCHINZEL/EP Marcel MOTTIER/EST Louis WALCKIERS/LHC Long-term contract Boards (LTCBs) (Categories 2 & 5a) Tiziano CAMPORESI/EP [Convener] Florence RANJARD/EP [Alternate] Jacques GRUBER/PS [until 30.6.2002] Roger BAILEY/SL [from 1.7. 2002] Peter SIEVERS/LHC [Alternate] Doris FORKEL-WIRTH/TIS Pierre NININ/ST [Alternate] Sue FOFFANO/AS Maarten WILBERS/DSU [Alternate] Werner ZAPF/HR[Secretary] LTCB 2 Categories 3, 4, 5b & 5c) Véronique PARIS/SL [Convener] Fabien PERRIOLLAT/PS [Alternate] Mats WILHELMSSON/ST Charles NUTTALL/TIS [Alternate] Lucie LINSSEN/EP Alfredo PLACCI/EP [Alternate] Patrick GEERAER...

  5. 18 CFR 39.13 - Regional Advisory Bodies.

    Science.gov (United States)

    2010-04-01

    ... THE ELECTRIC RELIABILITY ORGANIZATION; AND PROCEDURES FOR THE ESTABLISHMENT, APPROVAL, AND ENFORCEMENT OF ELECTRIC RELIABILITY STANDARDS § 39.13 Regional Advisory Bodies. (a) The Commission will establish... same region; (2) Whether a Reliability Standard proposed to apply within the region is just, reasonable...

  6. Improving PSA quality of KSNP PSA model

    International Nuclear Information System (INIS)

    Yang, Joon Eon; Ha, Jae Joo

    2004-01-01

    In the RIR (Risk-informed Regulation), PSA (Probabilistic Safety Assessment) plays a major role because it provides overall risk insights for the regulatory body and utility. Therefore, the scope, the level of details and the technical adequacy of PSA, i.e. the quality of PSA is to be ensured for the successful RIR. To improve the quality of Korean PSA, we evaluate the quality of the KSNP (Korean Standard Nuclear Power Plant) internal full-power PSA model based on the 'ASME PRA Standard' and the 'NEI PRA Peer Review Process Guidance.' As a working group, PSA experts of the regulatory body and industry also participated in the evaluation process. It is finally judged that the overall quality of the KSNP PSA is between the ASME Standard Capability Category I and II. We also derive some items to be improved for upgrading the quality of the PSA up to the ASME Standard Capability Category II. In this paper, we show the result of quality evaluation, and the activities to improve the quality of the KSNP PSA model

  7. Quality PSA for PSA applications

    International Nuclear Information System (INIS)

    Carska, K.; Rybar, J.

    2012-03-01

    The safety guideline defines with more precision Nuclear Regulatory Authority of the Slovak Republic requirements of the quality of probabilistic safety assessment (PSA) for PSA application. Term of quality of PSA is explained in detail. Procedure for determining the quality of PSA is provided. The categorization of PSA study according the quality of PSA is suggested. A comprehensive list of PSA applications for nuclear facilities is provided. What technical features of a PSA should be satisfied to support the PSA applications of interest is stated. (authors)

  8. Prostate-Specific Antigen (PSA) Test

    Science.gov (United States)

    ... Cancer Prostate Cancer Screening Research Prostate-Specific Antigen (PSA) Test On This Page What is the PSA ... parts of the body before being detected. The PSA test may give false-positive or false-negative ...

  9. Living PSA

    International Nuclear Information System (INIS)

    Evans, M.G.K.

    1997-01-01

    The aim of this presentation is to gain an understanding of the requirements for a PSA to be considered a Living PSA. The presentation is divided into the following topics: Definition; Planning/Documentation; Task Performance; Maintenance; Management. 4 figs

  10. Status of the PSA use in the Czech regulatory process

    International Nuclear Information System (INIS)

    Dusek, J.

    1994-01-01

    A review of previous probabilistic safety assessment (PSA) activities initiated by regulatory body and preparation of the preliminary PSA study and final PSA study (released in January 1994) for the nuclear power plant Dukovany with WWER-440 type 213 reactor is described. A brief information about the NPP Temelin (with WWER-1000) PSA Study, shutdown and PSA risk monitor current activities for the NPP Dukovany, next PSA activities in 1994 and about planned PSA activities in future is attached. (author). 21 refs

  11. PSA methodology

    Energy Technology Data Exchange (ETDEWEB)

    Magne, L

    1997-12-31

    The purpose of this text is first to ask a certain number of questions on the methods related to PSAs. Notably we will explore the positioning of the French methodological approach - as applied in the EPS 1300{sup 1} and EPS 900{sup 2} PSAs - compared to other approaches (Part One). This reflection leads to more general reflection: what contents, for what PSA? This is why, in Part Two, we will try to offer a framework for definition of the criteria a PSA should satisfy to meet the clearly identified needs. Finally, Part Three will quickly summarize the questions approached in the first two parts, as an introduction to the debate. 15 refs.

  12. PSA methodology

    International Nuclear Information System (INIS)

    Magne, L.

    1996-01-01

    The purpose of this text is first to ask a certain number of questions on the methods related to PSAs. Notably we will explore the positioning of the French methodological approach - as applied in the EPS 1300 1 and EPS 900 2 PSAs - compared to other approaches (Part One). This reflection leads to more general reflection: what contents, for what PSA? This is why, in Part Two, we will try to offer a framework for definition of the criteria a PSA should satisfy to meet the clearly identified needs. Finally, Part Three will quickly summarize the questions approached in the first two parts, as an introduction to the debate. 15 refs

  13. PSA applications

    Energy Technology Data Exchange (ETDEWEB)

    Dubreuil Chambardel, A

    1997-12-31

    The IAEA now defines three types of PSA applications: Validation of design and of operation procedures; optimization of plant operation; and regulatory applications. The applications of PSA are manifold: only a few are dealt with here (precursor analysis is dealt with in session 3, topic 4). For each of them, we will do the utmost to demonstrate the main difficulties encountered, EDF`s viewpoint on the matter, and the points remaining to be solved. In what follows, unless explicitly stated otherwise, we have made every effort to represent the different applications as they are practiced by all concerned in the international community, and to describe the inherent difficulties the international community has encountered with these applications with all objectivity. It goes without saying that the comments below are simply those of the ESF department, and are submitted here for discussion by the experts. 13 refs.

  14. PSA applications

    International Nuclear Information System (INIS)

    Dubreuil Chambardel, A.

    1996-01-01

    The IAEA now defines three types of PSA applications: Validation of design and of operation procedures; optimization of plant operation; and regulatory applications. The applications of PSA are manifold: only a few are dealt with here (precursor analysis is dealt with in session 3, topic 4). For each of them, we will do the utmost to demonstrate the main difficulties encountered, EDF's viewpoint on the matter, and the points remaining to be solved. In what follows, unless explicitly stated otherwise, we have made every effort to represent the different applications as they are practiced by all concerned in the international community, and to describe the inherent difficulties the international community has encountered with these applications with all objectivity. It goes without saying that the comments below are simply those of the ESF department, and are submitted here for discussion by the experts. 13 refs

  15. Applicability of living PSA in NPP modernization

    International Nuclear Information System (INIS)

    Himanen, R.

    1999-01-01

    Recently the utility Teollisuuden Voima Oy (TVO) has modernized the Olkiluoto 1 and 2 nuclear units and increased the net electric power by 18 per cent. Level 2 PSA was performed during the modernization project and the living level 1 PSA was used to support the design of the plant modifications. The plant specific living PSA model was a powerful tool when evaluating modernization alternatives. Successive support of safety management with the PSA model requires, that both the utility and the Regulatory Body understand capability and limitations of the model in details. TVO has prepared an internal procedure that presents in detail the practices and responsibilities concerning living PSA. The procedure is based on general guidelines and requirements on probabilistic safety analysis of nuclear power plants in Finland, released by the Regulatory Body. Living PSA requires that also the procedure for the use of living PSA is living. The recently published USNRC Regulatory Guides on PSA will be taken into account in the next version of the TVO PSA procedure. The PSA Peer Review Certification Process is one way to evaluate the quality of PSA in general, but also to detect the weaknesses of the PSA. However, the Certification Process cover only limited scope of PSA omitting e.g. all other external events except internal floods. This paper gives an overview on the scope of living PSA for Olkiluoto 1 and 2, and presents some examples on the real use of PSA concerning the modernization of the plant. Definition of quantitative dependability requirements for renovated systems is possible, but on the other hand, proving of these targets is in some cases extremely difficult, because of lacking dependability data. The problems are mainly concerned in systems with of programmable logic control. (au)

  16. Clinical and Patient-reported Outcomes in Patients with Psoriatic Arthritis (PsA) by Body Surface Area Affected by Psoriasis: Results from the Corrona PsA/Spondyloarthritis Registry.

    Science.gov (United States)

    Mease, Philip J; Karki, Chitra; Palmer, Jacqueline B; Etzel, Carol J; Kavanaugh, Arthur; Ritchlin, Christopher T; Malley, Wendi; Herrera, Vivian; Tran, Melody; Greenberg, Jeffrey D

    2017-08-01

    Psoriatic arthritis (PsA) is commonly comorbid with psoriasis; the extent of skin lesions is a major contributor to psoriatic disease severity/burden. We evaluated whether extent of skin involvement with psoriasis [body surface area (BSA) > 3% vs ≤ 3%] affects overall clinical and patient-reported outcomes (PRO) in patients with PsA. Using the Corrona PsA/Spondyloarthritis Registry, patient characteristics, disease activity, and PRO at registry enrollment were assessed for patients with PsA aged ≥ 18 years with BSA > 3% versus ≤ 3%. Regression models were used to evaluate associations of BSA level with outcome [modified minimal disease activity (MDA), Health Assessment Questionnaire (HAQ) score, patient-reported pain and fatigue, and the Work Productivity and Activity Impairment questionnaire score]. Adjustments were made for age, sex, race, body mass index, disease duration, and history of biologics, disease-modifying antirheumatic drug, and prednisone use. This analysis included 1240 patients with PsA with known BSA level (n = 451, BSA > 3%; n = 789, BSA ≤ 3%). After adjusting for potential confounding variables, patients with BSA > 3% versus ≤ 3% had greater patient-reported pain and fatigue and higher HAQ scores (p = 2.33 × 10 -8 , p = 0.002, and p = 1.21 × 10 -7 , respectively), were 1.7× more likely not to be in modified MDA (95% CI 1.21-2.41, p = 0.002), and were 2.1× more likely to have overall work impairment (1.37-3.21, p = 0.0001). These Corrona Registry data show that substantial skin involvement (BSA > 3%) is associated with greater PsA disease burden, underscoring the importance of assessing and effectively managing psoriasis in patients with PsA because this may be a contributing factor in PsA severity.

  17. Putting PSA to work

    International Nuclear Information System (INIS)

    Gubler, R.; Gomez-Cobo, A.

    1998-01-01

    The IAEA has, during the last three years, been working intensively on PSA applications. The draft TECDOC prepared during these activities, ''PSA Applications'' is summarized in this paper. Actual events at nuclear facilities provide an important basis to compare PSAs with reality. PSA based operational event analysis therefore can be used to evaluate the importance of operational events from a risk perspective but also can contribute to validating and enhancing PSAs and to continuously check whether or not the PSA models are adequate, appropriate and complete. The work of the IAEA in this area is therefore summarized as well. In a companion paper, titled ''Towards a credible PSA fit for applications'', two specific aspects regarding the quality of the PSA to be used are discussed in detail, namely the Living PSA concept, which ensures that the PSA reflects actual design and operational features and Quality Assurance for PSA. (author)

  18. Inclusion in political and public life: the experiences of people with intellectual disability on government disability advisory bodies in Australia.

    Science.gov (United States)

    Frawley, Patsie; Bigby, Christine

    2011-03-01

    Civil and political participation lies at the core of citizenship. Increasingly, people with intellectual disability are members of disability advisory bodies. This study investigated the political orientations of advisory body members with intellectual disability, their participatory experiences, and the types of support they received. The 9 people with intellectual disability who in 2005 were members of disability advisory bodies at a state, national, and Victorian local government level were interviewed, together with 12 other members or secretariat staff of these bodies. Observations were also conducted of advisory body meetings. The political perspective of members with intellectual disability varied, but all had a background in self-advocacy. They found the work hard but rewarding and encountered both practical and intangible obstacles to participation. Members received varying types of practical support, but a supportive collegial milieu was characteristic among members who felt most confident about their participation. The milieu, structures, and processes of advisory bodies must all be adjusted to accommodate people with intellectual disability if they are to participate meaningfully.

  19. PSA Review Handbook

    International Nuclear Information System (INIS)

    Hallman, Anders; Nyman, Ralph; Knochenhauer, Michael

    2004-05-01

    The Swedish Nuclear Power Inspectorate (SKI) expresses requirements on the performance of PSAs as well as on PSA activities in general in the the regulatory document 'Regulations Concerning Safety in Certain Nuclear Facilities', SKlFS 1998:1. The follow-up of these activities is part of the inspection tasks of the SKI. In view or this, there is a need for documented guidelines on now to perform these inspections and reviews. The SKI PSA Review Handbook is intended to be a support in the SKI inspection and control of the PSA activities or the licensees. These PSA activities include both the organisation and working procedures of the licensee, the layout and contents of the PSA, and its areas of application. Using the regulation SKIFS 1998:1 as a starting point, the review handbook presents important aspects to be considered when judging whether a licensee fulfils the requirements on PSA activities, including the performance of PSA:s or PSA applications. The handbook shall also be a guidance for the review of PSA:s. However, the intention of the PSA Review Handbook is not to be a handbook for how a PSA is performed. The PSA Review Handbook is applicable to all types or initiating events and all operating conditions, and has been structured in a way, which stresses the integrated characteristics of PSA in the creation of the risk picture of a plant. The PSA Review Handbook has been based on the requirements for PSA of nuclear power plants, as this is the most extensive application. However, the relevant parts of it are also applicable when analysing other nuclear installations. The PSA Review Handbook is published as a research report as its contents are judged to be of general interest, and the SKI welcomes comments to the handbook. An update or the PSA Review Handbook may be required as experience with the use of the handbook is acquired and if general PSA requirements change

  20. National advisory bodies in the system of public governance in science and higher education: european practices

    Directory of Open Access Journals (Sweden)

    I. O. Degtyarova

    2015-12-01

    Full Text Available The article is focused on the analysis of organizational and legal conditions for the functioning of the highest advisory bodies in the fields of research and higher education, created at the state level at the central governing institutions in Ukraine and selected European countries. The article is aimed at the research of the model of formation and functioning of the national advisory bodies on research and higher education in Poland, Germany, and Czech Republic in the system of science management, based on the national legislation. The following national bodies are studied in the paper: National Council of Science and Higher Education of Poland, the Committee of Science Policy of Poland, the Council for Research, Development and Innovation of Czech Republic, National Council for Research, Innovation and Science Policy of Hungary, the German Research Council and others. It is proved that advisory bodies are an important element of the system of public governance, as well as actors in shaping of the national science and higher education policy. They are formed in a democratic way due to the principle of shared governance and mostly of institutional representation. The article considered selected aspects of the establishment of the National R&D Council of Ukraine, as stated in the Law of Ukraine «On Scientific and R&D Activity» comparing with the relevant European institutions. The analysis of the concept for the National Council for Science and Technologies (R&D of Ukraine along with the administrative and management risks could be considered while implementation of the Law of Ukraine «On Scientific and R&D Activity».

  1. Correlative study of SPECT bone scan, serum tPSA and fPSA/tPSA ratio and the pathological grade of prostate cancer with bone metastasis

    International Nuclear Information System (INIS)

    Xu Haiqing; Duan Jun

    2011-01-01

    Objective: To study the rules and characteristics of SPECT bone scan, serum TPSA, fPSA/tPSA ratio and the pathological grade of prostate cancer with bone metastasis. Methods: Nuclear medicine SPECT bone scan as the gold standard, retrospective analysis of the in vitro radioimmunoassay in 107 patients with prostate cancer serum PSA (prostate specific antigen) levels, serum fPSA/tPSA ratio and whole body bone imaging studies and pathological classification. Results: 107 patients with prostate cancer : 49 patients had bone metastases, accounting for 45.8% (49/107), in which groups of different pathological comparison between the incidence of bone metastasis significantly, the lower the degree of differentiation, the more the incidence of bone metastases high; with elevated levels of tPSA, the incidence of bone metastasis increased significantly; serum tPSA 4 - 40 ng/ml, the use of fPSA/tPSA ratio may improve the diagnostic specificity of prostate cancer. Conclusion: Patients with bone metastases of prostate cancer incidence and degree of differentiation of prostate cancer, serum PSA levels and fPSA/tPSA ratio of a certain relationship. The lower degree of differentiation,the higher the incidence of bone metastasis. (authors)

  2. Regulatory requirements on PSA level 2: Review, aspects and applications

    International Nuclear Information System (INIS)

    Husarcek, J.

    2003-01-01

    The general requirements concerning utility obligations, probabilistic safety criteria (CDF should not exceed 1.0E-4/reactor year and LERF should not exceed 1.0E-5/reactor year), documentation and results, living PSA requirements and major steps in level 2 PSA are presented. PSA developments in Slovakia, collection and assembly of information, plant damage states, containment performance and failure modes, severe accident progression analyses, containment failure modes and source terms as a part of performed level 2 PSA are discussed. The PSA applications in design and operation evaluation, support to plant upgrade and modifications are also described. At the end, the following conclusion is made: more extensive PSA application needs to foster the exchange of experience and communication between PSA specialists, non-PSA engineers, designers, and the regulatory body staff responsible for safety assessment, inspection and enforcement

  3. Comparative evaluation of PSA-Density, percent free PSA and total PSA

    OpenAIRE

    Ströbel, Greta

    2010-01-01

    BACKGROUND The objective of this study was to evaluate the prostate specific antigen (PSA) density (PSAD) (the quotient of PSA and prostate volume) compared with the percent free PSA (%fPSA) and total PSA (tPSA) in different total PSA (tPSA) ranges from 2 ng/mL to 20 ng/mL. Possible cut-off levels depending on the tPSA should be established. METHODS In total, 1809 men with no pretreatment of the prostate were enrolled between 1996 and 2004. Total and free PSA were measured with t...

  4. The process of setting micronutrient recommendations: a cross-European comparison of nutrition-related scientific advisory bodies

    NARCIS (Netherlands)

    Timotijevic, L.; Barnett, J.; Brown, K.; Shepherd, R.; Fernandez-Celemin, L.; Domolki, L.; Ruprich, J.; Dhonukshe-Rutten, R.A.M.; Sonne, A.M.; Hermoso, M.; Koletzko, B.; Frost-Andersen, L.; Timmer, A.; Raats, M.M.

    2011-01-01

    Objective - To examine the workings of the nutrition-related scientific advisory bodies in Europe, paying particular attention to the internal and external contexts within which they operate. Design - Desk research based on two data collection strategies: a questionnaire completed by key informants

  5. PSA, PSA derivatives, proPSA and prostate health index in the diagnosis of prostate cancer

    OpenAIRE

    Ayyıldız, Sema Nur; Ayyıldız, Ali

    2014-01-01

    Currently, prostate- specific antigen (PSA) is the most common oncological marker used for prostate cancer screening. However, high levels of PSA in benign prostatic hyperplasia and prostatitis decrease the specificity of PSA as a cancer marker. To increase the specificity of PSA, PSA derivatives and PSA kinetics have been used. However, these new techniques were not able to increase the diagnostic specificity for prostate cancer. Therefore, the search for new molecules and derivatives of PSA...

  6. Committee of the Regions: From Advisory Body to the Second Chamber of the European Parliament

    Directory of Open Access Journals (Sweden)

    Petr KANIOK

    2013-10-01

    Full Text Available The EU decision-making system is a unique combination of the power of the states and supranational institutions. The relationship between the institutions and the states allows us to establish several competing theoretical explanations while trying to describe and explain this mutual relationship. One of the most influential theoretical explanations is the institutionalism of rational choice and the associated principal – agent model. This article is based on the analysis of the youngest EU advisory body, the Committee of the Regions (CoR. The article examines the evolution of the relationship between principal (Member states and agent (CoR and the trend that can be observed in this process.

  7. Understanding PSA and its derivatives in prediction of tumor volume: Addressing health disparities in prostate cancer risk stratification.

    Science.gov (United States)

    Chinea, Felix M; Lyapichev, Kirill; Epstein, Jonathan I; Kwon, Deukwoo; Smith, Paul Taylor; Pollack, Alan; Cote, Richard J; Kryvenko, Oleksandr N

    2017-03-28

    To address health disparities in risk stratification of U.S. Hispanic/Latino men by characterizing influences of prostate weight, body mass index, and race/ethnicity on the correlation of PSA derivatives with Gleason score 6 (Grade Group 1) tumor volume in a diverse cohort. Using published PSA density and PSA mass density cutoff values, men with higher body mass indices and prostate weights were less likely to have a tumor volume PSA derivatives when predicting for tumor volume. In receiver operator characteristic analysis, area under the curve values for all PSA derivatives varied across race/ethnicity with lower optimal cutoff values for Hispanic/Latino (PSA=2.79, PSA density=0.06, PSA mass=0.37, PSA mass density=0.011) and Non-Hispanic Black (PSA=3.75, PSA density=0.07, PSA mass=0.46, PSA mass density=0.008) compared to Non-Hispanic White men (PSA=4.20, PSA density=0.11 PSA mass=0.53, PSA mass density=0.014). We retrospectively analyzed 589 patients with low-risk prostate cancer at radical prostatectomy. Pre-operative PSA, patient height, body weight, and prostate weight were used to calculate all PSA derivatives. Receiver operating characteristic curves were constructed for each PSA derivative per racial/ethnic group to establish optimal cutoff values predicting for tumor volume ≥0.5 cm3. Increasing prostate weight and body mass index negatively influence PSA derivatives for predicting tumor volume. PSA derivatives' ability to predict tumor volume varies significantly across race/ethnicity. Hispanic/Latino and Non-Hispanic Black men have lower optimal cutoff values for all PSA derivatives, which may impact risk assessment for prostate cancer.

  8. Whooping Cough PSA (:30)

    Centers for Disease Control (CDC) Podcasts

    This 30 second PSA encourages pregnant women to get the whooping cough vaccine, called Tdap, during the third trimester of each pregnancy in order to pass antibodies to their babies so they are born with protection against this serious disease.

  9. Seismic Level 2 PSA

    International Nuclear Information System (INIS)

    Dirksen, Gerben; Pellissetti, Manuel; Duncan-Whiteman, Paul

    2014-01-01

    For most external events, the calculation of the core damage frequency (CDF) in Level 1 PSA is sufficient to be able to show that the contribution of the event to the plant risk is negligible. However, it is not sufficient to compare the CDF due to the external event to the total plant CDF; instead the Level 1 PSA result for the event should be compared to the large early release frequency (LERF), or alternatively arguments should be given why the CDF from the external event will not contribute mostly to LERF. For seismic events in particular, it can often not be easily excluded that sequences leading to core damage would not also result in LERF. Since the confinement function is one of the most essential functions for Level 2 PSA, special care must be taken of the containment penetrations. For example systems with containment penetrations that are normally closed during operation or are designed to withstand more than the maximum containment pressure are normally screened out in the Level 2 PSA for the containment isolation function, however the possibility of LOCA in such systems due to an earthquake may nevertheless lead to containment bypass. Additionally, the functionality of passive features may be compromised in case of a beyond design earthquake. In the present paper, we present crucial ingredients of a methodology for a Level 2 seismic PSA. This methodology consists of the following steps: Extension of the seismic equipment list (SEL) to include Level 2 PSA relevant systems (e.g. containment isolation system, features for core melt stabilization, hydrogen mitigation systems), Determination of the systems within the existing SEL with increased demands in case of severe accidents, Determination of essential components for which a dedicated fragility analysis needs to be performed. (author)

  10. UV/EB curable psa's

    International Nuclear Information System (INIS)

    Glotfelter, C.A.

    1995-01-01

    The author describe both water-based and 100% solids UV/EB curable PSA's (Pressure Sensitive Adhesives) and their properties. A new acrylate monomer, ethoxylated nonyl phenol acrylate, has great utility in the formulation of water-based PSA's

  11. Tools for PSA reviews

    International Nuclear Information System (INIS)

    Linden, J. von

    1998-01-01

    It is desirable to have a uniform and competent procedure for the review of PSAs which are performed within the framework of the Periodic Safety Review of German Nuclear Power Plants. Guidelines for the review process should therefore be evaluated within task A. 1 of project SR 2096. The basis for this work is the experience and knowledge within GRS derived from PSA-related work and from several review projects as well as the German PSA Guide with its appendices. Furthermore, the review processes in the USA, Switzerland and Sweden and the Guidelines for the International Peer Review Service (IPERS Guidelines) were utilized. As a result, recommendations are given for the review process, with individual recommendations concerning the organization of the review, task allocation between the reviewers, interface problems, assessment criteria, the scope and depth of the review as well as the supporting documents. An additional result are checklists for the technical elements of the PSA, which are listed to facilicate the review work. It is not the intention of this report to work out complete review guidelines. Its aims is rather more to give recommondations and support for the review in addition to what can be derived from the existing documents that should be used for the review. The recommendations reflect the view of GRS and go beyond the statements given in the German PSA Guide (Leitfaden Probabilistische Sicherheitsanalyse /PSUe97/) in some points. (orig.) [de

  12. Binge Drinking PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    This PSA is based on the October, 2010 CDC Vital Signs report which indicates that drinking too much, including binge drinking, causes more than 79,000 deaths in the U.S. each year and is the third leading preventable cause of death.

  13. Introduction to PSA applications

    International Nuclear Information System (INIS)

    Evans, M.G.K.

    1997-01-01

    The aim of this presentation is to show how the PSA can be used to determine the risk impact of the various deterministic processes for plant design or operational changes, and the evaluation of off normal events that occurred at the plant. The presentation is divided into the following topics: Identification of issues; Tasks/element identification; Modelling changes; Data changes. 6 figs

  14. Guideline level-3 PSA

    International Nuclear Information System (INIS)

    Roelofsen, P.M.; Van der Steen, J.

    1993-09-01

    For several applications of radioactive materials calculations must be executed to determine the radiation risk for the population. A guideline for the risk calculation method of two main sources: nuclear power plants, and other intended and unintended activities with radioactive materials, is given. The standards, recommendations and regulations in this report concern mainly the analysis of the radiological (external) consequences of nuclear power plant accidents, classified as level-3 PSA (Probabilistic Safety Analysis). Level-3 PSA falls within the scales 5-7 of the International Nuclear Event Scale (INES). The standards, etc., focus on the risks for groups of people and the so-called maximum individual risk. In chapter two the standards and regulations are formulated for each part of level-3 PSA: the source term spectrum, atmospheric distribution and deposition, exposure to radiation doses and calculation of radiation doses, dose-response relationships, measures to reduce the effect of radiation doses, design basis accidents, and finally uncertainty analysis. In chapter four, modelled descriptions are given of the standards and regulations, which could or should be used in a calculation program in case of level-3 PSA. In chapter three the practical execution of a probabilistic consequences analysis, the collection of input data and the presentation of the results are dealt with. 2 figs., 14 tabs., 64 refs

  15. Babesiosis PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2012-04-25

    This 60 second PSA describes babesiosis, a preventable and treatable tickborne disease, including the signs and symptoms of infection and ways to prevent it.  Created: 4/25/2012 by Center for Global Health, Division of Parasitic Diseases and Malaria.   Date Released: 4/26/2012.

  16. PSA in America

    International Nuclear Information System (INIS)

    Linn, M.A.; Cunningham, M.A.; Johnson, D.H.

    1996-01-01

    Although the concept of acceptable risk has always been the foundation of the nuclear industry design, the use of formal PSA (or PRA-probabilistic risk assessment) in the U.S. nuclear power industry has followed an unusual path in arriving at its current level of notability. Prior to 1975, probabilistic evaluations were limited to a few specific applications such as the evaluation of man-made (i.e., airplane crashes) and natural (i.e., earthquakes) hazards. In 1975, the industry was introduced to comprehensive PSA by the Reactor Safety Study (WASH-1400). However, the study languished in relative obscurity until the accident at Three Mile Island 2 (TMI-2) in 1979. This event significantly altered the industry's view of severe accidents in the U.S. and worldwide. Investigative committees of TMI-2 recommended that PSA techniques be more widely used to augment the traditional deterministic methods of determining nuclear plant safety. This initiated an unprecedented effort by nuclear regulators and licensees worldwide to significantly improve the state of knowledge of severe accidents at nuclear power plants. In the U.S., use of PSA began to increase as evidenced by its application in the anticipated transient without scram and station blackout rulemakings, generic issue prioritization and resolution, risk-based inspection guidelines, backfit policy, and technical specification improvements. However, broad application of probabilistic techniques to the industry as a whole was initiated in 1986 with the publication of Safety Goals for the Operation of Nuclear Power Plant; Policy Statement. This put PSA front and center in the U.S. regulatory arena by open-quotes establish[ing] goals that broadly define an acceptable level of radiological risk that might be imposed on the public as a result of nuclear power plant operation.close quotes Both qualitative safety goals and quantitative objectives were articulated in this policy statement

  17. PSA in operator training

    International Nuclear Information System (INIS)

    Nos, V.; Faig, J.; Plesa, P.; Delgado, J. L.

    2000-01-01

    The systematic approach to training is internationally accepted as the best method to achieve and maintain the qualification and competence of power plant personnel and to guarantee the quality of their training. Following the recommendations and guidelines of international organisations competent in the field, TECNATOM SA has developed projects based on the systematic approach to training for all Spanish nuclear power plants. One of the latest projects was the systematic approach to training developed for the operation personnel of ASCO Nuclear Power Plant. In this case, certain results of the Probabilistic Safety Analysis (PSA) which complement the systematic safety and reliability criteria of the systematic approach to training process have been incorporated in the traditional processes of work and task analysis and training plan design. This incorporation provides the training manager with additional criteria based not only on safety aspects obtained through the statistical treatment of considerations of skilled technical personnel (operators, operation chief supervisors, etc), but also on the independent criterion of the PSA. The inclusion of this approach basically affects all systematics in two of its stages: During the selection process of operating practices in SMR or SGI, the possible scenarios have been associated with all those situations where human actions which lead to an initiating event or human actions to mitigate an initiating event, may take place, as defined in the PSA. During the scenario development process, the instruments involved in the performance of human actions which originate or mitigate an event taking place have been identified. This pakes it possible to reconcile the scenario event sequence with the sequence considered in the PSA study, as the most likely to provoke a more serious accident. The incorporation of these PSA results contributes to the strengthening of safety aspects in training in an objective way, and confirms that

  18. NPP Krsko Living PSA Concept

    International Nuclear Information System (INIS)

    Vrbanic, I.; Spiler, J.

    2000-01-01

    NPP Krsko developed PSA model of internal and external initiators within the frame of the Individual Plant Examination (IPE) project. Within this project PSA model was used to examine the existing plant design features. In order to continue with use of this PSA model upon the completion of IPE in various risk-informed applications in support of plant operation and evaluations of design changes, an appropriate living PSA concept needed to be defined. The Living PSA concept is in NPP Krsko considered as being a set of activities pursued in order to update existing PSA model in a manner that it appropriately represents the plant design, operation practice and history. Only a PSA model which is being updated in this manner can serve as a platform for plant-specific risk informed applications. The NPP Krsko living PSA concept is based on the following major ponts. First, the baseline PSA model is defined, which is to be maintained and updated and which is to be reference point for any risk-informed application. Second, issues having a potential for impact on baseline PSA model are identified and procedure and responsibilities for their permanent monitoring and evaluation are established. Third, manner is defined in which consequential changes to baseline PSA model are implemented and controlled, together with associated responsibilities. Finally, the process is defined by which the existing version of baseline PSA model is superseded by a new one. Each time a new version of baseline PSA model is released, it would be re-quantified and the results evaluated and interpreted. By documenting these re-quantifications and evaluations of results in a sequence, the track is being kept of changes in long-term averaged risk perspective, represented by long-term averaged frequencies of core damage and pre-defined release categories. These major topics of NPP Krsko living PSA concept are presented and discussed in the paper. (author)

  19. Whooping Cough PSA (:30)

    Centers for Disease Control (CDC) Podcasts

    2015-01-22

    This 30 second PSA encourages pregnant women to get the whooping cough vaccine, called Tdap, during the third trimester of each pregnancy in order to pass antibodies to their babies so they are born with protection against this serious disease.  Created: 1/22/2015 by National Center for Immunization and Respiratory Diseases (NCIRD), Division of Bacterial Diseases (DBD), Meningitis and Vaccine Preventable Diseases Branch (MVPDB).   Date Released: 1/22/2015.

  20. Binge Drinking PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2010-10-05

    This PSA is based on the October, 2010 CDC Vital Signs report which indicates that drinking too much, including binge drinking, causes more than 79,000 deaths in the U.S. each year and is the third leading preventable cause of death.  Created: 10/5/2010 by Centers for Disease Control and Prevention (CDC).   Date Released: 10/5/2010.

  1. PSA kinetics after prostate brachytherapy: PSA bounce phenomenon and its implications for PSA doubling time

    International Nuclear Information System (INIS)

    Ciezki, Jay P.; Reddy, Chandana A.; Garcia, Jorge; Angermeier, Kenneth; Ulchaker, James; Mahadevan, Arul; Chehade, Nabil; Altman, Andrew; Klein, Eric A.

    2006-01-01

    Purpose: To analyze prostate-specific antigen (PSA) kinetics in patients treated with prostate brachytherapy (PI) with a minimum of 5 years of PSA follow-up. Methods and Materials: The records of 162 patients treated with PI for localized prostate cancer with a minimum of 5 years of PSA follow-up were reviewed. A variety of pretreatment and posttreatment variables were examined. Patients were coded as having a PSA bounce if their PSA achieved a nadir, elevated at least 0.2 ng/mL greater than that nadir, and decreased to, or below, the initial nadir. Two definitions of biochemical failure (bF) or biochemical relapse-free survival (bRFS) were used: the classic American Society for Therapeutic Radiology and Oncology consensus definition of three consecutive rises (bF3) and the nadir plus 2 ng/mL definition (bFn+2). Associations between a PSA bounce and the various pre- and posttreatment factors were assessed with logistic regression analysis, and the association between a PSA bounce and bF was examined with the log-rank test. The Mann-Whitney U test was applied to test for differences in the PSA doubling time (PSADT) and the time to a PSA rise between the PSA bounce patients and the bF patients. PSADT was calculated from the nadir to the time of the first PSA rise, because this point is known first in the clinical setting. Results: The 5-year overall bRFS rate was 87% for the bF3 definition and 96% for the bFn+2 definition. A PSA bounce was experienced by 75 patients (46.3%). Patients who experienced a PSA bounce were less likely to have a bF, regardless of the bRFS definition used (bF3: p = 0.0015; bFn+2: p = 0.0040). Among the pre- and posttreatment factors, only younger age predicted for a PSA bounce on multivariate analysis (p = 0.0018). The use of androgen deprivation had no effect on PSA bounce. No difference was found in the PSADT between patients who had a PSA bounce and those with bF. The median PSADT for those with a PSA bounce was 8.3 months vs. 10.3 months

  2. Results of level 1 PSA in Trillo 1 NPP

    International Nuclear Information System (INIS)

    Gomez, F.; Lopez, C.

    1998-01-01

    In July 1991, C. N. Trillo I was requested by the Spanish Regulatory Body (CSN) to perform a PSA that should include: - Level 1 PSA at power - Internal flooding analysis - Level 2 PSA including containment capacity analysis. - External event analyses (fires, external flooding, seismic events and other external events) - Risk analysis for off power conditions (shutdown and low power) - Risk analysis due to other sources of radioactivity In 1992 the Project Plan was issued and the PSA team for the performance of Level 1 PSA was established. Before finishing the Project, it was decided to develop a Phase B to take into account some important modifications that had been accomplished in the Plant and that, probably, could affect the results. Level 1 PSA was finished in March 1998. Both the results of the study and the main conclusions derived from the importance, uncertainty and sensibility analysis performed are presented in this paper. These results de not include the internal flooding analysis conclusions and correspond to PSA revision 0 that is currently being evaluated by the Spanish Regulatory Body. (Author)

  3. PSA results and trends for Spain's NPPs

    International Nuclear Information System (INIS)

    Carretero, J.A.

    1993-01-01

    The Spain regulatory authority CSN demanded performance of PSA for all Spain nuclear power plants. The specific data analysis carried out as a part of the PSA has contributed to the realistic view on the results which could be achieved by the PSA. The main characteristics of the PSA in Spain and PSA trends in the development are presented in the paper

  4. Implementation guidelines for seismic PSA

    International Nuclear Information System (INIS)

    Coman, Ovidiu; Samaddar, Sujit; Hibino, Kenta; )

    2014-01-01

    The presentation was devoted to development of guidelines for implementation of a seismic PSA. If successful, these guidelines can close an important gap. ASME/ANS PRA standards and the related IAEA Safety Guide (IAEA NS-G-2.13) describe capability requirements for seismic PSA in order to support risk-informed applications. However, practical guidance on how to meet these requirements is limited. Such guidelines could significantly contribute to improving risk-informed safety demonstration, safety management and decision making. Extensions of this effort to further PSA areas, particularly to PSA for other external hazards, can enhance risk-informed applications

  5. COMPOSITION OF STAFF REVIEW ADVISORY BODIES - 2000 COMPOSITION OF THE JOINT TRAINING BOARD (JTB) - 2000/2001

    CERN Multimedia

    HR Division

    2000-01-01

    For the present staff review, the advisory bodies set up to prepare recommendations are composed as follows:Senior Staff Advancement Committee (SSAC)D. Treille / EP (Convener)C. Benvenuti / ESTD. O. Williams /ITTechnical Engineers & Administrative Careers Committee (TEACC) C. Hauviller / EPL. Leistam / ESTS. Jarp / IT [Chairman]F. Pedersen / PSR. Lauckner / SLC. Roche / ETTLong-term contract Boards (LTCBs) (Categories 2 &5a)Tiziano Camporesi / EP [Convener]Florence Ranjard / EP\t[Alternate]Jacques Gruber / PSPeter Sievers / LHCThomas Pettersson / ESTMichel Mayoud / ESTSue Foffano / ASThierry Lagrange / SPLWerner Zapf / HR (Secretary) LTCB 2(Categories 3, 4, 5b & 5c)Véronique Paris / SL [Convener]Fabien Pérriolat / PS\t [Alternate]Mats Wilhelmsson / STVéronique Fassnacht / TISLucie Linssen / EPMichel Mayoud / ESTPatrick Geeraert / FIJohn Cuthbert / HRSeamus Hegarty / HR (Secretary) Composition of the Joint Training Board (JT...

  6. PSA Update Procedures, an Ultimate Need for Living PSA

    International Nuclear Information System (INIS)

    Hegedus, D.

    1998-01-01

    Nuclear facilities by their complex nature, change with time. These changes can be both physical (plant modification, etc.), operational (enhanced procedures, etc.) and organizational. In addition, there are also changes in our understanding of the plant, due to operational experience, data collection, technology enhancements, etc. Therefore, it is imperative that PSA model must be frequently up-dated or modified to reflect these changes. Over the last ten years. these has been a remarkable growth of the use of Probabilistic Safety Assessments (PSAs). The most rapidly growing area of the PSA Applications is their use to support operational decision-making. Many of these applications are characterized by the potential for not only improving the safety level but also for providing guidance on the optimal use of resources and reducing regulatory burden. To enable a wider use of the PSA model as a tool for safety activities it is essential to maintain the model in a controlled state. Moreover, to fulfill requirements for L iving PSA , the PSA model has to be constantly updated and/or monitored to reflect the current plant configuration. It should be noted that the PSA model should not only represent the plant design but should also represent the operational and emergency procedures. To keep the PSA model up-to-date several issues should be clearly defined including: - Responsibility should be divided among the PSA group, - Procedures for implementing changes should be established, and - QA requirements/program should be established to assure documentation and reporting. (author)

  7. Photoadvisory: the photography in the press advisory body in the Maringá City Hall Administration Fotoassessorismo: a imagem fotográfica na assessoria de imprensa da Prefeitura Municipal de Maringá

    Directory of Open Access Journals (Sweden)

    Cibele Abdo Rodella

    2011-08-01

    Full Text Available Guided by the methodological perspective of analytical deconstruction, this work analyses photographic images from Maringa´s Prefecture press advisory. It seeks to answer to the following question: What strategies of senses do the photographic images build in the press advisement? In this attempt, it aims to: 1 To conceptualize the aspect of communicational intentionality; 2 To infer about its use on press advisory services; 3 To analyze if formats and genres of photographic image in journalism remain in the press advisory body. As a discourse, the photographic image in the press advisory body aims to build positive senses for the advised. In this case, with technical and photographic language domain, photojournalists intent to build elements, objects and characters to build up concepts, values and positive representation of the advised. For analysis of the photojournalists’ intentionality, they were used photographs taken from the site of the press advisory body of Maringá (PR Prefecture, referring to several articles.

  8. Development of PSA workstation KIRAP

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Tae Un; Han, Sang Hoon; Kim, Kil You; Yang, Jun Eon; Jeong, Won Dae; Chang, Seung Cheol; Sung, Tae Yong; Kang, Dae Il; Park, Jin Hee; Lee, Yoon Hwan; Hwang, Mi Jeong

    1997-01-01

    Advanced Research Group of Korea Atomic Energy Research Institute has been developing the Probabilistic Safety Assessment(PSA) workstation KIRAP from 1992. This report describes the recent development activities of PSA workstation KIRAP. The first is to develop and improve the methodologies for PSA quantification, that are the incorporation of fault tree modularization technique, the improvement of cut set generation method, the development of rule-based recovery, the development of methodology to solve a fault tree which has the logical loops and to handle a fault tree which has several initiators. These methodologies are incorporated in the PSA quantification software KIRAP-CUT. The second is to convert PSA modeling softwares for Windows, which have been used on the DOS environment since 1987. The developed softwares are the fault tree editor KWTREE, the event tree editor CONPAS, and Data manager KWDBMAN for event data and common cause failure (CCF) data. With the development of PSA workstation, it makes PSA modeling and PSA quantification and automation easier and faster. (author). 8 refs.

  9. Development of PSA workstation KIRAP

    International Nuclear Information System (INIS)

    Kim, Tae Un; Han, Sang Hoon; Kim, Kil You; Yang, Jun Eon; Jeong, Won Dae; Chang, Seung Cheol; Sung, Tae Yong; Kang, Dae Il; Park, Jin Hee; Lee, Yoon Hwan; Hwang, Mi Jeong.

    1997-01-01

    Advanced Research Group of Korea Atomic Energy Research Institute has been developing the Probabilistic Safety Assessment(PSA) workstation KIRAP from 1992. This report describes the recent development activities of PSA workstation KIRAP. The first is to develop and improve the methodologies for PSA quantification, that are the incorporation of fault tree modularization technique, the improvement of cut set generation method, the development of rule-based recovery, the development of methodology to solve a fault tree which has the logical loops and to handle a fault tree which has several initiators. These methodologies are incorporated in the PSA quantification software KIRAP-CUT. The second is to convert PSA modeling softwares for Windows, which have been used on the DOS environment since 1987. The developed softwares are the fault tree editor KWTREE, the event tree editor CONPAS, and Data manager KWDBMAN for event data and common cause failure (CCF) data. With the development of PSA workstation, it makes PSA modeling and PSA quantification and automation easier and faster. (author). 8 refs

  10. Detection of prostate cancer with complexed PSA and complexed/total PSA ratio - is there any advantage?

    OpenAIRE

    Strittmatter, F; Stieber, P; Nagel, D; Füllhase, C; Walther, S; Stief, CG; Waidelich, R

    2011-01-01

    Abstract Objective To evaluate the performance of total PSA (tPSA), the free/total PSA ratio (f/tPSA), complexed PSA (cPSA) and the complexed/total PSA ratio (c/tPSA) in prostate cancer detection. Methods Frozen sera of 442 patients have been analysed for tPSA, free PSA (fPSA) and cPSA. 131 patients had prostate cancer and 311 patients benign prostatic hyperplasia. Results Differences in the distribution of the biomarkers were seen as follows: tPSA, cPSA and c/tPSA were significantly higher i...

  11. Serum complexed and free prostate-specific antigen (PSA) for the diagnosis of the polycystic ovarian syndrome (PCOS).

    Science.gov (United States)

    Diamandis, Eleftherios P; Stanczyk, Frank Z; Wheeler, Sarah; Mathew, Anu; Stengelin, Martin; Nikolenko, Galina; Glezer, Eli N; Brown, Marshall D; Zheng, Yingye; Chen, Yen-Hao; Wu, Hsiao-Li; Azziz, Ricardo

    2017-10-26

    Polycystic ovarian syndrome (PCOS) is a common cause of reproductive and metabolic dysfunction. We hypothesized that serum prostate-specific antigen (PSA) may constitute a new biomarker for hyperandrogenism in PCOS. We conducted a cross-sectional study of 45 women with PCOS and 40 controls. Serum from these women was analyzed for androgenic steroids and for complexed PSA (cPSA) and free PSA (fPSA) with a novel fifth- generation assay with a sensitivity of ~10 fg/mL for cPSA and 140 fg/mL for fPSA. cPSA and fPSA levels were about three times higher in PCOS compared to controls. However, in PCOS, cPSA and fPSA did not differ according to waist-to-hip ratio, Ferriman-Gallwey score, or degree of hyperandrogenemia or oligo-ovulation. In PCOS and control women, serum cPSA and fPSA levels were highly correlated with each other, and with free and total testosterone levels, but not with other hormones. Adjusting for age, body mass index (BMI) and race, cPSA was significantly associated with PCOS, with an odds ratio (OR) of 5.67 (95% confidence interval [CI]: 1.86, 22.0). The OR of PCOS for fPSA was 7.04 (95% CI: 1.65, 40.4). A multivariate model that included age, BMI, race and cPSA yielded an area-under-the-receiver-operating-characteristic curve of 0.89. Serum cPSA and fPSA are novel biomarkers for hyperandrogenism in PCOS and may have value for disease diagnosis.

  12. Determining if pretreatment PSA doubling time predicts PSA trajectories after radiation therapy for localized prostate cancer

    International Nuclear Information System (INIS)

    Soto, Daniel E.; Andridge, Rebecca R.; Pan, Charlie C.; Williams, Scott G.; Taylor, Jeremy M.G.; Sandler, Howard M.

    2009-01-01

    Introduction: To determine if pretreatment PSA doubling time (PSA-DT) can predict post-radiation therapy (RT) PSA trajectories for localized prostate cancer. Materials and methods: Three hundred and seventy-five prostate cancer patients treated with external beam RT without androgen deprivation therapy (ADT) were identified with an adequate number of PSA values. We utilized a linear mixed model (LMM) analysis to model longitudinal PSA data sets after definitive treatment. Post-treatment PSA trajectories were allowed to depend on the pre-RT PSA-DT, pre-RT PSA (iPSA), Gleason score (GS), and T-stage. Results: Pre-RT PSA-DT had a borderline impact on predicting the rate of PSA rise after nadir (p = 0.08). For a typical low risk patient (T1, GS ≤ 6, iPSA 10), the predicted PSA-DT post-nadir was 21% shorter for pre-RT PSA-DT 24 month (19 month vs. 24 month). Additional significant predictors of post-RT PSA rate of rise included GS (p < 0.0001), iPSA (p < 0.0001), and T-stage (p = 0.02). Conclusions: We observed a trend between rapidly rising pre-RT PSA and the post-RT post-nadir PSA rise. This effect appeared to be independent of iPSA, GS, or T-stage. The results presented suggest that pretreatment PSA-DT may help predict post-RT PSA trajectories

  13. Methodology - PSA Regulatory handbook. Comparisons to a modern PSA study

    International Nuclear Information System (INIS)

    Bostroem, Urban; Jung, Gunnar; Flodin, Yngve

    2003-03-01

    The regulatory handbook is applicable to all types of initiating events and all operating conditions. It should be noted that it does not make the traditional subdivision of PSA into internal and external events, level 1 and level 2 PSA, or power operation and shut-down. The reason for this is that this has given the regulatory handbook a more logical structure, and that this approach underlines the integrated character of PSA when it comes to creating the plan risk profile. The regulatory handbook has been structured following the requirements on a PSA for a nuclear power plant, as this is the most demanding application. However, it is applicable also to the analysis of other nuclear installations. The purpose of the comparative review presented in this report has been to, as part of a quality review establish the PSA Handbook, compare (parts of) the handbook and its criteria with a recent PSA analysis, and to identify major discrepancies. Considerable weight has also been allocated to a review of the plant model (Risk Spectrum event trees and fault trees). The results presented in the report are not based on a complete review of the PSA in question (or of the complete PSA Handbook). Following discussions between the SKI and SwedPower, and based on the experience of the SwedPower reviewers, the following issues were chosen to be the main parts of the project: 1) General comparison according to content and transparency - Levels of ambition in PSA Handbook, PSA method description and actual PSA report. 2) Detailed comparison of: Selected component failure data - Assumptions regarding room events - CCI frequencies, realism, identification, categorisation - Taking credit for non-safety classified systems - Event tree modelling - Presentation of results 3) Fault tree model, specifically - Time frame for crediting of battery capacity - Modelling of regulators - Modelling of dependencies for room events - general quality, like how the paper documentation and the logic

  14. Early diagnostic role of PSA combined miR-155 detection in prostate cancer.

    Science.gov (United States)

    Guo, T; Wang, X-X; Fu, H; Tang, Y-C; Meng, B-Q; Chen, C-H

    2018-03-01

    As a kind of malignant tumor in the male genitourinary system, prostate cancer exhibits significantly increased occurrence. Prostate-specific antigen (PSA) expression can be seen in the prostate cancer, prostatitis, and other diseases, therefore, lack of diagnostic specificity. The miR-155 expression is abnormally increased in the tumors. Therefore, this study aims to explore the clinical significance of PSA combined miR-155 detection in the early diagnosis of prostate cancer. A total of 86 patients diagnosed with prostate cancer were enrolled in this study. PSA and miR-155 gene expression in tumor tissue were detected by using Real-time PCR. The serum levels of PSA were measured by using enzyme-linked immunosorbent assay (ELISA). The correlation of PSA and miR-155 expression with age, body mass index (BMI), tumor volume, tumor-node-metastasis (TNM) stage, lymph node metastasis (LNM), and other clinicopathological features were analyzed, respectively. Serum PSA expression and PSA gene in tumor tissue were significantly higher compared to that in adjacent tissues (pPSA gene and protein increased significantly with the clinical stage of TNM and decreased following the increase of grade (pPSA and miR-155 expressions were positively correlated with TNM stage, tumor volume, and LNM, and negatively correlated with grade (pPSA and miR-155 were closely related to the clinicopathological features of prostate cancer. Combined detection is helpful for the early diagnosis of prostate cancer.

  15. Blackpool: More evidence on PSA

    International Nuclear Information System (INIS)

    Cullingford, M.

    1985-01-01

    PSA is spreading widely throughout the world, with 30 IAEA Member States having active programmes in this area. The main reason for its popularity is that it offers insights critical in the safety decision-making process available from no other method. It allows power plant designers, regulators, and operators to discriminate between issues important to safety and those which are trivial. Although it is beneficial to perform a PSA to utilize the potential products available from such a study, it is especially important to realize that the PSA process itself is a valuable experience. The main points such as potential users of PSA, safety evaluations, treatment of uncertainties as well as future trends are briefly discussed in this paper

  16. Development of a PSA information database system

    International Nuclear Information System (INIS)

    Kim, Seung Hwan

    2005-01-01

    The need to develop the PSA information database for performing a PSA has been growing rapidly. For example, performing a PSA requires a lot of data to analyze, to evaluate the risk, to trace the process of results and to verify the results. PSA information database is a system that stores all PSA related information into the database and file system with cross links to jump to the physical documents whenever they are needed. Korea Atomic Energy Research Institute is developing a PSA information database system, AIMS (Advanced Information Management System for PSA). The objective is to integrate and computerize all the distributed information of a PSA into a system and to enhance the accessibility to PSA information for all PSA related activities. This paper describes how we implemented such a database centered application in the view of two areas, database design and data (document) service

  17. Human behaviour in PSA

    International Nuclear Information System (INIS)

    Schott, H.

    1999-01-01

    Based on the current international state of the art of methodology for evaluation of human errors for PSA, many research projects have been initiated by the competent departments of the BMU and the BfS (Federal Min. of the Environment and Reactor Safety, Federal Radiation Protection Office). Three major areas of the research activities are discussed: Database: - Specific investigations into the applicability of generic data (THERP) to other than the original cases, possibly elaboration of approaches for application-specific modification, further evaluation of operating results; - general enhancement of insight into human performance and errors, e.g. with respect to causes of error and application areas (influence of organisation, cognitive performance); interviews with experts as a supplementary approach for data verification and database enhancement. Sensitivity analysis: - Identification of information describing human errors essentially contributing to frequency of occurrence of incidents and system non-availability; - establishment of relevance rating system, methodology for uncertainty analysis. Further development of methodology: - Modelling of repair activities and knowledge-based behaviour. (orig./CB) [de

  18. Regulatory aspects of the use of PSA to evaluate technical specifications

    International Nuclear Information System (INIS)

    Rumpf, J.

    1991-01-01

    Based on experiences gained in PSA activities the regulatory body of the GDR initiated a programme to investigate the feasibility of using PSA for the evaluation of technical specifications. This programme is just under work. In addition, to improve PSA, the GDR takes part in a programme which is aimed at performing plant specific level 1, PSA as well as and which enables operating organizations to carry out PSA on their own. The most important of some preliminary general findings presented in this paper are: - Technical specifications form a well established envelope of operational conditions and procedures. A total re-evaluation is not considered necessary; Probabilistic evaluation of technical specifications should be an integrated part of PSA activities (at least level 1). Single assessment is not considered reasonable; Probabilistic evaluation of technical specifications has to be based on plant specific information and realistic accident sequence calculations; Up to now no quantitative probabilistic criteria for technical specifications have been established. (author)

  19. Survey of Dynamic PSA Methodologies

    International Nuclear Information System (INIS)

    Lee, Hansul; Kim, Hyeonmin; Heo, Gyunyoung; Kim, Taewan

    2015-01-01

    Event Tree(ET)/Fault Tree(FT) are significant methodology in Probabilistic Safety Assessment(PSA) for Nuclear Power Plants(NPPs). ET/FT methodology has the advantage for users to be able to easily learn and model. It enables better communication between engineers engaged in the same field. However, conventional methodologies are difficult to cope with the dynamic behavior (e.g. operation mode changes or sequence-dependent failure) and integrated situation of mechanical failure and human errors. Meanwhile, new possibilities are coming for the improved PSA by virtue of the dramatic development on digital hardware, software, information technology, and data analysis.. More specifically, the computing environment has been greatly improved with being compared to the past, so we are able to conduct risk analysis with the large amount of data actually available. One method which can take the technological advantages aforementioned should be the dynamic PSA such that conventional ET/FT can have time- and condition-dependent behaviors in accident scenarios. In this paper, we investigated the various enabling techniques for the dynamic PSA. Even though its history and academic achievement was great, it seems less interesting from industrial and regulatory viewpoint. Authors expect this can contribute to better understanding of dynamic PSA in terms of algorithm, practice, and applicability. In paper, the overview for the dynamic PSA was conducted. Most of methodologies share similar concepts. Among them, DDET seems a backbone for most of methodologies since it can be applied to large problems. The common characteristics sharing the concept of DDET are as follows: • Both deterministic and stochastic approaches • Improves the identification of PSA success criteria • Helps to limit detrimental effects of sequence binning (normally adopted in PSA) • Helps to avoid defining non-optimal success criteria that may distort the risk • Framework for comprehensively considering

  20. Survey of Dynamic PSA Methodologies

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hansul; Kim, Hyeonmin; Heo, Gyunyoung [Kyung Hee University, Yongin (Korea, Republic of); Kim, Taewan [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2015-05-15

    Event Tree(ET)/Fault Tree(FT) are significant methodology in Probabilistic Safety Assessment(PSA) for Nuclear Power Plants(NPPs). ET/FT methodology has the advantage for users to be able to easily learn and model. It enables better communication between engineers engaged in the same field. However, conventional methodologies are difficult to cope with the dynamic behavior (e.g. operation mode changes or sequence-dependent failure) and integrated situation of mechanical failure and human errors. Meanwhile, new possibilities are coming for the improved PSA by virtue of the dramatic development on digital hardware, software, information technology, and data analysis.. More specifically, the computing environment has been greatly improved with being compared to the past, so we are able to conduct risk analysis with the large amount of data actually available. One method which can take the technological advantages aforementioned should be the dynamic PSA such that conventional ET/FT can have time- and condition-dependent behaviors in accident scenarios. In this paper, we investigated the various enabling techniques for the dynamic PSA. Even though its history and academic achievement was great, it seems less interesting from industrial and regulatory viewpoint. Authors expect this can contribute to better understanding of dynamic PSA in terms of algorithm, practice, and applicability. In paper, the overview for the dynamic PSA was conducted. Most of methodologies share similar concepts. Among them, DDET seems a backbone for most of methodologies since it can be applied to large problems. The common characteristics sharing the concept of DDET are as follows: • Both deterministic and stochastic approaches • Improves the identification of PSA success criteria • Helps to limit detrimental effects of sequence binning (normally adopted in PSA) • Helps to avoid defining non-optimal success criteria that may distort the risk • Framework for comprehensively considering

  1. NRC regulatory uses of PSA

    International Nuclear Information System (INIS)

    Murley, T.E.

    1991-01-01

    The publication in 1975 of WASH-1400, with its new probabilistic safety assessment (PSA) methodology, had the effect of presenting a pair of eyeglasses to a man with poor eyesight. Suddenly, it gave us a view of nuclear safety with a new clarity, and it allowed us to sort out the important safety issues from the unimportant. In the intervening years, PSA insights have permeated the fabric of nearly all our safety judgments. This acceptance can be seen from the following list of broad areas where the Nuclear Regulatory Commission (NRC) staff uses PSA insights and methodology: evaluating the safety significance of operating events and recommending safety improvements where warranted; requesting licensees to systematically look for design vulnerabilities in each operating reactor; evaluating the safety significance of design weaknesses or non-compliances when judging the time frame for necessary improvements; conducting sensitivity analyses to judge where safety improvements are most effective; assessing the relative safety benefits of design features for future reactors. In judging where PSA methodology can be improved to give better safety insights, it is believed that the following areas need more attention: better modeling of cognitive errors; more comprehensive modeling of accident sequences initiated from conditions other than full power; more comprehensive modeling of inter-system loss of coolant accident (ISLOCA) sequences. Although PSA is widely used in the staff's regulatory activities, the NRC deliberately chooses not to include probabilistic prescriptions in regulations or guidance documents. The staff finds the bottom line risk estimates to be one of the least reliable products of a PSA. The reason for this view is that PSA cannot adequately address cognitive errors nor assess the effects of a pervasive poor safety attitude

  2. The Missions of National Commissions: Mapping the Forms and Functions of Bioethics Advisory Bodies.

    Science.gov (United States)

    Schmidt, Harald; Schwartz, Jason L

    The findings, conclusions, and recommendations of national ethics commissions (NECs) have received considerable attention throughout the 40-year history of these groups in the United States and worldwide. However, the procedures or types of argument by which these bodies arrive at their decisions have received far less scrutiny. This paper explores how the diversity of ethical principles, concepts, or theories is featured in publications or decisions of these bodies, with particular emphasis on the need for NECs to be inclusive of pluralist positions that typically exist in contemporary democracies. The discussion is centered on the extent to which NECs may focus on providing focal frameworks, primarily framing the ethical issues at stake, or normative frameworks, additionally providing transparent justifications for any conclusions and recommendations that are made. The structure allows for assessments of the relative merits and drawbacks of different approaches in both theory and practice.

  3. The inverse relationship between prostate-specific antigen (PSA) and obesity.

    Science.gov (United States)

    Aref, Adel; Vincent, Andrew D; O'Callaghan, Michael; Martin, Sean; Sutherland, Peter; Hoy, Andrew; Butler, Lisa M; Wittert, Gary

    2018-06-25

    Obese men have lower serum prostate-specific antigen (PSA) than comparably aged lean men, but the underlying mechanism remains unclear. The aim of this study was to determine the effect of obesity on PSA and the potential contributing mechanisms. A cohort of 1195 men aged 35 years and over at recruitment, with demographic, anthropometric (body mass index (BMI), waist circumference (WC)) and serum hormone (serum testosterone (T), estradiol (E2)), PSA and hematology assessments obtained over two waves was assessed. Men with a history of prostate cancer or missing PSA were excluded, leaving 970 men for the final analysis. Mixed-effects regressions and mediation analyses adjusting for hormonal and volumetric factors explore the potential mechanisms relating obesity to PSA. After adjusting for age, PSA levels were lower in men with greater WC (p=0.001). In a multivariable model including WC, age, E2/T and PlasV as predictors, no statistically significant associations were observed between with PSA and either WC (p=0.36) or PlasV (p=0.49), while strong associations were observed with both E2/T (pPSA (p=0.31), while when E2/T is a mediator; the ACME explained roughly 0.5 of the effect (pPSA levels in obese men, as compared to normal weight men, can be explained both by hormonal changes (elevated E2/T ratio) and haemodilution. Hormonal factors therefore represent a substantial but underappreciated mediating pathway.

  4. The role of PSA in safety management

    International Nuclear Information System (INIS)

    Szikszai, T.

    1997-01-01

    The presentation discusses the following issues: defence in depth principle (the role of the barriers, how does PSA represents the barriers?); the safety management and nuclear power plants; the probabilistic and deterministic approaches; the PSA applications and safety management

  5. Development of a PSA information management system

    International Nuclear Information System (INIS)

    Ho, Seok; Dong Kyu, Kim; Sun Koo, Kang

    2007-01-01

    In general, Probabilistic Safety Agreement (PSA) is a very complicated work that uses and generates a lot of resources such as reports, procedures, drawings, assumptions, calculation sheets, PSA model, and so on. In many PSAs, however, the data, materials and knowledge considered and generated during performing PSA are scattered in many documents so that overall structure of PSA and information relationship between documents and models cannot easily be understood. To organize and manage all documents related to PSA, to capture knowledge of analysts, and finally to improve the quality of PSA, a PSA information management system (PIMS) was developed. The PIMS can manage all the documents of a PSA in a database and connect the causal relation between one information to another in the scattered documents via link. The PIMS can manage all the assumptions and technical basis used in PSA, and it can keep the record of the design changes the revision of PSA model. It can also control the review results of PSA models. The link of the PIMS can explicitly describe and reveal the expertise of the PSA analysts, and it enables the users to capture the knowledge and to understand the structure and contents of a PSA with ease. We are planning to apply the PIMS to the PSA of Shin Kori Units 1 and 2 as feasibility study and then to all the PSAs of the nuclear power plants in Korea. The PIMS is expected to contribute to enhancing the quality and confidence of PSA and reducing the efforts and costs of maintenance and update of PSA. (authors)

  6. PSA - a tool for the nuclear safety

    International Nuclear Information System (INIS)

    Himanen, R.

    1992-01-01

    The PSA-model for BWR-type reactors of Finnish power company, Teollisuuden Voima Oy (TVO) was finished in year 1989. This basic PSA model included all safety systems, normal operating systems and auxiliary systems. Today TVO is working to enlarge the PSA to level 2 (environmental effects, for the fires, for the floodings and the outages). The TVO's experiences has been showed the PSA an useful tool for the developing the safety of BWR's (orig.)

  7. Development of a PSA information management system

    Energy Technology Data Exchange (ETDEWEB)

    Ho, Seok; Dong Kyu, Kim; Sun Koo, Kang [Korea Power Engineering Company, Inc (Korea, Republic of)

    2007-07-01

    In general, Probabilistic Safety Agreement (PSA) is a very complicated work that uses and generates a lot of resources such as reports, procedures, drawings, assumptions, calculation sheets, PSA model, and so on. In many PSAs, however, the data, materials and knowledge considered and generated during performing PSA are scattered in many documents so that overall structure of PSA and information relationship between documents and models cannot easily be understood. To organize and manage all documents related to PSA, to capture knowledge of analysts, and finally to improve the quality of PSA, a PSA information management system (PIMS) was developed. The PIMS can manage all the documents of a PSA in a database and connect the causal relation between one information to another in the scattered documents via link. The PIMS can manage all the assumptions and technical basis used in PSA, and it can keep the record of the design changes the revision of PSA model. It can also control the review results of PSA models. The link of the PIMS can explicitly describe and reveal the expertise of the PSA analysts, and it enables the users to capture the knowledge and to understand the structure and contents of a PSA with ease. We are planning to apply the PIMS to the PSA of Shin Kori Units 1 and 2 as feasibility study and then to all the PSAs of the nuclear power plants in Korea. The PIMS is expected to contribute to enhancing the quality and confidence of PSA and reducing the efforts and costs of maintenance and update of PSA. (authors)

  8. Hepatitis Awareness Month PSA (:30)

    Centers for Disease Control (CDC) Podcasts

    2011-05-11

    May is National Hepatitis Awareness Month. This 30 second PSA discusses hepatitis and encourages listners to talk to their health care professional about getting tested.  Created: 5/11/2011 by National Center for HIV/AIDS, Viral Hepatitis, STD, and TB Prevention.   Date Released: 5/11/2011.

  9. World AIDS Day PSA (:30)

    Centers for Disease Control (CDC) Podcasts

    2011-11-16

    December 1 is World AIDS Day. In this PSA, communities are encouraged to get tested for HIV.  Created: 11/16/2011 by National Center for HIV/AIDS, Viral Hepatitis, STD, and TB Prevention (NCHHSTP).   Date Released: 11/16/2011.

  10. Raccoon Roundworm Infection PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2012-08-27

    This 60 second PSA describes the signs and symptoms of and ways to prevent Baylisascaris infection, a parasitic roundworm infection that is spread through raccoon feces.  Created: 8/27/2012 by Centers for Disease Control and Prevention (CDC).   Date Released: 8/28/2012.

  11. Methods and use of PSA

    International Nuclear Information System (INIS)

    Vaurio, J.

    2005-01-01

    The objective is to introduce possible methods and methodological issues for application of PSA for decision making at nuclear power plants based on risk and cost, to present a number of application examples, and to describe recommendations and regulatory guides for risk-informed applications. (orig.)

  12. State of living PSA and further development

    International Nuclear Information System (INIS)

    1999-01-01

    In October 1985 OECD-Principal Working Group (PWG 5) - Risk Assessment has initiated the Task Force 7 'Use of PSA in Nuclear Power Plant Management' to explore and report on the principles, characteristics, requirements and status of PSA oriented safety management. During this study, it became apparent that the utilisation of PSA techniques in nuclear plant safety management requires the development of supporting programmes to ensure that PSA models are being updated to reflect plant changes, and to direct their use towards the evaluation and determination of plant changes. These requirements also influence the software and hardware characteristics necessary to support the programme. This overall process is known as Living PSA. In this context OECD-PWG 5 has arranged international workshops on Living PSA application to support this development, to facilitate exchange of international experience and to summarise the state-of-the-art of L-PSA methodology. These activities were accompanied by following Task Groups of OECD-PWG 5 and the work results were published in state-of-the-art reports. According to the increasing development of Living PSA in the international field and its capacity to support plant safety management in a broad sense, OECD PWG 5 continues its work in setting up the Task Group 96-1 'State of Living PSA and Further Development' to clarify specific aspects of Living PSA. This report summarises the state of Living PSA in the international field based on the four Living PSA Workshops from 1988 to 1994 (Chapter 2) and the state of Reliability Data Collection based on the results of Task Group 12 'Reliability Data Collection and Analysis to Support PSA' and the two Data-Workshops from 1995 and 1998 (Chapter 3). The specific items of further development of Living PSA application as mentioned above are treated in Chapter 4. Chapter 5 gives a summary of the current state of Living PSA as well as outlook and recommendations of further development

  13. Prevalence and causes of abnormal PSA recovery.

    Science.gov (United States)

    Lautenbach, Noémie; Müntener, Michael; Zanoni, Paolo; Saleh, Lanja; Saba, Karim; Umbehr, Martin; Velagapudi, Srividya; Hof, Danielle; Sulser, Tullio; Wild, Peter J; von Eckardstein, Arnold; Poyet, Cédric

    2018-01-26

    Prostate-specific antigen (PSA) test is of paramount importance as a diagnostic tool for the detection and monitoring of patients with prostate cancer. In the presence of interfering factors such as heterophilic antibodies or anti-PSA antibodies the PSA test can yield significantly falsified results. The prevalence of these factors is unknown. We determined the recovery of PSA concentrations diluting patient samples with a standard serum of known PSA concentration. Based on the frequency distribution of recoveries in a pre-study on 268 samples, samples with recoveries 120% were defined as suspect, re-tested and further characterized to identify the cause of interference. A total of 1158 consecutive serum samples were analyzed. Four samples (0.3%) showed reproducibly disturbed recoveries of 10%, 68%, 166% and 4441%. In three samples heterophilic antibodies were identified as the probable cause, in the fourth anti-PSA-autoantibodies. The very low recovery caused by the latter interference was confirmed in serum, as well as heparin- and EDTA plasma of blood samples obtained 6 months later. Analysis by eight different immunoassays showed recoveries ranging between PSA which however did not show any disturbed PSA recovery. About 0.3% of PSA determinations by the electrochemiluminescence assay (ECLIA) of Roche diagnostics are disturbed by heterophilic or anti-PSA autoantibodies. Although they are rare, these interferences can cause relevant misinterpretations of a PSA test result.

  14. PSA applications. Good practices and documentation

    International Nuclear Information System (INIS)

    Dewailly, J.; Magne, L.

    1997-10-01

    In this paper, it is shown what the condensed documentation of the main strategic choices and technical assumptions related to a PSA could contain: how to select the internal and external initiating events, how the detail the plant configuration and the general organization of the plant and operating staff, how to highlight the assumptions related to physical models, etc. The proposals in this documentation are based on the R and D D's experience with PSA (construction of PSA models, use of PSA models for operation or maintenance, PSA tools). This document also presents different types of rules or recommendations related to PSA modelling for various applications involved in nuclear power plant operating. Finally, the paper stresses the main difficulties encountered (appropriate use of uncertainties, communication of PSA results to non-specialist users) and it also outlines some prospects for the future. (author)

  15. Methodology for seismic PSA of NPPs

    International Nuclear Information System (INIS)

    Jirsa, P.

    1999-09-01

    A general methodology is outlined for seismic PSA (probabilistic safety assessment). The main objectives of seismic PSA include: description of the course of an event; understanding the most probable failure sequences; gaining insight into the overall probability of reactor core damage; identification of the main seismic risk contributors; identification of the range of peak ground accelerations contributing significantly to the plant risk; and comparison of the seismic risk with risks from other events. The results of seismic PSA are typically compared with those of internal PSA and of PSA of other external events. If the results of internal and external PSA are available, sensitivity studies and cost benefit analyses are performed prior to any decision regarding corrective actions. If the seismic PSA involves analysis of the containment, useful information can be gained regarding potential seismic damage of the containment. (P.A.)

  16. Review of UCN 5,6 Fire PSA Model based on ANS Fire PRA Standard

    International Nuclear Information System (INIS)

    Yang, Joon Eon; Lee, Yoon Hwan

    2006-12-01

    Recently, under the de-regulation environment, nuclear industry has attempted various approaches to improve the economics of Nuclear Power Plants (NPP). This approach uses the fire risk and performance information to manage the resources effectively and efficiently that are used in the operation of NPP. In fire risk informed/performance-based decision/operation, fire PSA quality is one of the most important things. The nuclear industry and regulatory body of U.S.A have developed a measure to evaluate the quality of fire PSA. ANS (American Nuclear Society) has developed a guidance called 'ANS Fire PRA Methodology Standard'. However, in Korea, there have been no attempts to evaluate the quality of fire PSA model itself. Therefore, we cannot be sure about the quality of fire PSA whether or not the present fire PSA model can be used for the risk-informed applications such as mentioned above. We can say that the evaluation of fire PSA model quality is the basis for the fire risk informed/performance-based decision/operation. In this report, we have evaluated the quality of fire PSA model for Ulchin 5 and 6 units based on the ANS Fire PRA Standard. We, also, have derived what items are to be improved to upgrade the quality of fire PSA model and how it can be improved. This report can be used as the base of the fire risk informed/performance-based decision/operation work in Korea

  17. Re-examining Prostate-specific Antigen (PSA) Density: Defining the Optimal PSA Range and Patients for Using PSA Density to Predict Prostate Cancer Using Extended Template Biopsy.

    Science.gov (United States)

    Jue, Joshua S; Barboza, Marcelo Panizzutti; Prakash, Nachiketh S; Venkatramani, Vivek; Sinha, Varsha R; Pavan, Nicola; Nahar, Bruno; Kanabur, Pratik; Ahdoot, Michael; Dong, Yan; Satyanarayana, Ramgopal; Parekh, Dipen J; Punnen, Sanoj

    2017-07-01

    To compare the predictive accuracy of prostate-specific antigen (PSA) density vs PSA across different PSA ranges and by prior biopsy status in a prospective cohort undergoing prostate biopsy. Men from a prospective trial underwent an extended template biopsy to evaluate for prostate cancer at 26 sites throughout the United States. The area under the receiver operating curve assessed the predictive accuracy of PSA density vs PSA across 3 PSA ranges (10 ng/mL). We also investigated the effect of varying the PSA density cutoffs on the detection of cancer and assessed the performance of PSA density vs PSA in men with or without a prior negative biopsy. Among 1290 patients, 585 (45%) and 284 (22%) men had prostate cancer and significant prostate cancer, respectively. PSA density performed better than PSA in detecting any prostate cancer within a PSA of 4-10 ng/mL (area under the receiver operating characteristic curve [AUC]: 0.70 vs 0.53, P PSA >10 mg/mL (AUC: 0.84 vs 0.65, P PSA density was significantly more predictive than PSA in detecting any prostate cancer in men without (AUC: 0.73 vs 0.67, P PSA increases, PSA density becomes a better marker for predicting prostate cancer compared with PSA alone. Additionally, PSA density performed better than PSA in men with a prior negative biopsy. Copyright © 2017 Elsevier Inc. All rights reserved.

  18. Too Much Sodium PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    This 60 second PSA is based on the February 2012 CDC Vital Signs report. Ninety percent of Americans age two and older eat too much sodium which can increase your risk for high blood pressure and often leads to heart disease and stroke, two leading causes of death in the US. Learn several small steps you can take to reduce the amount of sodium in your diet.

  19. Programmable automation systems in PSA

    International Nuclear Information System (INIS)

    Pulkkinen, U.

    1997-06-01

    The Finnish safety authority (STUK) requires plant specific PSAs, and quantitative safety goals are set on different levels. The reliability analysis is more problematic when critical safety functions are realized by applying programmable automation systems. Conventional modeling techniques do not necessarily apply to the analysis of these systems, and the quantification seems to be impossible. However, it is important to analyze contribution of programmable automation systems to the plant safety and PSA is the only method with system analytical view over the safety. This report discusses the applicability of PSA methodology (fault tree analyses, failure modes and effects analyses) in the analysis of programmable automation systems. The problem of how to decompose programmable automation systems for reliability modeling purposes is discussed. In addition to the qualitative analysis and structural reliability modeling issues, the possibility to evaluate failure probabilities of programmable automation systems is considered. One solution to the quantification issue is the use of expert judgements, and the principles to apply expert judgements is discussed in the paper. A framework to apply expert judgements is outlined. Further, the impacts of subjective estimates on the interpretation of PSA results are discussed. (orig.) (13 refs.)

  20. THE DISCRIMINATIVE ABILITY OF PERCENT FREE PSA IN ...

    African Journals Online (AJOL)

    Blood samples were collected from all patients, and total PSA, free PSA and % free PSA were calculated in all specimens. Total PSA was measured using the Imx ... Un prélèvement de sang a été réalisé chez tous les patients avec un dosage du PSA total et de la fraction libre de PSA. Le PSA total a été mesuré par un kit ...

  1. Qualification of calculation aids for PSA

    International Nuclear Information System (INIS)

    Goetz, K.; Hennigs, W.; Kirstein, B.M.; Reinhardt, C.

    1998-01-01

    In Germany Probabilistic Safety Analysis (PSA) are part of the evaluation of a nuclear power plants safety. The German PSA guide stipulates that the used software must enable a PSA according to the state of the art. This software must be qualified to assure that its features, mathematic methods and its performance enable a PSA like this. In this research work specifications and requirements are developed, which allow the testing of software. A procedure was developed to qualify PSA software according to the PSA guide and the experiences of users of PSA. Setting up a procedure, a tool for a systematic and uniform examination was crated. Additionally the options, mathematic fundamentals and performance of PSA-programs were analyzed. According to this all programs that were analyzed are capable to sovle their original task, that is the calculation of the safety of high available system based on high available components. Against that the requirements of modern PSA, e.g. to handle less available functions, HRA and fire analyses, based on the use of modern software and the implementation of new developments in the field of PSA are not supported adequately by all programs. (orig.) [de

  2. Use of PSA in a regulatory framework

    International Nuclear Information System (INIS)

    Ross, P.J.

    1994-01-01

    The paper will briefly describe the use of PSA in the licensing process for the Sizewell 'B' PWR Power Station currently under construction in the U.K. There are two distinct phases in the licensing process - (i) A PSA has been performed to support the application to construct Sizewell 'B'. At that stage the PSA was used as a design tool (along with deterministic design requirements) for Sizewell 'B' and as such lead to a number of significant design changes in the early design process. (ii) A PSA is currently being performed to support the application to operate Sizewell 'B'. The PSA is required to support the claim that the design has included all reasonably practical measures to prevent and mitigate accidents. The comprehensive PSA being produced for the second phase of the licensing process will be described. The way the regulators/designer/analysts have interacted over the years has affected the scope, complexity, detail and bias of the comprehensive PSA. The paper will discuss these issues and highlight some of the more significant ones. The benefits and drawbacks of providing a PSA in a regulatory framework will be discussed. One of the conclusions of the paper is that the use of true ''best-estimates'' in the PSA is difficult to achieve in a regulatory framework where persistent bias to the conservative side is apparent in the designers, analysts and regulators judgements. The usefulness of the PSA is therefore, potentially, compromised by giving misleading outputs or diverting resources to unnecessary areas. (author)

  3. Incorporating Level-2 PSA Feature of CONPAS into AIMS-PSA Software

    International Nuclear Information System (INIS)

    Han, Sang Hoon; Lim, Hogon; Ahn, Kwang Il

    2014-01-01

    CONPAS (CONtainment Performance Analysis System) utilizes a methodology to treat containment phenomena in detail like APET but in simple way. In mid 2000's, KAERI has developed very fast cut set generator FTREX and PC's OS (Operating system) has changed into Windows 95. Thus, KAERI has developed new Level-1 PSA software, called AIMS-PSA (Advanced Information Management System for PSA) to replace KIRAP. Recently, KAERI has been developing an integrated PSA platform, called OCEANS (On-line Consolidator and Evaluator of All mode risk for Nuclear System), for the risk assessment of all power modes and all hazards. CONPAS for Level-2 PSA was developed in 1990's using the Visual Basic 6.0 compiler which is not supported any more. It needs to be updated for the integrated PSA software framework. This paper describes a study to incorporate the features of CONPAS into AIMS-PSA. The basic idea is to follow the approach of CONPAS, but in the integrated way. Various approaches for Level-2 PSA have been used since WASH-1400. APET approach of NUREG-1150 study would be most comprehensive and complex methodology for containment event tree analysis. CONPAS is the Level-2 PSA software to utilize an approach to treat containment phenomena in detail like APET but in simple way. But, new Level-2 PSA software is required to develop more integrated PSA framework. A modified approach of CONPAS is developed and incorporated in AIMS-PSA software that can handle Level-1 and Level-2 PSA in the integrated way (from the viewpoint of event tree and fault tree). AIMS-PSA combines whole Level-2 PSA model to produce a One Top fault tree and to generate cut sets in the same way as Level-1 PSA. Quantification results of Level-2 PSA such as frequency for each STC can be calculated from the minimal cut sets

  4. Antigenic determinants of prostate-specific antigen (PSA) and development of assays specific for different forms of PSA.

    OpenAIRE

    Nilsson, O.; Peter, A.; Andersson, I.; Nilsson, K.; Grundstr?m, B.; Karlsson, B.

    1997-01-01

    Monoclonal antibodies were raised against prostate-specific antigen (PSA) by immunization with purified free PSA, i.e. not in complex with any protease inhibitor (F-PSA) and PSA in complex with alpha1-anti-chymotrypsin (PSA-ACT). Epitope mapping of PSA using the established monoclonal antibody revealed a complex pattern of independent and partly overlapping antigenic domains in the PSA molecule. Four independent antigenic domains and at least three partly overlapping domains were exposed both...

  5. Opium consumption is negatively associated with serum prostate-specific antigen (PSA), free PSA, and percentage of free PSA levels.

    Science.gov (United States)

    Safarinejad, Mohammad Reza; Asgari, Seyyed Alaeddin; Farshi, Alireza; Iravani, Shahrokh; Khoshdel, Alireza; Shekarchi, Babak

    2013-01-01

    Addiction to opium continues to be a major worldwide medical and social problem. The study addressing the association between opium consumption and serum prostate-specific antigen (PSA) level is lacking. We determined the effects of opium consumption on serum PSA levels in opium-addict men. Our study subjects comprised 438 opium-addict men with a mean age of 52.2 ± 6.4 years (group 1). We compared these men with 446 men who did not indicate current or past opium use (group 2). Serum total PSA (tPSA), free PSA (fPSA), % fPSA, and sex hormones were compared between the 2 groups. The mean serum tPSA level was significantly lower in group 1 (1.05 ng/mL) than in controls (1.45 ng/mL) (P = 0.001). Opium consumption was also associated with lower fPSA (P = 0.001) and % fPSA (P = 0.001). Serum free testosterone level in opium-addict patients (132.5 ± 42 pg/mL) was significantly lower than that in controls (156.2 ± 43 pg/mL) (P = 0.03). However, no significant correlation existed between tPSA and free testosterone levels (r = 0.28, 95% CI, -0.036 to 0.51, P = 0.34). Among the patients with cancer in group 1, 35% were found to have high-grade tumor (Gleason score ≥ 7) compared with 26.7% in group 2 (P = 0.02). Total PSA and fPSA were strongly correlated with duration of opium use (r = -0.06, 95% CI, -0.04 to -0.08, P = 0.0001; and r = -0.05, 95% CI, -0.03 to -0.07, P = 0.0001, respectively). Opium consumption is independently and negatively associated with serum tPSA, fPSA, and % fPSA levels.

  6. Development and perspectives of PSA in Cuba

    International Nuclear Information System (INIS)

    1996-01-01

    During the last decade the GDA/PSA has carried out the pre-operational PSA task for the Juragua Nuclear Power Plant. Since 1991 the work has been accomplished in the frames of the IAEA Technical Assistance Project CUB/9/008. The paper describes the stages of this study, (concluding with the Final Report of the pre-operational Level 1 PSA Rev. O), its assumptions, limitations and the main results and concluding remarks

  7. PSA, subjective probability and decision making

    International Nuclear Information System (INIS)

    Clarotti, C.A.

    1989-01-01

    PSA is the natural way to making decisions in face of uncertainty relative to potentially dangerous plants; subjective probability, subjective utility and Bayes statistics are the ideal tools for carrying out a PSA. This paper reports that in order to support this statement the various stages of the PSA procedure are examined in detail and step by step the superiority of Bayes techniques with respect to sampling theory machinery is proven

  8. Status and use of PSA in Sweden

    International Nuclear Information System (INIS)

    Knochenhauer, M.

    1996-05-01

    The performance and use of PSA:s in Sweden goes back about two decades. During all of this time, the field of PSA has been developing intensively, both internationally and within Sweden. The latest years have been characterised by an increased use of PSA models and results, and by major extensions of existing PSA models. The aim of this document is to describe PSA in Sweden with respect to development, scope and maturity, as well as to the contents of the analyses and the use of results. PSA activities will be described from the point of view of both the authorities and the utilities. The report gives an overview of the development within the area of PSA in Sweden both its history and current trends. The aim has been to include a reasonable amount of detail, both on the methods and results in PSA:s performed and on the numerous supporting research programs dealing with various aspects of PSA. 39 refs 39 refs

  9. Status and use of PSA in Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Knochenhauer, M

    1996-05-01

    The performance and use of PSA:s in Sweden goes back about two decades. During all of this time, the field of PSA has been developing intensively, both internationally and within Sweden. The latest years have been characterised by an increased use of PSA models and results, and by major extensions of existing PSA models. The aim of this document is to describe PSA in Sweden with respect to development, scope and maturity, as well as to the contents of the analyses and the use of results. PSA activities will be described from the point of view of both the authorities and the utilities. The report gives an overview of the development within the area of PSA in Sweden both its history and current trends. The aim has been to include a reasonable amount of detail, both on the methods and results in PSA:s performed and on the numerous supporting research programs dealing with various aspects of PSA. 39 refs 39 refs.

  10. Model engineering in a modular PSA

    International Nuclear Information System (INIS)

    Friedlhuber, Thomas

    2014-01-01

    For the purpose of PSA (Probabilistic Safety Analysis) for complex industrial systems, often PSA models in the form of fault and event trees are developed to model the risk of unwanted situations (hazards). While the recent decades, PSA models have gained high acceptance and have been developed massively. This lead to an increase in model sizes and complexity. Today, PSA models are often difficult to understand and maintain. This manuscript presents the concept of a modular PSA. A modular PSA tries to cope with the increased complexity by the techniques of modularization and instantiation. Modularization targets to treat a model by smaller pieces (the 'modules') to regain control over models. Instantiation aims to configure a generic model to different contexts. Both try to reduce model complexity. A modular PSA proposes new functionality to manage PSA models. Current model management is rather limited and not efficient. This manuscript shows new methods to manage the evolutions (versions) and deviations (variants) of PSA models in a modular PSA. The concepts of version and variant management are presented in this thesis. In this context, a model comparison and fusion of PSA models is precised. Model comparison provides important feedback to model engineers and model fusion kind of combines the work from different model engineers (concurrent model engineering). Apart from model management, methods to understand the content of PSA models are presented. The methods focus to highlight the dependencies between modules rather than their contents. Dependencies are automatically derived from a model structure. They express relations between model objects (for example a fault tree may have dependencies to basic events). To visualize those dependencies (for example in form of a model cartography) can constitute a crucial aid to model engineers for understanding complex interrelations in PSA models. Within the scope of this thesis, a software named 'Andromeda' has been

  11. Too Much Sodium PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2012-02-07

    This 60 second PSA is based on the February 2012 CDC Vital Signs report. Ninety percent of Americans age two and older eat too much sodium which can increase your risk for high blood pressure and often leads to heart disease and stroke, two leading causes of death in the US. Learn several small steps you can take to reduce the amount of sodium in your diet.  Created: 2/7/2012 by Centers for Disease Control and Prevention (CDC).   Date Released: 2/7/2012.

  12. PSA-based evaluation and rating of operational events

    International Nuclear Information System (INIS)

    Gomez Cobo, A.

    1997-01-01

    The presentation discusses the PSA-based evaluation and rating of operational events, including the following: historical background, procedures for event evaluation using PSA, use of PSA for event rating, current activities

  13. PSA Level 2:Scope And Method Of PSA Level 2 For Nuclear Power Plant

    International Nuclear Information System (INIS)

    Widodo, Surip; Antariksawan, Anhar R.

    2001-01-01

    A study of scope and method of PSA Level 2 had been conducted. The background of the study is the need to gain the capability to well perform PSA Level 2 for nuclear facilities. This study is a literature survey. The scope of PSA Level 2 consists of generating plant damage states, accident progression analysis, and grouping source terms. Concerning accident progression analysis, several methods are used, among others event tree method, named accident progression event tree (APET) or containment event tree (CET), and fault tree method. The end result of PSA Level 2 is release end states which is grouped into release bins. The results will be used for PSA Level 3

  14. [PSA interest and prostatitis: literature review].

    Science.gov (United States)

    Bruyère, F; Amine Lakmichi, M

    2013-12-01

    Prostatitis is easily diagnosed but sometimes associated with PSA measurement. An increased PSA in an asymptomatic patient may be associated with antibiotic use to eliminate the inflammatory part and to confirm prostate biopsy. It seems interesting to confirm or infirm these attitudes with a systematic review of the literature We performed a literature review using the words [prostatitis], [acute prostatitis], [prostate specific antigen], [PSA], in the MEDLINE, Pubmed and AMBASE database searching for articles in French or English published in the past 20 years. PSA is not always increased during an acute prostatitis episode. An increased PSA in an asymptomatic man does not seem to be systematically correlated to prostate inflammation. Analyzing the studies, it seems inaccurate to measure PSA value during a febrile urinary infection episode in men. Systematic use of antibiotic to decrease PSA and not performing prostate biopsy is not relevant and may induce resistance to antibiotic and doesn't induce a reduction risk of having prostate biopsy. PSA is unnecessary in case of febrile urinary tract infection in men. Copyright © 2013 Elsevier Masson SAS. All rights reserved.

  15. Impact of total PSA, PSA doubling time and PSA velocity on detection rates of 11C-Choline positron emission tomography in recurrent prostate cancer

    NARCIS (Netherlands)

    Rybalov, Maxim; Breeuwsma, Anthonius J.; Leliveld, Anna M.; Pruim, Jan; Dierckx, Rudi A.; de Jong, Igle J.

    PURPOSE: To evaluate the effect of total PSA (tPSA) and PSA kinetics on the detection rates of (11)C-Choline PET in patients with biochemical recurrence (BCR) after radical prostatectomy (RP) or external beam radiotherapy (EBRT). METHODS: We included 185 patients with BCR after RP (PSA >0.2 ng/ml)

  16. Decision criteria in PSA applications

    International Nuclear Information System (INIS)

    Holmberg, J.E.; Pulkkinen, U.; Rosqvist, T.; Simola, K.

    2001-11-01

    Along with the adoption of risk informed decision making principles, the need for formal probabilistic decision rule or criteria has been risen. However, there are many practical and theoretical problems in the application of probabilistic criteria. One has to think what is the proper way to apply probabilistic rules together with deterministic ones and how the criteria are weighted with respect to each other. In this report, we approach the above questions from the decision theoretic point of view. We give a short review of the most well known probabilistic criteria, and discuss examples of their use. We present a decision analytic framework for evaluating the criteria, and we analyse how the different criteria behave under incompleteness or uncertainty of the PSA model. As the conclusion of our analysis we give recommendations on the application of the criteria in different decision situations. (au)

  17. Radiometric assays for the measurement of PSA

    International Nuclear Information System (INIS)

    Venkatesh, M.

    1997-01-01

    Prostate Specific Antigen, a serine protease enzyme, of M.W. ∼ 26-33 kDa, is widely considered to be a very useful marker for prostate cancer. It satisfies nearly all the requirements of an ideal 'Tumour Marker' and has hence attracted a lot of attention in the past decade. PSA is present in multiple forms in serum, with an appreciable fraction bound to the protease inhibitor α-1-antichymotrypsin (ACT) and to a small extent to other proteins such as α-2-macroglobulin (AMG) leaving the rest in the free form. The total PSA levels have been reported to have 80% sensitivity and 60% specificity towards the detection of prostate cancer. The lack of specificity occurs mainly due to the high levels of t-PSA in benign prostatic hypertrophy(BPH) apart from the cancer. The concept of free PSA has been introduced in the recent past and the ratio of free/total PSA levels have been shown to be advantageous in the differential diagnosis of BPH from prostate cancer. The f/t ratio is considered to be particularly useful in the grey zones of decision making (t-PSA levels 4-20 ng/mL). The need for the development of assays for total and free PSA is felt due to: a. the high incidence of prostate cancers being detected currently; b. the high cost of tests (higher for free PSA assay, and the cost becomes an important parameter when a patient has to be regularly monitored after therapy) that is not affordable for many patients; c. the potential for research in the area of prostate cancer management where the PSA (total and free) assays will be of great help

  18. The clinical study of serum PSA and fPSA assayed by CLIA in diagnosing prostate disease

    International Nuclear Information System (INIS)

    Xiong Jiang; Qian Xiaoyu; Ji Hong; Yang Su; Ding Ying; Zhu Ruisen; Chen Zhong

    2003-01-01

    The purpose of this study is to evaluate the clinical value of PSA (prostate specific antigen) and fPSA(free prostate specific antigen) in differentiating prostate disease. CLIA was used to quantitatively assay PSA, fPSA and fPSA/PSA in 30 cases of normal controls, 32 cases of prostate cancer patients and 76 cases of BPH patients. The result showed that if liminal value of PSA was set at 4 ng/mL, the diagnostic sensitivity and specificity of prostate cancer were 100% and 50.6% respectively. Meanwhile, if liminal value of fPSA/PSA set at 16% was added, the diagnostic sensitivity and specificity of prostate cancer were 100% and 85.3% respectively. It was concluded that the combining assay of PSA and fPSA could increase the diagnostic specificity of prostate cancer in a certain degree

  19. PSA as a tool for decision making

    International Nuclear Information System (INIS)

    Niehaus, F.; Lederman, L.

    1986-01-01

    The question on ''How safe is safe enough'' is being responded presently by deterministic criteria. Probabilistic criteria in support to more rational and less emotional decisions in regulatory and licensing issues, rationalization of resource allocation and research prioritization, among others, have a potential which is only marginally being explored. This paper discussed PSA limitations and proposes three areas for the use of PSA in decision making, namely: preventing accidents, mitigating accidents, and defining regulatory requirements. Current activities of the International Atomic Energy Agency in these areas are mentioned. PSA studies depict clearly the uncertainties and this is viewed as a positive aspect, which is unique to the use of probabilistic methods. (orig.)

  20. PSA as a tool for decision making

    Energy Technology Data Exchange (ETDEWEB)

    Niehaus, F; Lederman, L

    1986-05-01

    The question on ''How safe is safe enough'' is being responded presently by deterministic criteria. Probabilistic criteria in support to more rational and less emotional decisions in regulatory and licensing issues, rationalization of resource allocation and research prioritization, among others, have a potential which is only marginally being explored. This paper discussed PSA limitations and proposes three areas for the use of PSA in decision making, namely: preventing accidents, mitigating accidents, and defining regulatory requirements. Current activities of the International Atomic Energy Agency in these areas are mentioned. PSA studies depict clearly the uncertainties and this is viewed as a positive aspect, which is unique to the use of probabilistic methods.

  1. The diagnostic value of PSA, cPSA and bone scintigraphy for early skeletal metastasis of prostate cancer

    International Nuclear Information System (INIS)

    Xue Zhongguang

    2007-01-01

    Objective: To evaluate the value of prostate specific antigen (PSA), complexed prostate specific antigen (cPSA) and bone scintigraphic imaging in diagnosis of early skeletal metastasis of prostate cancer. Methods: 152 patients (74 with prostate cancer, 78 with benign prostate disease) and 90 controls were examined for the serum concentrations of PSA and cPSA. At the same time, the 74 patients with PCa were examined with bone scintigraphy. The cPSA/PSA ratio was calculated. Results: Serum PSA, cPSA levels and cPSA/PSA ratio of patients with prostate cancer were significantly higher than those in benign prostate patients and controls. In addition, the serum PSA, cPSA levels and cPSA/PSA ratio in prostate cancer patients with skeletal metastasis were remarkably higher than those in patients without skeletal metastasis, and the differences were significant (P 20 μg/L, cPSA>10 μg/L, cPSA/PSA>0.80, there is a high probability that skeletal metastasis of prostate cancer would be present and bone scintigraphy should be performed. (authors)

  2. Development of the Level 1 PSA Model for PGSFR Regulatory

    International Nuclear Information System (INIS)

    Na, Hyun Ju; Lee, Yong Suk; Shin, Andong; Suh, Nam Duk

    2014-01-01

    SFR (sodium-cooled fast reactor) is Gen-IV nuclear energy system, which is designed for stability, sustainability and proliferation resistance. KALIMER-600 and PGSFR (Prototype Gen-IV SFR) are under development in Korea with enhanced passive safety concepts, e.g. passive reactor shutdown, passive residual heat removal, and etc. Risk analysis from a regulatory perspective is necessary for regulatory body to support the safety and licensing review of SFR. Safety issues should be identified in the early design phase in order to prevent the unexpected cost increase and the delay of PGSFR licensing schedule. In this respect, the preliminary PSA Model of KALIMER-600 had been developed for regulatory. In this study, the development of PSA Level 1 Model is presented. The important impact factors in the risk analysis for the PGSFR, such as Core Damage Frequency (CDF), have been identified and the related safety insights have been derived. The PSA level 1 model for PGSFR regulatory is developed and the risk analysis is conducted. Regarding CDF, LOISF frequency, uncertainty parameter for passive system CCF, loss of 125V DC control center bus and damper CCF are identified as the important factors. Sensitivity analyses show that the CDF would be differentiated (lowered) according to their values

  3. Review of SFR Design Safety using Preliminary Regulatory PSA Model

    International Nuclear Information System (INIS)

    Na, Hyun Ju; Lee, Yong Suk; Shin, Andong; Suh, Nam Duk

    2013-01-01

    The major objective of this research is to develop a risk model for regulatory verification of the SFR design, and thereby, make sure that the SFR design is adequate from a risk perspective. In this paper, the development result of preliminary regulatory PSA model of SFR is discussed. In this paper, development and quantification result of preliminary regulatory PSA model of SFR is discussed. It was confirmed that the importance PDRC and ADRC dampers is significant as stated in the result of KAERI PSA model. However, the importance can be changed significantly depending on assumption of CCCG and CCF factor of PDRC and ADRC dampers. SFR (sodium-cooled fast reactor) which is Gen-IV nuclear energy system, is designed to accord with the concept of stability, sustainability and proliferation resistance. KALIMER-600, which is under development in Korea, includes passive safety systems (e. g. passive reactor shutdown, passive residual heat removal, and etc.) as well as active safety systems. Risk analysis from a regulatory perspective is needed to support the regulatory body in its safety and licensing review for SFR (KALIMER-600). Safety issues should be identified in the early design phase in order to prevent the unexpected cost increase and delay of the SFR licensing schedule that may be caused otherwise

  4. Issues reporting PSA in prostate cancer

    International Nuclear Information System (INIS)

    Lange, Paul H.

    1996-01-01

    The National Cancer Institute Prostate; Lung; Colon; Ovarian Cancer Screening (PLCO) project is a multi-center trial developed to investigate the effectiveness of DRE and PSA testing in the early detection and outcome of patients with prostate cancer. Accordingly, the Prostate Cancer Intervention versus Observation Trial (PIVOT) has been launched and is a randomized trial comparing radical prostatectomy versus expectant management for ALCaP. PSA: Initially PSA was thought to be of little value for diagnosis because 20% of men undergoing radical prostatectomy have 'normal' PSA and patients with apparently only symptomatic BPH have 'elevated' levels as follows: 4-10 ng/ml (Tandem-R) - 20%, >10 ng/ml -3%. Yet, PSA has looked attractive as a diagnostic tool in many studies; for example, when PSA was used in a screening approach as the first test which then drove further evaluation (Catalona, Brawer). It was shown that the positive predictive value for PSA's between 4 and 10 is approximately 20% and > 10 approximately 55%. The value of serial PSA's (velocity) is unknown but is under intense study: one major issue is determination of what represents a significant rise (details to be presented). Studies have also revealed that a DRE and PSA are important for optimal results. About 18% of clinically detectable cancers are only DRE positive while about 25 - 30% are only PSA positive. When both a DRE and PSA are used together, very few clinically apparent cancers are missed (3-5%). Recent ROC curves suggest that 4 ng/ml is reasonable. Recently, PSA values for men without apparent cancer were stratified by age, and taking the 2SD, age specific reference values were generated as follows: age 40-49 (0-2.5 ng/ml), 50-59 (0-3.5), 60-69 (0-4.5), 70-70 (0-6.5). Finally, there is the issue about different PSA assays regarding the compatabilities/reliability of the upper limit of normal and serial values. Much of the confusion is because there is no international PSA standard and

  5. Probability of an Abnormal Screening PSA Result Based on Age, Race, and PSA Threshold

    Science.gov (United States)

    Espaldon, Roxanne; Kirby, Katharine A.; Fung, Kathy Z.; Hoffman, Richard M.; Powell, Adam A.; Freedland, Stephen J.; Walter, Louise C.

    2014-01-01

    Objective To determine the distribution of screening PSA values in older men and how different PSA thresholds affect the proportion of white, black, and Latino men who would have an abnormal screening result across advancing age groups. Methods We used linked national VA and Medicare data to determine the value of the first screening PSA test (ng/mL) of 327,284 men age 65+ who underwent PSA screening in the VA healthcare system in 2003. We calculated the proportion of men with an abnormal PSA result based on age, race, and common PSA thresholds. Results Among men age 65+, 8.4% had a PSA >4.0ng/mL. The percentage of men with a PSA >4.0ng/mL increased with age and was highest in black men (13.8%) versus white (8.0%) or Latino men (10.0%) (PPSA >4.0ng/mL ranged from 5.1% of Latino men age 65–69 to 27.4% of black men age 85+. Raising the PSA threshold from >4.0ng/mL to >10.0ng/mL, reclassified the greatest percentage of black men age 85+ (18.3% absolute change) and the lowest percentage of Latino men age 65–69 (4.8% absolute change) as being under the biopsy threshold (PPSA threshold together affect the pre-test probability of an abnormal screening PSA result. Based on screening PSA distributions, stopping screening among men whose PSA 10ng/ml has the greatest effect on reducing the number of older black men who will face biopsy decisions after screening. PMID:24439009

  6. Review of KSNP LPSD PSA model based of ANS LPSD PRA standard, rev.0

    International Nuclear Information System (INIS)

    Jang, S. C.; Park, J. H.; Kim, T. W.; Lim, H. G.; Yang, J. E.; Ha, J. J.

    2004-02-01

    Recently, under the de-regulation environment, nuclear industry has attempted various approaches to improve the economics of Nuclear Power Plants (NPP). One of these efforts is the Risk Informed/Performance-based Operation (RIPBO). This approach uses the risk and performance information to manage the resources effectively and efficiently that are used in the operation of NPP. In RIPBO, PSA quality is one of the most important things. The nuclear industry and regulatory body of U.S.A have developed a measure to evaluate the quality of PSA. NEI (Nuclear Energy Institute) has developed a guidance called 'NEI PRA Peer Review Guidance,' and NRC (Nuclear Regulatory Committee) and ASME have developed the 'PRA Standard.' In Korea, several projects are on going now, such as the extension of AOT/STI of RPS/ESFAS, Risk-informed In-service Inspection (RI-ISI). However, in Korea, there have been no attempts to evaluate the quality of PSA model itself. Therefore, we cannot be sure about the quality of PSA whether or not the present PSA model can be used for the risk-informed applications such as mentioned above. We can say that the evaluation of PSA model quality is the basis for the RIPBO. In this report, we have evaluated the quality of PSA model at Low power and Shutdown operation model for Yongkwang 5 and 6 units based on the ANS LPSD PRA Standard. We, also, have derived what items are to be improved to upgrade the quality of LPSD PSA model and how it can be improved. This report can be used as the base of RIPBO work in Korea

  7. More Adults Are Walking PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    This 60 second PSA is based on the August 2012 CDC Vital Signs report. While more adults are walking, only half get the recommended amount of physical activity. Listen to learn how communities, employers, and individuals may help increase walking.

  8. Methodology for fire PSA during design process

    International Nuclear Information System (INIS)

    Kollasko, Heiko; Blombach, Joerg

    2009-01-01

    Fire PSA is an essential part of a full scope level 1 PSA. Cable fires play an important role in fire PSA. Usually, cable routing is therefore modeled in detail. During the design of new nuclear power plants the information on cable routing is not yet available. However, for the use of probabilistic safety insights during the design and for licensing purposes a fire PSA may be requested. Therefore a methodology has been developed which makes use of the strictly divisional separation of redundancies in the design of modern nuclear power plants: cable routing is not needed within one division but replaced by the conservative assumption that all equipment fails due to a fire in the concerned division; critical fire areas are defined where components belonging to different divisions may be affected by a fire. For the determination of fire frequencies a component based approach is proposed. The resulting core damage frequencies due to fire are conservative. (orig.)

  9. A preliminary investigation of PSA validation methods

    Energy Technology Data Exchange (ETDEWEB)

    Unwin, S D [Science Applications International Corp., (United States)

    1995-09-01

    This document has been prepared to support the initial phase of the Atomic Energy Control Board`s program to review and evaluate Probabilistic Safety Assessment (PSA) studies conducted by nuclear generating station designers and licensees. The document provides (1) a review of current and prospective applications of PSA technology in the Canadian nuclear power industry; (2) an assessment of existing practices and techniques for the review or risk and hazard identification studies in the international nuclear power sector and other technological sectors; and (3) proposed analytical framework in which to develop systematic techniques for the scrutiny and evaluation of a PSA model. These frameworks are based on consideration of the mathematical structure of a PSA model and are intended to facilitate the development of methods to evaluate a model relative to intended end-uses. (author). 34 refs., 10 tabs., 3 figs.

  10. A preliminary investigation of PSA validation methods

    International Nuclear Information System (INIS)

    Unwin, S.D.

    1995-09-01

    This document has been prepared to support the initial phase of the Atomic Energy Control Board's program to review and evaluate Probabilistic Safety Assessment (PSA) studies conducted by nuclear generating station designers and licensees. The document provides (1) a review of current and prospective applications of PSA technology in the Canadian nuclear power industry; (2) an assessment of existing practices and techniques for the review or risk and hazard identification studies in the international nuclear power sector and other technological sectors; and (3) proposed analytical framework in which to develop systematic techniques for the scrutiny and evaluation of a PSA model. These frameworks are based on consideration of the mathematical structure of a PSA model and are intended to facilitate the development of methods to evaluate a model relative to intended end-uses. (author). 34 refs., 10 tabs., 3 figs

  11. PDS4 Challenges in the PSA

    Science.gov (United States)

    Saiz, J.; Barbarisi, I.; Docasal, R.; Rios, C.; Montero, A.; Macfarlane, A.; Laantee, C.; Besse, S.; Vallat, C.; Marcos, J.; Arenas, J.; Osinde, J.; Arviset, C.

    2018-04-01

    The Planetary Science Archive (PSA) stores products from all planetary ESA missions. Adopting PDS4 as the standard for new missions, while being compatible with existing PDS3 products, has driven a design with several difficulties to overcome.

  12. Proceedings of the 10th Korea-Japan joint workshop on PSA. For Asian PSA network

    International Nuclear Information System (INIS)

    Yang, Joon-Eon; Homma, Toshimitsu

    2009-12-01

    The tenth Korea-Japan Joint Workshop on Probabilistic Safety Assessment (PSA) was held in the Jeju island of Korea, on May 18-20, 2009 organized by Korea Atomic Energy Research Institute (KAERI). The purpose of the workshop was to provide a forum for presentation and discussions on experiences and technical achievements related to PSA, risk-informed and performance-based approach, and other relevant issues in both countries. Since the first Korea-Japan Joint Workshop on PSA started in 1992, the workshops have provided an important and timely opportunity for exchange and discussion of the relevant information to all PSA practitioners and users of risk information in the industry, research, academia and regulatory arena. This was the tenth anniversary of the Joint Workshop with the main theme of 'For Asian PSA Network' and participants included those from China, Taiwan and the United States of America besides Korea and Japan. Two keynote speeches were presented by the former chairmen of this workshop, Prof. Chang-Sun Kang of Seoul National University and Prof. emeritus Shunsuke Kondo of Tokyo University. We had two special lectures, 70 papers presented by experts at 10 technical sessions related PSA, the special session on the status of PSA in Korea, Japan, China and Taiwan and panel discussion on their cooperation in PSA. This report provides the summary of each session, and all the presentation materials presented in the 10th Korea-Japan Joint Workshop on PSA. (author)

  13. IAEA work with guides for PSA quality

    International Nuclear Information System (INIS)

    Hellstroem, Per

    2004-09-01

    IAEA has a project on development of a TECDOC 'PSA Quality for Various Applications'. The project develops the guidance document in stages with intermediate meetings with exchange of ideas, thoughts and experience. Draft versions are being produced successively. The objective with the project is to use attributes to describe the quality of different elements of a PSA (Analysis of initiating events, accident progression, system, data, human reliability, etc) making the PSA suitable for application in various risk informed activities. Two of the meetings in this project took place in February 2004 and in July 2004. The February meeting discussed different aspects of PSA quality in relation to applications and a draft of the TECDOC was reviewed. The meeting made recommendations for preparation of a final document and set priorities for further work in the area. The July meeting elaborated the document further in a small working group and a new draft version was prepared. A final version is expected to be published during 2005. The project has come to the conclusion that it is a limited number of PSA element attributes that are specific for a certain application. Most of the attributes concern plant specificity, realism and level of detail in a general manner, how plant specific is the model, how realistic and how detailed? Many attributes have the characteristic that they are good to have, but not necessarily needed to do the job. This last statement is valid both for a baseline PSA and a PSA application. The IAEA project has identified a limited number of attributes that are necessary to describe characteristics needed for specific applications. The PSA scope needed for a specific application is not covered by the project/document, even though it is obvious that different applications will need different scope or approaches to handle scope limitations. The guidance on performing a PSA available today is old. It is a need to review these guides and update with regard

  14. Review of APR+ Level 2 PSA

    International Nuclear Information System (INIS)

    Lehner, J.R.; Mubayi, V.; Pratt, W.T.

    2012-01-01

    Brookhaven National Laboratory (BNL) assisted the Korea Institute of Nuclear Safety (KINS) in reviewing the Level 2 Probabilistic Safety Assessment (PSA) of the APR+ Advanced Pressurized Water Reactor (PWR) prepared by the Korea Hydro and Nuclear Power Co., Ltd (KHNP) and KEPCO Engineering and Construction Co., Inc. (KEPCO-E and C). The work described in this report involves a review of the APR+ Level 2 PSA submittal (Ref. 1). The PSA and, therefore, the review is limited to consideration of accidents initiated by internal events. As part of the review process, the review team also developed three sets of Requests for Additional Information (RAIs). These RAIs were provided to KHNP and KEPCO-E and C for their evaluation and response. This final detailed report documents the review findings for each technical element of the PSA and includes consideration of all of the RAIs made by the reviewers as well as the associated responses. This final report was preceded by an interim report (Ref. 2) that focused on identifying important issues regarding the PSA. In addition, a final meeting on the project was held at BNL on November 21-22, 2011, where BNL and KINS reviewers discussed their preliminary review findings with KHNP and KEPCO-E and C staffs. Additional information obtained during this final meeting was also used to inform the review findings of this final report. The review focused not only on the robustness of the APR+ design to withstand severe accidents, but also on the capability and acceptability of the Level 2 PSA in terms of level of detail and completeness. The Korean nuclear regulatory authorities will decide whether the PSA is acceptable and the BNL review team is providing its comments for KINS consideration. Section 2.0 provides the basis for the BNL review. Section 3.0 presents the review of each technical element of the PSA. Conclusions and a summary are presented in Section 4.0. Section 5.0 contains the references.

  15. State of the art of probabilistic safety analysis (PSA) in the FRG, and principles of a PSA-guideline

    International Nuclear Information System (INIS)

    Balfanz, H.P.

    1987-01-01

    Contents of the articles: Survey of PSA performed during licensing procedures of an NPP; German Nuclear Standards' requirements on the reliability of safety systems; PSA-guideline for NPP: Principles and suggestions; Motivation and tasks of PSA; Aspects of the methodology of safety analyses; Structure of event tree and fault tree analyses; Extent of safety analyses; Performance and limits of PSA. (orig./HSCH)

  16. Development of multipurpose regulatory PSA model

    International Nuclear Information System (INIS)

    Lee, Chang Ju; Sung, Key Yong; Kim, Hho Jung; Yang, Joon Eon; Ha, Jae Joo

    2004-01-01

    Generally, risk information for nuclear facilities comes from the results of Probabilistic safety assessment (PSA). PSA is a systematic tool to ensure the safety of nuclear facilities, since it is based on thorough and consistent application of probability models. In particular, the PSA has been widely utilized for risk-informed regulation (RIR), including various licensee-initiated risk-informed applications (RIA). In any regulatory decision, the main goal is to make a sound safety decision based on technically defensible information. Also, due to the increased public requests for giving a safety guarantee, the regulator should provide the visible means of safety. The use of PSA by the regulator can give the answer on this problem. Therefore, in order to study the applicability of risk information for regulatory safety management, it is a demanding task to prepare a well-established regulatory PSA model and tool. In 2002, KINS and KAERI together made a research cooperation to form a working group to develop the regulatory PSA model - so-called MPAS model. The MPAS stands for multipurpose probabilistic analysis of safety. For instance, a role of the MPAS model is to give some risk insights in the preparation of various regulatory programs. Another role of this model is to provide an independent risk information to the regulator during regulatory decision-making, not depending on the licensee's information

  17. Development of seismic PSA methodology at JAERI

    International Nuclear Information System (INIS)

    Muramatsu, K.; Ebisawa, K.; Matsumoto, K.; Oikawa, T.; Kondo, M.

    1995-01-01

    The Japan Atomic Energy Research Institute (JAERI) is developing a methodology for seismic probabilistic safety assessment (PSA) of nuclear power plants, aiming at providing a set of procedures, computer codes and data suitable for performing seismic PSA in Japan. In order to demonstrate the usefulness of JAERI's methodology and to obtain better understanding on the controlling factors of the results of seismic PSAs, a seismic PSA for a BWR is in progress. In the course of this PSA, various improvements were made on the methodology. In the area of the hazard analysis, the application of the current method to the model plant site is being carried out. In the area of response analysis, the response factor method was modified to consider the non-linear response effect of the building. As for the capacity evaluation of components, since capacity data for PSA in Japan are very scarce, capacities of selected components used in Japan were evaluated. In the systems analysis, the improvement of the SECOM2 code was made to perform importance analysis and sensitivity analysis for the effect of correlation of responses and correlation of capacities. This paper summarizes the recent progress of the seismic PSA research at JAERI with emphasis on the evaluation of component capacity and the methodology improvement of systems reliability analysis. (author)

  18. SERIAL PERCENT-FREE PSA IN COMBINATION WITH PSA FOR POPULATION-BASED EARLY DETECTION OF PROSTATE CANCER

    Science.gov (United States)

    Ankerst, Donna Pauler; Gelfond, Jonathan; Goros, Martin; Herrera, Jesus; Strobl, Andreas; Thompson, Ian M.; Hernandez, Javier; Leach, Robin J.

    2016-01-01

    PURPOSE To characterize the diagnostic properties of serial percent-free prostate-specific antigen (PSA) in relation to PSA in a multi-ethnic, multi-racial cohort of healthy men. MATERIALS AND METHODS 6,982 percent-free PSA and PSA measures were obtained from participants in a 12 year+ Texas screening study comprising 1625 men who never underwent biopsy, 497 who underwent one or more biopsies negative for prostate cancer, and 61 diagnosed with prostate cancer. Area underneath the receiver-operating-characteristic-curve (AUC) for percent-free PSA, and the proportion of patients with fluctuating values across multiple visits were determined according to two thresholds (under 15% versus 25%) were evaluated. The proportion of cancer cases where percent-free PSA indicated a positive test before PSA > 4 ng/mL did and the number of negative biopsies that would have been spared by percent-free PSA testing negative were computed. RESULTS Percent-free PSA fluctuated around its threshold of PSA tested positive earlier than PSA in 71.4% (34.2%) of cancer cases, and among men with multiple negative biopsies and a PSA > 4 ng/mL, percent-free PSA would have tested negative in 31.6% (65.8%) instances. CONCLUSIONS Percent-free PSA should accompany PSA testing in order to potentially spare unnecessary biopsies or detect cancer earlier. When near the threshold, both tests should be repeated due to commonly observed fluctuation. PMID:26979652

  19. Evaluation of total PSA assay on vitros ECi and correlation with Kryptor-PSA assay.

    Science.gov (United States)

    Cassinat, B; Wacquet, M; Toubert, M E; Rain, J D; Schlageter, M H

    2001-01-01

    An increasing number of multiparametric immuno-analysers for PSA assays are available. As different immuno-assays may vary in their analytical quality and their accuracy for the follow-up of patients, expertise is necessary for each new assay. The PSA assay on the Vitros-ECi analyser has been evaluated and compared with the PSA assay from the Kryptor analyser. Variation coefficients were 0.91 to 1.98% for within-run assays, and 4.2% to 5.4% for interassay (PSA levels = 0.8 microgram/L to 33.6 micrograms/L). Dilution tests showed 93 to 136% recovery until 70 micrograms/L PSA. Functional sensitivity was estimated at 0.03 microgram/L. Equimolarity of the test was confirmed. Correlation of PSA levels measured with Vitros-ECi and Kryptor analysers displayed a correlation coefficient r2 of 0.9716. The half-lives and doubling times of PSA were similar using both methods. Vitros-ECi PSA assay meets the major criteria for the management of prostate cancer patients.

  20. Purification of PSA from human semen

    International Nuclear Information System (INIS)

    Venkatesh, M.

    1997-01-01

    Full text: 1. Human seminal plasma collected from many volunteers are pooled and passed through a column of phenyl sepharose equilibrated with 1.25 M ammonium sulphate. Elution is carried out with 1.25 M ammonium sulphate initially, to remove the bulk non-adsorbing proteins. Gradient elution of the absorbed proteins with 0.01 M Tris-HCl, 0.25 M NaCl, pH 7.0 buffer gives a sharp peak containing PSA. At each stage, PSA has to be identified by an independent method such as immunodiffusion or an immunoassay. 2. The absorbed protein peak containing PSA is then lyophilised, redissolved in Tris-HCl buffer and chromatographed in a Superdex-75 or Sephadex-75 column. The absorbed proteins elute out as multiple peaks and PSA is eluted as a sharp peak.At each stage, PSA has to be identified by an independent method such as immunodiffusion or an immunoassay. 3. Step 2 is repeated for better purity. 4. The PSA peak is lyophilised, dissolved in Tris-HCl buffer without NaCl and further purified on an ion exchange column (either anion or cation exchange columns such as DEAE Sephadex or CM-Sephadex or Mono Q). Gradient elution using Tris-HCl buffer without NaCl and Tris-HCl buffer with 0.25 M NaCl resulted in a sharp pure PSA peak (homogenous, sharp single band on SDS-PAGE). This procedure is based on that reported by Wang et al., Oncology, 39,1,1982

  1. Perspectives of Living PSA in NPP Krsko

    International Nuclear Information System (INIS)

    Vrbanic, I.; Kastelan, M.

    1996-01-01

    Nuclear power plant Krsko has completed the Level 1/Level 2 Probabilistic Safety Analysis (PSA) for internal initiating events and is in the process of completing the same for the external initiators. The analysis completed up to now has provided a valuable insight into a plant risk profile. In NPP Krsko there is a plan to use the PSA model as a permanent tool for the risk based applications and incorporate it into a decision making process. In order to achieve this there is a need to permanently maintain the PSA model in a manner that it reflects both the plan configuration/design at a time point and the operational experience up to the time point. All the activities aimed toward keeping the PSA model up-to-dated in this sense are usually referred to as a Living PSA (LPSA) program. NPP Krsko is in the process of defining and proceduralizing a LPSA program that would be plant specific and based on known world practices. Further, in order to be suitable for risk based applications the PSA model must be flexible in a sense that modifications to the base case model may be done easily and requantifications performed quickly as to evaluate various conditions imposed by real or hypothetical situations. NPP Krsko PSA model has been based on licensing type software. The requirements specified above dictate the transfer of the overall model to an application oriented software of newer generation with larger capabilities. The transfer becomes a part of a mentioned ongoing effort aimed at establishing LPSA model and concept. The paper present this effort and the perspectives of LPSA concept and risk based applications in NPP Krsko. (author)

  2. Vergleichende Einschätzung der diagnostischen Aussagekraft der Kenngrößen freies PSA, Alpha1-Antichymotrypsin-PSA und komplexiertes PSA in der Diagnostik des Prostatakarzinoms

    OpenAIRE

    Baumgart E; Deger S; Jung K; Lein M; Loening SA; Schnorr D

    2001-01-01

    Ziel der Studie war die vergleichende Einschätzung der diagnostischen Aussagekraft von Gesamt-PSA (tPSA), freiem PSA (fPSA), alpha1-Antichymotrypsin-PSA (ACT-PSA) und komplexiertem PSA (cPSA) sowie der entsprechenden Quotienten zur Differenzierung zwischen einem Prostatakarzinom (PCa) und einer Benignen Prostatahyperplasie (BPH). Die Bestimmung erfolgte bei insgesamt 324 Männern (PCa: n = 144; BPH: n = 89; Kontrollen: n = 91). Die tPSA- und cPSA-Konzentrationen wurden mit dem Bayer Immuno 1 S...

  3. Evaluation of serum PSA after cyproterone compound treatment compared with oral contraceptive pill in hirsute polycystic ovary syndrome patients

    OpenAIRE

    R. Taheripanah; M. Sepahvandi; A. Entezari; Z. Amiri; E. Neisani Samani

    2010-01-01

    Objective: To evaluate the effect of oral contraceptive on the serum free prostatic specific antigen (PSA) in women with polycystic ovary syndrome (PCOD) compared with cyproterone compound. Materials and methods: In this randomized clinical trial, 60 hirsute PCOD patients that referred to Imam Hossein hospital were enrolled. Baseline Ferriman–Gallway score (FG), body mass index (BMI), free PSA, 17-hydroxy progesterone (17-OHP), free testosterone, and dehydroepiandrestandione sulfate (DHEAS...

  4. Can PSA Reflex Algorithm be a valid alternative to other PSA-based prostate cancer screening strategies?

    Science.gov (United States)

    Caldarelli, G; Troiano, G; Rosadini, D; Nante, N

    2017-01-01

    The available laboratory tests for the differential diagnosis of prostate cancer, are represented by the total PSA, the free PSA, and the free/total PSA ratio. In Italy most of doctors tend to request both total and free PSA for their patients even in cases where the total PSA doesn't justify the further request of free PSA, with a consequent growth of the costs for the National Health System. The aim of our study was to predict the saving in Euro (due to reagents) and reduction in free PSA tests, applying the "PSA Reflex" algorithm. We calculated the number of total PSA and free PSA exams performed in 2014 in the Hospital of Grosseto and, simulating the application of the "PSA Reflex" algorithm in the same year, we calculated the decrease in the number of free PSA requests and we tried to predict the Euro savings in reagents, obtained from this reduction. In 2014 in the Hospital of Grosseto 25,955 total PSA tests have been performed: 3,631 (14%) resulted greater than 10 ng / ml; 7,686 (29.6%) between 2 and 10 ng / ml; 14,638 (56.4%) lower than 2 ng / ml. The performed free PSA tests were 16904. Simulating the use of "PSA Reflex" algorithm, the free PSA tests would be performed only in cases with total PSA values between 2 and 10 ng / mL with a saving of 54.5% of free PSA exams and of 8,971 euros, only for reagents. Our study showed that the "PSA Reflex" algorithm is a valid alternative leading to a reduction of the costs. The estimated intralaboratory savings, due to the reagents, seem to be modest, however, they are followed by the additional savings due to the other diagnostic processes for prostate cancers.

  5. Insulin promotes cell migration by regulating PSA-NCAM

    Energy Technology Data Exchange (ETDEWEB)

    Monzo, Hector J.; Coppieters, Natacha [Centre for Brain Research, Faculty of Medical and Health Sciences, The University of Auckland, Private Bag, 92019, Auckland (New Zealand); Department of Anatomy and Medical Imaging, Faculty of Medical and Health Sciences, The University of Auckland, Private Bag, 92019, Auckland (New Zealand); Park, Thomas I.H. [Centre for Brain Research, Faculty of Medical and Health Sciences, The University of Auckland, Private Bag, 92019, Auckland (New Zealand); Department of Pharmacology, Faculty of Medical and Health Sciences, The University of Auckland, Private Bag, 92019, Auckland (New Zealand); Dieriks, Birger V.; Faull, Richard L.M. [Centre for Brain Research, Faculty of Medical and Health Sciences, The University of Auckland, Private Bag, 92019, Auckland (New Zealand); Department of Anatomy and Medical Imaging, Faculty of Medical and Health Sciences, The University of Auckland, Private Bag, 92019, Auckland (New Zealand); Dragunow, Mike [Centre for Brain Research, Faculty of Medical and Health Sciences, The University of Auckland, Private Bag, 92019, Auckland (New Zealand); Department of Pharmacology, Faculty of Medical and Health Sciences, The University of Auckland, Private Bag, 92019, Auckland (New Zealand); Curtis, Maurice A., E-mail: m.curtis@auckland.ac.nz [Centre for Brain Research, Faculty of Medical and Health Sciences, The University of Auckland, Private Bag, 92019, Auckland (New Zealand); Department of Anatomy and Medical Imaging, Faculty of Medical and Health Sciences, The University of Auckland, Private Bag, 92019, Auckland (New Zealand)

    2017-06-01

    Cellular interactions with the extracellular environment are modulated by cell surface polysialic acid (PSA) carried by the neural cell adhesion molecule (NCAM). PSA-NCAM is involved in cellular processes such as differentiation, plasticity, and migration, and is elevated in Alzheimer's disease as well as in metastatic tumour cells. Our previous work demonstrated that insulin enhances the abundance of cell surface PSA by inhibiting PSA-NCAM endocytosis. In the present study we have identified a mechanism for insulin-dependent inhibition of PSA-NCAM turnover affecting cell migration. Insulin enhanced the phosphorylation of the focal adhesion kinase leading to dissociation of αv-integrin/PSA-NCAM clusters, and promoted cell migration. Our results show that αv-integrin plays a key role in the PSA-NCAM turnover process. αv-integrin knockdown stopped PSA-NCAM from being endocytosed, and αv-integrin/PSA-NCAM clusters co-labelled intracellularly with Rab5, altogether indicating a role for αv-integrin as a carrier for PSA-NCAM during internalisation. Furthermore, inhibition of p-FAK caused dissociation of αv-integrin/PSA-NCAM clusters and counteracted the insulin-induced accumulation of PSA at the cell surface and cell migration was impaired. Our data reveal a functional association between the insulin/p-FAK-dependent regulation of PSA-NCAM turnover and cell migration through the extracellular matrix. Most importantly, they identify a novel mechanism for insulin-stimulated cell migration. - Highlights: • Insulin modulates PSA-NCAM turnover through upregulation of p-FAK. • P-FAK modulates αv-integrin/PSA-NCAM clustering. • αv-integrin acts as a carrier for PSA-NCAM endocytosis. • Cell migration is promoted by cell surface PSA. • Insulin promotes PSA-dependent migration in vitro.

  6. Insulin promotes cell migration by regulating PSA-NCAM

    International Nuclear Information System (INIS)

    Monzo, Hector J.; Coppieters, Natacha; Park, Thomas I.H.; Dieriks, Birger V.; Faull, Richard L.M.; Dragunow, Mike; Curtis, Maurice A.

    2017-01-01

    Cellular interactions with the extracellular environment are modulated by cell surface polysialic acid (PSA) carried by the neural cell adhesion molecule (NCAM). PSA-NCAM is involved in cellular processes such as differentiation, plasticity, and migration, and is elevated in Alzheimer's disease as well as in metastatic tumour cells. Our previous work demonstrated that insulin enhances the abundance of cell surface PSA by inhibiting PSA-NCAM endocytosis. In the present study we have identified a mechanism for insulin-dependent inhibition of PSA-NCAM turnover affecting cell migration. Insulin enhanced the phosphorylation of the focal adhesion kinase leading to dissociation of αv-integrin/PSA-NCAM clusters, and promoted cell migration. Our results show that αv-integrin plays a key role in the PSA-NCAM turnover process. αv-integrin knockdown stopped PSA-NCAM from being endocytosed, and αv-integrin/PSA-NCAM clusters co-labelled intracellularly with Rab5, altogether indicating a role for αv-integrin as a carrier for PSA-NCAM during internalisation. Furthermore, inhibition of p-FAK caused dissociation of αv-integrin/PSA-NCAM clusters and counteracted the insulin-induced accumulation of PSA at the cell surface and cell migration was impaired. Our data reveal a functional association between the insulin/p-FAK-dependent regulation of PSA-NCAM turnover and cell migration through the extracellular matrix. Most importantly, they identify a novel mechanism for insulin-stimulated cell migration. - Highlights: • Insulin modulates PSA-NCAM turnover through upregulation of p-FAK. • P-FAK modulates αv-integrin/PSA-NCAM clustering. • αv-integrin acts as a carrier for PSA-NCAM endocytosis. • Cell migration is promoted by cell surface PSA. • Insulin promotes PSA-dependent migration in vitro.

  7. A methodology for PSA model validation

    International Nuclear Information System (INIS)

    Unwin, S.D.

    1995-09-01

    This document reports Phase 2 of work undertaken by Science Applications International Corporation (SAIC) in support of the Atomic Energy Control Board's Probabilistic Safety Assessment (PSA) review. A methodology is presented for the systematic review and evaluation of a PSA model. These methods are intended to support consideration of the following question: To within the scope and depth of modeling resolution of a PSA study, is the resultant model a complete and accurate representation of the subject plant? This question was identified as a key PSA validation issue in SAIC's Phase 1 project. The validation methods are based on a model transformation process devised to enhance the transparency of the modeling assumptions. Through conversion to a 'success-oriented' framework, a closer correspondence to plant design and operational specifications is achieved. This can both enhance the scrutability of the model by plant personnel, and provide an alternative perspective on the model that may assist in the identification of deficiencies. The model transformation process is defined and applied to fault trees documented in the Darlington Probabilistic Safety Evaluation. A tentative real-time process is outlined for implementation and documentation of a PSA review based on the proposed methods. (author). 11 refs., 9 tabs., 30 refs

  8. The Tobacco Use Epidemic – What You Need to Know PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    This 60 second PSA is based on the September, 2011 CDC Vital Signs report. Fewer Americans are smoking cigarettes, and daily smokers are smoking less; however, even occasional smoking causes harm. The best option for any smoker is to quit completely. Quitting at any age has benefits, and the sooner you quit, the sooner your body can begin to heal.

  9. Proteolytic activity of prostate-specific antigen (PSA towards protein substrates and effect of peptides stimulating PSA activity.

    Directory of Open Access Journals (Sweden)

    Johanna M Mattsson

    Full Text Available Prostate-specific antigen (PSA or kallikrein-related peptidase-3, KLK3 exerts chymotrypsin-like proteolytic activity. The main biological function of PSA is the liquefaction of the clot formed after ejaculation by cleavage of semenogelins I and II in seminal fluid. PSA also cleaves several other substrates, which may explain its putative functions in prostate cancer and its antiangiogenic activity. We compared the proteolytic efficiency of PSA towards several protein and peptide substrates and studied the effect of peptides stimulating the activity of PSA with these substrates. An endothelial cell tube formation model was used to analyze the effect of PSA-degraded protein fragments on angiogenesis. We showed that PSA degrades semenogelins I and II much more efficiently than other previously identified protein substrates, e.g., fibronectin, galectin-3 and IGFBP-3. We identified nidogen-1 as a new substrate for PSA. Peptides B2 and C4 that stimulate the activity of PSA towards small peptide substrates also enhanced the proteolytic activity of PSA towards protein substrates. Nidogen-1, galectin-3 or their fragments produced by PSA did not have any effect on endothelial cell tube formation. Although PSA cleaves several other protein substrates, in addition to semenogelins, the physiological importance of this activity remains speculative. The PSA levels in prostate are very high, but several other highly active proteases, such as hK2 and trypsin, are also expressed in the prostate and may cleave protein substrates that are weakly cleaved by PSA.

  10. Proteolytic Activity of Prostate-Specific Antigen (PSA) towards Protein Substrates and Effect of Peptides Stimulating PSA Activity

    Science.gov (United States)

    Mattsson, Johanna M.; Ravela, Suvi; Hekim, Can; Jonsson, Magnus; Malm, Johan; Närvänen, Ale; Stenman, Ulf-Håkan; Koistinen, Hannu

    2014-01-01

    Prostate-specific antigen (PSA or kallikrein-related peptidase-3, KLK3) exerts chymotrypsin-like proteolytic activity. The main biological function of PSA is the liquefaction of the clot formed after ejaculation by cleavage of semenogelins I and II in seminal fluid. PSA also cleaves several other substrates, which may explain its putative functions in prostate cancer and its antiangiogenic activity. We compared the proteolytic efficiency of PSA towards several protein and peptide substrates and studied the effect of peptides stimulating the activity of PSA with these substrates. An endothelial cell tube formation model was used to analyze the effect of PSA-degraded protein fragments on angiogenesis. We showed that PSA degrades semenogelins I and II much more efficiently than other previously identified protein substrates, e.g., fibronectin, galectin-3 and IGFBP-3. We identified nidogen-1 as a new substrate for PSA. Peptides B2 and C4 that stimulate the activity of PSA towards small peptide substrates also enhanced the proteolytic activity of PSA towards protein substrates. Nidogen-1, galectin-3 or their fragments produced by PSA did not have any effect on endothelial cell tube formation. Although PSA cleaves several other protein substrates, in addition to semenogelins, the physiological importance of this activity remains speculative. The PSA levels in prostate are very high, but several other highly active proteases, such as hK2 and trypsin, are also expressed in the prostate and may cleave protein substrates that are weakly cleaved by PSA. PMID:25237904

  11. Design review of SPWR with PSA methodology

    International Nuclear Information System (INIS)

    Oikawa, Tetsukuni; Muramatsu, Ken; Iwamura, Takamichi; Tone, Tatsuzo; Kasahara, Takeo; Mizuno, Yoshio

    1993-01-01

    This paper presents the procedures and results of a PSA (Probabilistic Safety Assessment) of the SPWR (System-Integrated PWR), which is being developed at the Japan Atomic Energy Research Institute (JAERI) as a medium sized innovative passive safe reactor, to assist in the design improvement of the SPWR by reviewing the design and identifying the design weaknesses. This PSA was performed in four steps: (1) identification of initiating events by the failure mode effect analysis and other methods, (2) delineation of accident sequences for three selected initiating events using accident progression flow charts and event trees, (3) quantification of event trees based on the review of past PSAs for LWRs, and (4) sensitivity analysis and interpretation of results. Qualitative and quantitative results of PSA provided very useful information for decision makings of design improvement and recommendations for further consideration in the process of detailed design

  12. A Preliminary Fire PSA on PGSFR

    International Nuclear Information System (INIS)

    Kim, Kilyoo; Han, Sanghoon; Lee, KwiLim

    2017-01-01

    A Prototype Generation IV Sodium Fast Reactor (PGSFR) is under design with defense in depth concept with active, passive, and inherent safety features to acquire a design approval for PGSFR from Korean regulatory authority by around 2017. A preliminary fire PSA on PGSFR is done in 2016 and a final fire PSA of PGSFR will be done in 2017. The characteristics of the preliminary fire PSA on PGSFR are described in this paper. Since PGSFR is very safe reactor, it is not bad approach to use a conservative assumption in the preliminary PSA. In addition, several drawings including cable routing are not yet issued, a conservative calculation for CDF is performed. As shown in Table 2, the CDF caused by the fire in the control room takes 89% portion of total CDF. Thus, a detailed fire modeling for control room is necessary for the final fire PSA on PGSFR. Also, the increased ignition frequency due to sodium leak would be derived by considering the sodium piping complexity in the final fire PSA on PGSFR. The 4th column of Table 2 is derived the 3rd column by multiplying the factor (592/1177). The 5th column is the ignition frequency caused by the sodium leak. The 6th column is derived by summing the 4th column and the 5th column. The 7th column is the CDF portion of each fire area. The control room (fire area F-A404A) is the most important area since the control room fire takes 89% portion of total CDF.

  13. Seminal plasma PSA in spinal cord injured men

    DEFF Research Database (Denmark)

    Brasso, K; Sønksen, J; Sommer, P

    1998-01-01

    The aim of the study was to evaluate the impact of spinal cord injury on seminal plasma PSA concentration.......The aim of the study was to evaluate the impact of spinal cord injury on seminal plasma PSA concentration....

  14. Use of PSA to support accident management at NPPs

    International Nuclear Information System (INIS)

    Gomez Cobo, A.

    1997-01-01

    The presentation discusses the following: Overview of PSA level 2; Introduction: Framework; Accident Progression Phenomena in the Confinement/containment; Severe Accident Sequences; Examples; Results and Insights. Accident Management: Concepts; Process; Use of PSA to support Accident; Management

  15. Molecular Form Differences Between Prostate-Specific Antigen (PSA) Standards Create Quantitative Discordances in PSA ELISA Measurements

    Science.gov (United States)

    McJimpsey, Erica L.

    2016-01-01

    The prostate-specific antigen (PSA) assays currently employed for the detection of prostate cancer (PCa) lack the specificity needed to differentiate PCa from benign prostatic hyperplasia and have high false positive rates. The PSA calibrants used to create calibration curves in these assays are typically purified from seminal plasma and contain many molecular forms (intact PSA and cleaved subforms). The purpose of this study was to determine if the composition of the PSA molecular forms found in these PSA standards contribute to the lack of PSA test reliability. To this end, seminal plasma purified PSA standards from different commercial sources were investigated by western blot (WB) and in multiple research grade PSA ELISAs. The WB results revealed that all of the PSA standards contained different mass concentrations of intact and cleaved molecular forms. Increased mass concentrations of intact PSA yielded higher immunoassay absorbance values, even between lots from the same manufacturer. Standardization of seminal plasma derived PSA calibrant molecular form mass concentrations and purification methods will assist in closing the gaps in PCa testing measurements that require the use of PSA values, such as the % free PSA and Prostate Health Index by increasing the accuracy of the calibration curves. PMID:26911983

  16. Molecular Form Differences Between Prostate-Specific Antigen (PSA) Standards Create Quantitative Discordances in PSA ELISA Measurements

    Science.gov (United States)

    McJimpsey, Erica L.

    2016-02-01

    The prostate-specific antigen (PSA) assays currently employed for the detection of prostate cancer (PCa) lack the specificity needed to differentiate PCa from benign prostatic hyperplasia and have high false positive rates. The PSA calibrants used to create calibration curves in these assays are typically purified from seminal plasma and contain many molecular forms (intact PSA and cleaved subforms). The purpose of this study was to determine if the composition of the PSA molecular forms found in these PSA standards contribute to the lack of PSA test reliability. To this end, seminal plasma purified PSA standards from different commercial sources were investigated by western blot (WB) and in multiple research grade PSA ELISAs. The WB results revealed that all of the PSA standards contained different mass concentrations of intact and cleaved molecular forms. Increased mass concentrations of intact PSA yielded higher immunoassay absorbance values, even between lots from the same manufacturer. Standardization of seminal plasma derived PSA calibrant molecular form mass concentrations and purification methods will assist in closing the gaps in PCa testing measurements that require the use of PSA values, such as the % free PSA and Prostate Health Index by increasing the accuracy of the calibration curves.

  17. The Domino Effect PSA (:30)

    Centers for Disease Control (CDC) Podcasts

    2017-10-24

    This 30 second public service announcement is about a deadly chain reaction in your body called sepsis.  Created: 10/24/2017 by Centers for Disease Control and Prevention (CDC).   Date Released: 10/24/2017.

  18. Are You Listening? PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2015-09-08

    This radio public service announcement encourages women to learn the symptoms of gynecologic cancer and pay attention to what their bodies are telling them.  Created: 9/8/2015 by National Center for Chronic Disease Prevention and Health Promotion (NCCDPHP).   Date Released: 9/8/2015.

  19. Are You Listening? PSA (:30)

    Centers for Disease Control (CDC) Podcasts

    2015-09-08

    This radio public service announcement encourages women to learn the symptoms of gynecologic cancer and pay attention to what their bodies are telling them.  Created: 9/8/2015 by National Center for Chronic Disease Prevention and Health Promotion (NCCDPHP).   Date Released: 9/8/2015.

  20. The use of PSA in the French regulatory practice

    International Nuclear Information System (INIS)

    Mennesiez, H.

    1994-01-01

    The presentation gives a description of fundamental documents (since 1977-1978) through which have been set up in France probabilistic objectives, and PSAs, including shutdown states, performed for 900-1300 MWe PWR-type nuclear power plants. PSA developments and use, including fire PSA, level 2 and PSA for the future French-German European Pressurized Reactor (EPR) are also discussed

  1. PSA methodology development and application in Japan

    International Nuclear Information System (INIS)

    Kazuo Sato; Toshiaki Tobioka; Kiyoharu Abe

    1987-01-01

    The outlines of Japanese activities on development and application of probabilistic safety assessment (PSA) methodologies are described. First the activities on methodology development are described for system reliability analysis, operational data analysis, core melt accident analysis, environmental consequence analysis and seismic risk analysis. Then the methodoligy application examples by the regulatory side and the industry side are described. (author)

  2. Screen for Life: Meryl Streep PSA (:30)

    Centers for Disease Control (CDC) Podcasts

    2013-05-16

    In this 30 second PSA, Academy Award®-winning actress Meryl Streep urges viewers to get screened for colorectal cancer.  Created: 5/16/2013 by Centers for Disease Control and Prevention (CDC).   Date Released: 5/16/2013.

  3. Screen for Life: Meryl Streep PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2013-05-16

    In this 60 second PSA, Academy Award®-winning actress Meryl Streep urges viewers to get screened for colorectal cancer.  Created: 5/16/2013 by Centers for Disease Control and Prevention (CDC).   Date Released: 5/16/2013.

  4. French 900 MWe PWR PSA preliminary results

    International Nuclear Information System (INIS)

    Lanore, J.M.; Brisbois, J.

    1988-10-01

    A PSA is performed by the Safety Assessment Department of CEA for a 900 MWe standardized plant. The paper presents the objectives, the scope of the study and the relative preliminary results. Some general insights are drawn, especially the benefit related to the implementation of emergency procedures

  5. Deepwater Horizon Oil Spill PSA (:24)

    Centers for Disease Control (CDC) Podcasts

    This 24 second PSA from Dr. Regina Benjamin, U.S. Surgeon General, encourages people to get help if they are feeling sad, angry, depressed, or stressed as a result of the Gulf oil spill. It was recorded so that localities can add their own "For more information" at the end, as appropriate.

  6. Take Charge. Take the Test. PSA (:30)

    Centers for Disease Control (CDC) Podcasts

    As part of the Take Charge. Take the Test. campaign, this 30 second PSA encourages African American women to get tested for HIV. Locations for a free HIV test can be found by visiting hivtest.org/takecharge or calling 1-800-CDC-INFO (1-800-232-4636).

  7. Communication Can Save Lives PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    This 60 second public service announcement (PSA) is based on the August 2015 CDC Vital Signs report. Antibiotic-resistant germs cause at least 23,000 deaths each year. Learn how public health authorities and health care facilities can work together to save lives.

  8. Safer Food Saves Lives PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    This 60 second PSA is based on the November 2015 CDC Vital Signs report. Contaminated food sent to several states can cause multistate outbreaks of foodborne illness and make a lot of people seriously ill. Learn what can be done to prevent and stop outbreaks.

  9. Interoperability in the Planetary Science Archive (PSA)

    Science.gov (United States)

    Rios Diaz, C.

    2017-09-01

    The protocols and standards currently being supported by the recently released new version of the Planetary Science Archive at this time are the Planetary Data Access Protocol (PDAP), the EuroPlanet- Table Access Protocol (EPN-TAP) and Open Geospatial Consortium (OGC) standards. We explore these protocols in more detail providing scientifically useful examples of their usage within the PSA.

  10. Secundaire analyses organisatiebeleid psychosociale arbeidsbelasting (PSA)

    NARCIS (Netherlands)

    Kraan, K.O.; Houtman, I.L.D.

    2016-01-01

    Hoe het organisatiebeleid rond psychosociale arbeidsbelasting (PSA) eruit ziet anno 2014 en welke samenhang er is met ander beleid en uitkomstmaten, zijn de centrale vragen in dit onderzoek. De resultaten van deze verdiepende analyses kunnen ten goede komen aan de lopende campagne ‘Check je

  11. STD Awareness PSA - College 2 (:30)

    Centers for Disease Control (CDC) Podcasts

    2010-04-22

    This PSA, targeted to college-aged youth and young adults, encourages listeners to get tested for STDs.  Created: 4/22/2010 by Centers for Disease Control and Prevention (CDC).   Date Released: 4/22/2010.

  12. STD Awareness PSA - College 1 (:30)

    Centers for Disease Control (CDC) Podcasts

    2010-04-22

    This PSA, targeted to college-aged youth and young adults, encourages listeners to get tested for STDs.  Created: 4/22/2010 by Centers for Disease Control and Prevention (CDC).   Date Released: 4/22/2010.

  13. STD Awareness PSA - Male Announcer 2 (:30)

    Centers for Disease Control (CDC) Podcasts

    2010-04-22

    This PSA encourages listeners to get tested for STDs. Target - Men who have sex with other men.  Created: 4/22/2010 by Centers for Disease Control and Prevention (CDC).   Date Released: 4/22/2010.

  14. Stop C. difficile Infections PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    This 60 second PSA is based on the March 2012 CDC Vital Signs report. C. difficile is a germ that causes diarrhea linked to 14,000 deaths in the US each year. This podcast helps health care professionals learn how to prevent C. difficile infections.

  15. Time to PSA rise differentiates the PSA bounce after HDR and LDR brachytherapy of prostate cancer.

    Science.gov (United States)

    Burchardt, Wojciech; Skowronek, Janusz

    2018-02-01

    To investigate the differences in prostate-specific antigen (PSA) bounce (PB) after high-dose-rate (HDR-BT) or low-dose-rate (LDR-BT) brachytherapy alone in prostate cancer patients. Ninety-four patients with localized prostate cancer (T1-T2cN0), age ranged 50-81 years, were treated with brachytherapy alone between 2008 and 2010. Patients were diagnosed with adenocarcinoma, Gleason score ≤ 7. The LDR-BT total dose was 144-145 Gy, in HDR-BT - 3 fractions of 10.5 or 15 Gy. The initial PSA level (iPSA) was assessed before treatment, then PSA was rated every 3 months over the first 2 years, and every 6 months during the next 3 years. Median follow-up was 3.0 years. Mean iPSA was 7.8 ng/ml. In 58 cases, PSA decreased gradually without PB or biochemical failure (BF). In 24% of patients, PB was observed. In 23 cases (24%), PB was observed using 0.2 ng/ml definition; in 10 cases (11%), BF was diagnosed using nadir + 2 ng/ml definition. The HDR-BT and LDR-BT techniques were not associated with higher level of PB (26 vs. 22%, p = 0.497). Time to the first PSA rise finished with PB was significantly shorter after HDR-BT then after LDR-BT (median, 10.5 vs. 18.0 months) during follow-up. Predictors for PB were observed only after HDR-BT. Androgen deprivation therapy (ADT) and higher Gleason score decreased the risk of PB (HR = 0.11, p = 0.03; HR = 0.51, p = 0.01). The higher PSA nadir and longer time to PSA nadir increased the risk of PB (HR 3.46, p = 0.02; HR 1.04, p = 0.04). There was no predictors for PB after LDR-BT. HDR-BT and LDR-BT for low and intermediate risk prostate cancer had similar PB rate. The PB occurred earlier after HDR-BT than after LDR-BT. ADT and higher Gleason score decreased, and higher PSA nadir and longer time to PSA nadir increased the risk of PB after HDR-BT.

  16. External Events PSA for the Paks NPP

    International Nuclear Information System (INIS)

    Bareith, Attila; Karsa, Zoltan; Siklossy, Tamas; Vida, Zoltan

    2014-01-01

    Initially, probabilistic safety assessment of external events was limited to the analysis of earthquakes for the Paks Nuclear Power Plant in Hungary. The level 1 seismic PSA was completed in 2002 showing a significant contribution of seismic failures to core damage risk. Although other external events of natural origin had previously been screened out from detailed plant PSA mostly on the basis of event frequencies, a review of recent experience on extreme weather phenomena made during the periodic safety review of the plant led to the initiation of PSA for external events other than earthquakes in 2009. In the meantime, the accident of the Fukushima Dai-ichi Nuclear Power Plant confirmed further the importance of such an analysis. The external event PSA for the Paks plant followed the commonly known steps: selection and screening of external hazards, hazard assessment for screened-in external events, analysis of plant response and fragility, PSA model development, and risk quantification and interpretation of results. As a result of event selection and screening the following weather related external hazards were subject to detailed analysis: extreme wind, extreme rainfall (precipitation), extreme snow, extremely high and extremely low temperatures, lightning, frost and ice formation. The analysis proved to be a significant challenge due to scarcity of data, lack of knowledge, as well as limitations of existing PSA methodologies. This paper presents an overview of the external events PSA performed for the Paks NPP. Important methodological aspects are summarised. Key analysis findings and unresolved issues that need further elaboration are highlighted. Development of external events PSA for the Paks NPP was completed by the end of 2012. The analysis followed the commonly known steps: selection and screening of external hazards, hazard assessment for screened-in external events, analysis of plant response and fragility, PSA model development, and risk

  17. PSA testing anxiety, psychological morbidity, and PSA utility in the management of prostate cancer.

    OpenAIRE

    Micsunescu, Anamaria Elia

    2017-01-01

    Anecdotal reports from urologists and medical oncologists have suggested that patients with prostate cancer (PCa) often present with anxiety related to ongoing monitoring of their PSA levels as part of their disease management. The purpose of the current study, therefore, was to determine the prevalence and severity of prostate specific antigen (PSA) testing anxiety in a population of patients with either localised or metastatic PCa living in Australia. Other aspects of psychological morbidit...

  18. Performance indicators at Embalse NPP: PSA and safety system indicators based on PSA models

    International Nuclear Information System (INIS)

    Fornero, D.A.

    2001-01-01

    Several indicators have been implemented at Embalse NPP. The objective was selecting some representative parameters to evaluate the performance of both the plant and the personnel activities, important for safety. A first set of indicators was defined in accordance with plant technical staff criteria. A complementary set of them was addressed later based on WANO guidance. This report presents the set of indicators used at Embalse NPP, centering the description to related to safety systems performance indicators (SSPI). Some considerations are done about the calculation methods, the need for aligning and updating their values following Embalse Probabilistic Safety Assessment (PSA) development, and some pros and cons of using the PSA model for getting systems indicators. Owing to the fact that PSA ownership by utilities is also a subject of the meeting, some characteristics of the organization of the PSA Project are described at the beginning of the report. At Embalse NPP a Level 1 PSA has been developed under the responsibility of its own plant and with an important contribution from the IAEA. PSA was developed at the site, conducting this to a study strongly interactive with the station staff. (author)

  19. Management and organisational factors in PSA; Organisations- und Management-Faktoren in der PSA

    Energy Technology Data Exchange (ETDEWEB)

    Balfanz, H.P. [TUEV Nord e.V., Hamburg (Germany)

    1999-04-01

    The constraints of PSA are increasingly considered with increasing application of PSA for the safety management of nuclear power plants (see US-NRC, 'Risk Informed Regulation', NRC-1). There is a vivid international discourse about the applicability of the variables of plant management and organisation in PSAs, which has lead to a great variety of research activities into this matter (see PSAM 4). This paper here summarizes the current state of progress of research work and discusses the applicability of results. The studies for comparative assessment of methodology and results were performed by the TUeV Nord under the roof of the BMU/BfS-sponsored project SR 2260, ''Further development of probabilistic methods for nuclear power plant safety assessment. (orig./CB) [German] Mit zunehmender Anwendung der PSA (Probabilistische Sicherheitsanalyse) im Sicherheitsmanagement von KKW (vergl. US-NRC, Einfuehrung des Konzepts 'Risk Informed Regulation' NRC-1) gewinnt die Beachtung der Grenzen der PSA zusaetzliche Bedeutung. International ist eine intensive Diskussion ueber die Moeglichkeiten einer Einbindung der Einflussgroesse von Organisation und Management in der PSA zu verzeichnen und wird belegt durch vielfaeltige Forschungs- und Entwicklungsarbeiten (vergl. PSAM 4). Dieser Beitrag setzt sich in erster Linie mit diesem Entwicklungsstand auseinander und diskutiert seinen Anwendungsstand fuer die PSA. Die hierzu vom TUeV Nord durchgefuehrten Arbeiten basieren auf dem BMU/BfS-Vorhaben SR 2260, 'Weiterentwicklung probabilistischer Methoden zur Sicherheitsbeurteilung von KKW'. (orig.)

  20. Generation of monoclonal antibodies against prostate specific antigen (PSA) for the detection of PSA and its purification

    International Nuclear Information System (INIS)

    Acevedo Castro, Boris Ernesto

    2012-01-01

    The prostate cancer in Cuba is a problem of health (2672 diagnosed cases and 2769 deaths in 2007). Various diagnostic methods have been implemented for the detection and management of this disease, emphasizing among them (PSA) prostate-specific antigen serological determination. At this work was generated and characterized a panel of 11 antibodies (AcMs) monoclonal IgG1 detected with high affinity described major epitopes of the PSA, both in solution and attached to the test plate. From the panel obtained AcMs was the standardization of an essay type ELISA for the detection of serum total PSA (associated and free) equimolar, based on antibody monoclonal CB-PSA.4 in the coating and the CB-PSA.9 coupled with biotin as liner, with a detection limit of 0.15 ng/mL. Similarly, standardized system for detection in serum free PSA, based on the AcMs CB-PSA.4 (coating) and CB-PSA.2 coupled with biotin (liner), with a detection limit of 0.5 ng/mL. Finally, with the purpose of using PSA as standard in trials type ELISA, developed a simple method of inmunopurificación based on the AcM, CB-PSA.2, which was obtained the PSA with a purity exceeding 90%. Immunoassay Centre on the basis of the AcMs panel and the results of this study, developed and recorded two diagnostic systems for the detection of PSA in human serum. (author)

  1. Clinical performance of serum [-2]proPSA derivatives, %p2PSA and PHI, in the detection and management of prostate cancer.

    Science.gov (United States)

    Huang, Ya-Qiang; Sun, Tong; Zhong, Wei-De; Wu, Chin-Lee

    2014-01-01

    Prostate-specific antigen (PSA) has been widely used as a serum marker for prostate cancer (PCa) screening or progression monitoring, which dramatically increased rate of early detection while significantly reduced PCa-specific mortality. However, a number of limitations of PSA have been noticed. Low specificity of PSA may lead to overtreatment in men who presenting with a total PSA (tPSA) level of PHI) and %p2PSA, which were defined as [(p2PSA/fPSA) × √ tPSA] and [(p2PSA/fPSA) × 100] respectively, have been suggested to be increased in PCa and can better distinguish PCa from benign prostatic diseases than tPSA or fPSA. We performed a systematic review of the available scientific evidences to evaluate the potentials of %p2PSA and PHI in clinical application. Mounting evidences suggested that both %p2PSA and PHI possess higher area under the ROC curve (AUC) and better specificity at a high sensitivity for PCa detection when compare with tPSA and %fPSA. It indicated that measurements of %p2PSA and PHI significantly improved the accuracy of PCa detection and diminished unnecessary biopsies. Furthermore, elevations of %p2PSA and PHI are related to more aggressive diseases. %p2PSA and PHI might be helpful in reducing overtreatment on indolent cases or assessing the progression of PCa in men who undergo active surveillance. Further studies are needed before being applied in routine clinical practice.

  2. An approach to develop a PSA workstation in KAERI

    International Nuclear Information System (INIS)

    Kim, T. W.; Han, S. H.; Park, C. K.

    1995-01-01

    This paper describes three kinds of efforts for the development of PSA workstation in KAERI; Development of a PSA tool, KIRAP, Reliability Database Development, Living PSA tool development. Korea has 9 nuclear power plants (NPPs) in operation and 9 NPPs under design or construction. For the NPPs recently constructed or designed, the probabilistic safety assessments (PSAs) have been performed by the Government requirements. For these PSAs, the MSDOS version of KIRAP has been used. For the consistent data management and the easiness of information handling needed in PSA, APSA workstation, KIRAP-Win is under development under Windows environment. For the reliability database on component failure rate, human error rate, and common cause failure rate, data used in international PSA or reliability data handbook are collected and processed to use in Korean new plants' PSAs. Finally, an effort for the development of a living PSA tool in KAERI based on dynamic PSA concept is described

  3. A Joint Report on PSA for New and Advanced Reactors

    International Nuclear Information System (INIS)

    2013-01-01

    This report addresses the application of Probabilistic Safety Assessment (PSA) to new and advanced nuclear reactors. As far as advanced reactors are concerned, the objectives were to characterize the ability of current PSA technology to address key questions regarding the development, acceptance and licensing of advanced reactor designs, to characterize the potential value of advanced PSA methods and tools for application to advanced reactors, and to develop recommendations for any needed developments regarding PSA for these reactors. As far as the design and commissioning of new nuclear power plants is concerned, the objectives were to identify and characterize current practices regarding the role of PSA, to identify key technical issues regarding PSA, lessons learned and issues requiring further work; to develop recommendations regarding the use of PSA, and to identify future international cooperative work on the identified issues. In order to reach these objectives, questionnaires had been sent to participating countries and organisations

  4. A PSA study for the SMART basic design

    International Nuclear Information System (INIS)

    Han, Sang Hoon; Kim, H. C.; Yang, S. H.; Lee, D. J.

    2002-03-01

    SMART (System-Integrated Modular Advanced Reactor) is under development that is an advanced integral type small and medium category nuclear power reactor with the rated thermal power of 330 MW. A Probabilistic Safety Analysis (PSA) for the SMART basic design has been performed to evaluate the safety and optimize the design. Currently, the basic design is done and the detailed design is not available for the SMART, we made several assumptions about the system design before performing the PSA. The scope of the PSA was limited to the Level-1 internal full power PSA. The level-2 and 3 PSA, the external PSA, and the low power/shutdown PSA will be performed in the final design stage

  5. The impact of sociodemographic factors and PSA screening among low-income Black and White men: data from the Southern Community Cohort Study.

    Science.gov (United States)

    Moses, K A; Zhao, Z; Bi, Y; Acquaye, J; Holmes, A; Blot, W J; Fowke, J H

    2017-12-01

    Variation in PSA screening is a potential source of disparity in prostate cancer survival, particularly among underserved populations. We sought to examine the impact of race and socioeconomic status (SES) on receipt of PSA testing among low-income men. Black (n=22 167) and White (n=9588) men aged ⩾40 years completed a baseline questionnaire from 2002 to 2009 as part of the Southern Community Cohort Study. Men reported whether they had ever received PSA testing and had testing within the prior 12 months. To evaluate the associations between SES, race and receipt of PSA testing, odds ratios (ORs) and 95% confidence intervals (CIs) were estimated from the multivariable logistic models where age, household income, insurance status, marital status, body mass index and educational level were adjusted. Black men were younger, had a lower income, less attained education and were more likely to be unmarried and uninsured (all PPSA testing rose from 50 more likely than Blacks to have received testing. Lower SES was significantly associated with less receipt of PSA testing in both groups. After adjustment for SES, White men had significantly lower odds of PSA testing (OR 0.81; 95% CI: 0.76-0.87). Greater PSA testing among White than Black men over the age of 50 years in this low-income population appears to be mainly a consequence of SES. Strategies for PSA screening may benefit from tailoring to the social circumstances of the men being screened.

  6. Early detection of prostate cancer in Syria using T.PSA and F.PSA

    International Nuclear Information System (INIS)

    Adel, M.; Abu Daher, D.

    2009-12-01

    The aim of the current study is performing an initial prostate cancer screening test using PSA and F PSA tumour markers. A total of 3000 men in 40-75 years of age were participated in this study. Demographic and clinical data for subjects were collected by the programme staff. Total PSA and free PSA assays were determined using the ImunoTech total and free PSA assay kits, based on IRMA technique (kindly provided by the International Atomic Energy Agency). Criteria for participating in this study included : 1) men of age 50-75 (men of age as low as 40 were included in case of positive family history). 2) No previous history of prostate cancer. The following parameters were followed to refer the suspicious cases to a specialized hospital specific tests: 1)PSA>3 ng/ml . 2)High PSA value according to the participant age group. 3) Low F/TPSA ratio. In the hospital the following tests were performed:1) Complete clinical exam including DRE.2)TRUS in some cases.3) Biopsy for highly suspicious cases. 4)The low suspicious cases were retested in six months. Out of 338 cases referred to a specialized hospital, 264 cases were shown prostatic benign prostatic hyperplasia (BPH),while 36 cases proved to be prostatic cancer. However, the contact was lost in 36 cases because of changing the phone number or travelling outside the country . The detection rate of prostate cancer among all participating cases in this study was 1.2%, while this ratio was 10.7% among the referred cases. F/TPSA ratio has shown a good ability to discriminate between prostate cancer and benign prostatic hyperplasia. (author)

  7. Experience from the comparison of two PSA-studies

    International Nuclear Information System (INIS)

    Holmberg, J.; Pulkkinen, U.

    2001-03-01

    Two probabilistic safety assessments (PSA) made for nearly identical reactors units (Forsmark 3 and Oskarshamn 3) have been compared. Two different analysis teams made the PSAs, and the analyses became quite different. The goal of the study is to identify, clarify and explain differences between PSA-studies. The purpose is to understand limitations and uncertainties in PSA, to explain reasons for differences between PSA-studies, and to give recommendations for comparison of PSA-studies and for improving the PSA-methodology. The reviews have been made by reading PSA-documentation, using the computer model and interviewing persons involved in the projects. The method and findings have been discussed within the project group. Both the PSA-project and various parts in the PSA-model have been reviewed. A major finding was that the two projects had different purpose and thus had different resources, scope and even methods in their study. The study shows that comparison of PSA results from different plants is normally not meaningful. It takes a very deep knowledge of the PSA studies to make a comparison of the results and usually one has to ensure that the compared studies have the same scope and are based on the same analysis methods. Harmonisation of the PSA-methodology is recommended in the presentation of results, presentation of methods, scope main limitation and assumption, and definitions for end states, initiating events and common cause failures. This would facilitate the comparison of the studies. Methods for validation of PSA for different application areas should be developed. The developed PSA review standards can be applied for a general validation of a study. The most important way to evaluate the real feasibility of PSA can take place only with practical applications. The PSA-documentation and models can be developed to facilitate the communication between PSA-experts and users. In any application consultation with the PSA-expert is however needed. Many

  8. Review of UCN 3,4 PSA model based on NEI PRA peer review process guidance, rev.0

    International Nuclear Information System (INIS)

    Yang, Joon Eon; Kang, D. I.; Kim, K. Y.; Lee, Y. H.; Jang, S. C.; Ha, J. J.; Han, S. H.; Han, S. J.; Hwang, M. J.

    2003-05-01

    Recently, under the de-regulation environment, nuclear industry has attempted various approaches to improve the economics of Nuclear Power Plants (NPP). One of these efforts is the Risk Informed/Performance-Based Operation (RIPBO). This approach uses the risk and performance information to manage the resources effectively and efficiently that are used in the operation of NPP. In RIPBO, PSA quality is one of the most important things. The nuclear industry and regulatory body of U.S.A have developed a measure to evaluate the quality of PSA. NEI (Nuclear Energy Institute) has developed a guidance called 'NEI PRA Peer Review Guidance,' and NRC (Nuclear Regulatory Committee) and ASME have developed the 'PRA Standard.' In Korea, several projects are on going now, such as the extension of AOT/STI of RPS/ESFAS, Risk-Informed In-Service Inspection (RI-ISI). However, in Korea, there have been no attempts to evaluate the quality of PSA model itself. Therefore, we cannot be sure about the quality of PSA whether or not the present PSA model can be used for the risk-informed applications such as mentioned above. We can say that the evaluation of PSA model quality is the basis for the RIPBO. In this report, we have evaluated the quality of PSA model for Ulchin 3 and 4 units based on the NEI guidance. We, also, have derived what items are to be improved to upgrade the quality of PSA model and how it can be improved. This report can be used as the base of RIPBO work in Korea. The review result based on ASME Standard is published as the separated technical report of KAERI

  9. Towards a PSA harmonization French-Belgian comparison of the level 1 PSA for two similar PWR types

    International Nuclear Information System (INIS)

    Dupuy, P.; Corenwinder, F.; Lanore, J.M.; Gryffroy, D.; Gelder, P. de; Hulsmans, M.

    2002-06-01

    In the framework of the cooperation between French and Belgian regulatory authorities, a PSA (Probabilistic Safety Assessment) comparison exercise has been carried out for several years. This comparison deals with two PSA level 1 studies for internal events, performed for both power and shutdown states: the French PSA of the 900 MWe-series PWR, and the Belgian PSA of the Tihange 1 PWR, which both concern PWRs with a similar Framatome design. The purpose of this paper is to describe the PSA comparison methodology and to present, in a qualitative way, an overview of the insights obtained up to now. It also shows that such an 'a posteriori' benchmark exercise turns out to be a step towards PSA harmonization, and gives more confidence in the results of plant specific PSA when used for applications like precursor analysis or evaluations of importance to safety. (authors)

  10. Management and organisational factors in PSA

    International Nuclear Information System (INIS)

    Balfanz, H.P.

    1999-01-01

    The constraints of PSA are increasingly considered with increasing application of PSA for the safety management of nuclear power plants (see US-NRC, 'Risk Informed Regulation', NRC-1). There is a vivid international discourse about the applicability of the variables of plant management and organisation in PSAs, which has lead to a great variety of research activities into this matter (see PSAM 4). This paper here summarizes the current state of progress of research work and discusses the applicability of results. The studies for comparative assessment of methodology and results were performed by the TUeV Nord under the roof of the BMU/BfS-sponsored project SR 2260, ''Further development of probabilistic methods for nuclear power plant safety assessment. (orig./CB) [de

  11. Safer Food Saves Lives PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2015-11-03

    This 60 second PSA is based on the November 2015 CDC Vital Signs report. Contaminated food sent to several states can cause multistate outbreaks of foodborne illness and make a lot of people seriously ill. Learn what can be done to prevent and stop outbreaks.  Created: 11/3/2015 by National Center for Emerging and Zoonotic Infectious Diseases (NCEZID).   Date Released: 11/3/2015.

  12. Communication Can Save Lives PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2015-08-04

    This 60 second public service announcement (PSA) is based on the August 2015 CDC Vital Signs report. Antibiotic-resistant germs cause at least 23,000 deaths each year. Learn how public health authorities and health care facilities can work together to save lives.  Created: 8/4/2015 by National Center for Emerging and Zoonotic Infectious Diseases (NCEZID).   Date Released: 8/4/2015.

  13. Take Charge. Take the Test. PSA (:30)

    Centers for Disease Control (CDC) Podcasts

    2012-03-07

    As part of the Take Charge. Take the Test. campaign, this 30 second PSA encourages African American women to get tested for HIV. Locations for a free HIV test can be found by visiting hivtest.org/takecharge or calling 1-800-CDC-INFO (1-800-232-4636).  Created: 3/7/2012 by National Center for HIV/AIDS, Viral Hepatitis, STD, and TB Prevention (NCHHSTP).   Date Released: 3/7/2012.

  14. Prioritization of design changes based on PSA

    International Nuclear Information System (INIS)

    Krajnc, B.; Mavko, B.

    1996-01-01

    Effective use of Probabilistic Safety Analyses (PSA) in the day to day plant operation is subject of intensive discussions among plant operators and regulators. There are several possible applications in which the PSA can be used, among those also to use the PSA approach for the quantification of influence of different proposed design changes to nuclear safety - influence on public safety - health. NPP Krsko is one of those plants that successfully completed its PSA project, with Level 1 and Level 2 analyses and effective know-how transfer. It also faces a number of regulatory and internally generated requirements for different design changes, mainly due to the fact that the plant is committed to continuous augmentation of nuclear safety. It is considered that the available tools and knowledge should be used and therefore applicable methodology should be developed for effective prioritization of proposed design changes by performing cost-benefit analyses for all major modifications - focusing on their influence on nuclear safety. Based on the above a new method for prioritization of design changes is proposed. The method uses Level 1 results (in the sense of plant damage states and their frequencies) directly as an input for further processing - first decision step to decide whether the proposed modification has or has no influence on nuclear safety. In Level 2 analyses the combination of probabilistic and deterministic approach was adopted. In fact the results of the deterministic analyses of severe accidents are treated in probabilistic manner due to large uncertainty of results. Finally to be able to perform plant specific cost benefit analyses so called partial Level 3 was defined. The proposed methods was preliminary tested and it gave favorable results. (author)

  15. More Adults Are Walking PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2012-07-31

    This 60 second PSA is based on the August 2012 CDC Vital Signs report. While more adults are walking, only half get the recommended amount of physical activity. Listen to learn how communities, employers, and individuals may help increase walking.  Created: 7/31/2012 by Centers for Disease Control and Prevention (CDC).   Date Released: 8/7/2012.

  16. Stop C. difficile Infections PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2012-03-06

    This 60 second PSA is based on the March 2012 CDC Vital Signs report. C. difficile is a germ that causes diarrhea linked to 14,000 deaths in the US each year. This podcast helps health care professionals learn how to prevent C. difficile infections.  Created: 3/6/2012 by Centers for Disease Control and Prevention (CDC).   Date Released: 3/6/2012.

  17. PSA application on the Tokai Reprocessing Plant

    International Nuclear Information System (INIS)

    Ishida, Michihiko; Nakano, Takafumi; Morimoto, Kazuyuki; Nojiri, Ichiro

    2003-01-01

    The Periodic Safety Review (PSR) of the Tokai Reprocessing Plant (TRP) has been carrying out to obtain an overall view of actual plant safety. As a part of the PSR, Probabilistic Safety Assessment (PSA) methodology has been applied to evaluate the relative importance of safety functions that prevent the progress of events causing to postulated accidents. Based on the results of the safety reassessments of the TRP that was carried out in 1999, event trees were developed to model sequences of postulated accidents. Event trees were quantified by using the results of fault tree analysis and human reliability analysis. In the quantification, the reliability data generally used in PSA of nuclear power plants were mainly used. Operating experiences of the TRP were also utilized to evaluated both component/system reliability and human reliability. The relative importance of safety functions was evaluated by using two major importance measures, Fussell-Vesely and Risk Achievement Worth both generally used in PSA of nuclear power plants. Through these evaluations, some useful insights into the safety of the TRP have been obtained. The results of the relative importance measures would be utilized to qualify TRP component/equipment important to the safety. (author)

  18. The organizational factor in PSA framework

    Energy Technology Data Exchange (ETDEWEB)

    Farcasiu, Mita, E-mail: mmfarcasiu@yahoo.com; Nitoi, Mirela

    2015-11-15

    The goals of the Man–Machine–Organization system analysis are to develop the suitable studies and techniques to identify, prevent and predict the cause of system unavailability. A descriptive concept of man–machine–organization system was developed. MMOS is defined in probability theory in the attempt to find ways for its qualitative and quantitative quantification in a PSA framework. The need for this study was demonstrated by analysis of variance of the complex system unavailability in relation to human error probability (HEP) and organizational error probability (OMP). The PSA model proposed in this paper assesses the organizational factor in MMOS by observing its influence on the human factor and equipment. Thus the influence of organizational factors is evaluated not only on component but also on the human performance. The study highlights the need to improve the understanding of the influence of organizational factors on the safe operation of nuclear installations. Using MMOS concept in PSA could identify any serious deficiencies of human and equipment performance which can sometime be corrected by improvement of the organizational factor.

  19. The organizational factor in PSA framework

    International Nuclear Information System (INIS)

    Farcasiu, Mita; Nitoi, Mirela

    2015-01-01

    The goals of the Man–Machine–Organization system analysis are to develop the suitable studies and techniques to identify, prevent and predict the cause of system unavailability. A descriptive concept of man–machine–organization system was developed. MMOS is defined in probability theory in the attempt to find ways for its qualitative and quantitative quantification in a PSA framework. The need for this study was demonstrated by analysis of variance of the complex system unavailability in relation to human error probability (HEP) and organizational error probability (OMP). The PSA model proposed in this paper assesses the organizational factor in MMOS by observing its influence on the human factor and equipment. Thus the influence of organizational factors is evaluated not only on component but also on the human performance. The study highlights the need to improve the understanding of the influence of organizational factors on the safe operation of nuclear installations. Using MMOS concept in PSA could identify any serious deficiencies of human and equipment performance which can sometime be corrected by improvement of the organizational factor.

  20. Clinical performance of serum [-2]proPSA derivatives, %p2PSA and PHI, in the detection and management of prostate cancer

    OpenAIRE

    Huang, Ya-Qiang; Sun, Tong; Zhong, Wei-De; Wu, Chin-Lee

    2014-01-01

    Prostate-specific antigen (PSA) has been widely used as a serum marker for prostate cancer (PCa) screening or progression monitoring, which dramatically increased rate of early detection while significantly reduced PCa-specific mortality. However, a number of limitations of PSA have been noticed. Low specificity of PSA may lead to overtreatment in men who presenting with a total PSA (tPSA) level of < 10 ng/mL. As a type of free PSA (fPSA), [-2]proPSA is differentially expressed in peripheral ...

  1. Effect of a 2-year home-based endurance training intervention on physiological function and PSA doubling time in prostate cancer patients

    DEFF Research Database (Denmark)

    Hvid, Thine; Lindegaard, Birgitte; Winding, Kamilla

    2016-01-01

    AIM: Physical activity after prostate cancer diagnosis has been shown to reduce the risk of disease progression. Here, we aimed to evaluate the effect of a 2-year home-based endurance training intervention on body composition, biomarkers levels, and prostate-specific antigen (PSA) doubling time...... composition, insulin sensitivity, and biomarkers were measured at 0, 6, and 24 months of intervention. PSA doubling time (PSADT) was calculated based on monthly PSA measurements. RESULTS: Twenty-five patients were enrolled, and 19 patients completed the study. PSADT increased in the training group from 28...

  2. Upgrade of internal events PSA model using the AESJ level-1 PSA standard for operating state

    International Nuclear Information System (INIS)

    Sato, Teruyoshi; Yoneyama, Mitsuru; Hirokawa, Naoki; Sato, Chikahiro; Sato, Eisuke; Tomizawa, Shigeatsu

    2009-01-01

    In 2003, the Atomic Energy Society of Japan (AESJ) started to develop the Level-1 Probabilistic Safety Assessment (PSA) standard of internal events for operating state (AESJ standard). The AESJ standard has been finished to be asked for public comment. Using the AESJ standard (draft version), the authors have upgraded the PSA model for Tokyo Electric Power Company (TEPCO) BWR-5 plant not only to reflect latest knowledge but also to ensure high quality of PSA model (not yet peer-reviewed) for the purpose of better operation and maintenance management of TEPCO BWR plants. For example, the categorization of structures, systems and components (SSCs) will be performed to improve nuclear reactor safety using information of risk importance. (author)

  3. Development of PSA audit guideline and regulatory PSA model for SMART

    International Nuclear Information System (INIS)

    Cho, Namchul; Lee, Chang-Ju; Kim, I.S.

    2012-01-01

    SMART is under development for dual purposes of power generation and seawater desalination in Korea. It is an integral reactor type with a thermal power output of 330 MW and employs advanced design features such as a passive system for the removal of residual heat and also the setting of all the components of the primary system inside the reactor pressure vessel. It is essential to develop new probabilistic safety assessment (PSA) validation guidance for SMART. For the purpose of regulatory verification to the risk level of SMART, the insights and key issues on the PSA are identified with referring some worldwide safety guides as well as its design characteristics. Regulatory PSA model under the development for the design confirmation and its preliminary result are also described. (authors)

  4. PSA-operations synergism for the advanced test reactor shutdown operations PSA

    International Nuclear Information System (INIS)

    Atkinson, S.A.

    1996-01-01

    The Advanced Test Reactor (ATR) Probabilistic Safety Assessment (PSA) for shutdown operations, cask handling, and canal draining is a successful example of the importance of good PSA-operations synergism for achieving a realistic and accepted assessment of the risks and for achieving desired risk reduction and safety improvement in a best and cost-effective manner. The implementation of the agreed-upon upgrades and improvements resulted in the reductions of the estimated mean frequency for core or canal irradiated fuel uncovery events, a total reduction in risk by a factor of nearly 1000 to a very low and acceptable risk level for potentially severe events

  5. Workshop on PSA for New and Advanced Reactors

    International Nuclear Information System (INIS)

    2012-01-01

    This workshop was organized by the NEA Working Group on Risk Assessment (WGRISK). The key objective of the workshop was to share the current state-of-the art on the PSA (Probabilistic Safety Assessment) applied for new reactors and advanced reactors. Fifty experts from 13 countries and one international organization (IAEA) participated in the present workshop, and 35 technical papers were presented. The main topics of interest, discussed during the workshop, included the followings: regulatory aspects, risk-informed methods, technical aspects of the PSA for new and advanced reactors, hazards of PSA (internal and external), severe accident/source term/Level 2 PSA, and consequence analysis/Level 3 PSA. Among the technical aspects of the PSA, the assessment of the reliability of passive safety systems appears to be a recurrent issue

  6. Experiences of Uncertainty in Men With an Elevated PSA.

    Science.gov (United States)

    Biddle, Caitlin; Brasel, Alicia; Underwood, Willie; Orom, Heather

    2015-05-15

    A significant proportion of men, ages 50 to 70 years, have, and continue to receive prostate specific antigen (PSA) tests to screen for prostate cancer (PCa). Approximately 70% of men with an elevated PSA level will not subsequently be diagnosed with PCa. Semistructured interviews were conducted with 13 men with an elevated PSA level who had not been diagnosed with PCa. Uncertainty was prominent in men's reactions to the PSA results, stemming from unanswered questions about the PSA test, PCa risk, and confusion about their management plan. Uncertainty was exacerbated or reduced depending on whether health care providers communicated in lay and empathetic ways, and provided opportunities for question asking. To manage uncertainty, men engaged in information and health care seeking, self-monitoring, and defensive cognition. Results inform strategies for meeting informational needs of men with an elevated PSA and confirm the primary importance of physician communication behavior for open information exchange and uncertainty reduction. © The Author(s) 2015.

  7. Lessons learned form IRSN review of Flamanville 3 Level PSA

    International Nuclear Information System (INIS)

    Georgescu, G.; Corenwinder, F.

    2012-01-01

    In the frame of the construction and licensing of Flamanville 3 NPP the PSA (Probabilistic Safety Assessment)plays an important role for the EPR Project assessment. The PSA was used for early design verification of EPR Reactor, several design improvement being defined based on these PSA insights and following the discussions with the French and German safety authorities. IRSN, as the French Safety Authority (ASN) technical support organization, performs the review of the PSA developed by the plant operator (EDF). The paper presents the main issues regarding the using of 'design PSA', identified by IRSN following the review of the internal events Level 1 PSA transmitted by EDF in the frame of the anticipated instruction of the application for operating license of the Flamanville 3 reactor. (authors)

  8. Elevation of PSA after prostate radiotherapy: Rebound or biochemical recurrence?

    International Nuclear Information System (INIS)

    Toledano, A.; Kanoui, A.; Chiche, R.; Lamallem, H.; Beley, S.; Thibault, F.; Sebe, P.

    2008-01-01

    The fact that external beam radiotherapy and brachytherapy are now considered to be curative techniques has led to major review of the modalities of follow-up after radiotherapy for prostate cancer. The problem concerns both the diagnosis of recurrence, rapidly announced by elevation of prostatic-specific antigen (PSA), usually at a subclinical stage, and the validity of criteria of biochemical recurrence to allow comparison of various study. Physicians involved in follow-up should be aware of the potential of bounce in PSA follow-up after external beam radiotherapy or brachytherapy. The PSA bounce phenomenon was defined by a rise of PSA values (+ 0.1 -0.8 ng/ml) with a subsequent fall. Biochemical failure after external beam radiotherapy or brachytherapy (with or without hormonotherapy) was defined by Phoenix criteria by a rise of 2 ng/ml above an initial PSA nadir. This definition was more correlated to PSA bounce phenomenon. (authors)

  9. Evaluating the Phoenix definition of biochemical failure after (125)I prostate brachytherapy: Can PSA kinetics distinguish PSA failures from PSA bounces?

    Science.gov (United States)

    Thompson, Anna; Keyes, Mira; Pickles, Tom; Palma, David; Moravan, Veronika; Spadinger, Ingrid; Lapointe, Vincent; Morris, W James

    2010-10-01

    To evaluate the prostate-specific antigen (PSA) kinetics of PSA failure (PSAf) and PSA bounce (PSAb) after permanent (125)I prostate brachytherapy (PB). The study included 1,006 consecutive low and "low tier" intermediate-risk patients treated with (125)I PB, with a potential minimum follow-up of 4 years. Patients who met the Phoenix definition of biochemical failure (nadir + 2 ng/mL(-1)) were identified. If the PSA subsequently fell to ≤0.5 ng/mL(-1)without intervention, this was considered a PSAb. All others were scored as true PSAf. Patient, tumor and dosimetric characteristics were compared between groups using the chi-square test and analysis of variance to evaluate factors associated with PSAf or PSAb. Median follow-up was 54 months. Of the 1,006 men, 57 patients triggered the Phoenix definition of PSA failure, 32 (56%) were true PSAf, and 25 PSAb (44%). The median time to trigger nadir + 2 was 20.6 months (range, 6-36) vs. 49 mo (range, 12-83) for PSAb vs. PSAf groups (p < 0.001). The PSAb patients were significantly younger (p < 0.0001), had shorter time to reach the nadir (median 6 vs. 11.5 months, p = 0.001) and had a shorter PSA doubling time (p = 0.05). Men younger than age 70 who trigger nadir +2 PSA failure within 38 months of implant have an 80% likelihood of having PSAb and 20% chance of PSAf. With adequate follow-up, 44% of PSA failures by the Phoenix definition in our cohort were found to be benign PSA bounces. Our study reinforces the need for adequate follow-up when reporting PB PSA outcomes, to ensure accurate estimates of treatment efficacy and to avoid unnecessary secondary interventions. 2010. Published by Elsevier Inc. All rights reserved.

  10. Evaluating the Phoenix Definition of Biochemical Failure After 125I Prostate Brachytherapy: Can PSA Kinetics Distinguish PSA Failures From PSA Bounces?

    International Nuclear Information System (INIS)

    Thompson, Anna; Keyes, Mira; Pickles, Tom

    2010-01-01

    Purpose: To evaluate the prostate-specific antigen (PSA) kinetics of PSA failure (PSAf) and PSA bounce (PSAb) after permanent 125 I prostate brachytherapy (PB). Methods and Materials: The study included 1,006 consecutive low and 'low tier' intermediate-risk patients treated with 125 I PB, with a potential minimum follow-up of 4 years. Patients who met the Phoenix definition of biochemical failure (nadir + 2 ng/mL -1 ) were identified. If the PSA subsequently fell to ≤0.5 ng/mL -1 without intervention, this was considered a PSAb. All others were scored as true PSAf. Patient, tumor and dosimetric characteristics were compared between groups using the chi-square test and analysis of variance to evaluate factors associated with PSAf or PSAb. Results: Median follow-up was 54 months. Of the 1,006 men, 57 patients triggered the Phoenix definition of PSA failure, 32 (56%) were true PSAf, and 25 PSAb (44%). The median time to trigger nadir + 2 was 20.6 months (range, 6-36) vs. 49 mo (range, 12-83) for PSAb vs. PSAf groups (p < 0.001). The PSAb patients were significantly younger (p < 0.0001), had shorter time to reach the nadir (median 6 vs. 11.5 months, p = 0.001) and had a shorter PSA doubling time (p = 0.05). Men younger than age 70 who trigger nadir +2 PSA failure within 38 months of implant have an 80% likelihood of having PSAb and 20% chance of PSAf. Conclusions: With adequate follow-up, 44% of PSA failures by the Phoenix definition in our cohort were found to be benign PSA bounces. Our study reinforces the need for adequate follow-up when reporting PB PSA outcomes, to ensure accurate estimates of treatment efficacy and to avoid unnecessary secondary interventions.

  11. Low Power Shutdown PSA for CANDU Type Plants

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Yeon Kyoung; Kim, Myung Su [KHNP CRI, Daejeon (Korea, Republic of)

    2016-10-15

    KHNP also have concentrated on full power PSA. Some recently constructed OPR1000 type plants and APR1400 type plants have performed the low power and shutdown (LPSD) PSA. The purpose of LPSD PSA is to identify the main contributors on the accident sequences of core damage and to find the measure of safety improvement. After the Fukushima accident, Korean regulatory agency required the shutdown severe accident management guidelines (SSAMG) development for safety enhancement. For the reliability of SSAMG, KHNP should develop the LPSD PSA. Especially, the LPSD PSA for CANDU type plant had developed for the first time in Korea. This paper illustrates how the LPSD PSA for CANDU type developed and the core damage frequency (CDF) is different with that of full power PSA. KHNP performed LPSD PSA to develop the SSAMG after the Fukushima accidents. The results show that risk at the specific operation mode during outage is higher than that of full power operation. Also, the results indicated that recovery failure of class 4 power at the POS 5A, 5B contribute dominantly to the total CDF from importances analysis. LPSD PSA results such as CDF with initiating events and POSs, risk results with plant damage state, and containment failure probability and frequency with POSs can be used by inputs for developing the SSAMG.

  12. PSA data base, comparison of the German and French approach

    International Nuclear Information System (INIS)

    Kreuser, A.; Tirira, J.

    2001-01-01

    The results of probabilistic safety assessments (PSA) of nuclear power plants strongly depend on the reliability data used. This report describes coarsely the general process to generate reliability data for components and resumes the differences between the German and French approaches. As has been shown in former studies which compared international PSA data, PSA data are closely related to the model definitions of the PSA. Therefore single PSA data cannot be compared directly without regard e.g. to the corresponding fault trees. These findings are confirmed by this study. The comparison of German and French methods shows a lot of differences concerning various details of the data generation process. Some differences between single reliability data should be eliminated when taking into account the complete fault tree analysis. But there are some other differences which have a direct impact on the obtained results of a PSA. In view of the all differences between both approaches concerning the definition of data and the data collection process, it is not possible to compare directly German and French PSA data. However, the database differences give no indication on the influence on the PSA results. Therefore, it is a need to perform a common IPSN/GRS assessment on how the different databases impact the PSA results. (orig.)

  13. Use of PSA for improving the safety of French PWRs

    International Nuclear Information System (INIS)

    Lanore, J.M.; Chambon, J.L.

    1994-06-01

    Two French PWR Probabilistic Safety Assessment (PSA) studies were conducted for the standardized PWR series of 900 and 1300 MWe. Both PSA 900 and PSA 1300 are level 1 PSAs, that means their objective is the evaluation of core meltdown frequency. These studies have some specific features, in particular the treatment of shutdown conditions, the treatment of long term post-accidental situations, and a wide use of French experience feedback. The PSAs are used for safety improvements of the French PWRs. Following the PSA results, several modifications to plants concerning the dominant sequences were decided. (R.P.). 2 refs., 4 figs

  14. DIAGNOSTIC AND PROGNOSTIC UTILITY OF SERUM PSA IN BREAST CANCER

    Institute of Scientific and Technical Information of China (English)

    张淑群; 强水云; 李妙羡; 纪宗正

    2004-01-01

    Objective To investigate the diagnostic and prognostic value of total and free prostate-specific antigen (PSA) in breast cancer women. Methods Using the microparticle enzyme immunoassay system, we measured the concentrations of these markers in the sera of 85 women with breast cancer and in 30 healthy women.Results Free PSA levels were significantly higher in women with breast cancer than healthy women (P <0. 05 ).The percentage of free PSA predominant subjects was 37. 6% in breast cancer patients and 3. 3% in healthy women.In women with breast cancer,total PSA positivity was 23.5% and free PSA positivity was 27. 1%. When compared to negatives,total PSA positive patients had a higher percentage of lymph node involvement tamours ( P >0. 05).However, patients with predominant free PSA had a higher percentage of early stage than patients with predominant PSA-ACT. Conclusion This study indicate clinical significance of preoperative measurement of serum total and free PSA in diagnosis and prognosis of women with breast cancer. The expression of KLKs is correlated with carcinogenesis of breast cancer.

  15. Serum PSA levels in the Indian population: Is it different?

    Science.gov (United States)

    Agrawal, Amit; Karan, Shailesh Chandra

    2017-04-01

    Serum prostate-specific antigen (PSA) is an important tumour, marker which is widely used to trigger trans-rectal ultrasound (TRUS)-guided prostate biopsy. However, the PSA levels vary with race and ethnicity. Therefore, there is a need to have an Indian reference range. All adult male patients meeting the inclusion and exclusion criteria were enrolled in this study. They were subjected to assessment of serum total PSA, digital rectal examination and trans-abdominal ultrasound. If any one or more of these were found abnormal, then a TRUS-guided 12-core prostate biopsy was done. Patients who were detected to have prostatic cancer were excluded from the final analysis. The data so obtained was grouped among the following three age groups: 40-49, 50-59 and 60-70 years, and the age-specific PSA values, prostatic volume and PSA density were found. A total of 1772 patients were analysed. The mean serum total PSA was 1.76 ng/ml with a standard deviation of 2.566 ng/ml. Group-wise age distribution of the mean serum total PSA was 1.22, 1.97 and 2.08 ng/ml in 40-49, 50-59 and 60-70 years age groups. The mean total PSA and the age-specific PSA range tend to be lower in the Indians than the Western population.

  16. Institute of nuclear power operations perspectives on PSA applications

    International Nuclear Information System (INIS)

    Webster, W.E.; Miller, W.J. Jr.

    1996-01-01

    The investment to develop a PSA is very substantial, and therefore, there is motivation to recover this investment through further use of the techniques used to develop it. It is not surprising that nuclear power plant staff are beginning to use PSA to make operational decisions. The Institute of Nuclear Power Operations is interested in those factors that impact the conduct of plant operations and therefore is actively monitoring the increased usage of PSA techniques. The purpose of this paper is to provide some thoughts and perspectives on the use of PSA as a factor in operational decision making, including decision making in activities performed by engineering, maintenance and operation personnel. (author)

  17. Daily Pill Can Prevent HIV PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    This 60 second public service announcement (PSA) is based on the November 24, 2015 CDC Vital Signs report. Preexposure prophylaxis, or PrEP, is a daily medicine that can be used to prevent getting HIV. PrEP is for people who don’t have HIV but who are at very high risk for getting it from sex or injection drug use. Unfortunately, many people who can benefit from PrEP aren’t taking it.

  18. Development of kits for total PSA monitoring

    International Nuclear Information System (INIS)

    Suprarop, P.

    1999-01-01

    The development of kits for Total PSA assay has shown promising results. All essential components of the assay were prepared with reproducibility and used to optimize the assay. By choosing two steps method, we could avoid the hook effect and obtain satisfactory Q.C. parameters of the standard curve i.e. blank = 0.8%, maximum binding = 65%. If reference material for calibration of the standard is agree upon, the validation could then be carried out with total confidence. Our final goal is to reduce the step of incubation to just one step with no interference from hook effect

  19. Prostate-Specific Antigen (PSA) Test: MedlinePlus Lab Test Information

    Science.gov (United States)

    ... medlineplus.gov/labtests/prostatespecificantigenpsatest.html Prostate-Specific Antigen (PSA) Test To use the sharing features on this ... enable JavaScript. What is a prostate-specific antigen (PSA) test? A prostate-specific antigen (PSA) test measures ...

  20. PSA - A utility perspective from the United Kingdom

    International Nuclear Information System (INIS)

    Ross, P.J.

    2004-01-01

    This paper provides an outline of the three stages of PSA used for the Sizewell B PWR. These stages cover the use of PSA during design, licensing and (in future) operation of Sizewell B. The paper discusses each of these stages in some detail, highlighting the differences in approach and lessons learnt at each stage. (author)

  1. Level 2 PSA methodology and severe accident management

    International Nuclear Information System (INIS)

    1997-01-01

    The objective of the work was to review current Level 2-PSA (Probabilistic Safety Assessment) methodologies and practices and to investigate how Level 2-PSA can support severe accident management programmes, i.e. the development, implementation, training and optimisation of accident management strategies and measures. For the most part, the presented material reflects the state in 1996. Current Level 2 PSA results and methodologies are reviewed and evaluated with respect to plant type specific and generic insights. Approaches and practices for using PSA results in the regulatory context and for supporting severe accident management programmes by input from level 2 PSAs are examined. The work is based on information contained in: PSA procedure guides, PSA review guides and regulatory guides for the use of PSA results in risk informed decision making; plant specific PSAs and PSA related literature exemplifying specific procedures, methods, analytical models, relevant input data and important results, use of computer codes and results of code calculations. The PSAs are evaluated with respect to results and insights. In the conclusion section, the present state of risk informed decision making, in particular in the level 2 domain, is described and substantiated by relevant examples

  2. Use of PSA in the development of SMRs

    International Nuclear Information System (INIS)

    Maioli, A.; Finnicum, D.J.; Lichtenstein, R.H.; Harsche, S.Y.

    2012-01-01

    This paper reviews the potential new scenarios where PSA (probabilistic safety assessment) may be of significant support to design and operation of SMRs (Small Modular Reactors); it reviews Westinghouse's experience and lessons learned in this endeavour and will discuss related challenges and what the PSA community is currently developing to address them. (authors)

  3. Child Injury: What You Need to Know PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    This 60 second PSA is based on the April 2012 CDC Vital Signs report. Many childhood deaths and injuries are preventable, including those caused by crashes, suffocation, poisoning, drowning, fires, and falls. The PSA discusses ways to help prevent these deaths and injuries.

  4. Quality of the current low power and shutdown PSA practice

    International Nuclear Information System (INIS)

    Jang, Seung Cheol; Park, Jin Hee; Lim, Ho Gon; Kim, Tae Woon

    2004-01-01

    A probabilistic safety assessment (PSA) for the low-power and shutdown (LPSD) modes in a Korea standard nuclear power plant (KSNP) has been performed for the purpose of estimating the LPSD risk and identifying the vulnerabilities of LPSD operations. Both the operational experience and PSA results indicate that the risks from LPSD operations could be comparable with those from power operations. However, the application of the LPSD risk insights to risk-informed decision making has been slow to be adopted in practice. It is largely due to the question of whether the current LPSD PSA practice is appropriate for application to risk-informed decision making or not. Such a question has to do with the quality of the current LPSD PSA practice. In this paper, we have performed self-assessment of the KSNP LPSD PSA quality based on the ANS Standard (draft as of 13 Sep. 2002). The aims of the work are to find the LPSD PSA technical areas insufficient for application to risk-informed decision making and to efficiently allocate the limited research resources to improve the LPSD PSA model quality. Many useful findings regarding the current LPSD PSA quality are presented in this paper

  5. PSA in design of passive/active safety reactors

    International Nuclear Information System (INIS)

    Sato, T.; Tanabe, A.; Kondo, S.

    1995-01-01

    PSAs in the design of advanced reactors are applied mainly in level 1 PSA areas. However, even in level 1 PSA, there are certain areas where special care must be taken depending on plant design concepts. This paper identifies these areas both for passive and active safety reactor concepts. For example, 'long-term PSA' and shutdown PSA are very important for a passive safety reactor concept from the standpoint of effectiveness of a grace period and passive safety systems. External events are also important for an active safety reactor concept. These kinds of special PSAs are difficult to conduct precisely in a conceptual design stage. This paper shows methods of conducting these kinds of special PSAs simply and conveniently and the use of acquired insights for the design of advanced reactors. This paper also clarifies the meaning or definition of a grace period from the standpoint of PSA

  6. Updating the Psoriatic Arthritis (PsA) Core Domain Set

    DEFF Research Database (Denmark)

    Orbai, Ana-Maria; de Wit, Maarten; Mease, Philip J

    2017-01-01

    OBJECTIVE: To include the patient perspective in accordance with the Outcome Measures in Rheumatology (OMERACT) Filter 2.0 in the updated Psoriatic Arthritis (PsA) Core Domain Set for randomized controlled trials (RCT) and longitudinal observational studies (LOS). METHODS: At OMERACT 2016, research...... conducted to update the PsA Core Domain Set was presented and discussed in breakout groups. The updated PsA Core Domain Set was voted on and endorsed by OMERACT participants. RESULTS: We conducted a systematic literature review of domains measured in PsA RCT and LOS, and identified 24 domains. We conducted...... and breakout groups at OMERACT 2016 in which findings were presented and discussed. The updated PsA Core Domain Set endorsed with 90% agreement by OMERACT 2016 participants included musculoskeletal disease activity, skin disease activity, fatigue, pain, patient's global assessment, physical function, health...

  7. Flooding PSA with Plant Specific Operating Experiences of Korean PWRs

    International Nuclear Information System (INIS)

    Choi, Sun Yeong; Yang, Joon Yull

    2006-01-01

    The purpose of this paper is to update the flooding PSA with Korean plant specific operating experience data and the appropriate estimation method for the flooding frequency to improve the PSA quality. The existing flooding PSA used the NPE (Nuclear Power Experience) database up to 1985 for the flooding frequency. They are all USA plant operating experiences. So an upgraded flooding frequency with Korean specific plant operation experience is required. We also propose a method of only using the PWR (Pressurized Water Reactor) data for the flooding frequency estimation in the case of the flooding area in the primary building even though the existing flooding PSA used both PWR and BWR (Boiled Water Reactor) data for all kinds of plant areas. We evaluate the CDF (Core Damage Frequency) with the modified flooding frequency and compare the results with that of the existing flooding PSA method

  8. Applications of probabilistic safety assessment (PSA) for nuclear power plants

    International Nuclear Information System (INIS)

    2001-02-01

    This report, which compiles information on a comprehensive set of PSA applications in the areas of NPP design, operation, and accident mitigation and management, is the culmination of an IAEA project on PSA Applications and Tools to Improve NPP Safety. In this regard, the Technical Committee Meeting (TCM) held in Madrid in February 1998 allowed participants to review and provide very valuable comments for this report. Several important facts related to PSA and its applications were highlighted during this TCM: living PSAs are the basis for the risk informed approach to decision making; development and use of safety/risk monitors as tools for configuration management is spreading fast; the different uses of PSA to support NPP testing and maintenance planning and optimization are amongst the most widespread PSA applications; plant specific PSAs are being used to support the safety upgrading programmes of plants built to earlier standards; not all countries have a regulatory framework for the use of the probabilistic approach in decision making. Some countries are still far from 'risk-informed' regulation, and this means that there is still considerable work ahead, both for regulators and utilities, to clarify approaches, to establish a framework and to reach a common understanding in relation to the use of PSA in decision making. This report is based on the premise that the use of PSA can provide useful information for the decision maker. This report is intended to provide an overview of current PSA applications. Section 2 addresses the PSA application process, outlines the general requirements for PSA tools and provides a discussion on PSA aspects such as PSA level, scope and level of detail, which have to be considered when planning/performing PSA applications. Section 3 discusses the technical aspects of individual applications and is divided into three parts. Section 3.1 is dedicated to the design related PSA applications. The second part of Section 3 considers

  9. The open PSA standard as a framework for migration of probabilistic models. Experiences with the KKB PSA

    International Nuclear Information System (INIS)

    Becker, G.; Hussels, U.; Epstein, S.; Rauzy, A.; Schubert, B.

    2008-01-01

    In its present state, the open PSA standard is helpful to determine capabilities of PSA approaches, which have been taken into account by those who formulated it. As soon, as tools come up, which can automatically bring a given PSA into the standard form, the data will be accessible by other software tools, which either are supplementary to the original one, or they may act in the context of quality control. Taking into account, that a PSA model represents a value of some two to ten person years (dependent on level of completeness and level of detail), it is important to have the data in a transparent way, which does not depend on proprietary formats, and can thus be used for more purposes than those, which are implemented in given PSA codes. (orig.)

  10. Daily Pill Can Prevent HIV PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2015-11-24

    This 60 second public service announcement (PSA) is based on the November 24, 2015 CDC Vital Signs report. Preexposure prophylaxis, or PrEP, is a daily medicine that can be used to prevent getting HIV. PrEP is for people who don’t have HIV but who are at very high risk for getting it from sex or injection drug use. Unfortunately, many people who can benefit from PrEP aren’t taking it.  Created: 11/24/2015 by National Center for HIV/AIDS, Viral Hepatitis, STD, and TB Prevention (NCHHSTP).   Date Released: 11/24/2015.

  11. Policy and System Approach (PSA: A primer

    Directory of Open Access Journals (Sweden)

    Chandrakant Lahariya

    2017-01-01

    Full Text Available A number of public health challenges have emerged at global and national level in the last two decades. The response to these challenges has rarely been swift and often “knee-jerk.” The national and state level program officials responsible for the activities often apportion the blame on weak health systems or fragmented health service delivery mechanisms, amongst other. In India, the viral illnesses (including those due to dengue and chikungunya are becoming the increasing realities. The Public health response of early identification, disease surveillance, reporting and the preventive and curative measures, remains suboptimal. The health challenges which require multidimensional interventions are usuallyattempted to be resolved through piece meal solutions. This article proposes “policy and system approach (PSA,” combining concepts of “Health in all policies” for intersectoral coordination and “health system approach” for intra-sectoral tackling of the emerging and existing health challenges.

  12. Cancer of the prostate - role of PSA

    International Nuclear Information System (INIS)

    Shittu, O.B.

    1999-02-01

    Since 1979 when prostate specific antigen (PSA), found in the cytoplasm of benign and malignant prostatic cells, was first purified, it has attained world wide popularity in prostate cancer detection. It is also a sensitive test for skeletal meta states from carcinoma of the prostate. Prostate cancer has become the number one cancer in men and constitutes 11% of all cancers. Approximately 50% of men over 50 years have symptoms referable to the lower urinary tract. 50% or more of patients at Ibadan present an advanced stage of the disease and are therefore not curable. Thus, lacking the skill to manage advanced manifestations, early detection and screening programs are the best means to reduce mortality due to prostate cancer

  13. Regulatory review of probabilistic safety assessment (PSA) Level 2

    International Nuclear Information System (INIS)

    2001-07-01

    Probabilistic safety assessment (PSA) is increasingly being used as part of the decision making process to assess the level of safety of nuclear power plants. The methodologies in use are maturing and the insights gained from the PSAs are being used along with those from deterministic analysis. Many regulatory authorities consider the current state of the art in PSA to be sufficiently well developed for results to be used centrally in the regulatory decision making process-referred to as risk informed regulation. For these applications to be successful, it will be necessary for the regulatory authority to have a high degree of confidence in the PSA. However, at the 1994 IAEA Technical Committee Meeting on Use of PSA in the Regulatory Process and at the OECD Nuclear Energy Agency Committee for Nuclear Regulatory Activities (CNRA) 'Special Issues' meeting in 1997 on Review Procedures and Criteria for Different Regulatory Applications of PSA, it was recognized that formal regulatory review guidance for PSA did not exist. The senior regulators noted that there was a need to produce some international guidance for reviewing PSAs to establish an agreed basis for assessing whether important technological and methodological issues in PSAs are treated adequately and to verify that conclusions reached are appropriate. In 1997, the IAEA and OECD Nuclear Energy Agency agreed to produce, in cooperation, guidance on Regulatory Review of PSA. This led to the publication of IAEA-TECDOC-1135 on the Regulatory Review of Probabilistic Safety Assessment (PSA) Level 1, which gives advice for the review of Level 1 PSA for initiating events occurring at power plants. This TECDOC extends the coverage to address the regulatory review of Level 2 PSA.These publications are intended to provide guidance to regulatory authorities on how to review the PSA for a nuclear power plant to gain confidence that it has been carried out to an acceptable level of quality so that it can be used as the

  14. A framework for a quality assurance programme for PSA

    International Nuclear Information System (INIS)

    1999-08-01

    Reviews organized by the IAEA of probabilistic safety assessments (PSAs) of nuclear facilities have, in the past years, shown significant progress in the technical methods and data used for these studies. The IAEA has made a considerable effort to support the development of technical capabilities for PSA in Member States and in writing technical procedures for carrying out PSAs. However, the reviews have also shown significant deficiencies in quality assurance (QA) for PSAs, ranging from no QA at all to inappropriate, inefficient or unbalanced QA. As a PSA represents a very complex model which describes the risk associated with a nuclear facility, an appropriate and efficient QA programme is crucial to obtain a quality PSA. Historically, in the first integral PSAs, many of the PSA elements were handled by independent groups. These elements were finally integrated and put together in the overall model. Many of the interfaces between the elements or tasks were handled as appropriate by exchanging information in oral or written form. Since WASH-1400, the first integral PSA, the process of constructing the PSA model has been further developed. PSA elements previously considered separately can now be handled together with the capable software developed in recent years. Software has made interface control and data transfer easier to perform, but also permits the development of more detailed and complex models. Previously, QA for PSA projects was organized in an ad hoc manner and was sometimes very limited. In recent years, increasingly comprehensive QA programmes have been developed and implemented for PSA projects. Today, a comprehensive, effective and performance-oriented QA is considered to be essential for a reliable and credible PSA. This report describes the framework for developing an adequate QA programme for PSA studies. The framework is based on and is in accordance with the related QA guidelines of the IAEA for safety in nuclear power plants and other nuclear

  15. Ascertaining the international state of the art of PSA methodology

    International Nuclear Information System (INIS)

    Linden, J. von

    1998-01-01

    Plant-specific PSAs, to be performed within the framework of the Periodic Safety Review of German Nuclear Power Plants require further development of the methodology. For that purpose foreign PSA-guidelines and PSA-reviewes as well as relevant literature are examined and appropriate insights are adopted within task A.2 of project SR 2096. The main goal of these activities is to achieve a comparison of the state of the art of PSA-methodologies applied abroad and in Germany. The German state of the art refers to the extent as is documented in the German PSA Guide (Leitfaden Probabilistische Sicherheitsanalyse /PSUe97/) which has to be used for the Periodic Safety Review of German Nuclear Power Plants. The structure for the evaluation is based on the working steps of a PSA. In total, according to the objectives of the Periodic Safety Review the German approach for plant-specific PSAs based on the German PSA Guide is conform to the state of the art abroad. Identified deviations in some details are evaluated reflecting the view of GRS. Particular aspects resulting from the evaluation should be considered for further development of the German PSA Guide. (orig.) [de

  16. Application of PSA in risk informed decision making

    International Nuclear Information System (INIS)

    Hari Prasad, M.; Vinod, Gopika; Saraf, R.K.; Ghosh, A.K.; Kushwaha, H.S.

    2006-01-01

    Probabilistic Safety Assessment (PSA) models have been successfully employed during design evaluation to assess weak links and carry out design modifications to improve system reliability and safety. Recently, studies are directed towards applying PSA in various decision making issues concerned with plant operations and safety regulations. This necessitates development of software tools like Living PSA, Risk Monitor etc. Risk Monitor is a PC based tool developed to assess the risk, based on the actual status of systems and components. Such tools find wide application with plant personnel and regulatory authorities since they can provide solutions to various plant issues and regulatory decision making issues respectively. (author)

  17. Regulatory review of probabilistic safety assessment (PSA) level 1

    International Nuclear Information System (INIS)

    2000-02-01

    Probabilistic safety assessment (PSA) is increasingly being used as part of the decision making process to assess the level of safety of nuclear power plants. The methodologies in use are maturing and the insights gained from the PSAs are being used along with those from the deterministic analysis. Many regulatory authorities consider that the current state of the art in PSA (especially Level 1 PSA) is sufficiently well developed that it can be used centrally in the regulatory decision making process - referred to as 'risk informed regulation'. For these applications to be successful, it will be necessary for regulatory authorities to have a high degree of confidence in PSA. However, at the IAEA Technical Committee Meeting on Use of PSA in the Regulatory Process in 1994 and at the OECD Nuclear Energy Agency Committee for Nuclear Regulatory Activities (CNRA) 'Special Issues' Meeting in 1997 on Review Procedures and Criteria for Different Regulatory Applications of PSA, it was recognized that formal regulatory review guidance for PSA did not exist. The senior regulators noted that there was a need to produce some international guidance for reviewing PSAs to establish an agreed basis for assessing whether important technological and methodological issues in PSAs are treated adequately and to verify that conclusions reached are appropriate. In 1997 the IAEA and OECD Nuclear Energy Agency agreed to produce in co-operation a technical document on the regulatory review of PSA. This publication is intended to provide guidance to regulatory authorities on how to review the PSA for a nuclear power plant to gain confidence that it has been carried out to an acceptable standard so that it can be used as the basis for taking risk informed decisions within a regulatory decision making process. The document gives guidance on how to set about reviewing a PSA and on the technical issues that need to be addressed. This publication gives guidance for the review of Level 1 PSA for

  18. Quality assurance in the Juragua Nuclear Power Plant preoperational PSA

    International Nuclear Information System (INIS)

    Valhuerdi Debesa, C.

    1996-01-01

    Quality Assurance (QA) is nowadays an important requirement for the competence of any production or service, making possible to get the desired quality at the lowest cost In the case of PSA, which are multidisciplinary, very detailed and complex analysis, with many interfaces between analyst tasks, QA plays an important role as a tool for the analytical process management, and it is recognized as one of the PSA issues which require additional development In this paper the QA system developed for the Juragua NPP preoperational PSA, its antecedents and the experiences of its application are described

  19. Development of Tsunami PSA method for Korean NPP site

    International Nuclear Information System (INIS)

    Kim, Min Kyu; Choi, In Kil; Park, Jin Hee

    2010-01-01

    A methodology of tsunami PSA was developed in this study. A tsunami PSA consists of tsunami hazard analysis, tsunami fragility analysis and system analysis. In the case of tsunami hazard analysis, evaluation of tsunami return period is major task. For the evaluation of tsunami return period, numerical analysis and empirical method can be applied. The application of this method was applied to a nuclear power plant, Ulchin 56 NPP, which is located in the east coast of Korean peninsula. Through this study, whole tsunami PSA working procedure was established and example calculation was performed for one of real nuclear power plant in Korea

  20. Characteristics Studies of 125I- and total PSA antibody's Binding with prostate specific antigen (PSA) in Human Uterus Tumors

    International Nuclear Information System (INIS)

    Al-Mudaffar, S.; Al-Salihi, J.

    2005-01-01

    Two groups of uterus tumors (benign and malignant) postmenopausal patients were used to investigate the presence of prostate specific antigen (PSA). Preliminary experiments were performed to follow the binding of '1 25 I-anti total PSA antibody with PSA in uterus tissues homogenates of the two groups with their corresponding antigen and found to be (8.8,7.1%) for benign and malignant tumors, respectively. An Immuno Radio Metric Assay (IRMA) procedure was developed for measuring PSA in benign and malignant uterus tumors homogenates. The optimum conditions of the binding of 125 I-anti total PSA antibody with PSA were as follows: PSA concentration (150,200 μg protein),tracer antibody concentration (125,250 μg protein), p H (7.6,7.2), temp (15,25?C) and time (1.5 hrs) for postmenopausal benign and malignant uterus tumors tissue homogenates, respectively. The use of different concentrations of Na + and Mg 2+ ions were shown to cause an increase in the binding at concentration of (125,75 mΜ) of Na 1+ ions (75,225 mΜ) of Mg 2+ ions for benign and malignant uterus tumors homogenates, respectively, while the use of different concentrations of urea and polyethylene glycol (PEG) Caused a decrease in the binding with the increase in the concentration of each of urea and PEG in the both cases

  1. 78 FR 69991 - Advisory Committee; Veterinary Medicine Advisory Committee; Termination

    Science.gov (United States)

    2013-11-22

    .... FDA-2013-N-1380] Advisory Committee; Veterinary Medicine Advisory Committee; Termination AGENCY: Food... announcing the termination of the Veterinary Medicine Advisory Committee. This document removes the Veterinary Advisory Committee from the Agency's list of standing advisory committees. DATES: This rule is...

  2. Long-term prediction of prostate cancer diagnosis and death using PSA and obesity related anthropometrics at early middle age: data from the malmö preventive project.

    Science.gov (United States)

    Assel, Melissa J; Gerdtsson, Axel; Thorek, Daniel L J; Carlsson, Sigrid V; Malm, Johan; Scardino, Peter T; Vickers, Andrew; Lilja, Hans; Ulmert, David

    2018-01-19

    To evaluate whether anthropometric parameters add to PSA measurements in middle-aged men for risk assessment of prostate cancer (PCa) diagnosis and death. After adjusting for PSA, both BMI and weight were significantly associated with an increased risk of PCa death with the odds of a death corresponding to a 10 kg/m2 or 10 kg increase being 1.58 (95% CI 1.10, 2.28; p = 0.013) and 1.14 (95% CI 1.02, 1.26; p = 0.016) times greater, respectively. AUCs did not meaningfully increase with the addition of weight or BMI to prediction models including PSA. In 1974 to 1986, 22,444 Swedish men aged 44 to 50 enrolled in Malmö Preventive Project, Sweden, and provided blood samples and anthropometric data. Rates of PSA screening in the cohort were very low. Documentation of PCa diagnosis and disease-specific death up to 2014 was retrieved through national registries. Among men with anthropometric measurements available at baseline, a total of 1692 men diagnosed with PCa were matched to 4190 controls, and 464 men who died of disease were matched to 1390 controls. Multivariable conditional logistic regression was used to determine whether diagnosis or death from PCa were associated with weight and body mass index (BMI) at adulthood after adjusting for PSA. Men with higher BMI and weight at early middle age have an increased risk of PCa diagnosis and death after adjusting for PSA. However, in a multi-variable numerical statistical model, BMI and weight do not importantly improve the predictive accuracy of PSA. Risk-stratification of screening should be based on PSA without reference to anthropometrics.

  3. Pattern of Prostate-Specific Antigen (PSA) Failure Dictates the Probability of a Positive Bone Scan in Patients With an Increasing PSA After Radical Prostatectomy

    Science.gov (United States)

    Dotan, Zohar A.; Bianco, Fernando J.; Rabbani, Farhang; Eastham, James A.; Fearn, Paul; Scher, Howard I.; Kelly, Kevin W.; Chen, Hui-Ni; Schöder, Heiko; Hricak, Hedvig; Scardino, Peter T.; Kattan, Michael W.

    2007-01-01

    Purpose Physicians often order periodic bone scans (BS) to check for metastases in patients with an increasing prostate-specific antigen (PSA; biochemical recurrence [BCR]) after radical prostatectomy (RP), but most scans are negative. We studied patient characteristics to build a predictive model for a positive scan. Patients and Methods From our prostate cancer database we identified all patients with detectable PSA after RP. We analyzed the following features at the time of each bone scan for association with a positive BS: preoperative PSA, time to BCR, pathologic findings of the RP, PSA before the BS (trigger PSA), PSA kinetics (PSA doubling time, PSA slope, and PSA velocity), and time from BCR to BS. The results were incorporated into a predictive model. Results There were 414 BS performed in 239 patients with BCR and no history of androgen deprivation therapy. Only 60 (14.5%) were positive for metastases. In univariate analysis, preoperative PSA (P = .04), seminal vesicle invasion (P = .02), PSA velocity (P < .001), and trigger PSA (P < .001) predicted a positive BS. In multivariate analysis, only PSA slope (odds ratio [OR], 2.71; P = .03), PSA velocity (OR, 0.93; P = .003), and trigger PSA (OR, 1.022; P < .001) predicted a positive BS. A nomogram for predicting the bone scan result was constructed with an overfit-corrected concordance index of 0.93. Conclusion Trigger PSA, PSA velocity, and slope were associated with a positive BS. A highly discriminating nomogram can be used to select patients according to their risk for a positive scan. Omitting scans in low-risk patients could reduce substantially the number of scans ordered. PMID:15774789

  4. Hand Hygiene in Healthcare Settings 2 PSA (:30)

    Centers for Disease Control (CDC) Podcasts

    This 30 second PSA encourages people to wash their hands often while in the hospital or visiting someone in the hospital. It also encourages them to remind their healthcare providers to wash their hands, too.

  5. Hand Hygiene in Healthcare Settings 1 PSA (:30)

    Centers for Disease Control (CDC) Podcasts

    This 30 second PSA encourages people to wash their hands often while in the hospital or visiting someone in the hospital. It also encourages them to remind their healthcare providers to wash their hands, too.

  6. PSA Velocity Does Not Improve Prostate Cancer Detection

    Science.gov (United States)

    A rapid increase in prostate-specific antigen (PSA) levels is not grounds for automatically recommending a prostate biopsy, according to a study published online February 24, 2011, in the Journal of the National Cancer Institute.

  7. PSA LEVEL 3 DAN IMPLEMENTASINYA PADA KAJIAN KESELAMATAN PWR

    Directory of Open Access Journals (Sweden)

    Pande Made Udiyani

    2015-03-01

    Full Text Available Kajian keselamatan PLTN menggunakan metodologi kajian probabilistik sangat penting selain kajian deterministik. Metodologi kajian menggunakan Probabilistic Safety Assessment (PSA Level 3 diperlukan terutama untuk estimasi kecelakaan parah atau kecelakaan luar dasar desain PLTN. Metode ini banyak dilakukan setelah kejadian kecelakaan Fukushima. Dalam penelitian ini dilakukan implementasi PSA Level 3 pada kajian keselamatan PWR, postulasi kecelakan luar dasar desain PWR AP-1000 dan disimulasikan di contoh tapak Bangka Barat. Rangkaian perhitungan yang dilakukan adalah: menghitung suku sumber dari kegagalan teras yang terjadi, pemodelan kondisi meteorologi tapak dan lingkungan, pemodelan jalur paparan, analisis dispersi radionuklida dan transportasi fenomena di lingkungan, analisis deposisi radionuklida, analisis dosis radiasi, analisis perlindungan & mitigasi, dan analisis risiko. Kajian menggunakan rangkaian subsistem pada perangkat lunak PC Cosyma. Hasil penelitian membuktikan bahwa implementasi metode kajian keselamatan PSA Level 3 sangat efektif dan komprehensif terhadap estimasi dampak, konsekuensi, risiko, kesiapsiagaan kedaruratan nuklir (nuclear emergency preparedness, dan manajemen kecelakaan reaktor terutama untuk kecelakaan parah atau kecelakaan luar dasar desain PLTN. Hasil kajian dapat digunakan sebagai umpan balik untuk kajian keselamatan PSA Level 1 dan PSA Level 2. Kata kunci: PSA level 3, kecelakaan, PWR   Reactor safety assessment of nuclear power plants using probabilistic assessment methodology is most important in addition to the deterministic assessment. The methodology of Level 3 Probabilistic Safety Assessment (PSA is especially required to estimate severe accident or beyond design basis accidents of nuclear power plants. This method is carried out after the Fukushima accident. In this research, the postulations beyond design basis accidentsof PWR AP - 1000 would be taken, and simulated at West Bangka sample site. The

  8. Influence of PSA, PSA velocity and PSA doubling time on contrast-enhanced 18F-choline PET/CT detection rate in patients with rising PSA after radical prostatectomy

    International Nuclear Information System (INIS)

    Schillaci, Orazio; Calabria, Ferdinando; Tavolozza, Mario; Caracciolo, Cristiana Ragano; Orlacchio, Antonio; Danieli, Roberta; Simonetti, Giovanni; Agro, Enrico Finazzi; Miano, Roberto

    2012-01-01

    To evaluate the accuracy of contrast-enhanced 18 F-choline PET/CT in restaging patients with prostate cancer after radical prostatectomy in relation to PSA, PSA velocity (PSAve) and PSA doubling time (PSAdt). PET/CT was performed in 49 patients (age range 58-87 years) with rising PSA (mean 4.13 ng/ml) who were divided in four groups according to PSA level: ≤1 ng/ml, 1 to ≤2 ng/ml, 2 to ≤4 ng/ml, and >4 ng/ml. PSAve and PSAdt were measured. PET and CT scans were interpreted separately and then together. PET/CT diagnosed relapse in 33 of the 49 patients (67%). The detection rates were 20%, 55%, 80% and 87% in the PSA groups ≤1, 1 to ≤2, 2 to ≤4 and >4 ng/ml, respectively. PET/CT was positive in 7 of 18 patients (38.9%) with a PSA ≤2 ng/ml, and in 26 of 31 (83.9%) with a PSA >2 ng/ml. PET/CT was positive in 7 of 25 patients (84%) with PSAdt ≤6 months, and in 12 of 24 patients (50%) with PSAdt >6 months, and was positive in 26 of 30 patients (86%) with a PSAve >2 ng/ml per year, and in 7 of 19 patients (36.8%) with PSAve ≤2 ng/ml per year. PET alone was positive in 31 of 49 patients (63.3%), and of these 31 patients, CT was negative in 14 but diagnosed bone lesions in 2 patients in whom PET alone was negative. CT with the administration of intravenous contrast medium did not provide any further information. Detection rate of 18 F-choline imaging is closely related to PSA and PSA kinetics. In particular, 18 F-choline PET/CT is recommended in patients with PSA >2 ng/ml, PSAdt ≤6 months and PSAve >2 ng/ml per year. CT is useful for detecting bone metastases that are not 18 F-choline-avid. The use of intravenous contrast agent seems unnecessary. (orig.)

  9. [Use of prostatic specific antigen in primary care (PSA)].

    Science.gov (United States)

    Panach-Navarrete, J; Gironés-Montagud, A; Sánchez-Cano, E; Doménech-Pérez, C; Martínez-Jabaloyas, J M

    2017-04-01

    In the literature it is shown that the use of PSA is occasionally wrong, by requesting this marker in very young or very old men, and repeated measurements in short periods of time. The main objective of this study was to describe the use of PSA in daily practice by primary care physicians in our area, dealing with aspects such as the importance of patient age, the value in the screening for prostate cancer, or the subjective beliefs about its usefulness. A secondary objective was the comparison of use, and beliefs among doctors who claim to know PSA well, and those who do not. A descriptive and comparative study was conducted using questionnaires that were handed to primary care doctors in all health centres in our area. A descriptive analysis was performed and response rates among doctors who thought they had enough information about PSA, and those who did not, were compared using the Chi-squared test. A total of 103 questionnaires were received from the physicians, with 83.5% claiming to have sufficient knowledge about the PSA. The professionals in this latter group request PSA at an earlier age (P=.029), with a higher frequency (P=.011) and have more doubts about its usefulness (P=.009) than those with less knowledge. Almost half (49.5%) said they request less than 50 determinations per year, and 33% between 50 and 100. More than half (53.4%) of doctors would not request the first PSA on a patient until their 50s, and up to 49% request it up to 80 years. The true value of PSA has been established many times by 64.1% of requesters, and 29.1% believe it is unhelpful in the diagnosis of cancer. In our study, 64% of primary care physicians have considered the true value of the PSA several times, and 29% believe it to be of little use in the diagnosis of prostate cancer. In addition, some data suggest it has limited use due to the fact that 50% made less than 50 PSA requests per years, and 28% of the professionals would never request it on a male without urinary

  10. Influence of PSA, PSA velocity and PSA doubling time on contrast-enhanced {sup 18}F-choline PET/CT detection rate in patients with rising PSA after radical prostatectomy

    Energy Technology Data Exchange (ETDEWEB)

    Schillaci, Orazio [University ' ' Tor Vergata' ' , Department of Biopathology and Diagnostic Imaging, Interventional, Rome (Italy); IRCCS Neuromed, Department of Nuclear Medicine and Molecular Imaging, Pozzilli (Italy); Calabria, Ferdinando [IRCCS Neuromed, Department of Nuclear Medicine and Molecular Imaging, Pozzilli (Italy); Tavolozza, Mario; Caracciolo, Cristiana Ragano; Orlacchio, Antonio; Danieli, Roberta; Simonetti, Giovanni [University ' ' Tor Vergata' ' , Department of Biopathology and Diagnostic Imaging, Interventional, Rome (Italy); Agro, Enrico Finazzi; Miano, Roberto [University Hospital ' ' Tor Vergata' ' , Department of Urology, Rome (Italy)

    2012-04-15

    To evaluate the accuracy of contrast-enhanced {sup 18}F-choline PET/CT in restaging patients with prostate cancer after radical prostatectomy in relation to PSA, PSA velocity (PSAve) and PSA doubling time (PSAdt). PET/CT was performed in 49 patients (age range 58-87 years) with rising PSA (mean 4.13 ng/ml) who were divided in four groups according to PSA level: {<=}1 ng/ml, 1 to {<=}2 ng/ml, 2 to {<=}4 ng/ml, and >4 ng/ml. PSAve and PSAdt were measured. PET and CT scans were interpreted separately and then together. PET/CT diagnosed relapse in 33 of the 49 patients (67%). The detection rates were 20%, 55%, 80% and 87% in the PSA groups {<=}1, 1 to {<=}2, 2 to {<=}4 and >4 ng/ml, respectively. PET/CT was positive in 7 of 18 patients (38.9%) with a PSA {<=}2 ng/ml, and in 26 of 31 (83.9%) with a PSA >2 ng/ml. PET/CT was positive in 7 of 25 patients (84%) with PSAdt {<=}6 months, and in 12 of 24 patients (50%) with PSAdt >6 months, and was positive in 26 of 30 patients (86%) with a PSAve >2 ng/ml per year, and in 7 of 19 patients (36.8%) with PSAve {<=}2 ng/ml per year. PET alone was positive in 31 of 49 patients (63.3%), and of these 31 patients, CT was negative in 14 but diagnosed bone lesions in 2 patients in whom PET alone was negative. CT with the administration of intravenous contrast medium did not provide any further information. Detection rate of {sup 18}F-choline imaging is closely related to PSA and PSA kinetics. In particular, {sup 18}F-choline PET/CT is recommended in patients with PSA >2 ng/ml, PSAdt {<=}6 months and PSAve >2 ng/ml per year. CT is useful for detecting bone metastases that are not {sup 18}F-choline-avid. The use of intravenous contrast agent seems unnecessary. (orig.)

  11. The optimal timing to perform 18F/11C-choline PET/CT in patients with suspicion of relapse of prostate cancer: trigger PSA versus PSA velocity and PSA doubling time.

    Science.gov (United States)

    Calabria, Ferdinando; Rubello, Domenico; Schillaci, Orazio

    2014-12-09

    In the present short communication we considered the main publications focused on trigger prostate-specific antigen (PSA) and PSA kinetics that systematically compared 18F to 11C-choline PET/CT in order to establish the optimal time to perform choline PET/CT in relation to the trigger values and velocity, as well as doubling time of PSA serum levels.

  12. Activities relating to PSA in the regulatory process

    International Nuclear Information System (INIS)

    Campbell, J.F.; Grint, G.C.

    1994-01-01

    In addition to the IAEA activities concerning the use of PSA in the regulatory process there are two other international initiatives in this area by the European Commission and the OECD's Committee for Nuclear Regulatory Authorities (CRNA). The paper gives a brief outline of these activities as well as introducing an update on the regulatory use of PSA in the UK. 3 refs, 3 tabs

  13. Estimation of the uncertainties considered in NPP PSA level 2

    International Nuclear Information System (INIS)

    Kalchev, B.; Hristova, R.

    2005-01-01

    The main approaches of the uncertainties analysis are presented. The sources of uncertainties which should be considered in PSA level 2 for WWER reactor such as: uncertainties propagated from level 1 PSA; uncertainties in input parameters; uncertainties related to the modelling of physical phenomena during the accident progression and uncertainties related to the estimation of source terms are defined. The methods for estimation of the uncertainties are also discussed in this paper

  14. Child Injury: What You Need to Know PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2012-04-16

    This 60 second PSA is based on the April 2012 CDC Vital Signs report. Many childhood deaths and injuries are preventable, including those caused by crashes, suffocation, poisoning, drowning, fires, and falls. The PSA discusses ways to help prevent these deaths and injuries.  Created: 4/16/2012 by Centers for Disease Control and Prevention (CDC).   Date Released: 4/16/2012.

  15. PSA Level 2 activities for RBMK reactors

    International Nuclear Information System (INIS)

    Gubler, R.

    1998-01-01

    Probabilistic safety analyses (PSAs) of the boiling water graphite moderated pressure tube reactors (RBMKs) have been developed only recently and they are limited to Level 1. Activities at the IAEA were first motivated because of the difficulties to characterize core damage for RBMK reactors. Core damage probability is used in documents of the IAEA as a convenient single valued measure, for example for probabilistic safety criteria. The limited number of PSAs that have been completed for the RBMK reactors have shown that several special features of these channel type reactors necessitate revisiting of the characterization of core damage for these reactors. Furthermore, it has become increasingly evident that detailed deterministic analysis of DBAs and beyond design basis accidents reveal considerable insights into RBMK response to various accident conditions. These analyses can also help in better characterizing the outstanding phenomenological uncertainties, improved EOPs and AM strategies, including potential risk-beneficial accident negative backfits. The deterministic efforts should be focused first on elucidating accident progression processes and phenomena, and second on finding, qualifying and implementing procedures to minimize the risk of severe accident states The IAEA PSA procedures were mainly developed in New of vessel type LWRs, and would therefore require extensions to make them directly applicable. to channel type reactors. (author) (author)

  16. Safety Goal, Multi-unit Risk and PSA Uncertainty

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Joon-Eon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The safety goal is an answer of each country to the question 'How safe is safe enough?'. Table 1 shows some examples of the safety goal. However, many countries including Korea do not have the official safety goal for NPPs up to now since the establishment of safety goal is not just a technical issue but a very complex socio-technical issue. In establishing the safety goal for nuclear facilities, we have to consider various factors including not only technical aspects but also social, cultural ones. Recently, Korea is trying to establish the official safety goal. In this paper, we will review the relationship between the safety goal and Probabilistic Safety Assessment (PSA). We will also address some important technical issues to be considered in establishing the safety goal for NPPs from PSA point of view, i.e. a multi-unit risk issue and the uncertainty of PSA. In this paper, we reviewed some issues related to the safety goal and PSA. We believe that the safety goal is to be established in Korea considering the multi-unit risk. In addition, the relationship between the safety goal and PSA should be also defined clearly since PSA is the only way to answer to the question 'How safe is safe enough?'.

  17. Development of Integrated PSA Database and Application Technology

    Energy Technology Data Exchange (ETDEWEB)

    Han, Sang Hoon; Park, Jin Hee; Kim, Seung Hwan; Choi, Sun Yeong; Jung, Woo Sik; Jeong, Kwang Sub; Ha Jae Joo; Yang, Joon Eon; Min Kyung Ran; Kim, Tae Woon

    2005-04-15

    The purpose of this project is to develop 1) the reliability database framework, 2) the methodology for the reactor trip and abnormal event analysis, and 3) the prototype PSA information DB system. We already have a part of the reactor trip and component reliability data. In this study, we extend the collection of data up to 2002. We construct the pilot reliability database for common cause failure and piping failure data. A reactor trip or a component failure may have an impact on the safety of a nuclear power plant. We perform the precursor analysis for such events that occurred in the KSNP, and to develop a procedure for the precursor analysis. A risk monitor provides a mean to trace the changes in the risk following the changes in the plant configurations. We develop a methodology incorporating the model of secondary system related to the reactor trip into the risk monitor model. We develop a prototype PSA information system for the UCN 3 and 4 PSA models where information for the PSA is inputted into the system such as PSA reports, analysis reports, thermal-hydraulic analysis results, system notebooks, and so on. We develop a unique coherent BDD method to quantify a fault tree and the fastest fault tree quantification engine FTREX. We develop quantification software for a full PSA model and a one top model.

  18. Development of PSA procedure for a criticality in reprocessing facilities

    International Nuclear Information System (INIS)

    Endo, Shigeki; Takanashi, Mitsuhiro; Ueda, Yoshinori

    2012-08-01

    Utilization of risk information for the nuclear safety regulation is being discussed in Japan. The development of probabilistic safety assessment (PSA) procedure is indispensable for the utilization of risk information. The Japan Nuclear Energy Safety Organization (JNES) has been conducting trial PSA to a model plant for major events, i.e. hydrogen explosion, solution boiling, rapid decomposition of TBP complexes, criticality, solvent fire, leakage of molten glass, leakage of high active concentrated liquid waste, loss of all AC electricity, drop of a fuel assembly, for the purpose of developing the PSA procedure for reprocessing facilities. For criticality events results of trial PSA were summarized as a report in which how to evaluate an amount of radioactive materials released from a facility and a health effect on the public were emphasized. Therefore, for criticality events the results of trial PSA were summarized in this report to emphasize procedures from making event progression scenarios to quantifying event sequences, which were not handled in the previous report, in a style of a document describing PSA procedures. (author)

  19. Generation of risk importance information from severe accident PSA model

    International Nuclear Information System (INIS)

    Seo, Mi Ro; Kim, Hyeong Taek; Moon, Chan Kook

    2012-01-01

    One of the important objects conducting Probabilistic Safety Assessment (PSA) is the relative evaluation of importance of the component or function that is greatly affected to the plant safety. This evaluation is performed by the importance assessment methods such as Risk Reduction Worth, Risk Achievement Worth, and Fuss el Vessley method from the aspect of core damage frequency (CDF). In the Level 1 PSA model, the importance of each component can be evaluated since the CDF is calculated by the combination of the branch probability of event tree and the component failure probability in the fault tree. But, the Level 2 PSA model in order to assess the containment integrity cannot evaluate the risk importance by the above methods because the model is consisted of 3 parts, plant damage status, containment event tree, and source term category. So, in the field that the Level 2 PSA risk importance information should be reflected, such as maintenance rule program, risk importance has been determined by the subjective judgment of the model developer. This study was performed in order to generate the risk importance information more objectively and systematically in the Level 2 PSA model, focused on the containment event tree in the domain PHWR Level 2 PSA model

  20. PSA Model Improvement Using Maintenance Rule Function Mapping

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Mi Ro [KHNP-CRI, Nuclear Safety Laboratory, Daejeon (Korea, Republic of)

    2011-10-15

    The Maintenance Rule (MR) program, in nature, is a performance-based program. Therefore, the risk information derived from the Probabilistic Safety Assessment model is introduced into the MR program during the Safety Significance determination and Performance Criteria selection processes. However, this process also facilitates the determination of the vulnerabilities in currently utilized PSA models and offers means of improving them. To find vulnerabilities in an existing PSA model, an initial review determines whether the safety-related MR functions are included in the PSA model. Because safety-related MR functions are related to accident prevention and mitigation, it is generally necessary for them to be included in the PSA model. In the process of determining the safety significance of each functions, quantitative risk importance levels are determined through a process known as PSA model basic event mapping to MR functions. During this process, it is common for some inadequate and overlooked models to be uncovered. In this paper, the PSA model and the MR program of Wolsong Unit 1 were used as references

  1. One Approach to the Fire PSA Uncertainty Analysis

    International Nuclear Information System (INIS)

    Simic, Z.; Mikulicic, V.; Vukovic, I.

    2002-01-01

    Experienced practical events and findings from the number of fire probabilistic safety assessment (PSA) studies show that fire has high relative importance for nuclear power plant safety. Fire PSA is a very challenging phenomenon and a number of issues are still in the area of research and development. This has a major impact on the conservatism of fire PSA findings. One way to reduce the level of conservatism is to conduct uncertainty analysis. At the top-level, uncertainty of the fire PSA can be separated in to three segments. The first segment is related to fire initiating events frequencies. The second uncertainty segment is connected to the uncertainty of fire damage. Finally, there is uncertainty related to the PSA model, which propagates this fire-initiated damage to the core damage or other analyzed risk. This paper discusses all three segments of uncertainty. Some recent experience with fire PSA study uncertainty analysis, usage of fire analysis code COMPBRN IIIe, and uncertainty evaluation importance to the final result is presented.(author)

  2. The Tobacco Use Epidemic – What You Need to Know PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2011-09-06

    This 60 second PSA is based on the September, 2011 CDC Vital Signs report. Fewer Americans are smoking cigarettes, and daily smokers are smoking less; however, even occasional smoking causes harm. The best option for any smoker is to quit completely. Quitting at any age has benefits, and the sooner you quit, the sooner your body can begin to heal.  Created: 9/6/2011 by Centers for Disease Control and Prevention (CDC).   Date Released: 9/6/2011.

  3. Predictor of response to salvage radiotherapy in patients with PSA recurrence after radical prostatectomy. The usefulness of PSA doubling time

    International Nuclear Information System (INIS)

    Numata, Kousaku; Azuma, Koji; Hashine, Katsuyoshi; Sumiyoshi, Yoshiteru

    2005-01-01

    We assessed predictors of response to salvage radiotherapy (sRT) in patients with prostate-specific antigen (PSA) recurrence after radical prostatectomy. A total of 21 patients receiving sRT for PSA recurrence without systemic progression after radical prostatectomy had medical records available for retrospective review. We defined sRT as external beam radiotherapy for patients with a continuous increase in PSA level≥0.2 ng/ml after radical prostatectomy. Response was defined as achievement of a PSA nadir of ≤0.1 ng/ml. Various pre-treatment parameters were evaluated retrospectively. The median follow-up period after sRT was 38 months. Of the 21 patients, 15 were good responders (71%). The only predictive factor was PSA doubling time (PSADT). Age and PSA level at diagnosis, Gleason score and surgical margin status were not significant predictors of response. The median PSADT in responders was 6.2 months versus 1.9 months in non-responders (P=0.019). The patients with a PSADT of ≥5 months were all responders. PSADT appears to be a good predictor of response to sRT. sRT was especially effective when PSADT was ≥5 months. (author)

  4. Murine polyomavirus virus-like particles carrying full-length human PSA protect BALB/c mice from outgrowth of a PSA expressing tumor.

    Directory of Open Access Journals (Sweden)

    Mathilda Eriksson

    Full Text Available Virus-like particles (VLPs consist of capsid proteins from viruses and have been shown to be usable as carriers of protein and peptide antigens for immune therapy. In this study, we have produced and assayed murine polyomavirus (MPyV VLPs carrying the entire human Prostate Specific Antigen (PSA (PSA-MPyVLPs for their potential use for immune therapy in a mouse model system. BALB/c mice immunized with PSA-MPyVLPs were only marginally protected against outgrowth of a PSA-expressing tumor. To improve protection, PSA-MPyVLPs were co-injected with adjuvant CpG, either alone or loaded onto murine dendritic cells (DCs. Immunization with PSA-MPyVLPs loaded onto DCs in the presence of CpG was shown to efficiently protect mice from tumor outgrowth. In addition, cellular and humoral immune responses after immunization were examined. PSA-specific CD4(+ and CD8(+ cells were demonstrated, but no PSA-specific IgG antibodies. Vaccination with DCs loaded with PSA-MPyVLPs induced an eight-fold lower titre of anti-VLP antibodies than vaccination with PSA-MPyVLPs alone. In conclusion, immunization of BALB/c mice with PSA-MPyVLPs, loaded onto DCs and co-injected with CpG, induces an efficient PSA-specific tumor protective immune response, including both CD4(+ and CD8(+ cells with a low induction of anti-VLP antibodies.

  5. Murine Polyomavirus Virus-Like Particles Carrying Full-Length Human PSA Protect BALB/c Mice from Outgrowth of a PSA Expressing Tumor

    Science.gov (United States)

    Eriksson, Mathilda; Andreasson, Kalle; Weidmann, Joachim; Lundberg, Kajsa; Tegerstedt, Karin

    2011-01-01

    Virus-like particles (VLPs) consist of capsid proteins from viruses and have been shown to be usable as carriers of protein and peptide antigens for immune therapy. In this study, we have produced and assayed murine polyomavirus (MPyV) VLPs carrying the entire human Prostate Specific Antigen (PSA) (PSA-MPyVLPs) for their potential use for immune therapy in a mouse model system. BALB/c mice immunized with PSA-MPyVLPs were only marginally protected against outgrowth of a PSA-expressing tumor. To improve protection, PSA-MPyVLPs were co-injected with adjuvant CpG, either alone or loaded onto murine dendritic cells (DCs). Immunization with PSA-MPyVLPs loaded onto DCs in the presence of CpG was shown to efficiently protect mice from tumor outgrowth. In addition, cellular and humoral immune responses after immunization were examined. PSA-specific CD4+ and CD8+ cells were demonstrated, but no PSA-specific IgG antibodies. Vaccination with DCs loaded with PSA-MPyVLPs induced an eight-fold lower titre of anti-VLP antibodies than vaccination with PSA-MPyVLPs alone. In conclusion, immunization of BALB/c mice with PSA-MPyVLPs, loaded onto DCs and co-injected with CpG, induces an efficient PSA-specific tumor protective immune response, including both CD4+ and CD8+ cells with a low induction of anti-VLP antibodies. PMID:21858228

  6. About the 'scientification' of politics by way of scientific expertise by advisory bodies. Social science expertise and desicion-making in social problem areas in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Wagner, P.

    1985-01-01

    Taking the examples of the Council of Economic Advisors, the Education Council and the Federal Parliament's Commission of Inquiry on Future Nuclear Energy Policy, this paper analyses political situations in the Federal Republic of Germany in which social science expertise entered public debate and decision-making in certain social problem areas in a very pronounced way. By considering the social context in which these advisory bodies were created, an attempt is made to link an analysis of different social actors' interests to a review of existing knowledge and patterns of interpretation in the social sciences. It is shown that by using social science findings some actors achieved advantages in justifying and legitimating their political positions and that subsequently the relations of actors in some arenas of conflict changed-without, however, allowing to relate this causally only to the use of scientific knowledge. If, however, the use of scientific arguments is rapidly generalized, the confrontation of expertise and counter-expertise by opposing actors becomes usual practice. This, in turn, provides for questions concerning their 'scientificity', which the social sciences are asked to take up in reflections of their relation to social practice. (orig./HSCH) [de

  7. 75 FR 2880 - Homeland Security Advisory Council

    Science.gov (United States)

    2010-01-19

    ... the Secretary's primary advisory body with the goal of providing strategic, timely and actionable... portions of the meeting will include updates on operational challenges, intelligence briefings, and pre... procedures. HSAC members will receive classified and sensitive intelligence briefings during the closed...

  8. Development of level 2 PSA technology

    International Nuclear Information System (INIS)

    Kim, Dong Ha; Park, Soo Yong; Kim, See Darl; Song, Yong Mann; Ahn, Kwang Il; Park, Jae Wu; Jin, Young Ho.

    1997-07-01

    The objective of this project is the development of the computer code system for level 2 probabilistic safety assessment (PSA) of nuclear power plants. The scope of the project can be divided into three areas. The first area is to develop the computer code (CONPAS) which can quantify the accident progression event trees. CONPAS beta version has been developed this year and it is comprised of four modules : 1) EDITOR for generating the event tree logic diagrams and 1) COMPUTER for event tree quantification and for additional use of the calculated results. 3) TEXT EDITOR and 4) CODE PLOTTER. Comparing with the existing computer code, the present code provides a flexible code reusability and user interface, convenient edition of logic diagram, data operation, and systematic quantification of the results. The methodology development of containment structural analysis is the second area. The specific tasks included the collection and analysis of the containment failure modes for the various containment types, and the methodology establishment for the containment structure analysis. Over twenty large dry PWR containments, the database for containment failure mode and pressure has been constructed and the simplified fragility model has been proposed to calculate the containment failure probability. They will be used as an important input not only in the containment analysis but also in the source term analysis. For the last, source term analyzing methodology and its applied computer code that is named as 'KORSOR' are developed. KORSOR which used parametric model approach combined modules which consist of accident sequence input module via user's logic rule, random sample generating module, parametric database module, and source term uncertainty quantification module. The characteristics of parametric data which use din the source term analyzing model is analyzed and the constructing idea and example for the parametric database is suggested. (author). 67 refs., 66 tabs

  9. Development of PSA module for computerized accident management support (CAMS)

    International Nuclear Information System (INIS)

    Iguchi, Yukihiro

    1996-10-01

    CAMS (Computerised Accident Management Support) is a system that will provide assistance in case of the accidents in a nuclear power plant. The PSA module was developed in order to give useful information in this situation applying the PSA method, which is a comprehensive source of safety knowledge. This module contains plant-specific PSA data, comprising event trees, failure probabilities etc. It has several event trees categorised according to the initiating events. Each event tree has an initiating event frequency and branching probabilities. The various support systems for branches are considered and their dependencies are calculated logically. This module can be activated by data from the state identification (SI) module of CAMS. If an initiating event occurs, the event tree is re-calculated and the PSA module shows which systems of the plant should be activated to bring the plant to a safe state. If the plant responds to the event in the normal way, the plant will be shut down and come to a safe state. However, if some functions do not work, the PSA module generates another path and gives information about the critical systems. If the state of the plant is changed, either by the operators or automatically by the control system, the PSA module follows the new path. Because the estimation of the core damage frequency should be very quick in the accident situation, a simplified model of the event tree and fault trees was adopted. It enabled the PSA module to calculates the CDF within 5 seconds on a standard type work station. The development of the module has been successful. However, further development of the functionality of the module is suggested like real connection to a plant and to the strategy generator module of CAMS, applications for operational support, low power operation optimisation, etc. (author)

  10. International network on incorporation of ageing effects into PSA

    International Nuclear Information System (INIS)

    Kirchsteiger, C.; Patrik, M.

    2006-01-01

    This paper describes the background and status of a new International Network on ''Incorporating Ageing Effects into Probabilistic Safety Assessment''. The Joint Research Centre (JRC) of the European Commission organized in September 2004 the kickoff meeting of this Network at JRC's Institute for Energy in Petten, Netherlands, with the aims to open the APSA Network, to start discussion of ageing issues in relation to incorporating ageing effects into PSA tools and to come to consensus on objectives and work packages of the Network, taking into account the specific expectations of potential Network partners. The presentations and discussions at the meeting confirmed the main conclusion from the previously organized PSAM 7 pre-conference workshop on ''Incorporating PSA into Ageing Management'', Budapest, June 2004, namely that incorporating ageing effects into PSA seems to be more and more a hot topic particularly for risk assessment and ageing management of nuclear power plants operating at advanced age (more than 25-30 years) and for the purpose of plant life extension. However, it also appeared that, especially regarding the situation in Europe, at present there are several on-going feasibility or full studies in this area, but not yet a completed Ageing PSA leading to applications. The project's working method is a NETWORK of operators, industry, research, academia and consultants with an active interest in the area (physical networking via a series of workshops and virtual networking via the Internet). The resulting knowledge should help PSA developers and users to incorporate the effects of equipment ageing into current PSA tools and models, to identify and/or develop most effective corresponding methods, to focus on dominant ageing contributors and components and to promote the use of PSA for ageing management of Nuclear Power Plants. (orig.)

  11. Comparative Study on Atmospheric Dispersion Module of Level 3 PSA

    Energy Technology Data Exchange (ETDEWEB)

    Kwon, Dahye; Jang, Misuk; Kang, Hyun Sik; Kim, Seoung Rae [NESS, Daejeon (Korea, Republic of)

    2016-10-15

    Some regulation documents such as Regulatory Guides and NUREG publications from the U.S. Nuclear Regulatory Commission (NRC) have influences on domestic radiation environmental analyses. As renewal versions of NUREG-0800 and NUREG-1555 have issued lately, the assessment for Severe Accident (SA) with Probabilistic Safety Assessment (PSA) should be added to Safety Analysis Report (SAR) and Radiation Environmental Report (RER). Because these reports are the required documents for obtaining the construction permit and operating license, it is important to understand the PSA methodology and it needs to improve the site-specific input data of L3PSA codes for SA. First, our review focuses on the atmospheric dispersion and deposition related input data of L3PSA code in this paper. Then we will continue to review the improvements of other input data. Two atmospheric dispersion models, which are PAVAN developed for design basis accident and ATMOS of MACCS2 code developed for SA, were reviewed in this paper. L3PSA deals with the effects of severe accidents and basically includes the evaluation of both short- and long-term effects. Therefore, both the deposition effects and nuclide information(type, amount, and chemical characteristics of released radionuclide) would be considered as the input parameters of atmospheric dispersion model for L3PSA. Additionally, the meteorological data would be sampled randomly to meet the purpose of probabilistic method. However, the sampling method would be selected according to analysis purpose. After review, ATMOS module and its input data are suitably developed for the atmospheric dispersion analysis of L3PSA. However, ATMOS module was developed using the site-specific terrain and environment characteristics. For the domestic application, it needs to study the input data reflecting the Korean terrain and environment characteristics. It would be also continuously improved in response to the time- and site-specific changes of weather

  12. Metastatic prostate cancer in the modern era of PSA screening

    Directory of Open Access Journals (Sweden)

    Philip A. Fontenot Jr

    Full Text Available ABSTRACT Introduction To characterize initial presentation and PSA screening status in a contemporary cohort of men treated for metastatic prostate cancer at our institution. Materials and methods We reviewed records of 160 men treated for metastatic prostate cancer between 2008-2014 and assessed initial presentation, categorizing patients into four groups. Groups 1 and 2 presented with localized disease and received treatment. These men suffered biochemical recurrence late (>1 year or earlier (<1 year, respectively, and developed metastases. Groups 3 and 4 had asymptomatic and symptomatic metastases at the outset of their diagnosis. Patients with a first PSA at age 55 or younger were considered to have guideline-directed screening. Results Complete records were available on 157 men for initial presentation and 155 men for PSA screening. Groups 1, 2, 3 and 4 included 27 (17%, 7 (5%, 69 (44% and 54 (34% patients, respectively. Twenty (13% patients received guideline-directed PSA screening, 5/155 (3% patients presented with metastases prior to age 55 with their first PSA, and 130/155 (84% had their first PSA after age 55, of which 122/130 (94% had metastasis at the time of diagnosis. Conclusion Despite widespread screening, most men treated for metastatic prostate cancer at our institution presented with metastases rather than progressed after definitive treatment. Furthermore, 25 (16% patients received guideline-directed PSA screening at or before age 55. These data highlight that, despite mass screening efforts, patients treated for incurable disease at our institution may not have been a result of a failed screening test, but a failure to be screened.

  13. Metastatic prostate cancer in the modern era of PSA screening

    Science.gov (United States)

    Fontenot, Philip A.; Nehra, Avinash; Parker, William; Wyre, Hadley; Mirza, Moben; Duchene, David A.; Holzbeierlein, Jeffrey; Thrasher, James Brantley; Veldhuizen, Peter Van; Lee, Eugene K.

    2017-01-01

    ABSTRACT Introduction To characterize initial presentation and PSA screening status in a contemporary cohort of men treated for metastatic prostate cancer at our institution. Materials and methods We reviewed records of 160 men treated for metastatic prostate cancer between 2008-2014 and assessed initial presentation, categorizing patients into four groups. Groups 1 and 2 presented with localized disease and received treatment. These men suffered biochemical recurrence late (>1 year) or earlier (<1 year), respectively, and developed metastases. Groups 3 and 4 had asymptomatic and symptomatic metastases at the outset of their diagnosis. Patients with a first PSA at age 55 or younger were considered to have guideline-directed screening. Results Complete records were available on 157 men for initial presentation and 155 men for PSA screening. Groups 1, 2, 3 and 4 included 27 (17%), 7 (5%), 69 (44%) and 54 (34%) patients, respectively. Twenty (13%) patients received guideline-directed PSA screening, 5/155 (3%) patients presented with metastases prior to age 55 with their first PSA, and 130/155 (84%) had their first PSA after age 55, of which 122/130 (94%) had metastasis at the time of diagnosis. Conclusion Despite widespread screening, most men treated for metastatic prostate cancer at our institution presented with metastases rather than progressed after definitive treatment. Furthermore, 25 (16%) patients received guideline-directed PSA screening at or before age 55. These data highlight that, despite mass screening efforts, patients treated for incurable disease at our institution may not have been a result of a failed screening test, but a failure to be screened. PMID:28338310

  14. Seismic PSA of nuclear power plants a case study

    International Nuclear Information System (INIS)

    Hari Prasad, M.; Dubey, P.N.; Reddy, G.R.; Saraf, R.K.; Ghosh, A.K.

    2006-07-01

    Seismic Probabilistic Safety Assessment (Seismic PSA) analysis is an external event PSA analysis. The objective of seismic PSA for the plants is to examine the existence of plant vulnerabilities against postulated earthquakes by numerically assessing the plant safety and to take appropriate measures to enhance the plant safety. Seismic PSA analysis integrates the seismic hazard analysis, seismic response analysis, seismic fragility analysis and system reliability/ accident sequence analysis. In general, the plant consists of normally operating and emergency standby systems and components. The failure during an earthquake (induced directly by excessive inertial stresses or indirectly following the failure of some other item) of an operating component will lead to a change in the state of the plant. In that case, various scenarios can follow depending on the initiating event and the status of other sub-systems. The analysis represents these possible chronological sequences by an event tree. The event trees and the associated fault trees model the sub-systems down to the level of individual components. The procedure has been applied for a typical Indian nuclear power plant. From the internal event PSA level I analysis significant contribution to the Core Damage Frequency (CDF) was found due to the Fire Water System. Hence, this system was selected to establish the procedure of seismic PSA. In this report the different elements that go into seismic PSA analysis have been discussed. Hazard curves have been developed for the site. Fragility curve for the seismically induced failure of Class IV power has been developed. The fragility curve for fire-water piping system has been generated. Event tree for Class IV power supply has been developed and the dominating accident sequences were identified. CDF has been estimated from these dominating accident sequences by convoluting hazard curves of initiating event and fragility curves of the safety systems. (author)

  15. ASAMPSA-E guidance for level 2 PSA Volume 2. Implementing external Events modelling in Level 2 PSA

    International Nuclear Information System (INIS)

    Cazzoli, E.; Vitazkova, J.; Loeffler, H.; Burgazzi, L.

    2016-01-01

    The objective of the present document is to provide guidance on the implementation of external events into an 'extended' L2 PSA. It has to be noted that L2 PSA addresses issues beginning with fuel degradation and ending with the release of radionuclides into the environment. Therefore, the present document may touch upon, but does not evaluate explicitly issues that involve events or phenomena which occur before the fuel begins to degrade. Following the accident at Fukushima Dai-ichi, the nuclear safety community has realized that much attention should be given to the areas of operator interventions and accidents that may develop at the same time in more than one unit if they are initiated by one or more common external events. For this reason and to fulfill the PSA end-users' wish list (as reflected by an ASAMPSA-E survey), the attention is mostly focused on interface between L1 and L2 PSA, fragility analysis, human response analysis and some consideration is given to L2 PSA modeling of severe accidents for multiple unit sites, even though it is premature to provide extensive guidance in this area. The following recommendations, mentioned in various sections within this document, are summarized here: 1. Vulnerability/fragility analyses should be performed with respect to all external hazards and all structures, systems and components potentially affected that could be relevant to L2 PSA, 2. Importance should be given to the assessment of human performance following extreme external events; for extreme circumstances with high stress level, low confidence is justified for SAM human interventions and for such conditions, human interventions could be analyzed as sensitivity cases only in L2 PSA, 3. Results presentation should include assessment of total risk measures compared with risk targets able to assess all contributions to the risk and to judge properly the safety, 4. Total risk measures shall be associated to appropriate information on all

  16. Risk Metrics and Measures for an Extended PSA

    International Nuclear Information System (INIS)

    Wielenberg, A.; Loeffler, H.; Hasnaoui, C.; Burgazzi, L.; Cazzoli, E.; Jan, P.; La Rovere, S.; Siklossy, T.; Vitazkova, J.; Raimond, E.

    2016-01-01

    This report provides a review of the main used risk measures for Level 1 and Level 2 PSA. It depicts their advantages, limitations and disadvantages and develops some more precise risk measures relevant for extended PSAs and helpful for decision-making. This report does not recommend or suggest any quantitative value for the risk measures. It does not discuss in details decision-making based on PSA results neither. The choice of one appropriate risk measure or a set of risk measures depends on the decision making approach as well as on the issue to be decided. The general approach for decision making aims at a multi-attribute approach. This can include the use of several risk measures as appropriate. Section 5 provides some recommendations on the main risk metrics to be used for an extended PSA. For Level 1 PSA, Fuel Damage Frequency and Radionuclide Mobilization Frequency are recommended. For Level 2 PSA, the characterization of loss of containment function and a total risk measure based on the aggregated activity releases of all sequences rated by their frequencies is proposed. (authors)

  17. Improvement of PSA Models Using Monitoring and Prognostics

    Energy Technology Data Exchange (ETDEWEB)

    Heo, Gyun Young; Chang, Yoon Suk; Kim, Hyun Dae [Kyung Hee University, Yongin (Korea, Republic of)

    2014-08-15

    Probabilistic Safety Assessment (PSA) has performed a significant role for quantitative decision-making by finding design and operational vulnerability and evaluating cost-benefit in improving such weak points. Especially, it has been widely used as the core methodology for Risk-Informed Applications (RIAs). Even though the nature of PSA seeks realistic results, there are still 'conservative' aspects. The sources for the conservatism come from the assumption of safety analysis and the estimation of failure frequency. Surveillance, Diagnosis, and Prognosis (SDP) utilizing massive database and information technology is worthwhile to be highlighted in terms of the capability of alleviating the conservatism in the conventional PSA. This paper provides enabling techniques to concretize the method to provide time- and condition-dependent risk by integrating a conventional PSA model with condition monitoring and prognostics techniques. We will discuss how to integrate the results with frequency of initiating events (IEs) and failure probability of basic events (BEs). Two illustrative examples will be introduced: how the failure probability of a passive system can be evaluated under different plant conditions and how the IE frequency for Steam Generator Tube Rupture (SGTR) can be updated in terms of operating time. We expect that the proposed PSA model can take a role of annunciator to show the variation of Core Damage Frequency (CDF) in terms of time and operational conditions.

  18. Impact of Pre-Initiators on PSA in Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Ochirbat, Chimedtseren [KAIST, Daejeon (Korea, Republic of); Kim, Sok Chul [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2014-10-15

    Most of nuclear power plants had already conducted PSA work to examine their plant safety for identifying vulnerability and preparing the mitigating strategies for severe accident. However, the PSA for research reactor has been conducted limitedly comparing with nuclear power plants due to lack of awareness and resources. Most of PSA results demonstrated that human failure events (HFEs) take a major role of risk contributor in terms of core damage frequency. HFEs are categorized as the following three types: pre-initiating event interaction (e.g., maintenance of errors, testing errors, calibration errors), initiating event related interactions (e.g., human error causing loss of power, human error causing system trip), and post-initiating event (e.g., all action actuating manual safety system backup of an automatic system). Lack of resources and utilization of research reactor calls a vicious circle in terms of safety degradation. The safety degradation poses the vulnerability of human failure during research reactor utilization process. Typically, evaluation of pre-initiators related to test and maintenance are not taking into account in PSA for research reactors. This paper aims to investigate the impact of pre-initiating events related to test and maintenance activities on PSA results in terms of core damage frequency for a research reactor.

  19. Impact of Pre-Initiators on PSA in Research Reactor

    International Nuclear Information System (INIS)

    Ochirbat, Chimedtseren; Kim, Sok Chul

    2014-01-01

    Most of nuclear power plants had already conducted PSA work to examine their plant safety for identifying vulnerability and preparing the mitigating strategies for severe accident. However, the PSA for research reactor has been conducted limitedly comparing with nuclear power plants due to lack of awareness and resources. Most of PSA results demonstrated that human failure events (HFEs) take a major role of risk contributor in terms of core damage frequency. HFEs are categorized as the following three types: pre-initiating event interaction (e.g., maintenance of errors, testing errors, calibration errors), initiating event related interactions (e.g., human error causing loss of power, human error causing system trip), and post-initiating event (e.g., all action actuating manual safety system backup of an automatic system). Lack of resources and utilization of research reactor calls a vicious circle in terms of safety degradation. The safety degradation poses the vulnerability of human failure during research reactor utilization process. Typically, evaluation of pre-initiators related to test and maintenance are not taking into account in PSA for research reactors. This paper aims to investigate the impact of pre-initiating events related to test and maintenance activities on PSA results in terms of core damage frequency for a research reactor

  20. IC modelling in the IRSN EPR level 1 PSA

    International Nuclear Information System (INIS)

    Delache, J.

    2012-01-01

    Today in France, an EPR (European Pressurized Water Reactor) Unit is under construction at the Flamanville site. The creation authorization was granted in April 2007 and the plant commissioning is planned for 2012. The plant operator (EDF) provided for the construction license several PSA (Probabilistic Safety Assessment) studies. IRSN, as TSO (Technical Safety Organisation), wishes to dispose of the appropriate knowledge and tools for the independent verification of the operator studies and so developed its own model of PSA level 1. The goal is not to rebuild the plant operator PSA (with a full scope...) but to dispose of a simplified model able to clearly point out specific important issues. In the IRSN model a particular effort has recently been done on the Digital IC modelling. The IC (Instrumentation and Control) is modelled in the IRSN EPR PSA by using Fault Trees. Instead, EDF EPR PSA applies the COMPACT model to simplify the command and instrumentation logics. The IRSN model is more detailed in order to be more accurate in the global analysis of the Digital IC. For instance the communication ways between automates are considered as well as the failure of support systems. The model is still under development mainly in order to define the CCF (Common Cause Failure) which may be considered. (authors)

  1. Review of updated design of SPWR with PSA methodology

    International Nuclear Information System (INIS)

    Oikawa, Tetsukuni; Muramatsu, Ken

    1995-01-01

    This paper presents the procedures and results of a PSA (Probabilistic Safety Assessment) of the SPWR (System-Integrated PWR), which is being developed at the Japan Atomic Energy Research Institute (JAERI) as a medium sized innovative passive safe reactor, to assist in the design improvement of the SPWR at the basic or conceptual design phase by reviewing the design and identifying the design vulnerability. The first phase PSA, which was carried out in 1991, was a scoping analysis in order to understand overall plant characteristics and to search for general design weakness. After discussing the results of the first phase PSA, the SPWR designer group changed some designs of the SPWR. The second phase PSA of the SPWR was performed for the modified design in order to identify the design vulnerability as well as to grasp its overall safety level. Special items of these PSAs are as follows: (1) systematic identification of initiating events related to newly designed systems by the failure mode effect analysis (FMEA), (2) delineation of accident sequences for the internal initiating events using accident progression flow charts which is cost effective for conceptual design phase, (3) quantification of event trees based on many engineering judgement, and (4) lots of sensitivity analyses to examine applicability of data assignment. Qualitative and quantitative results of PSA provided very useful information for decision makings of design improvement and recommendations for further consideration in the process of detailed design. (author)

  2. Combination of signal intensity measurements of lesions in the peripheral zone of prostate with MRI and serum PSA level for differentiating benign disease from prostate cancer

    Energy Technology Data Exchange (ETDEWEB)

    Engelhard, K.; Kreckel, M. [Department of Radiology, Martha-Maria Hospital Nuernberg (Germany); Hollenbach, H.P.; Deimling, M. [Siemens Medical Engineering Group, Erlangen (Germany); Riedl, C. [Dept. of Urology, University of Erlangen-Nuernberg, Erlangen (Germany)

    2000-12-01

    The aim of this study was to predict the benign or malignant nature of a prostatic lesion by defining a threshold value of signal intensity ratio and a limiting value of serum prostate-specific antigen (PSA) in patients with elevated PSA level. Twenty-six patients with elevated PSA level and no hypoechogenic lesions at endosonography underwent MR imaging using an endorectal body phased-array coil at 1.5 T (Siemens Magnetom Symphony). A T2-weighted turbo-spin-echo (TSE) pulse sequence was applied in a transverse orientation. Two radiologists evaluated the images. In the presence of a pathological finding they defined regions of interest (ROI) in the suspicious pathological area of the peripheral zone and in muscle for reference. The quotient of the two ROIs was calculated and then correlated with the actual PSA level. Diagnosis was confirmed by prostate biopsy. Ten of 12 patients with quotients smaller than 4 showed cancer at histology. Nine of 12 men with cancer proven by biopsy had PSA levels higher than 10 ng/ml. A significant difference (p < 0.001) was found between the quotients of cancer and quotients of chronic prostatitis, fibrosis, or glandular atrophy. The accuracy of tumor differentiation of the method was 77 %. Measurement of signal intensity quotients in the peripheral zone of the prostate in combination with knowledge of defined limits of PSA levels the technique could be helpful in detecting additional cancer areas for prostate biopsy. False-negative tumor results of standard sextant biopsy can be reduced. In men with high PSA values the method has a role in differentiating between patients who require prostate biopsy and those of clinical observation. (orig.)

  3. Association of PSA, free-PSA and testosteron levels in serum of patients with benign prostate hyperplasia (BPH) and prostate cancer

    International Nuclear Information System (INIS)

    Wiwin Mailana; Kristina Dwi P; Sri Insani WW; Puji Widayati

    2015-01-01

    Prostate cancer screening can be done by measuring the concentration levels of PSA, free-PSA and testosterone in serum that examined with radioimmunoassay (RIA). A total of 30 patients of 45-81 years old had enrolled in this study and were taken their venous blood. The aim of research is to know the relationship between PSA and testosterone free-PSA with BPH and prostate cancer. Results showed that there was no correlation between age with BPH and prostate cancer (p = 0.06), but there is a relationship between PSA with BPH and prostate cancer (p = 0.002), the relationship between free-PSA with BPH and prostate cancer (p = 0.001). No correlation was found between PSA ratio with BPH and prostate cancer as well as the absence of a relationship between testosterone with BPH and prostate cancer (p = 0.924). (author)

  4. Australian Government health advisory groups and health policy: seeking a horse, finding a camel.

    Science.gov (United States)

    Russell, Lesley M; Boxall, Anne-Marie; Leeder, Stephen R

    2008-11-17

    Since its election, the Rudd Labor Government has created 10 new advisory bodies in the health portfolio, in addition to the 100 or more that were already established. An expansive and devolved advisory system could improve the health policy-making process, but only if it is integrated into the processes of government. We outline eight simple and practical measures that, if implemented, would make Australia's health advisory system more transparent and effective. Past experience shows that the most important factor governing the impact of health policy advisory bodies is political leadership.

  5. Comparison of SKIFS 2004:1 and Tillsynshandbok PSA against the ASME PRA Standard and European requirements on PSA

    International Nuclear Information System (INIS)

    Hellstroem, Per

    2005-04-01

    Requirements on PSA for risk informed applications are expressed in different international documents. The ASME PRA standard published in spring 2002 is one such document, PSA requirements are also expressed in the European Utility Requirements (EUR) for new reactors. The Swedish PSA requirements are provided in the Swedish regulators (SKI) statutes SKIFS 2004:1. SKI also has a review handbook for PSA activities (SKI report 2003:48). The review handbook is a support during review of the utilities PSA activities and the PSAs themselves. The review handbook expresses SKIs expectations by providing so called important aspects for both the PSA work and the PSAs, A comparison of SKIFS requirements and the important aspects in the Review handbook, on one side, and the requirements on PSA in EUR and ASME on the other side, is presented. The comparison shows a large difference in the level of detail in the different documents, where ASME is most detailed and specific. This is expected since the SKI review handbook not is a 'PSA guide' in the same way as the ASME PRA standard. A direct comparison of the ASME PRA standard requirements with the important aspects in the review handbook cannot answer the question which ASME capacity level that is achieved by a PSA meeting all important aspects. The conclusion is that it is not likely to achieve capacity level 2 and 3, since very few ASME level 3 attributes are explicitly expressed as important aspects, though many are expressed in general terms. The review handbook important aspects that are most similar to the ASME capacity level 1 attributes are initiating events, sequence analysis, and system analysis while less similarity is found for analysis of operator actions data analysis, quantification and containment analysis (level 2). Less similarity is found for capacity level 2 and 3. However, the number of additional ASME attributes on capacity level 2 and 3 are few. There are also important aspects in the review handbook that

  6. Improved Monte Carlo Method for PSA Uncertainty Analysis

    International Nuclear Information System (INIS)

    Choi, Jongsoo

    2016-01-01

    The treatment of uncertainty is an important issue for regulatory decisions. Uncertainties exist from knowledge limitations. A probabilistic approach has exposed some of these limitations and provided a framework to assess their significance and assist in developing a strategy to accommodate them in the regulatory process. The uncertainty analysis (UA) is usually based on the Monte Carlo method. This paper proposes a Monte Carlo UA approach to calculate the mean risk metrics accounting for the SOKC between basic events (including CCFs) using efficient random number generators and to meet Capability Category III of the ASME/ANS PRA standard. Audit calculation is needed in PSA regulatory reviews of uncertainty analysis results submitted for licensing. The proposed Monte Carlo UA approach provides a high degree of confidence in PSA reviews. All PSA needs accounting for the SOKC between event probabilities to meet the ASME/ANS PRA standard

  7. Study of methodology for low power/shutdown fire PSA

    International Nuclear Information System (INIS)

    Yan Zhen; Li Zhaohua; Li Lin; Song Lei

    2014-01-01

    As a risk assessment technology based on probability, the fire PSA is accepted abroad by nuclear industry in its application in the risk assessment for nuclear power plants. Based on the industry experience, the fire-induced impact on the plant safety during low power and shutdown operation cannot be neglected, therefore fire PSA can be used to assess the corresponding fire risk. However, there is no corresponding domestic guidance/standard as well as accepted analysis methodology up to date. Through investigating the latest evolvement on fire PSA during low power and shutdown operation, and integrating its characteristic with the corresponding engineering experience, an engineering methodology to evaluate the fire risk during low power and shutdown operation for nuclear power plant is established in this paper. In addition, an analysis demonstration as an example is given. (authors)

  8. Experience in PSA fault tree modularization at the ASCO NPP

    International Nuclear Information System (INIS)

    Nos Llorens, V.; Frances Urmeneta, M.; Fraig Sureda, J.

    1995-01-01

    Probabilistic Safety Analysis (PSA) is a basic tool in decision-making for the optimization of back fittings, procedures and maintenance practices. ASCO NPP PSA was developed with a high level of detail in the models. This required considerable computer resources (long running time) to carry out the quantification. The quantification time had therefore to be flexible to allow continuous evaluation of the impact on the estimation and reduction of risk in the plant, and also to facilitate post-PSA applications. The most suitable way of achieving this flexibility was by compacting and reducing the detailed fault trees of the project by means of a modularization process. The purpose of the paper is to present the practical experience acquired with modularization carried out in the UTE UNITEC-INYPSA-EMPRESARIOS AGRUPADOS framework and the method applied, the support computer programs devised and their degree of effectiveness. (Author)

  9. Simulation and optimization of an industrial PSA unit

    Directory of Open Access Journals (Sweden)

    Barg C.

    2000-01-01

    Full Text Available The Pressure Swing Adsorption (PSA units have been used as a low cost alternative to the usual gas separation processes. Its largest commercial application is for hydrogen purification systems. Several studies have been made about the simulation of pressure swing adsorption units, but there are only few reports on the optimization of such processes. The objective of this study is to simulate and optimize an industrial PSA unit for hydrogen purification. This unit consists of six beds, each of them have three layers of different kinds of adsorbents. The main impurities are methane, carbon monoxide and sulfidric gas. The product stream has 99.99% purity in hydrogen, and the recovery is around 90%. A mathematical model for a commercial PSA unit is developed. The cycle time and the pressure swing steps are optimized. All the features concerning with complex commercial processes are considered.

  10. Improved Monte Carlo Method for PSA Uncertainty Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Jongsoo [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2016-10-15

    The treatment of uncertainty is an important issue for regulatory decisions. Uncertainties exist from knowledge limitations. A probabilistic approach has exposed some of these limitations and provided a framework to assess their significance and assist in developing a strategy to accommodate them in the regulatory process. The uncertainty analysis (UA) is usually based on the Monte Carlo method. This paper proposes a Monte Carlo UA approach to calculate the mean risk metrics accounting for the SOKC between basic events (including CCFs) using efficient random number generators and to meet Capability Category III of the ASME/ANS PRA standard. Audit calculation is needed in PSA regulatory reviews of uncertainty analysis results submitted for licensing. The proposed Monte Carlo UA approach provides a high degree of confidence in PSA reviews. All PSA needs accounting for the SOKC between event probabilities to meet the ASME/ANS PRA standard.

  11. PROSTATE CANCER SCREENING: PSA TEST AWARENESS AMONG ADULT MALES.

    Science.gov (United States)

    Obana, Michael; O'Lawrence, Henry

    2015-01-01

    The overall purpose of this study was to determine whether visits to the doctor in the last 12 months, education level, and annual household income for adult males increased the awareness of prostate-specific antigen (PSA) tests. The effect of these factors for the knowledge of PSA exams was performed using statistical analysis. A retrospective secondary database was utilized for this study using the questionnaire in the California Health Interview Survey from 2009. Based on this survey, annual visits to the doctor, higher educational levels attained, and greater take-home pay were statistically significant and the results of the study were equivalent to those hypothesized. This also reflects the consideration of marketing PSA blood test screenings to those adult males who are poor, uneducated, and do not see the doctor on a consistent basis.

  12. The relationship between serum PSA, six sex hormones and the benign or malignant prostate diseases

    International Nuclear Information System (INIS)

    Xu Yancun

    2008-01-01

    In order to study clinical significance of serum prostate-specific antigen (PSA), free prostate specific antigen (PSA), f/tPSA and six sex hormones in prostate diseases, the serum levels of PSA, fPSA, f/tPSA, T, P, E 2 , PRL, LH and FSH in 72 cases of hyperplasia of prostate patients and 40 patients with prostate cancer were determined by RIA. The results showed that the serum levels of T, E 2 , PRL, LH, FSH in the BPH Group were significantly lower than those of in Pca group, the serum level of P in Pca group were significantly lower than those in BPH group; the levels of fPSA and f/tPSA ratio in BPH Group were significantly higher than those in Pca group. The results suggest that benign and malignant prostate disease (BPH and Pca) was related with the hormone imbalance. The serum total PSA and fPSA can be regarded as important indicators in the diagnosis of BPH and Pea. The combined determination of PSA, fPSA and f/tPSA may improve the diagnostic accuracy of Pca. (authors)

  13. Improvement of level-1 PSA computer code package

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Tae Woon; Park, C. K.; Kim, K. Y.; Han, S. H.; Jung, W. D.; Chang, S. C.; Yang, J. E.; Sung, T. Y.; Kang, D. I.; Park, J. H.; Lee, Y. H.; Kim, S. H.; Hwang, M. J.; Choi, S. Y.

    1997-07-01

    This year the fifth (final) year of the phase-I of the Government-sponsored Mid- and Long-term Nuclear Power Technology Development Project. The scope of this subproject titled on `The improvement of level-1 PSA Computer Codes` is divided into two main activities : (1) improvement of level-1 PSA methodology, (2) development of applications methodology of PSA techniques to operations and maintenance of nuclear power plant. Level-1 PSA code KIRAP is converted to PC-Windows environment. For the improvement of efficiency in performing PSA, the fast cutset generation algorithm and an analytical technique for handling logical loop in fault tree modeling are developed. Using about 30 foreign generic data sources, generic component reliability database (GDB) are developed considering dependency among source data. A computer program which handles dependency among data sources are also developed based on three stage bayesian updating technique. Common cause failure (CCF) analysis methods are reviewed and CCF database are established. Impact vectors can be estimated from this CCF database. A computer code, called MPRIDP, which handles CCF database are also developed. A CCF analysis reflecting plant-specific defensive strategy against CCF event is also performed. A risk monitor computer program, called Risk Monster, are being developed for the application to the operation and maintenance of nuclear power plant. The PSA application technique is applied to review the feasibility study of on-line maintenance and to the prioritization of in-service test (IST) of motor-operated valves (MOV). Finally, the root cause analysis (RCA) and reliability-centered maintenance (RCM) technologies are adopted and applied to the improvement of reliability of emergency diesel generators (EDG) of nuclear power plant. To help RCA and RCM analyses, two software programs are developed, which are EPIS and RAM Pro. (author). 129 refs., 20 tabs., 60 figs.

  14. Improvement of level-1 PSA computer code package

    International Nuclear Information System (INIS)

    Kim, Tae Woon; Park, C. K.; Kim, K. Y.; Han, S. H.; Jung, W. D.; Chang, S. C.; Yang, J. E.; Sung, T. Y.; Kang, D. I.; Park, J. H.; Lee, Y. H.; Kim, S. H.; Hwang, M. J.; Choi, S. Y.

    1997-07-01

    This year the fifth (final) year of the phase-I of the Government-sponsored Mid- and Long-term Nuclear Power Technology Development Project. The scope of this subproject titled on 'The improvement of level-1 PSA Computer Codes' is divided into two main activities : 1) improvement of level-1 PSA methodology, 2) development of applications methodology of PSA techniques to operations and maintenance of nuclear power plant. Level-1 PSA code KIRAP is converted to PC-Windows environment. For the improvement of efficiency in performing PSA, the fast cutset generation algorithm and an analytical technique for handling logical loop in fault tree modeling are developed. Using about 30 foreign generic data sources, generic component reliability database (GDB) are developed considering dependency among source data. A computer program which handles dependency among data sources are also developed based on three stage bayesian updating technique. Common cause failure (CCF) analysis methods are reviewed and CCF database are established. Impact vectors can be estimated from this CCF database. A computer code, called MPRIDP, which handles CCF database are also developed. A CCF analysis reflecting plant-specific defensive strategy against CCF event is also performed. A risk monitor computer program, called Risk Monster, are being developed for the application to the operation and maintenance of nuclear power plant. The PSA application technique is applied to review the feasibility study of on-line maintenance and to the prioritization of in-service test (IST) of motor-operated valves (MOV). Finally, the root cause analysis (RCA) and reliability-centered maintenance (RCM) technologies are adopted and applied to the improvement of reliability of emergency diesel generators (EDG) of nuclear power plant. To help RCA and RCM analyses, two software programs are developed, which are EPIS and RAM Pro. (author). 129 refs., 20 tabs., 60 figs

  15. PSA modeling of long-term accident sequences

    International Nuclear Information System (INIS)

    Georgescu, Gabriel; Corenwinder, Francois; Lanore, Jeanne-Marie

    2014-01-01

    In the context of the extension of PSA scope to include external hazards, in France, both operator (EDF) and IRSN work for the improvement of methods to better take into account in the PSA the accident sequences induced by initiators which affect a whole site containing several nuclear units (reactors, fuel pools,...). These methodological improvements represent an essential prerequisite for the development of external hazards PSA. However, it has to be noted that in French PSA, even before Fukushima, long term accident sequences were taken into account: many insight were therefore used, as complementary information, to enhance the safety level of the plants. IRSN proposed an external events PSA development program. One of the first steps of the program is the development of methods to model in the PSA the long term accident sequences, based on the experience gained. At short term IRSN intends to enhance the modeling of the 'long term' accident sequences induced by the loss of the heat sink or/and the loss of external power supply. The experience gained by IRSN and EDF from the development of several probabilistic studies treating long term accident sequences shows that the simple extension of the mission time of the mitigation systems from 24 hours to longer times is not sufficient to realistically quantify the risk and to obtain a correct ranking of the risk contributions and that treatment of recoveries is also necessary. IRSN intends to develop a generic study which can be used as a general methodology for the assessment of the long term accident sequences, mainly generated by external hazards and their combinations. This first attempt to develop this generic study allowed identifying some aspects, which may be hazard (or combinations of hazards) or related to initial boundary conditions, which should be taken into account for further developments. (authors)

  16. Application and Use of PSA-based Event Analysis in Belgium

    International Nuclear Information System (INIS)

    Hulsmans, M.; De Gelder, P.

    2003-01-01

    The paper describes the experiences of the Belgian nuclear regulatory body AVN with the application and the use of the PSAEA guidelines (PSA-based Event Analysis). In 2000, risk-based precursor analysis has increasingly become a part of the AVN process of feedback of operating experience, and constitutes in fact the first PSA application for the Belgian plants. The PSAEA guidelines were established by a consultant in the framework of an international project. In a first stage, AVN applied the PSAEA guidelines to two test cases in order to explore the feasibility and the interest of this type of probabilistic precursor analysis. These pilot studies demonstrated the applicability of the PSAEA method in general, and its applicability to the computer models of the Belgian state-of-the- art PSAs in particular. They revealed insights regarding the event analysis methodology, the resulting event severity and the PSA model itself. The consideration of relevant what-if questions allowed to identify - and in some cases also to quantify - several potential safety issues for improvement. The internal evaluation of PSAEA was positive and AVN decided to routinely perform several PSAEA studies per year. During 2000, PSAEA has increasingly become a part of the AVN process of feedback of operating experience. The objectives of the AVN precursor program have been clearly stated. A first pragmatic set of screening rules for operational events has been drawn up and applied. Six more operational events have been analysed in detail (initiating events as well as condition events) and resulted in a wide spectrum of event severity. In addition to the particular conclusions for each event, relevant insights have been gained regarding for instance event modelling and the interpretation of results. Particular attention has been devoted to the form of the analysis report. After an initial presentation of some key concepts, the particular context of this program and of AVN's objectives, the

  17. Cost implications of PSA screening differ by age.

    Science.gov (United States)

    Rao, Karthik; Liang, Stella; Cardamone, Michael; Joshu, Corinne E; Marmen, Kyle; Bhavsar, Nrupen; Nelson, William G; Ballentine Carter, H; Albert, Michael C; Platz, Elizabeth A; Pollack, Craig E

    2018-05-09

    Multiple guidelines seek to alter rates of prostate-specific antigen (PSA)-based prostate cancer screening. The costs borne by payers associated with PSA-based screening for men of different age groups-including the costs of screening and subsequent diagnosis, treatment, and adverse events-remain uncertain. We sought to develop a model of PSA costs that could be used by payers and health care systems to inform cost considerations under a range of different scenarios. We determined the prevalence of PSA screening among men aged 50 and higher using 2013-2014 data from a large, multispecialty group, obtained reimbursed costs associated with screening, diagnosis, and treatment from a commercial health plan, and identified transition probabilities for biopsy, diagnosis, treatment, and complications from the literature to generate a cost model. We estimated annual total costs for groups of men ages 50-54, 55-69, and 70+ years, and varied annual prostate cancer screening prevalence in each group from 5 to 50% and tested hypothetical examples of different test characteristics (e.g., true/false positive rate). Under the baseline screening patterns, costs of the PSA screening represented 10.1% of the total costs; costs of biopsies and associated complications were 23.3% of total costs; and, although only 0.3% of all screen eligible patients were treated, they accounted for 66.7% of total costs. For each 5-percentage point decrease in PSA screening among men aged 70 and older for a single calendar year, total costs associated with prostate cancer screening decreased by 13.8%. For each 5-percentage point decrease in PSA screening among men 50-54 and 55-69 years old, costs were 2.3% and 7.3% lower respectively. With constrained financial resources and with national pressure to decrease use of clinically unnecessary PSA-based prostate cancer screening, there is an opportunity for cost savings, especially by focusing on the downstream costs disproportionately associated with

  18. Repeat prostate-specific antigen (PSA) test before prostate biopsy: a 20% decrease in PSA values is associated with a reduced risk of cancer and particularly of high-grade cancer.

    Science.gov (United States)

    De Nunzio, Cosimo; Lombardo, Riccardo; Nacchia, Antonio; Tema, Giorgia; Tubaro, Andrea

    2018-07-01

    To analyse the impact of repeating a prostate-specific antigen (PSA) level assessment on prostate biopsy decision in a cohort of men undergoing prostate biopsy. From 2015 onwards, we consecutively enrolled, at a single institution in Italy, men undergoing 12-core transrectal ultrasonography-guided prostate needle biopsy. Indication for prostate biopsy was a PSA level of ≥4 ng/mL. Demographic, clinical, and histopathological data were collected. The PSA level was tested at enrolment (PSA 1 ) and 4 weeks later on the day before biopsy (PSA 2 ). Variations in PSA level were defined as: stable PSA 2 within a 10% variation, stable PSA 2 within a 20% variation, PSA 2 decreased by ≥10%, PSA 2 decreased by ≥20%, PSA 2 increased by ≥10%, PSA 2 increased by ≥20%, and PSA 2 PSA within 20% variation had a higher risk of prostate cancer (odds ratio [OR] 1.80, P PSA2 decreased by ≥20% had a lower risk of prostate cancer (OR 0.37, P PSA2 increased by ≥10% had an increased risk of high-grade prostate cancer (OR 1.93, P PSA returned to normal values (PSA levels significantly reduced the risk of high-grade prostate cancer. Further multicentre studies should validate our present results. © 2018 The Authors BJU International © 2018 BJU International Published by John Wiley & Sons Ltd.

  19. Advisory Committee Handbook.

    Science.gov (United States)

    Black Hawk Coll., Moline, IL.

    An advisory committee is generally comprised of persons outside the education profession who have specialized knowledge in a given area. The committee advises, makes recommendations, and gives service to the college and its students, instructors, and administrators. At Black Hawk College, there are four types of advisory committees: community,…

  20. ASAMPSA-E guidance for level 2 PSA Volume 3. Verification and improvement of SAM strategies with L2 PSA

    International Nuclear Information System (INIS)

    Rahni, N.; Raimond, E.; Jan, P.; Lopez, J.; Loeffler, H.; Mildenberger, O.; Kubicek, J.; Vitazkova, J.; Ivanov, I.; Groudev, P.; Lajtha, G.; Serrano, C.; Zhabin, O.; Prosek, Andrej; Dirksen, G.; Yu, S.; Oury, L.; Hultqvist, G.

    2016-01-01

    For each NPP, severe accident management (SAM) strategies shall make use of components or systems and human resources to limit as far as possible the consequences of any severe accident on-site and off-site. L2 PSA is one of the tools that can be used to verify and improve these strategies. The present report (deliverable D40.5 of the project ASAMPSA-E) provides an opportunity for a comparison of objectives in the different countries in terms of SAM strategies verification and improvement. The report summarizes also experience of each partner (including potential deficiencies) involved in this activity, in order to derive some good practices and required progress, addressing: - SAM modeling in L2 PSA, - Positive and negative aspects in current SAM practices, - Discussion on possible criteria related to L2 PSA for verification and improvement: risk reduction (in relation with WP30 activities on risk metrics), reduction of uncertainties on the severe accident progression paths until NPP stabilization, reduction of human failure conditional probabilities (depending on the SAM strategy, the environmental conditions...), - Review with a perspective of verification and improvement of the main SAM strategies (corium cooling, RCS depressurization, control of flammable gases, reactivity control, containment function, containment pressure control, limitation of radioactive releases,...), - SAM strategies to be considered in the context of an extended L2 PSA (as far possible, depending on existing experience), taking into account all operating modes, accidents also occurring in the SFPs and long term and multi-unit accidents. The deliverable D40.5 is developed from the partners' experience. Many of the topics described here are beyond the common practices of L2 PSA applications: in some countries, L2 PSA application is limited to the calculations of frequencies of release categories with no formal requirement for SAM verification and improvement. (authors)

  1. Clinical diagnostic value of combined determination of serum tPSA, cPSA and IGF-I levels in patients with prostatic disorders

    International Nuclear Information System (INIS)

    Zhang Bashan; Zhang Zigang; Lai Fudi

    2008-01-01

    Objective: To investigate the diagnostic value of combined determination of serum total prostatic specific antigen (tPSA), complex prostatic specific antigen (cPSA) and IGF-I levels in patients with prostatic disorders. Methods: Serum tPSA, cPSA (with CLIA) and IGF-I (with IRMA) levels were determined in 41 patients with prostatic carcinoma, 60 patients with benign prosta- tic hypertrophy (BPH) and 55 controls. Results: The serum tPSA, cPSA and IGF-I levels in patients with prostatic cancer were significantly higher than those in patients with BPH and controls (P<0.01). Taking the cut-off values of 4ng/ml, 3.6ng/ml and 150 for tPSA, cPSA and IGF-I respectively, the combined determination of these three items would yield a sensitivity of 88.6%, specificity of 84.9%, positive predicative value of 83% and negative predicative value of 90.0% for diagnosis of prostatic cancer. Conclusion: Combined determination of tPSA, cPSA and IGF-I would yield better sensitive and accurate diagnostic rate in patients with prostatic cancer, especially in those with laboratory values within the 'grey zone'. (authors)

  2. Relationship of chronic histologic prostatic inflammation in biopsy specimens with serum isoform [-2]proPSA (p2PSA), %p2PSA, and prostate health index in men with a total prostate-specific antigen of 4-10 ng/ml and normal digital rectal examination.

    Science.gov (United States)

    Lazzeri, Massimo; Abrate, Alberto; Lughezzani, Giovanni; Gadda, Giulio Maria; Freschi, Massimo; Mistretta, Francesco; Lista, Giuliana; Fossati, Nicola; Larcher, Alessandro; Kinzikeeva, Ella; Buffi, Nicolòmaria; Dell'Acqua, Vincenzo; Bini, Vittorio; Montorsi, Francesco; Guazzoni, Giorgio

    2014-03-01

    To investigate the relationship between serum [-2]proPSA (p2PSA) and derivatives with chronic histologic prostatic inflammation (CHPI) in men undergoing prostate biopsy for suspected prostate cancer (PCa). This nested case-control study resulted from an observational prospective trial for the definition of sensibility, specificity, and accuracy of p2PSA, %p2PSA, and Beckman Coulter Prostate Health Index (PHI), in men undergoing prostate biopsy, with a total prostate-specific antigen (PSA) of 4-10 ng/mL and normal digital rectal examination. CHPI was the outcome of interest and defined as the presence of moderate to large infiltration of lymphomononuclear cells with interstitial and/or glandular disruption in absence of PCa. p2PSA, %p2PSA, and PHI were considered the index tests and compared with the established biomarker reference standard tests: tPSA, fPSA, %fPSA. Of 267 patients subjected to prostate biopsy, 73 (27.3%) patients were diagnosed with CHPI. Comparing CHPI with PCa patients, %p2PSA and PHI were found to be significantly lower, whereas fPSA and %fPSA were significantly higher. %p2PSA and PHI were the most accurate predictors of CHPI at biopsy, significantly outperforming tPSA, fPSA, and %fPSA. On the contrary, no significant differences were found in PSA, p2PSA, and derivatives between CHPI and benign prostatic hyperplasia (BPH) patients. Our findings showed that p2PSA, %p2PSA, and PHI values might discriminate PCa from CHPI or BPH, but not CHPI from BPH, in men with a total PSA 4-10 ng/mL and normal digital rectal examination. p2PSA isoform and its derivatives could be useful in clinical decision making to avoid unnecessary biopsies in patients with CHPI and elevated tPSA value. Copyright © 2014 Elsevier Inc. All rights reserved.

  3. Time from first detectable PSA following radical prostatectomy to biochemical recurrence: A competing risk analysis

    Science.gov (United States)

    de Boo, Leonora; Pintilie, Melania; Yip, Paul; Baniel, Jack; Fleshner, Neil; Margel, David

    2015-01-01

    Introduction: In this study, we estimated the time from first detectable prostate-specific antigen (PSA) following radical prostatectomy (RP) to commonly used definitions of biochemical recurrence (BCR). We also identified the predictors of time to BCR. Methods: We identified subjects who underwent a RP and had an undetectable PSA after surgery followed by at least 1 detectable PSA between 2000 and 2011. The primary outcome was time to BCR (PSA ≥0.2 and successive PSA ≥0.2) and prediction of the rate of PSA rise. Outcomes were calculated using a competing risk analysis, with univariable and multivariable Fine and Grey models. We employed a mixed effect model to test clinical predictors that are associated with the rate of PSA rise. Results: The cohort included 376 patients. The median follow-up from surgery was 60.5 months (interquartile range [IQR] 40.8–91.5) and from detectable PSA was 18 months (IQR 11–32). Only 45.74% (n = 172) had PSA values ≥0.2 ng/mL, while 15.16% (n = 57) reached the PSA level of ≥0.4 ng/mL and rising. On multivariable analysis, the values of the first detectable PSA and pathologic Gleason grade 8 or higher were consistently independent predictors of time to BCR. In the mixed effect model rate, the PSA rise was associated with time from surgery to first detectable PSA, Gleason score, and prostate volume. The main limitation of this study is the large proportion of patients that received treatment without reaching BCR. It is plausible that shorter estimated median times would occur at a centre that does not use salvage therapy at such an early state. Conclusion: The time from first detectable PSA to BCR may be lengthy. Our analyses of the predictors of the rate of PSA rise can help determine a personalized approach for patients with a detectable PSA after surgery. PMID:25624961

  4. Rapid elimination kinetics of free PSA or human kallikrein-related peptidase 2 after initiation of gonadotropin-releasing hormone-antagonist treatment of prostate cancer

    DEFF Research Database (Denmark)

    Ulmert, David; Vickers, Andrew J; Scher, Howard I

    2012-01-01

    The utility of conventional prostate-specific antigen (PSA) measurements in blood for monitoring rapid responses to treatment for prostate cancer is limited because of its slow elimination rate. Prior studies have shown that free PSA (fPSA), intact PSA (iPSA) and human kallikrein-related peptidase...... of tPSA, fPSA, iPSA and hK2 after rapid induction of castration with degarelix (Firmagon(®)), a novel GnRH antagonist....

  5. The correlation of PSA nadir and biochemical freedom from cancer after external beam treatment: effects of stage, grade and pretreatment PSA groupings

    International Nuclear Information System (INIS)

    Pinover, W.H.; Hanlon, A.L.; Lee, W.R.; Hanks, G.E.

    1996-01-01

    Purpose: This study demonstrates the correlation of various post-irradiation PSA nadirs with long term biochemical freedom from disease (bNED) survival in patients treated mainly with conformal external beam radiation therapy. It also shows the effects of various groupings of pretreatment (prerx) PSA level, stage, and Gleason score on the rate of achieving a favorable PSA nadir. Materials and Methods: Three hundred forty patients with known pretreatment PSA, >2 years followup treated with radiation alone (278 conformal, 62 conventional) are reported. The median followup is 41 months (range 24 to 96 mos.). Patient grouping by pretreatment PSA levels are <10 ng/ml (143 patients), 10-19.9 ng/ml (108 patients), ≥20 ng/ml (89 patients); by palpation stage are T1C,2AB (240 patients) and T2C,3,4 (100 patients); and by differentiation are Gleason 2-4 (108 patients), Gleason 5-7 (221 patients), Gleason 8-10 (11 patients). The PSA nadir response is given for all patients, and for each of the above prerx groupings. The 5 year actuarial bNED survival is determined for all patients by PSA nadir. Biochemical failure is a PSA ≥1.5 ng/ml and rising on two consecutive measures. Multivariate analysis (MVA) is performed to determine factors predictive of favorable PSA nadir response and predictive of bNED survival. Results: The PSA nadir responses and 5 year bNED survival rates are shown in the table for all patients according to PSA nadir. 66% of patients achieved a favorable nadir (<1.0 ng/ml) which was associated with a 75%-87% 5 year bNED rate, while 34% achieved an unfavorable nadir associated with an 18-32% bNED survival rate at 5 years. The figure illustrates the dramatic separation in outcome associated with the nadir response. The table also illustrates the fraction of patients that achieve various nadir levels subdivided by prerx PSA level, palpation stage and Gleason score. A favorable PSA nadir is obtained in 90%, 63%, and 31% of patients with a prerx PSA <10, 10

  6. Generation of monoclonal antibodies against prostate specific antigen (PSA) for the detection of PSA and its purification; Generación de anticuerpos monoclonales contra el antígeno específico de próstata (PSA) para la detección del PSA y su purificación

    Energy Technology Data Exchange (ETDEWEB)

    Acevedo Castro, Boris Ernesto [Centro de Ingeniería Genética y Biotecnología, CIGB, La Habana (Cuba)

    2012-07-01

    The prostate cancer in Cuba is a problem of health (2672 diagnosed cases and 2769 deaths in 2007). Various diagnostic methods have been implemented for the detection and management of this disease, emphasizing among them (PSA) prostate-specific antigen serological determination. At this work was generated and characterized a panel of 11 antibodies (AcMs) monoclonal IgG1 detected with high affinity described major epitopes of the PSA, both in solution and attached to the test plate. From the panel obtained AcMs was the standardization of an essay type ELISA for the detection of serum total PSA (associated and free) equimolar, based on antibody monoclonal CB-PSA.4 in the coating and the CB-PSA.9 coupled with biotin as liner, with a detection limit of 0.15 ng/mL. Similarly, standardized system for detection in serum free PSA, based on the AcMs CB-PSA.4 (coating) and CB-PSA.2 coupled with biotin (liner), with a detection limit of 0.5 ng/mL. Finally, with the purpose of using PSA as standard in trials type ELISA, developed a simple method of inmunopurificación based on the AcM, CB-PSA.2, which was obtained the PSA with a purity exceeding 90%. Immunoassay Centre on the basis of the AcMs panel and the results of this study, developed and recorded two diagnostic systems for the detection of PSA in human serum. (author)

  7. On-line maintenance PSA support at NPP Krsko

    International Nuclear Information System (INIS)

    Prosen, R.; Vrbanic, I.; Kastelan, M.

    2000-01-01

    In 1997 Krsko NPP initiated the on-line maintenance (OLM) practice. On-line maintenance constitutes of corrective activities, preventive activities, surveillance activities, tests and inspections, as well as calibrations and modifications, taking place during the normal power operations. The on-line maintenance is a multidisciplinary process consisting of activity specification, planning, and preparation and performing of the OLM activity of interest. The primary role of the PSA group is to assess from the r isk perspective , using the plant-specific NEK PSA model, system unavailability and the impact to the plant operational risk. The intent is to support planning of the on-line maintenance activities from the risk perspective. The risk evaluation of the OLM activities is based on the probability of core damage evaluation for the defined discrete plant configuration states, determined by the OLM activities. Within this application, the optimized, plant-specific PSA model is used on Risk Spectrum platform. To perform the risk assessment of the on-line maintenance activities, first the systems to be affected are defined based on the planned OLM activities. The next important step is the assessment of the planned work schedule. To define the final schedule, the co-ordination and optimizing the planned OLM activities needs activation of all participating departments, supported also from PSA group. The P3 (i.e. Primavera) planning tool system windows are defined for different systems and groups of systems, and the activities are sorted in particular weeks according to these windows. (author)

  8. System analysis procedures for conducting PSA of nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Yoon Hwan; Jeong, Won Dae; Kim, Tae Un; Kim, Kil You; Han, Sang Hoon; Chang, Seung Chul; Sung, Tae Yong; Yang, Jun Eon; Kang, Dae Il; Park, Jin Hee; Hwang, Mi Jeong; Jin, Young Ho.

    1997-03-01

    This document, the Probabilistic Safety Assessment(PSA) procedures guide for system analysis, is intended to provide the guidelines to analyze the target of system consistently and technically in the performance of PSA for nuclear power plants(NPPs). The guide has been prepared in accordance with the procedures and techniques for fault tree analysis(FTA) used in system analysis. Normally the main objective of system analysis is to assess the reliability of system modeled by Event Tree Analysis(ETA). A variety of analytical techniques can be used for the system analysis, however, FTA method is used in this procedures guide. FTA is the method used for representing the failure logic of plant systems deductively using AND, OR or NOT gates. The fault tree should reflect all possible failure modes that may contribute to the system unavailability. This should include contributions due to the mechanical failures of the components, Common Cause Failures (CCFs), human errors and outages for testing and maintenance. After the construction of fault tree is completed, system unavailability is calculated with the CUT module of KIRAP, and the qualitative and quantitative analysis is performed through the process as above stated. As above mentioned, the procedures for system analysis is based on PSA procedures and methods which has been applied to the safety assessments of constructing NPPs in the country. Accordingly, the method of FTA stated in this procedures guide will be applicable to PSA for the NPPs to be constructed in the future. (author). 6 tabs., 11 figs., 7 refs

  9. Asian and Pacific Islander HIV/AIDS Awareness PSA (:30)

    Centers for Disease Control (CDC) Podcasts

    2010-05-12

    In this PSA, Asians and Pacific Islanders are encouraged to talk about HIV and get tested for HIV.  Created: 5/12/2010 by Centers for Disease Control and Prevention (CDC).   Date Released: 5/12/2010.

  10. Safety and efficacy of procedural sedation and analgesia (PSA ...

    African Journals Online (AJOL)

    Safety and efficacy of procedural sedation and analgesia (PSA) conducted by medical officers in a level 1 hospital in Cape Town. ... Respiratory complications were treated with simple airway manoeuvres; no patient required intubation or experienced respiratory problems after waking up. There was no significant difference ...

  11. Take Charge. Take the Test. "You Know" PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    As part of the Take Charge. Take the Test. campaign, this 60 second PSA encourages African American women to get tested for HIV. Locations for a free HIV test can be found by visiting hivtest.org/takecharge or calling 1-800-CDC-INFO (1-800-232-4636).

  12. Reducing the Risk of Methadone Overdose PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2012-07-03

    This 60 second PSA is based on the July 2012 CDC Vital Signs report. Approximately 14 people die every day of overdoses related to methadone. Listen to learn how to reduce your risk of an overdose.  Created: 7/3/2012 by Centers for Disease Control and Prevention (CDC).   Date Released: 7/3/2012.

  13. System analysis procedures for conducting PSA of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yoon Hwan; Jeong, Won Dae; Kim, Tae Un; Kim, Kil You; Han, Sang Hoon; Chang, Seung Chul; Sung, Tae Yong; Yang, Jun Eon; Kang, Dae Il; Park, Jin Hee; Hwang, Mi Jeong; Jin, Young Ho

    1997-03-01

    This document, the Probabilistic Safety Assessment(PSA) procedures guide for system analysis, is intended to provide the guidelines to analyze the target of system consistently and technically in the performance of PSA for nuclear power plants(NPPs). The guide has been prepared in accordance with the procedures and techniques for fault tree analysis(FTA) used in system analysis. Normally the main objective of system analysis is to assess the reliability of system modeled by Event Tree Analysis(ETA). A variety of analytical techniques can be used for the system analysis, however, FTA method is used in this procedures guide. FTA is the method used for representing the failure logic of plant systems deductively using AND, OR or NOT gates. The fault tree should reflect all possible failure modes that may contribute to the system unavailability. This should include contributions due to the mechanical failures of the components, Common Cause Failures (CCFs), human errors and outages for testing and maintenance. After the construction of fault tree is completed, system unavailability is calculated with the CUT module of KIRAP, and the qualitative and quantitative analysis is performed through the process as above stated. As above mentioned, the procedures for system analysis is based on PSA procedures and methods which has been applied to the safety assessments of constructing NPPs in the country. Accordingly, the method of FTA stated in this procedures guide will be applicable to PSA for the NPPs to be constructed in the future. (author). 6 tabs., 11 figs., 7 refs.

  14. GIS Technologies for the Planetary Science Archive (PSA)

    Science.gov (United States)

    Docasal, R.

    2017-09-01

    In my abstract I try to show how a GIS and 3D visual tools architecture could handle the different approaches for visualizing the spatial info, depending on the nature and shape of the object (planet, satellite, comet...etc) to be mapped in a multi-mission website such as the new PSA.

  15. Teen Pregnancy - What You Need to Know PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    This 60 second PSA is based on the April, 2011 CDC Vital Signs report. Having a child during the teen years comes at a high cost to the young mother, her child, and the community. Get tips to help break the cycle of teen pregnancy.

  16. Asthma - What You Need to Know PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    This 60 second Public Service Announcement (PSA) is based on the May, 2011 CDC Vital Signs report. Children and adults can have asthma and attacks can be frightening. To help control asthma, know the warning signs of an attack, stay away from asthma triggers, and follow your health care provider's advice.

  17. The PSA assessment of Defense in Depth Memorandum and proposals

    International Nuclear Information System (INIS)

    Fiorini, Gian-Luigi; La Rovere, Stefano

    2016-01-01

    This report concerns the peculiar roles of the Defence-in-Depth (DiD) concept and the Probabilistic Safety Assessment (PSA) approach for the optimization of the safety performances of the nuclear installation. It proposes a conceptual framework and related process for the assessment of the 'safety architecture' implementing DiD, which is articulated in four main steps devoted to (1) the formulation of the safety objectives, (2) the identification of loads and environmental conditions, (3) the representation of the safety architecture and (4) the evaluation of the physical performance and reliability of the levels of DiD. A final additional step achieves the practical assessment of the safety architecture and the corresponding DiD with the support of the PSA. The comprehensive safety assessment of the implemented architecture needs its multi-dimensional representation, i.e. for given initiating event, sequence of possible failures, affected safety function and level of DiD. The risk space (frequency/probability of occurrence, versus consequences) is the framework for the integration between the DiD concept and the PSA approach. Additional qualitative key-notions are introduced in order to address the compliance of the safety architecture with a number of international safety requirements. In this context, the role of the PSA is no longer limited to the verification of the fulfilment of probabilistic targets but includes different contributions to the assessment of the DiD identified in this report. (authors)

  18. PyPSA: Python for Power System Analysis

    Directory of Open Access Journals (Sweden)

    Thomas Brown

    2018-01-01

    Full Text Available Python for Power System Analysis (PyPSA is a free software toolbox for simulating and optimising modern electrical power systems over multiple periods. PyPSA includes models for conventional generators with unit commitment, variable renewable generation, storage units, coupling to other energy sectors, and mixed alternating and direct current networks. It is designed to be easily extensible and to scale well with large networks and long time series. In this paper the basic functionality of PyPSA is described, including the formulation of the full power flow equations and the multi-period optimisation of operation and investment with linear power flow equations. PyPSA is positioned in the existing free software landscape as a bridge between traditional power flow analysis tools for steady-state analysis and full multi-period energy system models. The functionality is demonstrated on two open datasets of the transmission system in Germany (based on SciGRID and Europe (based on GridKit.   Funding statement: This research was conducted as part of the CoNDyNet project, which is supported by the German Federal Ministry of Education and Research under grant no. 03SF0472C. The responsibility for the contents lies solely with the authors

  19. Hand Hygiene in Healthcare Settings 1 PSA (:30)

    Centers for Disease Control (CDC) Podcasts

    2010-08-19

    This 30 second PSA encourages people to wash their hands often while in the hospital or visiting someone in the hospital. It also encourages them to remind their healthcare providers to wash their hands, too.  Created: 8/19/2010 by Centers for Disease Control and Prevention (CDC).   Date Released: 8/19/2010.

  20. Hand Hygiene in Healthcare Settings 2 PSA (:30)

    Centers for Disease Control (CDC) Podcasts

    2010-08-19

    This 30 second PSA encourages people to wash their hands often while in the hospital or visiting someone in the hospital. It also encourages them to remind their healthcare providers to wash their hands, too.  Created: 8/19/2010 by Centers for Disease Control and Prevention (CDC).   Date Released: 8/19/2010.

  1. Living PSA issues in France on pressurized water reactors

    International Nuclear Information System (INIS)

    Dewailly, J.; Deriot, S.; Dubreuil Chambardel, A.; Francois, P.; Magne, L.

    1993-09-01

    Two Probabilistic Safety Assessments (PSAs) carried out in France on 900 and 1300 MWe Pressurized Water Reactor units ended in 1990. These PSAs determined the core damage frequency for all plant operating conditions ranging from cold shutdown for refuelling to full power operation. Since 1990, these PSAs have been used increasingly as tools for applications such as accident precursor analysis, risk-based Technical Specifications, and maintenance optimization. In turn, these applications are used to enhance the initial PSAs. The notion of a ''living'' PSA which can be used and updated is slowly taking form. The accident precursor analysis consists in applying PSA event trees to obtain quick information on the potential consequences of a precursor event and on the corresponding probabilities of occurrence. A feedback on PSAs is provided by comparing them with actual operating incidents. The computation of the allowed outage time during power operation, based on the computerized models of Probabilistic Safety Assessments, requires adjustments: calculation of hourly risk of core damage under different reactor conditions without equipment unavailabilities. The proposed method also turns out to be an aid in determining the safe shutdown condition and procedure. Furthermore, when introducing a sufficient level of detail, PSA reliability models make it possible to compute contributions and to perform sensitivity studies in order to highlight those components for which a maintenance effort should be made. From the experience acquired up to now, there was felt to be a strong need to create guidelines for using PSAs that would simplify their implementation by the experts in charge of determining Technical Specifications, of maintenance programs, etc. who are not generally specialists in PSAs. For this purpose, it is necessary to improve the intelligibility of the models made in order for them to be used and to offer user's guides adapted to each application. Documents

  2. [Relationship between tumor volume and PSA recurrence after radical prostatectomy].

    Science.gov (United States)

    Hashimoto, Yasuhiro; Momose, Akishi; Okamoto, Akiko; Yamamoto, Hayato; Hatakeyama, Shingo; Iwabuchi, Ikuya; Yoneyama, Takahiro; Koie, Takuya; Kamimura, Noritaka; Ohyama, Chikara

    2010-02-01

    We examined whether the tumor volume (TV) is a good predictor of PSA recurrence after radical prostatectomy. Data were collected for 158 patients with clinically localized prostate cancer undergoing radical prostatectomy without neoadjuvant hormonal therapy in our hospital since April 2005 to September 2007. Along with the routine pathological assessment, TV was assessed in all prostatectomy specimens. PSA recurrence was defined as PSA levels of greater than 0.2 ng/ml. The TVs were 1.81+/-1.66 ml (mean +/-SD) ranging from 0.02 to 8.20 ml. The TV in cT1c was 1.77+/-1.64, and 1.89+/-1.72 ml in cT2 (not significant). Significant differences were observed between TV and pT. The TVs in pT2a, pT2b and pT3/4 were 0.54+/-0.54, 1.63+/-1.47 and 2.67+/-1.80 ml, respectively. The median follow-up period was 32.3 months (range from 15 to 45) after radical prostatectomy, and PSA recurrence was observed in 32 cases. Patients with smaller TV (TV TV (TV > or = 1.3 ml, 66.7%) with a significant difference atp TV, pT, Gleason Score (GS), and surgical margins. Significant differences were observed for GS, and surgical margins, but not for TV. Clinically organ-confined disease in Japanese patients with prostate cancer included various cancers from clinically insignificant to locally advanced ones. In our series, TV was not regarded as a predictor of PSA recurrence after radical prostatectomy.

  3. Prostate-specific antigen bounce following stereotactic body radiation therapy for prostate cancer

    Directory of Open Access Journals (Sweden)

    Charles C. Vu

    2014-01-01

    Full Text Available Introduction: Prostate-specific antigen (PSA bounce after brachytherapy has been well-documented. This phenomenon has also been identified in patients undergoing stereotactic body radiation therapy (SBRT. While the parameters that predict PSA bounce have been extensively studied in prostate brachytherapy patients, this study is the first to analyze the clinical and pathologic predictors of PSA bounce in prostate SBRT patients. Materials and Methods: Our institution has maintained a prospective database of patients undergoing SBRT for prostate cancer since 2006. Our study population includes patients between May 2006 and November 2011 who have at least 18 months of follow-up. All patients were treated using the CyberKnife treatment system. The prescription dose was 3500-3625cGy in 5 fractions.Results: 120 patients were included in our study. Median PSA follow-up was 24 months (range 18-78 months. 34 (28% patients had a PSA bounce. The median time to PSA bounce was 9 months, and the median bounce size was 0.50ng/mL. On univariate analysis, only younger age (p = .011 was shown to be associated with an increased incidence of PSA bounce. Other patient factors, including race, prostate size, prior treatment by hormones, and family history of prostate cancer, did not predict PSA bounces. None of the tumor characteristics studied, including Gleason score, pre-treatment PSA, T-stage, or risk classification by NCCN guidelines, was associated with increased incidence of PSA bounces. Younger age was the only statistically significant predictor of PSA bounce on multivariate analysis (OR = 0.937, p = 0.009.Conclusion: PSA bounce, which has been reported after prostate brachytherapy, is also seen in a significant percentage of patients after CyberKnife SBRT. Close observation rather than biopsy can be considered for these patients. Younger age was the only factor that predicted PSA bounce.

  4. Prostate-specific antigen (PSA) density in the diagnostic algorithm of prostate cancer.

    Science.gov (United States)

    Nordström, Tobias; Akre, Olof; Aly, Markus; Grönberg, Henrik; Eklund, Martin

    2018-04-01

    Screening for prostate cancer using prostate-specific antigen (PSA) alone leads to un-necessary biopsying and overdiagnosis. PSA density is easily accessible, but early evidence on its use for biopsy decisions was conflicting and use of PSA density is not commonly recommended in guidelines. We analyzed biopsy outcomes in 5291 men in the population-based STHLM3 study with PSA ≥ 3 ng/ml and ultrasound-guided prostate volume measurements by using percentages and regression models. PSA density was calculated as total PSA (ng/ml) divided by prostate volume (ml). Main endpoint was clinically significant cancer (csPCa) defined as Gleason Score ≥ 7. The median PSA-density was 0.10 ng/ml 2 (IQR 0.075-0.14). PSA-density was associated with the risk of finding csPCa both with and without adjusting for the additional clinical information age, family history, previous biopsies, total PSA and free/total PSA (OR 1.06; 95% CI:1.05-1.07 and OR 1.07, 95% CI 1.06-1.08). Discrimination for csPCa was better when PSA density was added to a model with additional clinical information (AUC 0.75 vs. 0.73, P PSA-density. Omitting prostate biopsy for men with PSA-density ≤0.07 ng/ml 2 would save 19.7% of biopsy procedures, while missing 6.9% of csPCa. PSA-density cutoffs of 0.10 ng/ml 2 and 0.15 ng/ml 2 resulted in detection of 77% (729/947) and 49% (461/947) of Gleason Score ≥7 tumors. PSA-density might inform biopsy decisions, and spare some men from the morbidity associated with a prostate biopsy and diagnosis of low-grade prostate cancer.

  5. Diagnostic value of serum free PSA and the ratio of free to total PSA in the diagnosis of prostate cancer

    International Nuclear Information System (INIS)

    Qiu Ningyan; Zhang Jingxin; Wu Jinchang; Gong Yiming; Li Huiping

    2005-01-01

    In order to evaluate the value of free prostate specific antigen (FPSA) and F/T PSA ratio in differential diagnosis of benign prostate hyperplasia (BPH) from prostate cancer (PC), serum FPSA and TPSA levels were measured in 85 patients with PC, 97 BPH and 89 healthy volunteers by chemiluminescence enzyme immunoassay (CLEIA), and the ratio of F/T PSA was calculated. The results showed that serum FPSA and TPSA levels were increased in healthy volunteers of 41-88 years old and were significantly higher in healthy volunteers of 61-88 years old than that in 20-40 gear old (P 10.0 μg/L were 65.0%, 30.9% and 4.1%, respectively, while they were 5.9%, 20.0% and 74.1% in PC patients (P<0.01). When the TPSA value was between 4.0-10.0 μg/L and the ratio of F/T PSA was at 0.10 and below, the probability of PC was larger(88.9%). But the ratio of F/T PSA was at 0.25 and above, the probability of PC was smaller(6.20%). Serum FPSA and TPSA both increased with age in healthy volunteers of 41-88 years old and were positively correlated with age. There were about 30.9% of BPH and 20.0% of PC patients with overlapping of TPSA level. Our conclusion is that the F/T PSA ratio can significantly enhance the specificity for PC diagnosis, especially when the TPSA is within the diagnostic gray zone. (authors)

  6. Summary report for the second TUV-workshop proceedings on living PSA application

    International Nuclear Information System (INIS)

    1991-01-01

    This workshop on living PSA Application was organized to support the OECD/NEA CSNI-Principal Working Group No.5 on Risk Assessment for an international exchange of experience on living PSA application. The first session was devoted to Living PSA Applications and the second session to Tools for Living PSA. Living PSA Applications: Reasons for performing PSA (regulatory requirement, targets; corporate requirement, targets; safety related activity prioritization; other); Logistic of Living PSA Management (Corporate management involvement, Decision making levels and guidance, Plant level involvement, Required personnel commitment, Frequency and extent of re-quantification of PSA, Types of safety/risk parameters to be monitored, Quality assurance on maintaining Living PSA); Examples of Application (Experiences of application, State of Living PSA/e.g. all accident sequences involved, Details of component level involvement). Tools for Living PSA: Data Collection Systems and Codes (Source and type of data collected, Probabilistic parameter quantification, Interface to basic event data, Data code systems). An executive summary of the workshop is given

  7. Prediction of PSA bounce after permanent prostate brachytherapy for localized prostate cancer

    International Nuclear Information System (INIS)

    Kanai, Kunimitsu; Nakashima, Jun; Sugawara, Akitomo

    2009-01-01

    We aimed to calculate the frequency and features of the development of a prostate-specific antigen (PSA) bounce after prostate brachytherapy alone, to correlate the bounce with clinical and dosimetric factors and to identify factors that predict PSA bounce. PSA bounce was evaluated in 86 patients with T1-T2 prostate cancer who underwent radioactive seed implantation using iodine-125 (I-125) without hormonal therapy or external-beam radiation therapy (EBRT) from September 2004 to December 2007. A PSA bounce was defined as a rise of at least 0.4 ng/ml greater than a previous PSA level with a subsequent decline equal to, or less than, the initial nadir. Calculated by the Kaplan-Meier method, the incidence of PSA bounce at a 2-year follow-up was 26%. Median time to the PSA bounce was 15 months. Univariate analysis demonstrated that age, dose received by 90% of the prostate gland (D90), volume of gland receiving 100% of the prescribed dose (V100), and V150 were significantly associated with the PSA bounce, while pretreatment PSA level, Gleason score, pretreatment prostate volume, clinical T stage, and V200 were not. In multivariate analysis, age 67 years or less and D90 more than 180 Gy were identified as independent factors for predicting the PSA bounce (P<0.05). PSA bounce is not a rare phenomenon after prostate brachytherapy. It is more common in younger patients and patients receiving higher doses of radiation. (author)

  8. PSA testing for men at average risk of prostate cancer

    Directory of Open Access Journals (Sweden)

    Bruce K Armstrong

    2017-07-01

    Full Text Available Prostate-specific antigen (PSA testing of men at normal risk of prostate cancer is one of the most contested issues in cancer screening. There is no formal screening program, but testing is common – arguably a practice that ran ahead of the evidence. Public and professional communication about PSA screening has been highly varied and potentially confusing for practitioners and patients alike. There has been much research and policy activity relating to PSA testing in recent years. Landmark randomised controlled trials have been reported; authorities – including the 2013 Prostate Cancer World Congress, the Prostate Cancer Foundation of Australia, Cancer Council Australia, and the National Health and Medical Research Council – have made or endorsed public statements and/or issued clinical practice guidelines; and the US Preventive Services Task Force is revising its recommendations. But disagreement continues. The contention is partly over what the new evidence means. It is also a result of different valuing and prioritisation of outcomes that are hard to compare: prostate cancer deaths prevented (a small and disputed number; prevention of metastatic disease (somewhat more common; and side-effects of treatment such as incontinence, impotence and bowel trouble (more common again. A sizeable proportion of men diagnosed through PSA testing (somewhere between 20% and 50% would never have had prostate cancer symptoms sufficient to prompt investigation; many of these men are older, with competing comorbidities. It is a complex picture. Below are four viewpoints from expert participants in the evolving debate, commissioned for this cancer screening themed issue of Public Health Research & Practice. We asked the authors to respond to the challenge of PSA testing of asymptomatic, normal-risk men. They raise important considerations: uncertainty, harms, the trustworthiness and interpretation of the evidence, cost (e.g. of using multiparametric

  9. Upgrade of Common Cause Failure Modelling of NPP Krsko PSA

    International Nuclear Information System (INIS)

    Vukovic, I.; Mikulicic, V.; Vrbanic, I.

    2006-01-01

    Over the last thirty years the probabilistic safety assessments (PSA) have been increasingly applied in technical engineering practice. Various failure modes of system of concern are mathematically and explicitly modelled by means of fault tree structure. Statistical independence of basic events from which the fault tree is built is not acceptable for an event category referred to as common cause failures (CCF). Based on overview of current international status of modelling of common cause failures in PSA several steps were made related to primary technical basis for methodology and data used for CCF model upgrade project in NPP Krsko (NEK) PSA. As a primary technical basis for methodological aspects of CCF modelling in Krsko PSA the following documents were considered: NUREG/CR-5485, NUREG/CR-4780, and Westinghouse Owners Group documents (WOG) WCAP-15674 and WCAP-15167. Use of these documents is supported by the most relevant guidelines and standards in the field, such as ASME PRA Standard and NRC Regulatory Guide 1.200. WCAP documents are in compliance with NUREG/CR-5485 and NUREG/CR-4780. Additionally, they provide WOG perspective on CCF modelling, which is important to consider since NEK follows WOG practice in resolving many generic and regulatory issues. It is, therefore, desirable that NEK CCF methodology and modelling is in general accordance with recommended WOG approaches. As a primary basis for CCF data needed to estimate CCF model parameters and their uncertainty, the main used documents were: NUREG/CR-5497, NUREG/CR-6268, WCAP-15167, and WCAP-16187. Use of NUREG/CR-5497 and NUREG/CR-6268 as a source of data for CCF parameter estimating is supported by the most relevant industry and regulatory PSA guides and standards currently existing in the field, including WOG. However, the WCAP document WCAP-16187 has provided a basis for CCF parameter values specific to Westinghouse PWR plants. Many of events from NRC / INEEL database were re-classified in WCAP

  10. Development of IRMA reagent and methodology for PSA

    International Nuclear Information System (INIS)

    Najafi, R.

    1997-01-01

    The PSA test is a solid phase two-site immunoassay. Rabbit anti PSA is coated or bound on surface of solid phase and monoclonal anti PSA labeled with 1-125. The PSA molecules present in the standard solution or serum are 'Sandwiched' between the two antibodies. After formation of coated antibody-antigen-labeled antibody complex, the unbound labeled antibody will removed by washing. The complex is measured by gamma counter. The concentration of analyte is proportional to the counts of test sample. In order to develop kits for IRMA PSA, it should be prepared three essential reagents Antibody coated solid phase, labeled antibody, standards and finally optimizing them to obtain an standard curve fit to measure specimen PSA in desired range of concentration. The type of solid phase and procedure(s) to coat or bind to antibody, is still main debatable subject in development and setting up RIA/IRMA kits. In our experiments, polystyrene beads, because of their easy to coat with antibody as well as easy to use, can be considered as a desired solid phase. Most antibodies are passively adsorbed to a plastic surface (e.g. Polystyrene, Propylene, and Polyvinyl chloride) from a diluted buffer. The antibody coated plastic surface, then acts as solid phase reagent. Poor efficiency and time required to reach equilibrium and also lack of reproducibility especially batch-to-batch variation between materials, are disadvantages in this simple coating procedure. Improvements can be made by coating second antibody on surface of beads, and reaction between second and primary antibodies. There is also possible to enhance more coating efficiency of beads by using Staphylococcus ureus-Protein A. Protein A is a major component of staphylococcus aureus cell wall which has an affinity for FC segment of immunoglobulin G (IgG) of some species, including human; rabbit; and mice. This property of Staphylococcal Protein A has made it a very useful tool in the purification of classes and subclasses

  11. VSWI Wetlands Advisory Layer

    Data.gov (United States)

    Vermont Center for Geographic Information — This dataset represents the DEC Wetlands Program's Advisory layer. This layer makes the most up-to-date, non-jurisdictional, wetlands mapping avaiable to the public...

  12. Comparison and lessons learned from plant specific PSA of German NPP

    International Nuclear Information System (INIS)

    Balfanz, Hans-Peter; Berg, H.P.

    2000-01-01

    PSA are launched in frame of Periodic Safety Reviews (PSR) in Germany. The aims are to identify overall safety level and relative weak points. Some backfitting measures have been realized for older plants to remove relative weak points and to bring these plants to the state of the art. In this field PSA is well accepted today and is seen as a valuable tool supplementing the deterministic analysis. Main application of PSA within PSR is planned to become mandatory as part of the revision of the German Atomic Energy Act. According to the German PSA Guideline plant specific PSA level 1+ were performed for all 19 In comparison with international practice German PSA are very detailed. Otherwise they do not handle all external events, non-power states and accident management measures as discussed before. The New PSA guideline will cover these aspects and therefore analysts have to take them into account in further PSA. Moreover gathering of plant specific data is needed. The development in this field is driven by the utilities (for instance in frame of their so-called ZEDB project). Public discussion about quantitative risk of industrial hazards is quite limited in Germany and PSA results have only few impacts to this respect. Independent from this PSA for NPP is understood as a diverse tool in supporting the deterministic licensing and supervision process. Risk based decision making as well as informed regulation are just only of the beginning. State of PSA of NPP in Germany, comparison of PSA result of different NPP, German PSA guideline and state of discussion of further development and recommendation of further development of PSA of NPP are discussed in this paper in more detail. (S.Y.)

  13. Comparison and lessons learned from plant specific PSA of German NPP

    Energy Technology Data Exchange (ETDEWEB)

    Balfanz, Hans-Peter [TUEV Nord, Hamburg (Germany); Berg, H.P.

    2000-07-01

    PSA are launched in frame of Periodic Safety Reviews (PSR) in Germany. The aims are to identify overall safety level and relative weak points. Some backfitting measures have been realized for older plants to remove relative weak points and to bring these plants to the state of the art. In this field PSA is well accepted today and is seen as a valuable tool supplementing the deterministic analysis. Main application of PSA within PSR is planned to become mandatory as part of the revision of the German Atomic Energy Act. According to the German PSA Guideline plant specific PSA level 1+ were performed for all 19 In comparison with international practice German PSA are very detailed. Otherwise they do not handle all external events, non-power states and accident management measures as discussed before. The New PSA guideline will cover these aspects and therefore analysts have to take them into account in further PSA. Moreover gathering of plant specific data is needed. The development in this field is driven by the utilities (for instance in frame of their so-called ZEDB project). Public discussion about quantitative risk of industrial hazards is quite limited in Germany and PSA results have only few impacts to this respect. Independent from this PSA for NPP is understood as a diverse tool in supporting the deterministic licensing and supervision process. Risk based decision making as well as informed regulation are just only of the beginning. State of PSA of NPP in Germany, comparison of PSA result of different NPP, German PSA guideline and state of discussion of further development and recommendation of further development of PSA of NPP are discussed in this paper in more detail. (S.Y.)

  14. Variability of assay methods for total and free PSA after WHO standardization.

    Science.gov (United States)

    Foj, L; Filella, X; Alcover, J; Augé, J M; Escudero, J M; Molina, R

    2014-03-01

    The variability of total PSA (tPSA) and free PSA (fPSA) results among commercial assays has been suggested to be decreased by calibration to World Health Organization (WHO) reference materials. To characterize the current situation, it is necessary to know its impact in the critical cutoffs used in clinical practice. In the present study, we tested 167 samples with tPSA concentrations of 0 to 20 μg/L using seven PSA and six fPSA commercial assays, including Access, ARCHITECT i2000, ADVIA Centaur XP, IMMULITE 2000, Elecsys, and Lumipulse G1200, in which we only measured tPSA. tPSA and fPSA were measured in Access using the Hybritech and WHO calibrators. Passing-Bablok analysis was performed for PSA, and percentage of fPSA with the Hybritech-calibrated access comparison assay. For tPSA, relative differences were more than 10 % at 0.2 μg/L for ARCHITECT i2000, and at a critical concentration of 3, 4, and 10 μg/L, the relative difference was exceeded by ADVIA Centaur XP and WHO-calibrated Access. For percent fPSA, at a critical concentration of 10 %, the 10 % relative difference limit was exceeded by IMMULITE 2000 assay. At a critical concentration of 20 and 25 %, ADVIA Centaur XP, ARCHITECT i2000, and IMMULITE 2000 assays exceeded the 10 % relative difference limit. We have shown significant discordances between assays included in this study despite advances in standardization conducted in the last years. Further harmonization efforts are required in order to obtain a complete clinical concordance.

  15. Method comparison for determination of the tumor markers AFP, CEA, PSA and free PSA between Immulite 2000 XPI and Dimension Vista 1500.

    Science.gov (United States)

    Zur, Berndt; Holdenrieder, Stefan; Walgenbach-Brünagel, Gisela; Albers, Eike; Stoffel-Wagner, Birgit

    2012-01-01

    For the Luminescent Oxygen Channeling Immunoassay (LOCI) technology as established for Dimension Vista 1500, assays have been developed for the serum tumor markers AFP, CEA, PSA and free PSA. We performed a method analysis for these parameters using the Immulite 2000 XPI. Determination of within-day and total imprecision of the methods was carried out according to CLSI guidelines with three serum pools. In addition, parallel measurements were performed with both systems in 1,871 routine serum samples and correlations were calculated. Calculated total imprecision of the three serum pools for AFP was 3.8 - 4.3%, for CEA 3.3 - 4.3%, for tPSA 3.6 - 4.0% and for fPSA it was 3.5 - 8.2%. Correlations of these markers across the entire value range were very good with the following correlation coefficients: 0.997 for AFP, 0.996 for CEA, 0.971 for tPSA and 0.988 for fPSA. While values for AFP and tPSA from both methods were comparable (slopes 1.02 and 1.01), lower values were measured for CEA and fPSA with the Dimension Vista (slopes 0.83 and 0.91). For AFP, a sample cluster with considerably higher values than with Dimension Vista was observed in the lower measurement range (CEA, tPSA and fPSA, as developed with the LOCI technology for the Dimension Vista, show good comparability with results obtained from the Immulite 2000 XPI. However, lower measurement ranges for CEA and fPSA as well as individual divergences, especially with AFP, must be taken into consideration in the event of method changeover.

  16. PSA for the shutdown mode for nuclear power plants

    International Nuclear Information System (INIS)

    1994-06-01

    The meeting, which was attended by more than 75 participants from 20 countries, provided a broad discussion forum where all the currently active major shutdown PSA programmes were reviewed. The meeting also addressed the issues related to actual performance of shutdown PSA studies as well as insight gained from the studies. This document, which was prepared during the TCM, contains the results of extensive discussions which were held in specific working groups. The papers presented at the meeting provide a comprehensive overview of the state of the art of shutdown risk assessment and remedial measures taken to reduce the risk in outages. It is hoped that this document will be very useful to all individuals with interest in increasing safety during outages at NPPs. Refs, figs and tabs

  17. Severe accident analysis for level 2 PSA of SMART reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jin Yong; Lee, Jeong Hun; Kim, Jong Uk; Yoo, Tae Geun; Chung, Soon Il; Kim, Min Gi [FNC Technology Co., Seoul (Korea, Republic of)

    2010-12-15

    The objectives of this study are to produce data for level 2 PSA and evaluation results of severe accident by analyzing severe accident sequence of transient events, producing fault tree of containment systems and evaluating direct containment heating of the SMART. In this project, severe accident analysis results were produced for general transient, loss of feedwater, station blackout, and steam line break events, and based on the results, design safety of SMART was verified. Also, direct containment heating phenomenon of the SMART was evaluated using TCE methodology. For level 2 PSA, fault tree of the containment isolation system, reactor cavity flooding system, plant chilled water system, and reactor containment building HVAC system was produced and analyzed

  18. Development of the SKI Handbook for reviewing PSA after the review of the of a PSA level 2 study; Utveckling av SKIs Tillsynshandbok foer PSA utifraan granskningen av en PSA Nivaa-2 studie

    Energy Technology Data Exchange (ETDEWEB)

    Lindholm, Ilona; Sairanen, Risto [VTT Processes, Helsinki (Finland)

    2003-02-01

    A review of the Oskarshamn 2 Level 2 PSA has been conducted by VTT Processes. One objective of the review was validation and development of Tillsynshandbok PSA applying it to Oskarshamn 2 PSA Level 2 study. The review was based on the PSA Level 2 documentation: the main report, the supporting reports on containment success criteria and release calculations with the MAAP4 code, and five phenomenological reports for selected specific questions. The main result of the phenomenological analyses is that none of the phenomena considered contributes to the conditional failure probability of the Oskarshamn 2 containment in severe accidents. The project was conducted as a set of separate studies and the project quality assurance has also focused on one part at the time. As such, the quality assurance is adequate. A high level QA ensuring that all separate studies and analysis steps use same assumptions seems to be missing. Results from the phenomenology reports are not always transferred to accident analyses and vice versa. There is no specific discussion of uncertainty or sensitivity analyses. In general, the number of sensitivity analyses could be larger. Such should have been provided for sequences or phenomena that could result in early or unmitigated release. Examples are pressure vessel failure at high pressure, the effect of larger hydrogen production, and the key assumptions used for steam explosion and direct containment heating. Suggestions for additional sensitivity studies have been given in discussion of phenomenological reports. The project documentation is generally good. Missing information is usually associated with transfer of results from one study to another. It can be assumed that the information exists also in this cases but has not been documented in the reports above. Documentation of the containment event trees and the assumptions used for them could be more detailed, maybe similar to the approach used in the Appendix of this report. More effort

  19. PSA use in accident management studies in Japan

    International Nuclear Information System (INIS)

    Hirano, Mitsumasa

    1994-01-01

    The safety of NPPs in Japan is secured by stringent safety regulations based on the deterministic method, minimizing the possibility a severe accident to a technologically negligible level. PSA is not required in the current regulatory procedures. Accident management based on PSA is a 'knowledge-based' action dependent on utilities' technical knowledge aimed at further reduction of the risk which is kept small enough by existing measures. The paper discusses the following three kinds of PSAs that have been conducted practically and efficiently on NPPs to provide supplemental information about their safety characteristics in addition to the deterministic evaluation used in the regulatory safety review: PSAs on typical NPPs, PSAs on all NPPs to examine candidates for accident management, and PSAs as part of periodic safety review (PSR). 1 fig., 5 tabs

  20. International survey of living PSA and safety indicators

    International Nuclear Information System (INIS)

    Holmberg, J.; Laakso, K.; Lehtinen, E.; Bjoere, S.

    1992-01-01

    The report contains an international overview of applications of living probabilistic assessment and development of operational safety indicators. Features of an ideal living PSA tool are summarized as well as a limited survey of code systems for managing a living probabilistic safety assessment (living PSA) is included. The international survey is used as an input for planning and performance of related tasks within the nordic NKS/SIK-1 project conducted in 1990-93. The research notes are distributed to the Nordic organizations involved or interested in the subject. The report includes an overview and conclusions from technical reports and articles available and presentations and discussions related to development and use of above methods for the evaluation and management of the operational safety of nuclear power plants. A large part of this material is based on material collected and discussed in connection to international specialist meetings relating to the subject

  1. Complement of existing ASAMPSA2 guidance for Level 2 PSA for shutdown states of reactors, Spent Fuel Pool and recent R and D results

    International Nuclear Information System (INIS)

    Kumar, M.; Olsson, A.; Loeffler, H.; Morandi, S.; Gumenyuk, D.; Dejardin, P.; Yu, S.; Jan, P.; Kubicek, J.; Serrano, C.; Raimond, E.; Dirksen, G.; Ivanov, I.; Groudev, P.; Kowal, K.; Prosek, Andrej; Nitoi, M.; Vitazkova, J.; Hirata, K.; Burgazzi, L.

    2016-01-01

    This report can be considered as an addendum to the existing ASAMPSA2 guidance for Level 2 PSA. It provides complementary guidance for Level 2 PSA for accident in the NPP shutdown states and on spent fuel pool and comments on the importance of these accidents on nuclear safety. It includes also information on recent research and development useful for Level 2 PSA developments. The conclusions of the ASAMPSA-E end-users survey and of technical meetings of WP10, WP21, WP22, and WP30 at Vienna University in September 2014 which are relevant for Level 2 PSA have been reflected and are taken into account as much as it is possible with the current status of knowledge. For Level 2 PSA in shutdown states, two plant conditions are to be distinguished: - accident sequences with RPV head closed, - accident sequences with RPV head open. When the RPV head is closed, core melt accident phenomena are very similar to the sequences going on in full power mode. Therefore, the large body of guidance which is available for full power mode is basically applicable to shutdown mode with RPV closed as well. When the RPV is open, some of the L2 PSA issues become irrelevant compared to full power mode, while others come into existence. The situation is different for aspects which do not exist or which are less pronounced in sequences with RPV closed. The report also covers containment issues in shutdown states and discusses the applicability of existing guidance, potential gaps and deficiencies and recommendations are provided. For spent fuel pool accidents in Level 2 PSA, a set of issues is identified and addressed. If the spent fuel pool is located inside the containment, the potential release paths to the environment are almost the same as for core melt accidents in the RPV. If the spent fuel pool is located outside the containment, the potential release paths to the environment depend very much on plant specific properties, e.g. ventilation systems, building doors, roof under thermal

  2. PSA Duration: Conquering the Prepayment Risk of Mortgage Portfolios

    OpenAIRE

    Boleslav Gulko

    1996-01-01

    Money managers have little control over the values of their individual holdings, but they have considerable control over the risk exposure of their portfolios. This article introduces new tools for the risk management of mortgage portfolios. We extend the traditional duration analysis to two dimensions, interest rates and mortgage prepayments, and develop independent hedging rules for the interest rate risk and the prepayment risk. In particular, we define the PSA duration as a formal measure...

  3. Take Charge. Take the Test. "You Know" PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2012-03-07

    As part of the Take Charge. Take the Test. campaign, this 60 second PSA encourages African American women to get tested for HIV. Locations for a free HIV test can be found by visiting hivtest.org/takecharge or calling 1-800-CDC-INFO (1-800-232-4636).  Created: 3/7/2012 by National Center for HIV/AIDS, Viral Hepatitis, STD, and TB Prevention (NCHHSTP).   Date Released: 3/7/2012.

  4. Asthma - What You Need to Know PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2011-05-03

    This 60 second Public Service Announcement (PSA) is based on the May, 2011 CDC Vital Signs report. Children and adults can have asthma and attacks can be frightening. To help control asthma, know the warning signs of an attack, stay away from asthma triggers, and follow your health care provider's advice.  Created: 5/3/2011 by Centers for Disease Control and Prevention (CDC).   Date Released: 5/3/2011.

  5. Regulatory requirement of the Juragua nuclear Power Plant PSA

    International Nuclear Information System (INIS)

    Valhuerdi Debesa, C.

    1996-01-01

    Probabilistic Safety Assessment has proved to be a powerful tool for improving the knowledge of the safety insides of Nuclear Power Plants and increasing the efficiency of the safety measures adopted by both operators and regulators. In this paper the regulatory approach adopted in Cuba with regard to the PSA , the scope of the requirement and the basis and proposal of this decision are presented

  6. Teen Pregnancy - What You Need to Know PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2011-04-05

    This 60 second PSA is based on the April, 2011 CDC Vital Signs report. Having a child during the teen years comes at a high cost to the young mother, her child, and the community. Get tips to help break the cycle of teen pregnancy.  Created: 4/5/2011 by Centers for Disease Control and Prevention (CDC).   Date Released: 4/5/2011.

  7. Summary report of seismic PSA of BWR model plant

    International Nuclear Information System (INIS)

    1999-05-01

    This report presents a seismic PSA (Probabilistic Safety Assessment) methodology developed at the Japan Atomic Energy Research Institute (JAERI) for evaluating risks of nuclear power plants (NPPs) and the results from an application of the methodology to a BWR plant in Japan, which is termed Model Plant'. The seismic PSA procedures developed at JAERI are to evaluate core damage frequency (CDF) and have the following four steps: (1) evaluation of seismic hazard, (2) evaluation of realistic response, (3) evaluation of component capacities and failure probabilities, and (4) evaluation of conditional probability of system failure and CDF. Although these procedures are based on the methodologies established and used in the United States, they include several unique features: (1) seismic hazard analysis is performed with use of available knowledge and database on seismological conditions in Japan; (2) response evaluation is performed with a response factor method which is cost effective and associated uncertainties can be reduced with use of modern methods of design calculations; (3) capacity evaluation is performed with use of test results available in Japan in combination with design information and generic capacity data in the U.S.A.; (4) systems reliability analysis, performed with use of the computer code SECOM-2 developed at JAERI, includes identification of dominant accident sequences, importance analysis of components and systems as well as the CDF evaluation with consideration of the effect of correlation of failures by a newly developed method based on the Monte Carlo method. The effect of correlation has been recognized as an important issue in seismic PSAs. The procedures was used to perform a seismic PSA of a 1100 MWe BWR plant. Results are shown as well as the insights derived and future research needs identified in this seismic PSA. (J.P.N.)

  8. Colorectal Cancer - What You Need to Know PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    This 60 second Public Service Announcement (PSA) is based on the July, 2011 CDC Vital Signs report. Colorectal cancer kills about 50,000 men and women every year. Screening can save lives! Screening can find abnormal growths so they can be removed before turning into cancer, and can find the cancer early, when it's easiest to treat. If you're over 50, talk to your doctor about getting screened for colorectal cancer.

  9. A living PSA based on use of expert systems

    International Nuclear Information System (INIS)

    Ancelin, C.; Bouissou, M.; Le, P.; De Saint-Quentin, S.; Villatte, N.

    1989-01-01

    This paper presents the expert systems that are developed by EDF in the framework of the French PSA. Aimed at automatically generating reliability models (fault trees, state graphs....), these expert systems are used for the reliability studies of safety systems in the Paluel nuclear power plant. Beyond the description of the implemented method, this paper insists on the new approach proposed to the reliability engineer, when using artificial intelligence techniques

  10. Recent Developments in Level 2 PSA and Severe Accident Management

    International Nuclear Information System (INIS)

    Ang, Ming Leang; Shepherd, Charles; Gauntt, Randall; Landgren, Vickie; Van Dorsselaere, Jean Pierre; Chaumont, Bernard; Raimond, Emmanuel; Magallon, Daniel; Prior, Robert; Mlady, Ondrej; Khatib-Rahbar, Mohsen; Lajtha, Gabor; Tinkler, Charles; Siu, Nathan

    2007-01-01

    In 1997, CSNI WGRISK produced a report on the state of the art in Level 2 PSA and severe accident management - NEA/CSNI/R(1997)11. Since then, there have been significant developments in that more Level 2 PSAs have been carried out worldwide for a variety of nuclear power plant designs including some that were not addressed in the original report. In addition, there is now a better understanding of the severe accident phenomena that can occur following core damage and the way that they should be modelled in the PSA. As requested by CSNI in December 2005, the objective of this study was to produce a report that updates the original report and gives an account of the developments that have taken place since 1997. The aim has been to capture the most significant new developments that have occurred rather than to provide a full update of the original report, most of which is still valid. This report is organised using the same structure as the original report as follows: Chapter 2: Summary on state of application, results and insights from recent Level 2 PSAs. Chapter 3: Discussion on key severe accident phenomena and modelling issues, identification of severe accident issues that should be treated in Level 2 PSAs for accident management applications, review of severe accident computer codes and the use of these codes in Level 2 PSAs. Chapter 4: Review of approaches and practices for accident management and SAM, evaluation of actions in Level 2 PSAs. Chapter 5: Review of available Level 2 PSA methodologies, including accident progression event tree / containment event tree development. Chapter 6: Aspects important to quantification, including the use of expert judgement and treatment of uncertainties. Chapter 7: Examples of the use of the results and insights from the Level 2 PSA in the context of an integrated (risk informed) decision making process

  11. 75 FR 43156 - Federal Advisory Committee; Missile Defense Advisory Committee

    Science.gov (United States)

    2010-07-23

    ... DEPARTMENT OF DEFENSE Office of the Secretary Federal Advisory Committee; Missile Defense Advisory Committee AGENCY: Missile Defense Agency (MDA), DoD. ACTION: Notice of closed meeting. SUMMARY: Under the... Defense announces that the Missile Defense Advisory Committee will meet on August 4 and 5, 2010, in...

  12. Review of probabilistic safety assessments by regulatory bodies

    International Nuclear Information System (INIS)

    2002-01-01

    This report provides guidance to assist regulatory bodies in carrying out reviews of the PSAs produced by utilities. In following this guidance, it is important that the regulatory body is able to satisfy itself that the PSA has been carried out to an acceptable standard and that it can be used for its intended applications. The review process becomes an important phase in determining the acceptability of the PSA since this provides a degree of assurance of the PSA scope, validity and limitations, as well as a better understanding of plants themselves. This report is also intended to assist technical experts managing or performing PSA reviews. A particular aim is to promote a standardized framework, terminology and form of documentation for the results of PSA reviews. The information presented in this report supports IAEA Safety Guide No. GS-G-1.2. Recommendations on the scope and methods to be used by the utility in the preparation of a PSA study is provided in IAEA Safety Guide No. NSG- 1.2. Information on these Safety Guides and other IAEA safety standards for nuclear power plants can be found on the following Internet site: http://www.iaea.org/ns/coordinet. The scope of this report covers the review of Level 1, 2 and 3 PSAs for event sequences occurring in all modes of plant operation (including full power, low power and shutdown). Where the scope of the analysis is narrower than this, a subset of the guidance can be identified and used. Information is provided on carrying out the review of a PSA throughout the PSA production process, i.e. from the initial decision to carry out the PSA through to the completion of the study and the production of the final PSA report. However, the same procedure can be applied to a completed PSA or to one already in progress. As a result of the performance of a PSA, changes to the design or operation of the plant are often identified that would increase the level of safety. This might include the addition of further safety

  13. A method for using expert judgement in PSA

    International Nuclear Information System (INIS)

    Pulkkinen, U.; Holmberg, J.

    1997-03-01

    The report discusses an expert judgement methodology development for applications at all levels of probabilistic safety assessment (PSA). The main applications are expected to be at PSA-levels 1 and 2. The method consists of several phases, including the selection and training of the experts, elicitation of experts' judgements, probabilistic modeling and combination of experts' judgements and documentation of the judgement process. The expert training and elicitation process is rather similar to that applied in the NUREG-1150 study. The combination of experts judgements is based on a Bayesian framework utilizing hierarchic models. The posterior distributions of the variables under analysis can be interpreted as a Bayesian counterpart of the combined or aggregated (consensus) distributions, and they are determined by applying Markov chain Monte-Carlo methods. The properties of the method are illustrated by some simple examples. The method is tested in a case study belonging to the benchmark exercise on the use of expert judgement in level 2 PSA, organized as a concerted action of European Commission Fourth Framework Programme on Nuclear Fission Safety. (14 refs.)

  14. Long-term longitudinal changes in baseline PSA distribution and estimated prevalence of prostate cancer in male Japanese participants of population-based PSA screening.

    Science.gov (United States)

    Oki, Ryo; Ito, Kazuto; Suzuki, Rie; Fujizuka, Yuji; Arai, Seiji; Miyazawa, Yoshiyuki; Sekine, Yoshitaka; Koike, Hidekazu; Matsui, Hiroshi; Shibata, Yasuhiro; Suzuki, Kazuhiro

    2018-04-26

    Japan has experienced a drastic increase in the incidence of prostate cancer (PC). To assess changes in the risk for PC, we investigated baseline prostate specific antigen (PSA) levels in first-time screened men, across a 25-year period. In total, 72,654 men, aged 50-79, underwent first-time PSA screening in Gunma prefecture between 1992 and 2016. Changes in the distribution of PSA levels were investigated, including the percentage of men with a PSA above cut-off values and linear regression analyses comparing log 10 PSA with age. The 'ultimate incidence' of PC and clinically significant PC (CSPC) were estimated using the PC risk calculator. Changes in the age-standardized incidence rate (AIR) during this period were analyzed. The calculated coefficients of linear regression for age versus log 10 PSA fluctuated during the 25-year period, but no trend was observed. In addition, the percentage of men with a PSA above cut-off values varied in each 5-year period, with no specific trend. The 'risk calculator (RC)-based AIR' of PC and CSPC were stable between 1992 and 2016. Therefore, the baseline risk for developing PC has remained unchanged in the past 25 years, in Japan. The drastic increase in the incidence of PC, beginning around 2000, may be primarily due to increased PSA screening in the country. © 2018 UICC.

  15. Clinical outcomes and nadir prostate-specific antigen (PSA) according to initial PSA levels in primary androgen deprivation therapy for metastatic prostate cancer.

    Science.gov (United States)

    Kitagawa, Yasuhide; Ueno, Satoru; Izumi, Kouji; Kadono, Yoshifumi; Mizokami, Atsushi; Hinotsu, Shiro; Akaza, Hideyuki; Namiki, Mikio

    2016-03-01

    To investigate the clinical outcomes of metastatic prostate cancer patients and the relationship between nadir prostate-specific antigen (PSA) levels and different types of primary androgen deprivation therapy (PADT). This study utilized data from the Japan Study Group of Prostate Cancer registry, which is a large, multicenter, population-based database. A total of 2982 patients treated with PADT were enrolled. Kaplan-Meier analysis was used to compare progression-free survival (PFS) and overall survival (OS) in patients treated using combined androgen blockade (CAB) and non-CAB therapies. The relationships between nadir PSA levels and PADT type according to initial serum PSA levels were also investigated. Among the 2982 enrolled patients, 2101 (70.5 %) were treated with CAB. Although CAB-treated patients had worse clinical characteristics, their probability of PFS and OS was higher compared with those treated with a non-CAB therapy. These results were due to a survival benefit with CAB in patients with an initial PSA level of 500-1000 ng/mL. Nadir PSA levels were significantly lower in CAB patients than in non-CAB patients with comparable initial serum PSA levels. A small survival benefit for CAB in metastatic prostate cancer was demonstrated in a Japanese large-scale prospective cohort study. The clinical significance of nadir PSA levels following PADT was evident, but the predictive impact of PSA nadir on OS was different between CAB and non-CAB therapy.

  16. Modular belt drive concept for the gasoline engine constructed in a cooperative project by BMW-PSA; Modulares Riemenantriebskonzept fuer den Ottomotor aus der BMW-PSA-Kooperation

    Energy Technology Data Exchange (ETDEWEB)

    Di Giacomo, T. [Dayco Group, Chieti Scalo (Italy); D' Amicantonio, L. [Dayco Europe Srl, Chieti Scalo (Italy); Lemberger, H. [BMW AG, Muenchen (Germany)

    2007-12-15

    BMW and PSA cooperated in developing a new series of four-cylinder engines. Apart from maximum power and optimum rotary momentum, the focus was on minimum fuel consumption. Dayco was chosen as supplier of the complete front belt drive system and developed an innovative, modular solution in cooperation with BMW and PSA. (orig.)

  17. Rate of PSA rise predicts metastatic versus local recurrence after definitive radiotherapy

    International Nuclear Information System (INIS)

    Sartor, C.I.; Strawderman, M.H.; Lin, X.; Kish, K.E.; McLaughlin, P.W.; Lichter, A.S.; Sandler, H.S.

    1995-01-01

    Objective: A rising PSA following treatment for adenocarcinoma of the prostate indicates eventual clinical failure, but the rate of rise can be quite different from patient to patient, as can the pattern of clinical failure. We sought to determine whether the rate of PSA rise could differentiate future local vs. metastatic failure. Materials and Methods: PSA values from our series of 671 patients treated between 1987 and 1994 with 3-D conformal radiotherapy for localized adenocarcinoma were analyzed. Patients who had a pre-treatment PSA and >4 post-treatment PSA values available, had received no hormonal therapy, and had information detailing clinical outcome were used in this analysis. First site of failure was determined by abnormal DRE or biopsy, abnormal bone scan or radiographic evidence of metastasis as directed by clinical symptoms or follow-up clinical exam. Each patient's PSA pattern was defined by the function PSA(t)=C 1 e - a 1 (t) + C 2 e a 2 (t) where -a 1 relates to the rate of decline and a 2 to the rate of rise, if any. Univariate analysis was used to determine the correlation between initial PSA or rising PSA and clinical failure. Adjacent category logistic regression analysis was used to analyze the rate of rise and pattern of clinical failure. Results: 671 patients were reviewed; 401 patients met the requirements and 2667 PSA values were analyzed. We confirmed the finding of others that pre-treatment PSA is a prognostic indicator: patients presenting with PSA 3-20ng/ml had a relative risk of 9 (p=0.03) and PSA>20ng/ml had a RR of 26 (p=0.002) for clinical failure when compared to presenting PSA 2 >1.5/year predicted metastatic as opposed to local failure when compared to PSA rise with a 2 between 0.5-1.5/yr or 1.5 log(ng/ml)/year vs. 0.5-1.5 log(ng/ml)/yr or <0.5 log(ng/ml)/yr. Conclusions: The rate of rise of PSA following definitive radiotherapy can predict clinical failure patterns, with a rapidly rising PSA indicating metastatic as opposed to

  18. [Prostate specific antigen--PSA and histopathological findings of endometrium in women with fibrocystic breast disease].

    Science.gov (United States)

    Radowicki, Stanisław; Kunicki, Michał

    2010-02-01

    The aim of the study was to evaluate the relationship between serum free and total PSA and histopathological findings in women with fibrocystic mastopathy. 176 women with fibrocystic breast disease, aged 18 to 45 years.--Group I: comprised 114 patients with cysts 10 mm in diameter. The control group consisted of 46 healthy women aged 18 - 45 years who had no breast pathology Total PSA (PSA-T) and free PSA (PSA-Free) were measured by an ultra-sensitive fluoroimmunometric DELFIA assay (Prostatus PSA Free/Total Wallac, Turku, Finland). The detection limit for PSA was 0.01 ng/ml. Endometrial samples have been obtained with Pipelle probe between 22 and 24 days of the menstrual cycle. In the control group secretory endometrium was more frequently detected than in the mastopathy group (chi2 = 11,15, p = 0.01). Proliferatory (chi2 = 8.27, p = 0.004) and presecretory endometrium (chi2 = 4.61, p = 0.03) were more frequently detected in the mastopathy group than in controls. We did not find statistically significant relationship between the mean PSA concentrations between the groups in relation to histopathological findings. No relationships between free and total PSA measured in the follicular phase of the menstrual cycle and endometrial findings were detected in our study. Further research is required to evaluate the relationship between PSA and endometrial findings.

  19. Image Guided Hypofractionated Radiotherapy by Helical Tomotherapy for Prostate Carcinoma: Toxicity and Impact on Nadir PSA

    Directory of Open Access Journals (Sweden)

    Salvina Barra

    2014-01-01

    Full Text Available Aim. To evaluate the toxicity of a hypofractionated schedule for primary radiotherapy (RT of prostate cancer as well as the value of the nadir PSA (nPSA and time to nadir PSA (tnPSA as surrogate efficacy of treatment. Material and Methods. Eighty patients underwent hypofractionated schedule by Helical Tomotherapy (HT. A dose of 70.2 Gy was administered in 27 daily fractions of 2.6 Gy. Acute and late toxicities were graded on the RTOG/EORTC scales. The nPSA and the tnPSA for patients treated with exclusive RT were compared to an equal cohort of 20 patients treated with conventional fractionation and standard conformal radiotherapy. Results. Most of patients (83% did not develop acute gastrointestinal (GI toxicity and 50% did not present genitourinary (GU toxicity. After a median follow-up of 36 months only grade 1 of GU and GI was reported in 6 and 3 patients as late toxicity. Average tnPSA was 30 months. The median value of nPSA after exclusive RT with HT was 0.28 ng/mL and was significantly lower than the median nPSA (0.67 ng/mL of the conventionally treated cohort (P=0.02. Conclusions. Hypofractionated RT schedule with HT for prostate cancer treatment reports very low toxicity and reaches a low level of nPSA that might correlate with good outcomes.

  20. Determination of Component Failure Modes for a Fire PSA by Using Decision Trees

    International Nuclear Information System (INIS)

    Kang, Dae Il; Han, Sang Hoon; Lim, Jae Won

    2007-01-01

    KAERI developed the method, called a mapping technique, for the quantification of external events PSA models with one top model for an internal events PSA. The mapping technique can be implemented by the construction of mapping tables. The mapping tables include initiating events and transfer events of fire, and internal PSA basic events affected by a fire. This year, KAERI is making mapping tables for the one top model for Ulchin Unit 3 and 4 fire PSA with previously conducted Fire PSA results for Ulchin Unit 3 and 4. A Fire PSA requires a PSA analyst to determine component failure modes affected by a fire. The component failure modes caused by a fire depend on several factors. These several factors are whether components are located at fire initiation and propagation areas or not, fire effects on control and power cables for components, designed failure modes of components, success criteria in a PSA model, etc. Thus, it is not easy to manually determine component failure modes caused by a fire. In this paper, we propose the use of decision trees for the determination of component failure modes affected by a fire and the selection of internal PSA basic events. Section 2 presents the procedure for previously performed the Ulchin Unit 3 and 4 fire PSA and mapping technique. Section 3 presents the process for identification of basic events and decision trees. Section 4 presents the concluding remarks

  1. Analysis of urinary PSA glycosylation is not indicative of high-risk prostate cancer.

    Science.gov (United States)

    Barrabés, Sílvia; Llop, Esther; Ferrer-Batallé, Montserrat; Ramírez, Manel; Aleixandre, Rosa N; Perry, Antoinette S; de Llorens, Rafael; Peracaula, Rosa

    2017-07-01

    The levels of core fucosylation and α2,3-linked sialic acid in serum Prostate Specific Antigen (PSA), using the lectins Pholiota squarrosa lectin (PhoSL) and Sambucus nigra agglutinin (SNA), can discriminate between Benign Prostatic Hyperplasia (BPH) and indolent prostate cancer (PCa) from aggressive PCa. In the present work we evaluated whether these glycosylation determinants could also be altered in urinary PSA obtained after digital rectal examination (DRE) and could also be useful for diagnosis determinations. For this purpose, α2,6-sialic acid and α1,6-fucose levels of urinary PSA from 53 patients, 18 biopsy-negative and 35 PCa patients of different aggressiveness degree, were analyzed by sandwich ELLA (Enzyme Linked Lectin Assay) using PhoSL and SNA. Changes in the levels of specific glycosylation determinants, that in serum PSA samples were indicative of PCa aggressiveness, were not found in PSA from DRE urine samples. Although urine is a simpler matrix for analyzing PSA glycosylation compared to serum, an immunopurification step was necessary to specifically detect the glycans on the PSA molecule. Those specific glycosylation determinants on urinary PSA were however not useful to improve PCa diagnosis. This could be probably due to the low proportion of PSA from the tumor in urine samples, which precludes the identification of aberrantly glycosylated PSA. Copyright © 2017 Elsevier B.V. All rights reserved.

  2. Prostate-Specific Antigen (PSA) Bounce After Dose-Escalated External Beam Radiation Therapy Is an Independent Predictor of PSA Recurrence, Metastasis, and Survival in Prostate Adenocarcinoma Patients.

    Science.gov (United States)

    Romesser, Paul B; Pei, Xin; Shi, Weiji; Zhang, Zhigang; Kollmeier, Marisa; McBride, Sean M; Zelefsky, Michael J

    2018-01-01

    To evaluate the difference in prostate-specific antigen (PSA) recurrence-free, distant metastasis-free, overall, and cancer-specific survival between PSA bounce (PSA-B) and non-bounce patients treated with dose-escalated external beam radiation therapy (DE-EBRT). During 1990-2010, 1898 prostate adenocarcinoma patients were treated with DE-EBRT to ≥75 Gy with ≥5 years follow-up. Patients receiving neoadjuvant/concurrent androgen-deprivation therapy (n=1035) or with fewer than 4 PSA values obtained 6 months or more after post-EBRT completion (n=87) were excluded. The evaluable 776 patients were treated (median, 81.0 Gy). Prostate-specific antigen bounce was defined as a ≥0.2-ng/mL increase above the interval PSA nadir, followed by a decrease to nadir or below. Prostate-specific antigen relapse was defined as post-radiation therapy PSA nadir + 2 ng/mL. Median follow-up was 9.2 years (interquartile range, 6.9-11.3 years). One hundred twenty-three patients (15.9%) experienced PSA-B after DE-EBRT at a median of 24.6 months (interquartile range, 16.1-38.5 months). On multivariate analysis, younger age (P=.001), lower Gleason score (P=.0003), and higher radiation therapy dose (P=.0002) independently predicted PSA-B. Prostate-specific antigen bounce was independently associated with decreased risk for PSA relapse (hazard ratio [HR] 0.53; 95% confidence interval [CI] 0.33-0.85; P=.008), distant metastatic disease (HR 0.34; 95% CI 0.12-0.94; P=.04), and all-cause mortality (HR 0.53; 95% CI 0.29-0.96; P=.04) on multivariate Cox analysis. Because all 50 prostate cancer-specific deaths in patients without PSA-B were in the non-bounce cohort, competing-risks analysis was not applicable. A nonparametric competing-risks test demonstrated that patients with PSA-B had superior cancer-specific survival compared with patients without PSA-B (P=.004). Patients treated with dose-escalated radiation therapy for prostate adenocarcinoma who experience posttreatment PSA-B have

  3. PSA kinetics following primary focal cryotherapy (hemiablation) in organ-confined prostate cancer patients.

    Science.gov (United States)

    Kongnyuy, Michael; Islam, Shahidul; Mbah, Alfred K; Halpern, Daniel M; Werneburg, Glenn T; Kosinski, Kaitlin E; Chen, Connie; Habibian, David J; Schiff, Jeffrey T; Corcoran, Anthony T; Katz, Aaron E

    2018-02-01

    We aim to evaluate prostate-specific antigen (PSA) trends in post-primary focal cryotherapy (PFC) patients. This was an institutional review board-approved retrospective study of PFC patients from 2010 to 2015. Patients with at least one post-PFC PSA were included in the study. Biochemical recurrence (BCR) was determined using the Phoenix criteria. PSA bounce was also assessed. We analyzed rates of change of PSA over time of post-PFC between BCR and no BCR groups. PSA-derived variables were analyzed as potential predictors of BCR. A total of 104 PFC patients were included in our analysis. Median (range) age and follow-up time were 66 (48-82) years and 19 (6.3-38.6) months, respectively. Four (3.8%) patients experienced PSA bounce. The median percent drop in first post-PFC PSA of 80.0% was not associated with BCR (p = 0.256) and may indicate elimination of the index lesion. The rate of increase of PSA in BCR patients was significantly higher compared to patients who did not recur (median PSA velocity (PSAV): 0.15 vs 0.04 ng/ml/month, p = 0.001). Similar to PSAV (HR 9.570, 95% CI 3.725-24.592, p PSA nadir ≥ 2 ng/ml [HR (hazard ratio) 1.251, 95% CI 1.100-1.422, p = 0.001] was independently associated with BCR. A significant drop in post-PFC PSA may indicate elimination of the index lesion. Patients who are likely to recur biochemically have a significantly higher PSAV compared to those who do not recur. Nadir PSA of less than 2 ng/ml may be considered the new normal PSA in focal cryotherapy (hemiablation) follow-up.

  4. Development of the SKI Handbook for reviewing PSA after the review of the of a PSA level 2 study

    International Nuclear Information System (INIS)

    Lindholm, Ilona; Sairanen, Risto

    2003-02-01

    A review of the Oskarshamn 2 Level 2 PSA has been conducted by VTT Processes. One objective of the review was validation and development of Tillsynshandbok PSA applying it to Oskarshamn 2 PSA Level 2 study. The review was based on the PSA Level 2 documentation: the main report, the supporting reports on containment success criteria and release calculations with the MAAP4 code, and five phenomenological reports for selected specific questions. The main result of the phenomenological analyses is that none of the phenomena considered contributes to the conditional failure probability of the Oskarshamn 2 containment in severe accidents. The project was conducted as a set of separate studies and the project quality assurance has also focused on one part at the time. As such, the quality assurance is adequate. A high level QA ensuring that all separate studies and analysis steps use same assumptions seems to be missing. Results from the phenomenology reports are not always transferred to accident analyses and vice versa. There is no specific discussion of uncertainty or sensitivity analyses. In general, the number of sensitivity analyses could be larger. Such should have been provided for sequences or phenomena that could result in early or unmitigated release. Examples are pressure vessel failure at high pressure, the effect of larger hydrogen production, and the key assumptions used for steam explosion and direct containment heating. Suggestions for additional sensitivity studies have been given in discussion of phenomenological reports. The project documentation is generally good. Missing information is usually associated with transfer of results from one study to another. It can be assumed that the information exists also in this cases but has not been documented in the reports above. Documentation of the containment event trees and the assumptions used for them could be more detailed, maybe similar to the approach used in the Appendix of this report. More effort

  5. The percentage of prostate-specific antigen (PSA) isoform [-2]proPSA and the Prostate Health Index improve the diagnostic accuracy for clinically relevant prostate cancer at initial and repeat biopsy compared with total PSA and percentage free PSA in men aged ≤65 years.

    Science.gov (United States)

    Boegemann, Martin; Stephan, Carsten; Cammann, Henning; Vincendeau, Sébastien; Houlgatte, Alain; Jung, Klaus; Blanchet, Jean-Sebastien; Semjonow, Axel

    2016-01-01

    To prospectively test the diagnostic accuracy of the percentage of prostate specific antigen (PSA) isoform [-2]proPSA (%p2PSA) and the Prostate Health Index (PHI), and to determine their role for discrimination between significant and insignificant prostate cancer at initial and repeat prostate biopsy in men aged ≤65 years. The diagnostic performance of %p2PSA and PHI were evaluated in a multicentre study. In all, 769 men aged ≤65 years scheduled for initial or repeat prostate biopsy were recruited in four sites based on a total PSA (t-PSA) level of 1.6-8.0 ng/mL World Health Organization (WHO) calibrated (2-10 ng/mL Hybritech-calibrated). Serum samples were measured for the concentration of t-PSA, free PSA (f-PSA) and p2PSA with Beckman Coulter immunoassays on Access-2 or DxI800 instruments. PHI was calculated as (p2PSA/f-PSA × √t-PSA). Uni- and multivariable logistic regression models and an artificial neural network (ANN) were complemented by decision curve analysis (DCA). In univariate analysis %p2PSA and PHI were the best predictors of prostate cancer detection in all patients (area under the curve [AUC] 0.72 and 0.73, respectively), at initial (AUC 0.67 and 0.69) and repeat biopsy (AUC 0.74 and 0.74). t-PSA and %f-PSA performed less accurately for all patients (AUC 0.54 and 0.62). For detection of significant prostate cancer (based on Prostate Cancer Research International Active Surveillance [PRIAS] criteria) the %p2PSA and PHI equally demonstrated best performance (AUC 0.70 and 0.73) compared with t-PSA and %f-PSA (AUC 0.54 and 0.59). In multivariate analysis PHI we added to a base model of age, prostate volume, digital rectal examination, t-PSA and %f-PSA. PHI was strongest in predicting prostate cancer in all patients, at initial and repeat biopsy and for significant prostate cancer (AUC 0.73, 0.68, 0.78 and 0.72, respectively). In DCA for all patients the ANN showed the broadest threshold probability and best net benefit. PHI as single parameter

  6. Naphthalene: Drinking water health advisory

    Energy Technology Data Exchange (ETDEWEB)

    1990-03-01

    The Drinking Water Health Advisory, Office of Water, U.S. Environmental Protection Agency, has issued its report on the chemical, naphthalene. Naphthalene is used in the manufacture of phthalic and anthranilic acids and other derivatives, and in making dyes; in the manufacture of resins, celluloid, lampblack and smokeless gunpowder; and as moth repellant, insecticide, anthelmintic, vermicide, and intestinal antiseptic. The report covers the following areas: the occurrence of the chemical in the environment; its environmental fate; the chemical's absorption, distribution, metabolism, and excretion in the human body; and its health effects on humans and animals, including its mutagenicity and carcinogenicity characteristics. Also included is the quantification of its toxicological effects.

  7. [Rates of total and free PSA prescriptions in France (2012-2014)].

    Science.gov (United States)

    Tuppin, Philippe; Leboucher, Claire; Peyre-Lanquar, Gabrielle; Lamy, Pierre-Jean; Gabach, Pierre; Rébillard, Xavier

    2017-10-01

    In 2010, the French Haute Autorité de santé (National Health Authority) confirmed the limited value of prostate cancer (PCa) screening by total prostate-specific antigen (PSA) assay. This study was designed to determine the modalities of ordering total PSA or free PSA assays (in the absence of PCa) according to various parameters and the corresponding sums reimbursed. Men aged 40 years and older covered by the national health insurance general scheme (73% of the French population) between 2012 and 2014 were selected. Data were derived from the Système national d'information inter-régimes de l'assurance maladie (Sniiram) (National health insurance information system) database. In 2014, 27% of the 11.6 million men 40 years and older underwent at least one total PSA assay and 5.6% underwent at least one free PSA assay, with marked variations according to the presence or absence of treated lower urinary tract symptoms (LUTS) (53% and 15% vs 24% and 5%) and from one administrative department to another. The peak total PSA assay rate was observed between the ages of 65 and 74 years: 64% of men with LUTS, 46% without LUTS. Between 2012 and 2014, men in whom at least one PSA assay had been performed underwent a mean of 1.8 total PSA assays and 1.7 free PSA assays, with means of 2.3 and 2, respectively, in the presence of LUTS. General practice specialists ordered 91% of the PSA tests reimbursed in 2014 (92% for total PSA and 87% for free PSA) and urologists ordered 4% of reimbursed tests. The total sum reimbursed was €28.5 million, comprising €8.7 million for free PSA. An average of 10 laboratory tests was performed at the same time as the PSA assay in the absence of treated LUTS. Total PSA and free PSA assays are performed in a large number of men, although the value of these tests as first-line test before biopsy remains controversial. These PSA assays are associated with many other laboratory tests looking for possible abnormalities, especially in younger

  8. Final guidance document for extended Level 2 PSA Volume 1. Summary report for external hazards implementation in extended L2 PSA, validation of SAMG strategy and complement of ASAMPSA2 L2PSA guidance

    International Nuclear Information System (INIS)

    Loeffler, H.; Raimond, E.

    2016-01-01

    The present document is a summary of the deliverables produced within the ASAMPSA-E project for extended L2 PSA. These deliverables are: D30.7 vol. 2, 'Implementing external Events modelling in Level 2 PSA': D30.7 vol. 3: 'Verification and improvement of SAM strategy: D30.7 vol. 4: 'Consideration of shutdown states, spent fuel pools and recent R and D results'. Among many others, the following summary statements are provided: Analyses of external events: - No need for new methodology, - It is necessary to develop L1 PSA first and then clearly defined boundary conditions for the L2 PSA must be generated, - The remaining challenge is how to address adverse environmental conditions due to external hazards. Multi units: - No practical methodology exists to treat the problem, - A new methodology is necessary to be developed first for the L1 PSA. This should, from the beginning, take into account the specific needs of L2 PSA so that the boundary conditions for subsequent level 2 analysis can be generated adequately. SAM strategies verification and improvement: - L2 PSA methodology can usefully by applied and experience exists for internal initiating events L2 PSA, - How to address adverse environmental conditions due to external hazards - needs for new methodology or examples of experience, - How to model the decision process when there is a conflict of interest - needs for new methodology or examples of experience. For L2 PSA in shutdown states with open RPV, some new technical issues (fission product release, thermal load to structures above RPV) have to be addressed. Spent fuel pool issues have been developed, in particular: - Heat load from the melting spent fuel to structures above (e.g. to the containment roof) is a severe challenge for the plant and for the present-day, methodology is missing. Recent R and D achievements with relevance for L2 PSA: - Basic research has been continued in the radiochemistry (iodine and ruthenium chemistry) field, but the existing

  9. 77 FR 69869 - National Advisory Council on Alcohol Abuse and Alcoholism, National Advisory Council on Drug...

    Science.gov (United States)

    2012-11-21

    ... Alcohol Abuse and Alcoholism, National Advisory Council on Drug Abuse, and National Cancer Advisory Board... Advisory Council on Alcohol Abuse and Alcoholism, National Advisory Council on Drug Abuse, and National...: National Advisory Council on Alcohol Abuse and Alcoholism, National Advisory Council on Drug Abuse, and...

  10. Association between PSA kinetics and cancer-specific mortality in patients with localised prostate cancer

    DEFF Research Database (Denmark)

    Thomsen, Frederik Birkebæk; Brasso, Klaus; Berg, Kasper Drimer

    2016-01-01

    BACKGROUND: The prognostic value of prostate-specific antigen (PSA) kinetics in untreated prostate cancer (PCa) patients is debatable. We investigated the association between PSA doubling time (PSAdt), PSA velocity (PSAvel) and PSAvel risk count (PSAvRC) and PCa mortality in a cohort of patients...... with localised PCa managed on watchful waiting. PATIENTS AND METHODS: Patients with clinically localised PCa managed observationally, who were randomised to and remained on placebo for minimum 18 months in the SPCG-6 study, were included. All patients survived at least 2 years and had a minimum of three PSA...... determinations available. The prognostic value of PSA kinetics was analysed and patients were stratified according to their PSA at consent: ≤10, 10.1-25, and >25 ng/ml. Cumulative incidences of PCa-specific mortality were estimated with the Aalen-Johansen method. RESULTS: Two hundred and sixty-three patients...

  11. Guidance for Decision Making based on Extended PSA. Volume 1 - Summary report

    International Nuclear Information System (INIS)

    Loeffler, H.; Kumar, M.; Raimond, E.

    2016-01-01

    This report of ASAMPSA-E project is a summary report of the WP30 activities which were intended to develop guidance on decision-making process based on extended PSA results, when the PSA scope has been extended to all sources of radioactivity, all internal and relevant external events. It summarizes the ASAMPSA-E recommendations on: - the lessons of Fukushima Dai-ichi accident for PSA, - the risk metrics, - the method for identifying Initiating Events and Hazards for an Extended PSA (screening), - the link between extended PSA and the defense-in-depth concept. The report then provides some general considerations on application of extended PSA results, criteria that can be applied and also some difficulties inherent to the status of extended PSAs. (authors)

  12. Low percentage of free prostate-specific antigen (PSA) is a strong predictor of later detection of prostate cancer among Japanese men with serum levels of total PSA of 4.0 ng/mL or less.

    Science.gov (United States)

    Sasaki, Mitsuharu; Ishidoya, Shigeto; Ito, Akihiro; Saito, Hideo; Yamada, Shigeyuki; Mitsuzuka, Koji; Kaiho, Yasuhiro; Shibuya, Daisuke; Yamaguchi, Takuhiro; Arai, Yoichi

    2014-11-01

    To investigate the effect of the percentage of free prostate-specific antigen (%fPSA) on future prostate cancer risk. We examined serum total PSA (tPSA) and %fPSA annually in a prostate cancer-screening cohort between July 2001 and June 2011. Men with tPSA >4.0 ng/mL or tPSA of 2.0-4.0 ng/mL with %fPSA ≤12% were screened as positive and were recommended to undergo a biopsy. The study population consisted of 6368 men, aged 40-79 years, who had tPSA ≤4.0 ng/mL at initial screening and who subsequently underwent 1 or more screenings. We calculated the cumulative risk and hazard ratio of prostate cancer stratified by the initial %fPSA groups as quartiles of prostate cancer patients. During a median follow-up of 36 months, 119 men were diagnosed with prostate cancer. The lowest quartile of %fPSA (22.2%). For the subset with an initial tPSA ≤1.0 ng/mL, all men diagnosed with cancer had an initial %fPSA ≤33.3% (median). For the subset with tPSA >1.0 ng/mL, men with %fPSA ≤23.0% (median) had significantly higher risk for cancer than those with %fPSA >23.0% (P men with prostate cancer in whom pathologic findings were available, 79 (69.3%) had a Gleason score ≥3 + 4 = 7. A low %fPSA is a strong predictor of a subsequent diagnosis of prostate cancer among men with tPSA levels ≤4.0 ng/mL. Measurement of %fPSA might enhance the detection of high-grade cancer that warrants aggressive treatment. Copyright © 2014 Elsevier Inc. All rights reserved.

  13. PSA bounce phenomenon after transperineal interstitial permanent prostate brachytherapy for localized prostate cancer

    International Nuclear Information System (INIS)

    Morita, Masashi; Lederer, J.L.; Fukagai, Takashi; Yoshida, Hideki; Shimada, Makoto

    2004-01-01

    We described the temporarily increase phenomenon in prostate-specific antigen level (PSA bounce) after transperineal interstitial permanent prostate brachytherapy (TIPPB) for localized prostate cancer. From December 1998 to May 2003, 500 consecutive patients with localized prostate cancer were treated with TIPPB using iodine-125 or palladium-103. We examined 200 patients who have more than 2-year PSA follow-up. Median follow-up length was 1,069 days (range, 712-1,411 days). No patient received neoadjuvant or adjuvant hormone therapy. PSA determinations were performed every 3 months for the first 2 years after procedure, and every 6 months hereafter. PSA bounce was defined as an increase of 0.1 ng/ml or greater above the preceding PSA level after implant followed by a subsequent decrease below that level. The American Society for Therapeutic Radiology and Oncology (ASTRO) consensus panel criteria 1996 were used to define biochemical failure. PSA bounce was observed in 40% (80/200) of the cases receiving TIPPB. The median time to PSA bounce was 13 months from the day of implant. The median magnitude of the PSA bounce was 0.3 ng/ml from the pre-bounce level. Twelve cases demonstrated biochemical failure according to the ASTRO consensus guidelines of three consecutive rises in PSA. Ten of these subsequently showed a drop in PSA, consistent with biologic control of their disease. Two cases remain classified as apparent biochemical failures. A transient rise in the PSA following TIPPB, the so-called ''bounce'' is a common occurrence. The apparent PSA control of ten of twelve cases failing by the ASTRO criteria raises some concern. Further observation will be necessary to determine ways to discriminate these from true disease progression. (author)

  14. What do PSA changes after radiotherapy with or without prior androgen deprivation mean?

    International Nuclear Information System (INIS)

    Denham, J.W.; Woodhead, D.; Lamb, D.S.; Duchesne, G.

    2003-01-01

    The TROG 96.01 randomised patients with Stage B2 and C prostate cancer to radiotherapy alone to 66 Gy (RT), 3 months maximal androgen deprivation (MAD) with goserelin and flutamide prior to and during RT, and 6 months MAD prior to and during RT. Minimum follow up time is now 3 years. Prior to preliminary analysis of one of the trial's main endpoints biochemical relapse free survival (bRFS), the prostate-specific antigen (PSA) time course for every patient was evaluated to assess the performance of the ASTRO definition of biochemical failure (BF). Following MAD and RT PSA levels immediately rise in the majority of cases (PSA 'rebound'). In over 50% of cases, PSA levels then plateau at <1 ng/ml for 2 - 3 years prior to clear evidence of failure. Premature diagnosis of BF is possible in some of these cases. Fluctuations in PSA level ('bouncing') are more frequent after MAD and RT. As a result there can be difficulty in interpreting the ASTRO definition of BF in cases where overall PSA trend is upwards shortly after completion of therapy. In patients experiencing BF, the rate of PSA rise often corresponds to the site of failure. PSA doubling times (DT) under 7 months are usually associated with development of bony metastases, while DTs greater than that are usually associated with local failure. Decline in PSA levels following RT alone is frequently not mono-exponential and patients with those patterns experience lower PSA nadir levels and are subject to lower risks of all forms of relapse. These patients also survive longer. In cases where PSA descent patterns are discernable after MAD and RT, opposite trends are seen. Caution is necessary in diagnosing BF after MAD plus RT. Variations in the natural history of prostate cancer are reflected by variations in the rate of PSA changes following therapy. The importance of monitoring this marker and evaluating its time course is emphasised. Prospective studies are needed

  15. PSA bounce after 125I-brachytherapy for prostate cancer as a favorable prognosticator

    International Nuclear Information System (INIS)

    Engeler, Daniel S.; Schwab, Christoph; Schmid, Hans-Peter; Thoeni, Armin F.; Hochreiter, Werner; Prikler, Ladislav; Suter, Stefan; Stucki, Patrick; Schiefer, Johann; Plasswilm, Ludwig; Putora, Paul Martin

    2015-01-01

    Permanent low-dose-rate brachytherapy (BT) with iodine 125 is an established curative treatment for localized prostate cancer. After treatment, prostate-specific antigen (PSA) kinetics may show a transient rise (PSA bounce). Our aim was to investigate the association of PSA bounce with biochemical control. Patients treated with BT in Switzerland were registered in a prospective database. Only patients with a follow-up of at least 2 years were included in our analysis. Clinical follow-up and PSA measurements were assessed after 1.5, 3, 6, and 12 months, and annually thereafter. If PSA increased, additional follow-up visits were scheduled. Cases of PSA bounce were defined as a rise of at least 0.2 ng/ml above the initial PSA nadir with a subsequent decline to or below the initial nadir without treatment. Biochemical failure was defined as a rise to nadir + 2 ng/ml. Between March 2001 and November 2010, 713 patients with prostate cancer undergoing BT with at least 2 years of follow-up were registered. Median follow-up time was 41 months. Biochemical failure occurred in 28 patients (3.9 %). PSA bounce occurred in 173 (24.3 %) patients; only three (1.7 %) patients with PSA bounce developed biochemical failure, in contrast to 25 (4.6 %) patients without previous bounce (p < 0.05). The median time to bounce was 12 months, the median time to biochemical failure was 30 months. The median bounce increase was 0.78 ng/ml. Twenty-eight patients with bounce (16.5 %) had a transient PSA rise of + 2 ng/ml above the nadir. In most cases, an early increase in PSA after BT indicates PSA bounce and is associated with a lower risk of biochemical failure. (orig.) [de

  16. Prebiopsy biparametric MRI: differences of PI-RADS version 2 in patients with different PSA levels.

    Science.gov (United States)

    Choi, M H; Lee, Y J; Jung, S E; Rha, S E; Byun, J Y

    2018-06-09

    To validate the diagnostic accuracy of Prostate Imaging-Reporting and Data System (PI-RADS) version 2 in detecting clinically significant prostate cancer (csPCa, Gleason score ≥7) on prebiopsy biparametric MRI (bpMRI) in patients with different prostate-specific antigen (PSA) levels. This retrospective study included 184 patients who underwent prebiopsy bpMRI followed by transrectal ultrasonography-guided biopsy between June 2015 and February 2017. Reader 1 performed a combination of systematic and targeted biopsy with cognitive fusion after reviewing bpMRI and reader 2 reviewed the bpMRIs retrospectively. PI-RADS categories 4 and 5 were considered positive, and the results of the biopsy were considered the reference standard. Diagnostic performance of PI-RADS of bpMRI was evaluated in two PSA groups with a PSA cut-off level of 10 ng/ml and compared to PSA and the PSA density using receiver operating characteristics (ROC) curve analysis. csPCa was diagnosed in 24 of 123 patients (19.5%) and 26 of 61 patients (42.6%) in the low and high PSA groups, respectively. A PI-RADS v2 category by either readers 1 or 2 had a significantly better performance to detect csPCa than PSA in both PSA groups. In the high PSA group, only one csPCa was missed by reader 2, but none by reader 1. In the low PSA group, readers 1 and 2 were unable to detect seven and five of the 24 csPCas, respectively. Prebiopsy bpMRI has good performance for detecting csPCa in the high PSA group but may miss small-volume csPCa in the low PSA group. Copyright © 2018 The Royal College of Radiologists. Published by Elsevier Ltd. All rights reserved.

  17. Development of an immunoradiometric method for the measurement of total PSA

    International Nuclear Information System (INIS)

    Venkatesh, M.; Korde, A.; Bapat, K.; Shukla, A.; Pillai, M.R.A.

    1999-01-01

    Development of an IRMA for total-PSA was taken up in our laboratories (Isotope Division, Bhabha Atomic Research Centre, Mumbai, India) and efforts were made to obtain monoclonals for PSA at our laboratory. Following the guidelines laid at the first meeting of this CRP we have used the reagents supplied by the Agency as well as our inhouse reagents, and attempted to develop assay procedures for measuring total-PSA in human sera

  18. Development of a Base Model for the New Fire PSA Training

    International Nuclear Information System (INIS)

    Kim, Kilyoo; Kang, Daeil; Kim, Wee Kyong; Do, Kyu Sik

    2013-01-01

    US NRC/EPRI issued a new fire PSA method represented by NUREG/CR 6850, and have been training many operators and inspectors to widely spread the new method. However, there is a limitation in time and efficiency for many foreigners, who generally have communication problem, to participate in the EPRI/NRC training to learn the new method. Since it is about time to introduce the new fire PSA method as a regulatory requirement for the fire protection in Korea, a simple and easy-understandable base model for the fire PSA training is required, and KAERI-KINS is jointly preparing the base model for the new fire PSA training. This paper describes how the base model is developed. Using an imaginary simple NPP, a base model of fire PSA following the new fire PSA method was developed in two ways from the internal PSA model. Since we have the base model and know the process of making the fire PSA model, the training for the new fire PSA method can be in detail performed in Korea

  19. Construction and Quantification of the One Top model of the Fire Events PSA

    International Nuclear Information System (INIS)

    Kang, Dae Il; Lee, Yoon Hwan; Han, Sang Hoon

    2008-01-01

    KAERI constructed the one top model of the fire events PSA for Ulchin Unit 3 and 4 by using the 'mapping technique'. The mapping technique was developed for the construction and quantification of external events PSA models with a one top model for an internal events PSA. With 'AIMS', the mapping technique can be implemented by the construction of mapping tables. The mapping tables include fire rooms, fire ignition frequency, related initiating events, fire transfer events, and the internal PSA basic events affected by a fire. The constructed one top fire PSA model is based on previously conducted fire PSA results for Ulchin Unit 3 and 4. In this paper, we introduce the construction procedure and quantification results of the one top model of the fire events PSA by using the mapping technique. As the one top model of the fire events PSA developed in this study is based on the previous study, we also introduce the previous fire PSA approach focused on quantification

  20. Development of the IPRO-zone for fire PSA and its applications

    International Nuclear Information System (INIS)

    Kang, D. I.; Han, S. H.

    2012-01-01

    A PSA analyst has been manually determining fire-induced component failure modes and modeling them into the PSA logics. These can be difficult and time-consuming tasks as they need much information and many events are to be modeled. KAERI has been developing the IPRO-ZONE (interface program for constructing zone effect table) to facilitate fire PSA works for identifying and modeling fire-induced component failure modes, and to construct a one top fire event PSA model. With the output of the IPRO-ZONE, the AIMS-PSA, and internal event one top PSA model, one top fire events PSA model is automatically constructed. The outputs of the IPRO-ZONE include information on fire zones/fire scenarios, fire propagation areas, equipment failure modes affected by a fire, internal PSA basic events corresponding to fire-induced equipment failure modes, and fire events to be modeled. This paper introduces the IPRO-ZONE, and its application results to fire PSA of Ulchin Unit 3 and SMART(System-integrated Modular Advanced Reactor). (authors)

  1. Development of the IPRO-zone for fire PSA and its applications

    Energy Technology Data Exchange (ETDEWEB)

    Kang, D. I.; Han, S. H. [Integrated Safety Assessment Div., Korea Atomic Energy Research Inst. KAERI, 1045 Daedeokdaero (150 Deokjin-Dong), Yuseong-Gu, Daejon, 305-353 (Korea, Republic of)

    2012-07-01

    A PSA analyst has been manually determining fire-induced component failure modes and modeling them into the PSA logics. These can be difficult and time-consuming tasks as they need much information and many events are to be modeled. KAERI has been developing the IPRO-ZONE (interface program for constructing zone effect table) to facilitate fire PSA works for identifying and modeling fire-induced component failure modes, and to construct a one top fire event PSA model. With the output of the IPRO-ZONE, the AIMS-PSA, and internal event one top PSA model, one top fire events PSA model is automatically constructed. The outputs of the IPRO-ZONE include information on fire zones/fire scenarios, fire propagation areas, equipment failure modes affected by a fire, internal PSA basic events corresponding to fire-induced equipment failure modes, and fire events to be modeled. This paper introduces the IPRO-ZONE, and its application results to fire PSA of Ulchin Unit 3 and SMART(System-integrated Modular Advanced Reactor). (authors)

  2. Short overview of PSA quantification methods, pitfalls on the road from approximate to exact results

    International Nuclear Information System (INIS)

    Banov, Reni; Simic, Zdenko; Sterc, Davor

    2014-01-01

    Over time the Probabilistic Safety Assessment (PSA) models have become an invaluable companion in the identification and understanding of key nuclear power plant (NPP) vulnerabilities. PSA is an effective tool for this purpose as it assists plant management to target resources where the largest benefit for plant safety can be obtained. PSA has quickly become an established technique to numerically quantify risk measures in nuclear power plants. As complexity of PSA models increases, the computational approaches become more or less feasible. The various computational approaches can be basically classified in two major groups: approximate and exact (BDD based) methods. In recent time modern commercially available PSA tools started to provide both methods for PSA model quantification. Besides availability of both methods in proven PSA tools the usage must still be taken carefully since there are many pitfalls which can drive to wrong conclusions and prevent efficient usage of PSA tool. For example, typical pitfalls involve the usage of higher precision approximation methods and getting a less precise result, or mixing minimal cuts and prime implicants in the exact computation method. The exact methods are sensitive to selected computational paths in which case a simple human assisted rearrangement may help and even switch from computationally non-feasible to feasible methods. Further improvements to exact method are possible and desirable which opens space for a new research. In this paper we will show how these pitfalls may be detected and how carefully actions must be done especially when working with large PSA models. (authors)

  3. The Planetary Science Archive (PSA): Exploration and discovery of scientific datasets from ESA's planetary missions

    Science.gov (United States)

    Vallat, C.; Besse, S.; Barbarisi, I.; Arviset, C.; De Marchi, G.; Barthelemy, M.; Coia, D.; Costa, M.; Docasal, R.; Fraga, D.; Heather, D. J.; Lim, T.; Macfarlane, A.; Martinez, S.; Rios, C.; Vallejo, F.; Said, J.

    2017-09-01

    The Planetary Science Archive (PSA) is the European Space Agency's (ESA) repository of science data from all planetary science and exploration missions. The PSA provides access to scientific datasets through various interfaces at http://psa.esa.int. All datasets are scientifically peer-reviewed by independent scientists, and are compliant with the Planetary Data System (PDS) standards. The PSA has started to implement a number of significant improvements, mostly driven by the evolution of the PDS standards, and the growing need for better interfaces and advanced applications to support science exploitation.

  4. Workshop on PSA applications, Sofia, Bulgaria, 7-11 October 1996. Lecturing materials

    International Nuclear Information System (INIS)

    1997-01-01

    The objective of this workshop was to present detailed, systematic and useful information about PSA-based tools and PSA applications. The first presentation of the workshop was titled ''The role of PSA in safety management''. This topic served to introduce the workshop and to highlight several concepts that were afterwards stressed during the week, i.e. the defence in depth principle and the use of deterministic and probabilistic approaches in a complementary way. This presentation provided a basis for the discussion of ''PSA applications''. As a complement to the theoretical lectures, there was a workshop during which three different exercises were run in parallel. For two of these, computer-based PSA tools were used. One of them was focused towards the analysis of design modifications and the other one towards demonstrating configuration control strategies. The objective of the third practice was to obtain Allowed Outage Times using different PSA-based approaches and to discuss the differences observed and the insights obtained. To conclude the workshop, stress was put on the importance of the quality of the PSA (the development of a high quality Living PSA should be the first step), the necessity to be cautious (before taking decisions both the qualitative and numerical results should be carefully analyzed), and the logical order for the implementation of PSA applications. Refs, figs, tabs

  5. Procedure for Application of Software Reliability Growth Models to NPP PSA

    International Nuclear Information System (INIS)

    Son, Han Seong; Kang, Hyun Gook; Chang, Seung Cheol

    2009-01-01

    As the use of software increases at nuclear power plants (NPPs), the necessity for including software reliability and/or safety into the NPP Probabilistic Safety Assessment (PSA) rises. This work proposes an application procedure of software reliability growth models (RGMs), which are most widely used to quantify software reliability, to NPP PSA. Through the proposed procedure, it can be determined if a software reliability growth model can be applied to the NPP PSA before its real application. The procedure proposed in this work is expected to be very helpful for incorporating software into NPP PSA

  6. Analytic expressions for the construction of a fire event PSA model

    International Nuclear Information System (INIS)

    Kang, Dae Il; Kim, Kil Yoo; Kim, Dong San; Hwang, Mee Jeong; Yang, Joon Eon

    2016-01-01

    In this study, the changing process of an internal event PSA model to a fire event PSA model is analytically presented and discussed. Many fire PSA models have fire induced initiating event fault trees not shown in an internal event PSA model. Fire-induced initiating fault tree models are developed for addressing multiple initiating event issues. A single fire event within a fire compartment or fire scenario can cause multiple initiating events. As an example, a fire in a turbine building area can cause a loss of the main feed-water and loss of off-site power initiating events. Up to now, there has been no analytic study on the construction of a fire event PSA model using an internal event PSA model with fault trees of initiating events. In this paper, the changing process of an internal event PSA model to a fire event PSA model was analytically presented and discussed. This study results show that additional cutsets can be obtained if the fault trees of initiating events for a fire event PSA model are not exactly developed.

  7. Benchmark exercises on PWR level-1 PSA (step 3). Analyses of accident sequence and conclusions

    International Nuclear Information System (INIS)

    Niwa, Yuji; Takahashi, Hideaki.

    1996-01-01

    The results of level 1 PSA generate fluctuations due to the assumptions based on several engineering judgements set in the stages of PSA analysis. On the purpose of the investigation of uncertainties due to assumptions, three kinds of a standard problem, what we call benchmark exercise have been set. In this report, sensitivity studies (benchmark exercise) of sequence analyses are treated and conclusions are mentioned. The treatment of inter-system dependency would generate uncertainly of PSA. In addition, as a conclusion of the PSA benchmark exercise, several findings in the sequence analysis together with previous benchmark analyses in earlier INSS Journals are treated. (author)

  8. Analytic expressions for the construction of a fire event PSA model

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Dae Il; Kim, Kil Yoo; Kim, Dong San; Hwang, Mee Jeong; Yang, Joon Eon [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    In this study, the changing process of an internal event PSA model to a fire event PSA model is analytically presented and discussed. Many fire PSA models have fire induced initiating event fault trees not shown in an internal event PSA model. Fire-induced initiating fault tree models are developed for addressing multiple initiating event issues. A single fire event within a fire compartment or fire scenario can cause multiple initiating events. As an example, a fire in a turbine building area can cause a loss of the main feed-water and loss of off-site power initiating events. Up to now, there has been no analytic study on the construction of a fire event PSA model using an internal event PSA model with fault trees of initiating events. In this paper, the changing process of an internal event PSA model to a fire event PSA model was analytically presented and discussed. This study results show that additional cutsets can be obtained if the fault trees of initiating events for a fire event PSA model are not exactly developed.

  9. Immunohistochemical staining of precursor forms of prostate-specific antigen (proPSA) in metastatic prostate cancer.

    Science.gov (United States)

    Parwani, Anil V; Marlow, Cameron; Demarzo, Angelo M; Mikolajczyk, Stephen D; Rittenhouse, Harry G; Veltri, Robert W; Chan, Theresa Y

    2006-10-01

    Precursors of prostate-specific antigen (proPSA) have been previously shown to be more concentrated in prostate cancer tissue. This study characterizes the immunohistochemical staining (IHS) of proPSA forms in metastatic prostate cancer compared with prostate specific antigen (PSA) and prostatic acid phosphatase (PAP). A tissue microarray, consisting of 74 cases of metastatic prostate carcinoma and control tissues, was used. IHS, using monoclonal antibodies against proPSA with a truncated proleader peptide containing 2 amino acids ([-2]pPSA), native ([-5/-7]pPSA), PSA, and PAP, was analyzed. The monoclonal antibodies were specific for both benign and malignant prostatic glandular tissue. IHS with [-5/-7]pPSA showed the least number of cases with negative staining (3%), and the most number of cases with moderate or strong staining (76%). In the 60 cases where all 4 stains could be evaluated, none of them were negative for proPSA and positive for PSA or PAP, and all 7 cases that were negative for both PSA and PAP showed IHS to proPSA. [-5/-7]pPSA (native proPSA) may be a better marker than PSA and PAP in characterizing metastatic prostate adenocarcinoma, with most of the cases showing positivity for the marker. Even cases that were negative for PSA and PAP, were reactive for proPSA. Such enhanced detection is particularly important in poorly differentiated carcinomas involving metastatic sites where prostate carcinoma is a consideration. A panel of markers, including proPSA, should be performed when metastatic prostate carcinoma is in the differential diagnosis.

  10. PSA-stratified detection rates for [68Ga]THP-PSMA, a novel probe for rapid kit-based 68Ga-labeling and PET imaging, in patients with biochemical recurrence after primary therapy for prostate cancer.

    Science.gov (United States)

    Derlin, Thorsten; Schmuck, Sebastian; Juhl, Cathleen; Zörgiebel, Johanna; Schneefeld, Sophie M; Walte, Almut C A; Hueper, Katja; von Klot, Christoph A; Henkenberens, Christoph; Christiansen, Hans; Thackeray, James T; Ross, Tobias L; Bengel, Frank M

    2018-06-01

    [ 68 Ga]Tris(hydroxypyridinone)(THP)-PSMA is a novel radiopharmaceutical for one-step kit-based radiolabelling, based on direct chelation of 68 Ga 3+ at low concentration, room temperature and over a wide pH range, using direct elution from a 68 Ge/ 68 Ga-generator. We evaluated the clinical detection rates of [ 68 Ga]THP-PSMA PET/CT in patients with biochemically recurrent prostate cancer after prostatectomy. Consecutive patients (n=99) referred for evaluation of biochemical relapse of prostate cancer by [ 68 Ga]THP-PSMA PET/CT were analyzed retrospectively. Patients underwent a standard whole-body PET/CT (1 h p.i.), followed by delayed (3 h p.i.) imaging of the abdomen. PSA-stratified cohorts of positive PET/CT results, standardized uptake values (SUVs) and target-to-background ratios (TBRs) were analyzed, and compared between standard and delayed imaging. At least one lesion suggestive of recurrent or metastatic prostate cancer was identified on PET images in 52 patients (52.5%). Detection rates of [ 68 Ga]THP-PSMA PET/CT increased with increasing PSA level: 94.1% for a PSA value of ≥10 ng/mL, 77.3% for a PSA value of 2 to PSA value of 1 to PSA value of 0.5 to PSA value of >0.2 to PSA value of 0.01 to 0.2 ng/mL. [ 68 Ga]THP-PSMA uptake (SUVs) in metastases decreased over time, whereas TBRs improved. Delayed imaging at 3 h p.i. exclusively identified pathologic findings in 2% of [ 68 Ga]THP-PSMA PET/CT scans. Detection rate was higher in patients with a Gleason score ≥8 (P=0.02) and in patients receiving androgen deprivation therapy (P=0.003). In this study, [ 68 Ga]THP-PSMA PET/CT showed suitable detection rates in patients with biochemical recurrence of prostate cancer and PSA levels ≥ 2 ng /mL. Detections rates were lower than in previous studies evaluating other PSMA ligands, though prospective direct radiotracer comparison studies are mandatory particularly in patients with low PSA levels to evaluate the relative performance of different PSMA ligands.

  11. Extreme conservation of the psaA/psaB intercistronic spacer reveals a translational motif coincident with the evolution of land plants.

    Science.gov (United States)

    Peredo, Elena L; Les, Donald H; King, Ursula M; Benoit, Lori K

    2012-12-01

    Although chloroplast transcriptional and translational mechanisms were derived originally from prokaryote endosymbionts, chloroplasts retain comparatively few genes as a consequence of the overall transfer to the nucleus of functions associated formerly with prokaryotic genomes. Various modifications reflect other evolutionary shifts toward eukaryotic regulation such as posttranscriptional transcript cleavage with individually processed cistrons in operons and gene expression regulated by nuclear-encoded sigma factors. We report a notable exception for the psaA-psaB-rps14 operon of land plant (embryophyte) chloroplasts, where the first two cistrons are separated by a spacer region to which no significant role had been attributed. We infer an important function of this region, as indicated by the conservation of identical, structurally significant sequences across embryophytes and their ancestral protist lineages, which diverged some 0.5 billion years ago. The psaA/psaB spacers of embryophytes and their progenitors exhibit few sequence and length variants, with most modeled transcripts resolving the same secondary structure: a loop with projecting Shine-Dalgarno site and well-defined stem that interacts with adjacent coding regions to sequester the psaB start codon. Although many functions of the original endosymbiont have been usurped by nuclear genes or interactions, conserved functional elements of embryophyte psaA/psaB spacers provide compelling evidence that translation of psaB is regulated here by a cis-acting mechanism comparable to those common in prokaryotes. Modeled transcripts also indicate that spacer variants in some plants (e.g., aquatic genus Najas) potentially reflect ecological adaptations to facilitate temperature-regulated translation of psaB.

  12. Updating the Psoriatic Arthritis (PsA) Core Domain Set: A Report from the PsA Workshop at OMERACT 2016.

    Science.gov (United States)

    Orbai, Ana-Maria; de Wit, Maarten; Mease, Philip J; Callis Duffin, Kristina; Elmamoun, Musaab; Tillett, William; Campbell, Willemina; FitzGerald, Oliver; Gladman, Dafna D; Goel, Niti; Gossec, Laure; Hoejgaard, Pil; Leung, Ying Ying; Lindsay, Chris; Strand, Vibeke; van der Heijde, Désirée M; Shea, Bev; Christensen, Robin; Coates, Laura; Eder, Lihi; McHugh, Neil; Kalyoncu, Umut; Steinkoenig, Ingrid; Ogdie, Alexis

    2017-10-01

    To include the patient perspective in accordance with the Outcome Measures in Rheumatology (OMERACT) Filter 2.0 in the updated Psoriatic Arthritis (PsA) Core Domain Set for randomized controlled trials (RCT) and longitudinal observational studies (LOS). At OMERACT 2016, research conducted to update the PsA Core Domain Set was presented and discussed in breakout groups. The updated PsA Core Domain Set was voted on and endorsed by OMERACT participants. We conducted a systematic literature review of domains measured in PsA RCT and LOS, and identified 24 domains. We conducted 24 focus groups with 130 patients from 7 countries representing 5 continents to identify patient domains. We achieved consensus through 2 rounds of separate surveys with 50 patients and 75 physicians, and a nominal group technique meeting with 12 patients and 12 physicians. We conducted a workshop and breakout groups at OMERACT 2016 in which findings were presented and discussed. The updated PsA Core Domain Set endorsed with 90% agreement by OMERACT 2016 participants included musculoskeletal disease activity, skin disease activity, fatigue, pain, patient's global assessment, physical function, health-related quality of life, and systemic inflammation, which were recommended for all RCT and LOS. These were important, but not required in all RCT and LOS: economic cost, emotional well-being, participation, and structural damage. Independence, sleep, stiffness, and treatment burden were on the research agenda. The updated PsA Core Domain Set was endorsed at OMERACT 2016. Next steps for the PsA working group include evaluation of PsA outcome measures and development of a PsA Core Outcome Measurement Set.

  13. An international nanoscience advisory board to improve and harmonize nanotechnology oversight

    International Nuclear Information System (INIS)

    Marchant, Gary E.; White, Andrew

    2011-01-01

    As governments around the world begin to implement regulations aimed at controlling nanotechnology, those regulations should be based upon the best available science, applied as consistently as possible within jurisdictions and, to the extent feasible, across jurisdictions. These goals would be easier to achieve with the creation of an international nanoscience advisory board. Such a body could be modeled on similar international scientific advisory bodies for other issues, such as the Intergovernmental Panel on Climate Change (IPCC) and the Intergovernmental Science-Policy Platform on Biodiversity and Ecosystem Services. Such a body should also take into account lessons learned from these similar organizations. An international nanoscience advisory board could assist regulatory bodies by providing a central source of accurate scientific information about the risks and benefits of nanotechnology, including relevant uncertainties, rather than having each regulatory body make these determinations independently. An international nanoscience advisory board could facilitate harmonization within and between jurisdictions by involving the top experts in the field to produce a centralized knowledge base for regulatory decisions. While an international nanoscience advisory board presents many potential benefits, it also faces significant difficulties, which are best illustrated by examining the history and challenges of existing international science advisory bodies.

  14. Pulse shaping amplifier (PSA) for nuclear spectroscopy system

    International Nuclear Information System (INIS)

    Lombigit, L.; Maslina Mohd Ibrahim; Nolida Yusup; Nur Aira Abdul Rahman; Yong, C.F.

    2014-01-01

    Pulse Shaping Amplifier (PSA) is an essential components in nuclear spectroscopy system. This networks have two functions; to shape the output pulse and performs noise filtering. In this paper, we describes procedure for design and development of a pulse shaping amplifier which can be used for nuclear spectroscopy system. This prototype was developed using high performance electronics devices and assembled on a FR4 type printed circuit board. Performance of this prototype was tested by comparing it with an equivalent commercial spectroscopy amplifier (Model SILENA 7611). The test results show that the performance of this prototype is comparable to the commercial spectroscopic amplifier. (author)

  15. Losing the Dark: A Planetarium PSA about Light Pollution

    Science.gov (United States)

    Petersen, Carolyn Collins; Walker, Constance

    2015-03-01

    Losing the Dark is a six-minute PSA video created for fulldome theaters by Loch Ness Productions, the International Dark Sky Association Education Committee headed by Dr. Constance Walker of the National Optical Astronomy Observatories, Dome3, Adler Planetarium, and Babak Tafreshi (The World at Night). It explains light pollution, its effects, and ways to implement ``wise lighting`` practices to mitigate light pollution. The show is also made in flat-screen HD format for classical planetariums, non-dome theaters, and for presentatons by IDA speakers.

  16. A survey on the quantitative incorporation organizational factors into PSA

    International Nuclear Information System (INIS)

    Park, S. Z.; Jea, M. S.; Ahn, N. S.

    2002-01-01

    The effects of organizational factors on the human performance and safety in nuclear power plants have been known through the results of research for several years. The organizational factor, which belongs to 11 elements of PSR (Periodic Safety Review), has been an important research area. In this study the state-of-the-art of qualitative and quantitative evaluation methodologies on organizational factors has been surveyed. The results of this study may contribute to developing a quantitative evaluation methodology on organizational factors as well as the basic research for conducting the PSR research, and for incorporating the quality of organization factors into PSA

  17. Plant operational states analysis in low power and shutdown PSA

    International Nuclear Information System (INIS)

    He Jiandong; Qiu Yongping; Zhang Qinfang; An Hongzhen; Li Maolin

    2013-01-01

    The purpose of Plant Operational States (POS) analysis is to disperse the continuous and dynamic process of low power and shutdown operation, which is the basis of developing event tree models for accident sequence analysis. According to the design of a 300 MW Nuclear Power Plant Project, operating experience and procedures of the reference plant, a detailed POS analysis is carried out based on relative criteria. Then, several kinds of POS are obtained, and the duration of each POS is calculated according to the operation records of the reference plant. The POS analysis is an important element in low power and shutdown PSA. The methodology and contents provide reference for POS analysis. (authors)

  18. Colorectal Cancer - What You Need to Know PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    2011-07-05

    This 60 second Public Service Announcement (PSA) is based on the July, 2011 CDC Vital Signs report. Colorectal cancer kills about 50,000 men and women every year. Screening can save lives! Screening can find abnormal growths so they can be removed before turning into cancer, and can find the cancer early, when it's easiest to treat. If you're over 50, talk to your doctor about getting screened for colorectal cancer.  Created: 7/5/2011 by Centers for Disease Control and Prevention (CDC).   Date Released: 7/5/2011.

  19. 76 FR 21877 - Environmental Management Advisory Board

    Science.gov (United States)

    2011-04-19

    ... DEPARTMENT OF ENERGY Environmental Management Advisory Board AGENCY: Department of Energy. ACTION: Notice of call for nominations for appointment to the Environmental Management Advisory Board. SUMMARY... Environmental Management Advisory Board. DATES: Nominations will be accepted through May 13, 2011. ADDRESSES...

  20. ITS Standards Advisory : Dynamic Message Signs (DMS)

    Science.gov (United States)

    2003-01-01

    ITS Standards Advisories provide the transportation community with information and guidance on key activities related to ITS standards, with each Advisory focusing on a single ITS application and its corresponding standards. This advisory focuses on ...

  1. Evaluation of PSA-age volume score in predicting prostate cancer in Chinese populationArticle Subject.

    Science.gov (United States)

    Wu, Yi-Shuo; Wu, Xiao-Bo; Zhang, Ning; Jiang, Guang-Liang; Yu, Yang; Tong, Shi-Jun; Jiang, Hao-Wen; Mao, Shan-Hua; Na, Rong; Ding, Qiang

    2018-02-06

    This study was performed to evaluate prostate-specific antigen-age volume (PSA-AV) scores in predicting prostate cancer (PCa) in a Chinese biopsy population. A total of 2355 men who underwent initial prostate biopsy from January 2006 to November 2015 in Huashan Hospital were recruited in the current study. The PSA-AV scores were calculated and assessed together with PSA and PSA density (PSAD) retrospectively. Among 2133 patients included in the analysis, 947 (44.4%) were diagnosed with PCa. The mean age, PSA, and positive rates of digital rectal examination result and transrectal ultrasound result were statistically higher in men diagnosed with PCa (all P PSA-AV were 0.864 and 0.851, respectively, in predicting PCa in the entire population, both performed better than PSA (AUC = 0.805; P PSA-AV was more obvious in subgroup with PSA ranging from 2.0 ng ml-1 to 20.0 ng ml-1. A PSA-AV score of 400 had a sensitivity and specificity of 93.7% and 40.0%, respectively. In conclusion, the PSA-AV score performed equally with PSAD and was better than PSA in predicting PCa. This indicated that PSA-AV score could be a useful tool for predicting PCa in Chinese population.

  2. PSA based vulnerability and protectability analysis for NPPs

    International Nuclear Information System (INIS)

    Gopika, V.; Sanyasi Rao, V.V.S.; Ghosh, A.K.; Kushwaha, H.S.

    2012-01-01

    Highlights: ► The paper describes the generation of location sets and protection sets. ► Vulnerability and protectability used to rank location sets and protection sets. ► Ranking helps in adequacy of protection measures employed in various locations. ► The procedure for PSA based vital area identification is demonstrated. ► This method has found practical applicability for Indian NPP. -- Abstract: Identification of vital areas in a facility involves assessing the facility and the locations, whose sabotage can result in undesirable (radiological) consequences. Probabilistic Safety Assessment (PSA) technique can find the component failures leading to core damage (a surrogate for radiological consequence) in a systematic manner, which can be extended to identification of vital areas. This paper describes the procedure for the generation of location sets (set of locations whose sabotage can lead to possible core damage) and protection sets (set of locations that must be protected to prevent possible core damage). In addition, measures such as vulnerability and protectability have been introduced, which can be used to rank location sets and protection sets.

  3. PSA based plant modifications and back-fits

    International Nuclear Information System (INIS)

    1997-01-01

    The mandate of Principal Working Group No. 5 - Risk Assessment states that 'The group should deal with the technology and methods for identifying contributors to risk and assessing their importance, and appropriate exchanges of information on current research'. Since being formulated in 1982, along with this mandate, the group has also endeavored to develop a common understanding of the different approaches taken in risk assessment. The focus of this report is to provide knowledge to experts on the role Probabilistic Safety Assessment (PSA) has had in safety decision making. PSA is a powerful tool for improving Nuclear Power Plant safety by identifying weaknesses in design or operation and setting priorities for plant modifications and back-fits. While the use is well recognised, it is also true that any safety decision is generally based on several elements, both probabilistic and deterministic. This document provides a general overview of insights gained from the representative set of examples collected from Member countries (Finland, France, Germany, Japan, Korea, Netherlands, Spain, Sweden, Switzerland, United Kingdom, United States). The report starts with basic types of plant modifications which were carried out (e.g. hardware or software, important or minor, etc.) and the characteristics of the PSAs used in the examples (e.g. level and scope, specific or generic, on-going or terminated, etc.). The insights gained from this small collection are then reviewed. The appendix gives a full text version of the Member country contributions

  4. PSA results for Hanford high level waste Tank 101-SY

    Energy Technology Data Exchange (ETDEWEB)

    MacFarlane, D.R.; Bott, T.F.; Brown, L.F.; Stack, D.W. [Los Alamos National Lab., NM (United States); Kindinger, J.; Deremer, R.K.; Medhekar, S.R.; Mikschl, T.J. [PLG, Inc., Newport Beach, CA (United States)

    1993-10-01

    Los Alamos National Laboratory has performed a comprehensive probabilistic safety assessment (PSA) that includes consideration of external events for the weapons-production wastes stored in tank number 241-SY-101, commonly known as Tank 101-SY, as configured in December 1992. This tank, which periodically releases (``burps``) a gaseous mixture of hydrogen, nitrous oxide, ammonia, and nitrogen, was analyzed because of public safety concerns associated with the potential for release of radioactive tank contents should this gas mixture be ignited during one of the burps. In an effort to mitigate the burping phenomenon, an experiment is underway in which a large pump has been inserted into the tank to determine if pump-induced circulation of the tank contents will promote a slow, controlled release of the gases. This PSA for Tank 101-SY, which did not consider the pump experiment or future tank-remediation activities, involved three distinct tasks. First, the accident sequence analysis identified and quantified those potential accidents whose consequences result in tank material release. Second, characteristics and release paths for the airborne and liquid radioactive source terms were determined. Finally, the consequences, primarily onsite and offsite potential health effects resulting from radionuclide release, were estimated, and overall risk curves were constructed. An overview of each of these tasks and a summary of the overall results of the analysis are presented in the following sections.

  5. PSA results for Hanford high level waste Tank 101-SY

    International Nuclear Information System (INIS)

    MacFarlane, D.R.; Bott, T.F.; Brown, L.F.; Stack, D.W.; Kindinger, J.; Deremer, R.K.; Medhekar, S.R.; Mikschl, T.J.

    1993-01-01

    Los Alamos National Laboratory has performed a comprehensive probabilistic safety assessment (PSA) that includes consideration of external events for the weapons-production wastes stored in tank number 241-SY-101, commonly known as Tank 101-SY, as configured in December 1992. This tank, which periodically releases (''burps'') a gaseous mixture of hydrogen, nitrous oxide, ammonia, and nitrogen, was analyzed because of public safety concerns associated with the potential for release of radioactive tank contents should this gas mixture be ignited during one of the burps. In an effort to mitigate the burping phenomenon, an experiment is underway in which a large pump has been inserted into the tank to determine if pump-induced circulation of the tank contents will promote a slow, controlled release of the gases. This PSA for Tank 101-SY, which did not consider the pump experiment or future tank-remediation activities, involved three distinct tasks. First, the accident sequence analysis identified and quantified those potential accidents whose consequences result in tank material release. Second, characteristics and release paths for the airborne and liquid radioactive source terms were determined. Finally, the consequences, primarily onsite and offsite potential health effects resulting from radionuclide release, were estimated, and overall risk curves were constructed. An overview of each of these tasks and a summary of the overall results of the analysis are presented in the following sections

  6. Importance of the multi-modules study in PSA

    International Nuclear Information System (INIS)

    Gonzalez R, V. J.; Nelson E, P. F.

    2015-09-01

    The current approach that has taken the Probabilistic Safety Analysis (PSA) consists of doing all the APS analysis including the existence of multi-units in the nuclear power plants (NPP), this new approach seeks to analyze the risk of site, evaluating all reactors together. The main reasons for this trend are: the accident occurred on March 2011 in Fukushima Daiichi in Japan, with serious consequences in more than one reactor of the NPP and the current planning and construction of new Small Modular Reactors, which host more than one module on the same NPP and are connected to a single control room. This study analyzes how to model the risk of a multi-module NPP. In 2013, the ASME/ANS standard for advanced reactors that are not light-water reactors was published, in which the requirements to realize a PSA including multi-units or modules are shown; however, does not describe the methodology to do that. This article presents a methodology to calculate the risk of the site in a PBMR plant with two modules. This methodology consists of two models of trees of different events, one that evaluates to a single PBMR module and another that evaluates the two modules together. Both models are responsible to show their differences and compare results to finally demonstrate the need for new methodologies for risk analysis site in multi-modules and units. (Author)

  7. A Tsunami PSA for Nuclear Power Plants in Korea

    International Nuclear Information System (INIS)

    Kim, Min Kyu; Choi, In Kil; Park, Jin Hee; Seo, Kyung Suk; Seo, Jeong Moon; Yang, Joon Eon

    2010-06-01

    For the evaluation of safety of NPP caused by Tsunami event, probabilistic safety assessment (PSA) method was applied in this study. At first, an empirical tsunami hazard analysis performed for an evaluation of tsunami return period. A procedure for tsunami fragility methodology was established, and target equipment and structures for investigation of Tsunami Hazard assessment were selected. A several fragility calculations were performed for equipment in Nuclear Power Plant and finally accident scenario of tsunami event in NPP was presented. Finally, a system analysis performed in the case of tsunami event for an evaluation of a CDF of Ulchin 56 NPP site. For the evaluation of safety of NPP caused by Tsunami event, probabilistic safety assessment (PSA) method was applied. A procedure for tsunami fragility methodology was established, and target equipment and structures for investigation of Tsunami Hazard assessment were selected. A several fragility calculations were performed for equipment in Nuclear Power Plant and finally accident scenario of tsunami event in NPP was presented. As a result, in the case of tsunami event, functional failure is mostly governed total failure probability of facilities in NPP site

  8. External events analysis in PSA studies for Czech NPPs

    International Nuclear Information System (INIS)

    Holy, J.; Hustak, S.; Kolar, L.; Jaros, M.; Hladky, M.; Mlady, O.

    2014-01-01

    The purpose of the paper is to summarize current status of natural external hazards analysis in the PSA projects maintained in Czech Republic for both Czech NPPs - Dukovany and Temelin. The focus of the presentation is put upon the basic milestones in external event analysis effort - identification of external hazards important for Czech NPPs sites, screening out of the irrelevant hazards, modeling of plant response to the initiating events, including the basic activities regarding vulnerability and fragility analysis (supported with on-site analysis), quantification of accident sequences, interpretation of results and development of measures decreasing external events risk. The following external hazards are discussed in the paper, which have been addressed during several last years in PSA projects for Czech NPPs: 1)seismicity, 2)extremely low temperature 3)extremely high temperature 4)extreme wind 5)extreme precipitation (water, snow) 6)transport of dangerous substances (as an example of man-made hazard with some differences identified in comparison with natural hazards) 7)other hazards, which are not considered as very important for Czech NPPs, were screened out in the initial phase of the analysis, but are known as potential problem areas abroad. The paper is a result of coordinated effort with participation of experts and staff from engineering support organization UJV Rez, a.s. and NPPs located in Czech Republic - Dukovany and Temelin. (authors)

  9. Interoperability In The New Planetary Science Archive (PSA)

    Science.gov (United States)

    Rios, C.; Barbarisi, I.; Docasal, R.; Macfarlane, A. J.; Gonzalez, J.; Arviset, C.; Grotheer, E.; Besse, S.; Martinez, S.; Heather, D.; De Marchi, G.; Lim, T.; Fraga, D.; Barthelemy, M.

    2015-12-01

    As the world becomes increasingly interconnected, there is a greater need to provide interoperability with software and applications that are commonly being used globally. For this purpose, the development of the new Planetary Science Archive (PSA), by the European Space Astronomy Centre (ESAC) Science Data Centre (ESDC), is focused on building a modern science archive that takes into account internationally recognised standards in order to provide access to the archive through tools from third parties, for example by the NASA Planetary Data System (PDS), the VESPA project from the Virtual Observatory of Paris as well as other international institutions. The protocols and standards currently being supported by the new Planetary Science Archive at this time are the Planetary Data Access Protocol (PDAP), the EuroPlanet-Table Access Protocol (EPN-TAP) and Open Geospatial Consortium (OGC) standards. The architecture of the PSA consists of a Geoserver (an open-source map server), the goal of which is to support use cases such as the distribution of search results, sharing and processing data through a OGC Web Feature Service (WFS) and a Web Map Service (WMS). This server also allows the retrieval of requested information in several standard output formats like Keyhole Markup Language (KML), Geography Markup Language (GML), shapefile, JavaScript Object Notation (JSON) and Comma Separated Values (CSV), among others. The provision of these various output formats enables end-users to be able to transfer retrieved data into popular applications such as Google Mars and NASA World Wind.

  10. Lessons of the Fukushima Dai-ichi accident for PSA

    International Nuclear Information System (INIS)

    Kumar, M.; Klug, J.; Alzbutas, R.; Burgazzi, L.; Farcasiu, M.; Nitoi, M.; Ivanov, I.; Bogdanov, D.; Hashimoto, K.; Hirata, K.; La Rovere, S.; Sevbo, O.; Vitazkova, J.; Hustak, S.; Wielenberg, A.; Raimond, E.

    2016-01-01

    The objective of this document is to identify some lessons learned from the Fukushima Dai-ichi accident for PSA. Based on the public information on the causes that have led to major radioactive release during the Fukushima Dai-ichi accident (initiating events, material and human response), the authors, ASAMPSA-E WP30 members have performed a review to examine the gaps/insufficiencies/incompleteness in the existing Level 1 and Level 2 PSAs. This is the aim of this report which is one of WP30 deliverables i.e. D30.2. The consideration of external initiating events for the different levels of defense-in-depth is one of the focal points in this review. Recommendations in the way of developing the different elements of PSAs have been proposed by the authors and were completed later during the ASAMPSA-E project. Moreover, first recommendations on the use of PSA information in decision making have been included as well. (authors)

  11. Improvements in progress for Russia's new PSA law

    International Nuclear Information System (INIS)

    Pugliaresi, L.; Hensel, A.C.

    1996-01-01

    Russian legislation making production sharing agreements (PSAs) fully legal under Russian law passed the upper house of the Russian Parliament (Federal Council) on December 19, 1995, was signed into law by President Boris Yeltsin on December 31, 1995, and took effect on January 11, 1996. While PSA legislation remains the central legal basis for large scale investment in the Russian petroleum sector, company views towards investment in this sector are tied to much more than the extent of legal guarantees. Investor attitudes are also shaped by expectations regarding political stability, behavior of Russian regulatory authorities, and prospects for the Russian economy. Furthermore, Western investors in the petroleum sector have some experience in dealing with the Russian government and existing frameworks for investment, particularly the joint venture (JV) deals with Russian entities and the often changing regulatory and tax treatment of these ventures. It is the view of the authors that attitudes among some Western companies in Russia on the political and economic environment may be too pessimistic and shaped more by press reports than actual conditions. News reports on violence, political instability, and a disastrous economy are not entirely borne out by the facts. Russian, of course, faces serious political and economic problems which must be carefully evaluated, but the overall outlook is much more complex, and some positive developments are underway. This paper reviews the economic, oil production and industry outlook as a result of the PSA law

  12. 34 CFR 461.50 - What are a State's responsibilities regarding a State advisory council on adult education and...

    Science.gov (United States)

    2010-07-01

    ... 34 Education 3 2010-07-01 2010-07-01 false What are a State's responsibilities regarding a State advisory council on adult education and literacy? 461.50 Section 461.50 Education Regulations of the...) Establish a State advisory council on adult education and literacy; or (2) Designate an existing body as the...

  13. 78 FR 58536 - Notification of a Public Meeting of the Science Advisory Board Panel for the Review of the EPA...

    Science.gov (United States)

    2013-09-24

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL--9901-26-OA] Notification of a Public Meeting of the Science Advisory Board Panel for the Review of the EPA Water Body Connectivity Report AGENCY: Environmental Protection Agency (EPA). ACTION: Notice. SUMMARY: The EPA Science Advisory Board (SAB) Staff Office announces...

  14. 76 FR 22924 - Re-Establishment of the National Space-Based Positioning, Navigation, and Timing (PNT) Advisory...

    Science.gov (United States)

    2011-04-25

    ... Government is necessary and in the public interest. Accordingly, NASA is re-establishing the National Space... advice on U.S. space-based PNT policy, planning, program management, and funding profiles in relation to... Advisory Board will function solely as an advisory body and will comply fully with the provisions of the...

  15. Analysis of PSA-Specific T-Cell Responses of Prostate Cancer Patients Given a PSA-Based Vaccine on a Clinical Trial

    National Research Council Canada - National Science Library

    Gulley, James

    2003-01-01

    .... This randomized, phase II clinical trial was designed to determine if a PSA-based vaccine could induce a specific immune response when combined with radiotherapy in patients with localized prostate cancer...

  16. PET/CT with (18)F-choline after radical prostatectomy in patients with PSA ≤2 ng/ml. Can PSA velocity and PSA doubling time help in patient selection?

    Science.gov (United States)

    Chiaravalloti, Agostino; Di Biagio, Daniele; Tavolozza, Mario; Calabria, Ferdinando; Schillaci, Orazio

    2016-07-01

    To investigate the performance of (18)F-fluorocholine ((18)F-FCH) PET/CT in relation to the prostate-specific antigen (PSA) kinetic indexes, PSA doubling time (PSAdt) and PSA velocity (PSAve), in detecting recurrent prostate cancer (PC) in a selected population of patients treated with radical prostatectomy and with PSA ≤2 ng/ml. The study group comprised 79 patients (mean age 70 ± 7 years, range 58 - 77 years) who had been treated with radical surgery 30 to 90 months previously and with biochemical failure (defined as a measurable serum PSA level) who were evaluated with (18)F-FCH PET/CT. In order to establish the optimal threshold for PSAdt and PSAve, the diagnostic performance of PSA, PSAdt and PSAve were compared by receiver operating characteristic analysis. In the population examined, PSA (mean ± SD) was 1.37 ± 0.44 ng/ml (range 0.21 - 2 ng/ml) before PET/CT examination, PSAdt was 10.04 ± 16.67 months and PSAve was 2.75 ± 3.11 ng/ml per year. (18)F-FCH PET/CT was positive in 44 patients (55 %). PSAve and PSAdt were significantly different between patients with a positive and a negative (18)F-FCH PET/CT scan. Thresholds of 6 months for PSAdt and 1 ng/ml per year for PSAve were selected. For PSAdt ≤6 months the detection rate (DR) was 65 %, and for PSAve >1 ng/ml per year the DR was 67 %. PSA values were not significantly different between patients with a positive and a negative PET/CT scan. The results of our study suggest that (18)F-FCH PET/CT could be considered for the evaluation of patients with biochemical recurrence of PC and with low PSA levels. Fast PSA kinetics could be useful in the selection of these patients.

  17. A formal treatment of uncertainty sources in a level 2 PSA

    International Nuclear Information System (INIS)

    Ahn, Kwang Il; Yang, Joon Eon

    2003-01-01

    The methodological framework of the level 2 PSA appears to be currently standardized in a formalized fashion, but there have been different opinions on the way the sources of uncertainty are characterized and treated. This is primarily because the level 2 PSA deals with complex phenomenological processes that are deterministic in nature rather than random processes, and there are no probabilistic models characterizing them clearly. As a result, the probabilistic quantification of the level 2 PSA is often subjected to two sources of uncertainty: (a) incomplete modeling of accident pathways or different predictions for the behavior of phenomenological events and (b) expert-to-expert variation in estimating the occurrence probability of phenomenological events. While a clear definition of the two sources of uncertainty involved in the level 2 PSA makes it possible to treat an uncertainty in a consistent manner, careless application of these different sources of uncertainty may produce different conclusions in the decision-making process. The primary purpose of this paper is to characterize typical sources of uncertainty that would often be addressed in the level 2 PSA and their impacts on the PSA level 2 risk results. An additional purpose of this paper is to give a formal approach on how to combine random uncertainties addressed in the level 1 PSA with subjectivistic uncertainties addressed in the level 2 PSA

  18. A formal guidance for handling different uncertainty sources employed in the level 2 PSA

    International Nuclear Information System (INIS)

    Ahn, Kwang Il; Yang, Joon Eon; Ha, Jae Joo

    2004-01-01

    The methodological framework of the level 2 PSA appears to be currently standardized in a formalized fashion, but there have been different opinions on the way the sources of uncertainty are characterized and treated. This is primarily because the level 2 PSA deals with complex phenomenological processes that are deterministic in nature rather than random processes, and there are no probabilistic models characterizing them clearly. As a result, the probabilistic quantification of the level 2 PSA CET/APET is often subjected to two sources of uncertainty: (a) incomplete modeling of accident pathways or different predictions for the behavior of phenomenological events and (b) expert-to-expert variation in estimating the occurrence probability of phenomenological events. While a clear definition of the two sources of uncertainty involved in the level 2 PSA makes it possible to treat an uncertainty in a consistent manner, careless application of these different sources of uncertainty may produce different conclusions in the decision-making process. The primary purpose of this paper is to characterize typical sources of uncertainty that would often be addressed in the level 2 PSA and to provide a formal guidance for quantifying their impacts on the PSA level 2 risk results. An additional purpose of this paper is to give a formal approach on how to combine random uncertainties addressed in the level 1 PSA with subjectivistic uncertainties addressed in the level 2 PSA

  19. utility of prostate specific antigen (psa) in the indigenous african man

    African Journals Online (AJOL)

    the standard PSA reference levels generated in non-African study subjects. Design: A ... the best use of PSA in the indigenous black African man but also his place in the new ... tendency as well as measures of dispersion. Inferential statistics assumed a 95% confidence interval and .... men: Results from a pilot study.

  20. Excess cases of prostate cancer and estimated overdiagnosis associated with PSA testing in East Anglia

    Science.gov (United States)

    Pashayan, N; Powles, J; Brown, C; Duffy, S W

    2006-01-01

    This study aimed to estimate the extent of ‘overdiagnosis' of prostate cancer attributable to prostate-specific antigen (PSA) testing in the Cambridge area between 1996 and 2002. Overdiagnosis was defined conceptually as detection of prostate cancer through PSA testing that otherwise would not have been diagnosed within the patient's lifetime. Records of PSA tests in Addenbrookes Hospital were linked to prostate cancer registrations by NHS number. Differences in prostate cancer registration rates between those receiving and not receiving prediagnosis PSA tests were calculated. The proportion of men aged 40 years or over with a prediagnosis PSA test increased from 1.4 to 5.2% from 1996 to 2002. The rate of diagnosis of prostate cancer was 45% higher (rate ratios (RR)=1.45, 95% confidence intervals (CI) 1.02–2.07) in men with a history of prediagnosis PSA testing. Assuming average lead times of 5 to 10 years, 40–64% of the PSA-detected cases were estimated to be overdiagnosed. In East Anglia, from 1996 to 2000, a 1.6% excess of cases was associated with PSA testing (around a quarter of the 5.3% excess incidence cases observed in East Anglia from 1996 to 2000). Further quantification of the overdiagnosis will result from continued surveillance and from linkage of incidence to testing in other hospitals. PMID:16832417

  1. [Clinical evaluation of TANDEM PSA in Japanese cases and comparison with other methods].

    Science.gov (United States)

    Kuriyama, M; Yamamoto, N; Shinoda, I; Kawada, Y; Akimoto, S; Shimazaki, J

    1995-01-01

    Clinical evaluation of TANDEM PSA which is the most frequently used prostate specific antigen (PSA) assay method in the world and a comparison with other methods were performed in Japanese cases in a cooperative research fashion. The minimum detectable level of the method was found to be 0.50 ng of PSA in one ml of serum and 1.9 ng/ml was regarded as the upper normal value in Japanese males. The distribution of serum PSA showed a significant difference between the benign prostate hypertrophy (BPH) cases and patients with stage C or D prostate cancer. The sero-diagnosis prostate cancer at an early stage with the TANDEM PSA was difficult. The correlation to other methods of PSA detection was very high. Furthermore, the clinical use of the method in following-up the clinical course of prostate cancer patients was very useful. These findings suggested that the PSA detection using TANDEM PSA is applicable even in Japanese cases although the upper cut-off level is decreased.

  2. PSA in licensing, safety reviews and design as applied in Germany

    International Nuclear Information System (INIS)

    Berg, H.P.; Goertz, R.; Schott, H.; Wendling, R.D.

    1994-01-01

    In this paper, two topics - the application of PSA in the regulatory process and the effort to improve PSA methods and models - are addressed. From the regulators' point of view, the most important application of PSA in Germany is presently within the safety reviews of nuclear power plants in operation. The current status of regulatory guidance which shall be provided to establish a uniform procedure for a periodic safety review is described with special emphasis on the role of PSA. An important goal is to have all plant-specific PSAs comparable as far as possible. Guidance for PSA review is under development likewise. Furthermore, the application of PSA in licensing of nuclear power plants is addressed as well as its use in the design process of future pressurized water reactors. The development of models and methods to be applied in PSA has been and will be supported by a number of studies and investigations. An overview of the main issues of these investigations is provided. A specific task was the elaboration of a proposal for incorporating fire events into the PSA. The status of these efforts is outlined. (author). 7 refs, 3 figs, 2 tabs

  3. Human actions treatment in the Juragua NPP pre-operational PSA

    International Nuclear Information System (INIS)

    Ferro Fernandez, R.

    1996-01-01

    The human reliability analysis is an important part of the Probabilistic Safety Analysis (PSA). Because Juragua NPP PSA has been accomplished during construction stage of the plant, no specific operational procedures nor experience for human reliability analysis task taking into account the worlds current methodologies in this field and the actual situation of the plant. This papers describes the approach we followed

  4. PSA-Based Screening Outcomes, Dietary Heterocyclic Amine Exposure, and Prostate Cancer Risk in African-Americans

    National Research Council Canada - National Science Library

    Bogen, Kenneth

    2006-01-01

    ... as more abnormal results from screening tests that correlate with current or eventual PC. A 3-year prospective clinic-based study is studying the performance of current (PSA and DRE) vs. (% free PSA...

  5. The clinical value of serum PSA and PAP determinations in prostate cancer patients

    International Nuclear Information System (INIS)

    Zeng Lei; Yu Renbo; Du Guowei; Pang Baozhong

    2001-01-01

    Objective: To investigate the clinical value of serum PSA and PAP determinations in diagnosis of prostate cancer patients. Methods: The serum PSA and PAP levels of 98 prostate cancer patients, 45 prostate benign disease patients and 40 normal subjects were tested by IRMA. Results: The serum PSA and PAP levels of prostate cancer patients were significantly higher than those in prostate benign disease patients and normal controls (P < 0.01). The diagnostic sensitivity and specificity of serum PSA for prostate cancer were 93.9% and 93.3% respectively. The diagnostic sensitivity and specificity of serum PAP for prostate cancer were 71.4% and 91.1% respectively. Conclusion: The determination of serum PSA and PAP was of high clinical value for diagnosis of early prostate cancer. It could be used as an important reference parameter for the clinical staging, follow-up of treatment result and prediction of prognosis

  6. Approach to development and use of PSA Level 2 analysis for the Cernavoda nuclear power plant

    International Nuclear Information System (INIS)

    Turcu, I.; Deaconu, R.; Radu, G.

    1998-01-01

    This paper first describes the status of PSA activities for the Cernavoda NPP and the extension of the PSA work to include Level 2 PSA. Important characteristics of this reactor type for Level 2 PSA are outlined. Due to the specific layout of the CANDU reactor the evolution of severe accidents is considerably different to vessel type LWRs. Accidents can be roughly categorized into three categories, ''''severe accidents'''' which lead to the loss of core structural integrity, delayed loss of core structural integrity as a consequence of the loss of heat sinks, and fuel channel failures. The current work for modelling accident progression in the core region is described. The elements for the Level 2 PSA including definition of PDSs, probabilistic containment logic and source term calculation are outlined. It is pointed out that uncertainties have to be considered which are contained in the models to bridge knowledge gaps. For this purpose sensitivity studies will be carried out for key modelling assumptions. (author)

  7. EOP Improvement Proposal for SGTR based on The OPR PSA Update

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jin Hee; Cho, Jae Hyun; Kim, Dong San; Yang, Joon Eon [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    This updating process was also focused to enhance the PSA quality and to respect the as built and as operated conditions of target plants. For this purpose, the EOP(Emergency Operating Procedure) and AOP(Abnormal Operating Procedure) of target plant were reviewed in detail and various thermal hydraulic(T/H) analysis were also performed to analyze the realistic PSA accident sequence model. In this paper, the unreasonable point of SGTR (Steam Generator Tube Rupture) EOP based on PSA perspective was identified and the initial proposal for EOP change items from PSA insight was proposed. In this paper, the unreasonable point of SGTR EOP based on PSA perspective was identified and the EOP improvement items are proposed to enhance safety and operator's convenience for the target plant.

  8. Sensitivity Studies on Revised PSA Model of KHNP Nuclear Power Plants

    International Nuclear Information System (INIS)

    Lee, Hyun-Gyo; Hwang, Seok-Won; Shin, Tae-Young

    2016-01-01

    Korea also performed safety revaluation for all nuclear power plants led by Korean regulatory and elicited 49 improvement factor for plants. One of those factors is Severe Accident Management Guidelines (SAMG) development, KHNP decided to develop Low Power and Shutdown(LPSD) Probabilistic Safety Assessment (PSA) models and upgrade full power PSA models of all operating plants for enhancement of guideline quality. In this paper we discuss about the effectiveness of post Fukushima equipment and improvements of each plant based on the results of revised full power PSA and newly developed LPSD PSA. Through sensitivity analysis based on revised PSA models we confirmed that the facilities installed or planned to installation as follow-up measures of Fukushima accident helped to enhance the safety of nuclear power plants. These results will provide various technical insights to scheduled studies which evaluate effectiveness of Fukushima post action items and develop accident management guideline. Also it will contribute to improve nuclear power plants safety

  9. Thermal-Hydraulic Analysis for SBLOCA in OPR1000 and Evaluation of Uncertainty for PSA

    International Nuclear Information System (INIS)

    Kim, Tae Jin; Park, Goon Cherl

    2012-01-01

    Probabilistic Safety assessment (PSA) is a mathematical tool to evaluate numerical estimates of risk for nuclear power plants (NPPs). But PSA has the problems about quality and reliability since the quantification of uncertainties from thermal hydraulic (TH) analysis has not been included in the quantification of overall uncertainties in PSA. From the former research, it is proved that the quantification of uncertainties from best-estimate LBLOCA analysis can improve the PSA quality by modifying the core damage frequency (CDF) from the existing PSA report. Basing on the similar concept, this study considers the quantification of SBLOCA analysis results. In this study, however, operator error parameters are also included in addition to the phenomenon parameters which are considered in LBLOCA analysis

  10. Development of high purity CO gas recovery system for BOF gas by modified PSA process

    Energy Technology Data Exchange (ETDEWEB)

    Sakuraya, Toshikazu; Fujii, Tetsuya; Yaji, Motoyasu; Matsuki, Takao; Matsui, Shigeo; Hayashi, Shigeki

    1985-01-01

    COPISA process (where two processes for separating CO-adsorptive gases and desorbing desorption-difficult gas are added to conventional PSA gas separation process) is outlined. In two units of PSA, CO/sub 2/ gas is adsorbed and separated in first PSA unit. The gas excluding CO/sub 2/ is fed to second PSA unit, where CO is adsorbed and separated from N/sub 2/ and H/sub 2/, and then desorbed and recovered under reduced pressure. For optimizing the process, a pilot plant was operated for about 1000 hrs. in a half year. The results confirm possibility of simplifying pre-treatment of coal gas. CO-PSA pressure swing pattern suitable for elimination of Co-adsorptive N/sub 2/ is established. Recovery of CO gas is enhanced. Optimization of gas flow pattern between adsorption towers required for reduction in operating cost is performed. (7 figs, 1 tab, 8 refs)

  11. Sensitivity Studies on Revised PSA Model of KHNP Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hyun-Gyo; Hwang, Seok-Won; Shin, Tae-Young [KHNP, Daejeon (Korea, Republic of)

    2016-10-15

    Korea also performed safety revaluation for all nuclear power plants led by Korean regulatory and elicited 49 improvement factor for plants. One of those factors is Severe Accident Management Guidelines (SAMG) development, KHNP decided to develop Low Power and Shutdown(LPSD) Probabilistic Safety Assessment (PSA) models and upgrade full power PSA models of all operating plants for enhancement of guideline quality. In this paper we discuss about the effectiveness of post Fukushima equipment and improvements of each plant based on the results of revised full power PSA and newly developed LPSD PSA. Through sensitivity analysis based on revised PSA models we confirmed that the facilities installed or planned to installation as follow-up measures of Fukushima accident helped to enhance the safety of nuclear power plants. These results will provide various technical insights to scheduled studies which evaluate effectiveness of Fukushima post action items and develop accident management guideline. Also it will contribute to improve nuclear power plants safety.

  12. The relation of serum PSA and Gleason's grade in patients with prostacic carcinoma

    Directory of Open Access Journals (Sweden)

    Živković Slađana

    2003-01-01

    Full Text Available The prostatic adenocarcinoma is one of the most frequent malignant tumors of men over 50 years of age. It is distinguished by agressive clinical course and heterogeneous multifocal hystomorphologic changes. PSA is the most reliable serum marker in diagnostics and observation of prostatic carcinoma and gleason's system of tumor-diferentiation grading is generally accepted way of determining the hystologic grade. Gleason's system is correlated with serum levels of PSA and with biological behaviour of the tumor. We presented 40 patients with verified ACP in whom the level of serum PSA, gleason's grade and score were compared. Highly significant correlation was found between serum level of PSA and the differentation grade of the tumor - Gleason's grade and score. Combination of PSA parameters and Gleason's score enables correct estimation of tumor's behaviour and correct therapeutic protocole.

  13. Level 1 PSA study of Mochovce unit 1 NPP (SM AA 10 and 08)

    International Nuclear Information System (INIS)

    Cillik, I.

    1997-01-01

    This paper presents genesis of Level 1 PSA project preparation for all operational modes of Mochovce NPP unit 1 including the description of its' main objectives, scope and working method. The PSA study which includes full power (FPSA) as well as shutdown and low power conditions (SPSA) Level 1 PSA has to support the nuclear safety improvements of the unit. They evaluate the basic design and the benefits of all improvements, which were found necessary to be incorporated before the start-up of the unit. The study includes internal events (transients and under-loss of coolant accident, LOCAs), internal hazards as fires and floods and selected external hazards as earthquake, influence of external industry, extreme meteorological conditions and aircraft crash.The PSA (both FPSA and SPSA) models is developed using the RISK SPECTRUM PSA code. (author)

  14. Prostate-Specific Antigen 5 Years following Stereotactic Body Radiation Therapy for Low- and Intermediate-Risk Prostate Cancer: An Ablative Procedure?

    Directory of Open Access Journals (Sweden)

    Shaan Kataria

    2017-07-01

    Full Text Available BackgroundOur previous work on early PSA kinetics following prostate stereotactic body radiation therapy (SBRT demonstrated that an initial rapid and then slow PSA decline may result in very low PSA nadirs. This retrospective study sought to evaluate the PSA nadir 5 years following SBRT for low- and intermediate-risk prostate cancer (PCa.Methods65 low- and 80 intermediate-risk PCa patients were treated definitively with SBRT to 35–37.5 Gy in 5 fractions at Georgetown University Hospital between January 2008 and October 2011. Patients who received androgen deprivation therapy were excluded from this study. Biochemical relapse was defined as a PSA rise >2 ng/ml above the nadir and analyzed using the Kaplan–Meier method. The PSA nadir was defined as the lowest PSA value prior to biochemical relapse or as the lowest value recorded during follow-up. Prostate ablation was defined as a PSA nadir <0.2 ng/ml. Univariate logistic regression analysis was used to evaluate relevant variables on the likelihood of achieving a PSA nadir <0.2 ng/ml.ResultsThe median age at the start of SBRT was 72 years. These patients had a median prostate volume of 36 cc with a median 25% of total cores involved. At a median follow-up of 5.6 years, 86 and 37% of patients achieved a PSA nadir ≤0.5 and <0.2 ng/ml, respectively. The median time to PSA nadir was 36 months. Two low and seven intermediate risk patients experienced a biochemical relapse. Regardless of the PSA outcome, the median PSA nadir for all patients was 0.2 ng/ml. The 5-year biochemical relapse free survival (bRFS rate for low- and intermediate-risk patients was 98.5 and 95%, respectively. Initial PSA (p = 0.024 and a lower testosterone at the time of the PSA nadir (p = 0.049 were found to be significant predictors of achieving a PSA nadir <0.2 ng/ml.ConclusionSBRT for low- and intermediate-risk PCa is a convenient treatment option with low PSA nadirs and a high rate of

  15. Review process of PSA level 2 of KBR - Concept and Experience

    International Nuclear Information System (INIS)

    Andernacht, M.; Glaser, H.; Sonnenkalb, M.

    2013-01-01

    In Germany, a periodic safety review (PSR) has to be performed every ten years by the utility. In the past, a PSR only included a plant-specific probabilistic safety analysis (PSA) Level 1 study. Since a revised version of the German PSA guideline has been released in 2005, these plant-specific PSAs have to include a PSA Level 2, too. For the NPP Brokdorf (KBR) PSA Level 2 project, an agreement was reached between all parties involved that the study will be performed not as a part of the PSR process, but supplementary to it. This paper will focus on conclusions and findings from an ongoing parallel review process of the first full scope PSA Level 2 performed by the utility for KBR, a typical German PWR-1300. The responsible authority 'Ministerium fuer Soziales, Gesundheit, Familie, Jugend und Senioren des Landes Schleswig- Holstein' (MSGF) initiated this parallel review process in agreement with the utility KBR and the E.ON Kernkraft in 2006. The project will be completed soon. Such a review process allows that essential steps of the PSA will be reviewed and commented before the PSA Level 2 will be finished. So the benefit from this parallel review process is a significant enhancement of the quality and completeness of the PSA Level 2 study as the majority of the recommendations given by the review team has been taken over by the utility and the developer of the PSA, the AREVA NP company. Further, a common understanding and agreement will be reached at the end between all parties involved on the major topics of the PSA Level 2 study. The paper is followed by the slides of the presentation. (authors)

  16. Review process of PSA Level 2 of KBR. Concept and experience

    International Nuclear Information System (INIS)

    Andernacht, Martin; Glaser, Hendrik; Sonnenkalb, Martin

    2009-01-01

    In Germany, a periodic safety review (PSR) has to be performed every 10 years by the utility. In the past, a PSR only included a plant-specific probabilistic safety analysis (PSA) Level 1 study. For the NPP Brokdorf (KBR) PSA Level 2 project, an agreement was reached between all parties involved that the study will be performed not as a part of the PSR process, but supplementary to it. Since a revised version of the German PSA guideline has been released in 2005, these plant-specific PSAs have to include a PSA Level 2, too. This paper will focus on conclusions and findings from a ongoing parallel review process of the first full scope PSA Level 2 performed by the utility for KBR, a typical German PWR-1300. The responsible authority 'Ministerium fuer Soziales, Gesundheit, Familie, Jugend und Senioren des Landes Schleswig-Holstein (MSGF)' (Ministry of Social Affairs, Health, Family, Youth and Senior Citizens of Schleswig-Holstein) initiated this parallel review process in agreement with the utility KBR and the E.ON Kernkraft in 2006. The project will be completed soon. Such a review process allows that essential steps of the PSA will be reviewed and commented before the PSA Level 2 will be finished. So the benefit from this parallel review process is a significant enhancement of the quality and completeness of the PSA Level 2 study as the majority of the recommendations given by the review team has been taken over by the utility and the developer of the PSA, the Areva NP company. Further, a common understanding and agreement will be reached at the end between all parties involved on the major topics of the PSA Level 2 study. (orig.)

  17. Automatic fault tree generation in the EPR PSA project

    International Nuclear Information System (INIS)

    Villatte, N; Nonclercq, P.; Taupy, S.

    2012-01-01

    Tools (KB3 and Atelier EPS) have been developed at EDF to assist the analysts in building fault trees for PSA (Probabilistic Safety Assessment) and importing them into RiskSpectrum (RiskSpectrum is a Swedish code used at EDF for PSA). System modelling is performed using KB3 software with a knowledge base describing generic classes of components with their behaviour and failure modes. Using these classes of components, the analyst can describe (using a graphical system editor): a simplified system diagram from the mechanical system drawings and functional descriptions, the missions of the studied system (in a form of high level fault trees) and its different configurations for the missions. He can also add specific knowledge about the system. Then, the analyst chooses missions and configurations to specify and launch fault trees generations. From the system description, KB3 produces by backward-chaining on rules, detailed system fault trees. These fault trees are finally imported into RiskSpectrum (they are converted by Atelier EPS into a format readable by RiskSpectrum). KB3 and Atelier EPS have been used to create the majority of the fault trees for the EDF EPR Probabilistic Safety Analysis conducted from November 2009 to March 2010. 25 systems were modelled, and 127 fault trees were automatically generated in a rather short time by different analysts with the help of these tools. A feedback shows a lot of advantages to use KB3 and Atelier EPS: homogeneity and consistency between the different generated fault trees, traceability of modelling, control of modelling and last but not least: the automation of detailed fault tree creation relieves the human analyst of this tedious task so that he can focus his attention on more important tasks: modelling the failure of a function. This industrial application has also helped us gather an interesting feedback from the analysts that should help us improve the handling of the tools. We propose in this paper indeed some

  18. The value of multimodality imaging in the investigation of a PSA recurrence after radical prostatectomy in the Irish hospital setting.

    Science.gov (United States)

    McLoughlin, L C; Inder, S; Moran, D; O'Rourke, C; Manecksha, R P; Lynch, T H

    2018-02-01

    The diagnostic evaluation of a PSA recurrence after RP in the Irish hospital setting involves multimodality imaging with MRI, CT, and bone scanning, despite the low diagnostic yield from imaging at low PSA levels. We aim to investigate the value of multimodality imaging in PC patients after RP with a PSA recurrence. Forty-eight patients with a PSA recurrence after RP who underwent multimodality imaging were evaluated. Demographic data, postoperative PSA levels, and imaging studies performed at those levels were evaluated. Eight (21%) MRIs, 6 (33%) CTs, and 4 (9%) bone scans had PCa-specific findings. Three (12%) patients had a positive MRI with a PSA PSA ≥1.1 ng/ml (p = 0.05). Zero patient had a positive CT TAP at a PSA level PSA levels PSA levels PSA levels ≥1.1 ng/ml. MRI alone is of investigative value at PSA <1.0 ng/ml. The indication for CT, MRI, or isotope bone scanning should be carefully correlated with the clinical question and how it will affect further management.

  19. Post treatment PSA nadirs support continuing dose escalation study in patients with pretreatment PSA levels >10 ng/ml, but not in those with PSA <10 NG/ML

    International Nuclear Information System (INIS)

    Herold, D.H.; Hanlon, A.L.; Movsas, B.; Hanks, G.E.

    1996-01-01

    Purpose: We have recently shown that ICRU reporting point radiation doses above 71 Gy are not associated with improved bNED survival in prostate cancer patients with pretreatment PSA level 20 ng/ml we found a strong correlation between dose and nadir values < 1.0 ng/ml (p=.003) as well as for nadir's < 0.5 ng/ml (p=.04). This dose/nadir effect held at several dose levels, but 74 Gy for nadir values < 1.0 ng/ml and 72 Gy for nadir's < 0.5 ng/ml remained the most significant. 32% of these patients achieved a nadir < 1.0ng/ml and 15% < 0.5ng/ml. Conclusions: This analysis provides strong additional support that patients with pretreatment PSA values of < 10 ng/ml do not benefit from dose escalation beyond an ICRU reporting point dose of 71 Gy. For patients with pretreatment PSA's of 10-19.9 ng/ml there is no dose/nadir response evaluated at a nadir of 1.0 ng/ml; however, there is a borderline effect observed at a nadir of 0.5 ng/ml. Patients with pretreatment PSA's of 20 ng/ml or greater clearly benefit from higher doses as evaluated by PSA nadirs of 1.0 ng/ml, and 0.5 ng/ml. These studies support the continued investigation of dose escalation in treating patients with PSA levels over 10 ng/ml, they do not support continued investigation of dose escalation beyond 71 Gy in patients with pretreatment PSA levels < 10 ng/ml. The failure to demonstrate any dose response for the low PSA group and the finding of only a borderline effect for the intermediate PSA group may be influenced by the relatively small number of patients in our series treated to doses < 70 Gy and the fact that none of our patients were treated to doses below 65.98 Gy. The lower limit of acceptible dose has yet to be defined

  20. A national multicenter phase 2 study of prostate-specific antigen (PSA) pox virus vaccine with sequential androgen ablation therapy in patients with PSA progression: ECOG 9802.

    Science.gov (United States)

    DiPaola, Robert S; Chen, Yu-Hui; Bubley, Glenn J; Stein, Mark N; Hahn, Noah M; Carducci, Michael A; Lattime, Edmund C; Gulley, James L; Arlen, Philip M; Butterfield, Lisa H; Wilding, George

    2015-09-01

    E9802 was a phase 2 multi-institution study conducted to evaluate the safety and effectiveness of vaccinia and fowlpox prostate-specific antigen (PSA) vaccine (step 1) followed by combination with androgen ablation therapy (step 2) in patients with PSA progression without visible metastasis. To test the hypothesis that vaccine therapy in this early disease setting will be safe and have a biochemical effect that would support future studies of immunotherapy in patients with minimal disease burden. Patients who had PSA progression following local therapy were treated with PROSTVAC-V (vaccinia)/TRICOM on cycle 1 followed by PROSTVAC-F (fowlpox)/TRICOM for subsequent cycles in combination with granulocyte-macrophage colony-stimulating factor (step 1). Androgen ablation was added on progression (step 2). Step 1 primary end points included progression at 6 mo and characterization of change in PSA velocity pretreatment to post-treatment. Step 2 end points included PSA response with combined vaccine and androgen ablation. In step 1, 25 of 40 eligible patients (63%) were progression free at 6 mo after registration (90% confidence interval [CI], 48-75). The median pretreatment PSA velocity was 0.13 log(PSA)/mo, in contrast to median postregistration velocity of 0.09 log(PSA)/mo (p=0.02), which is an increase in median PSA doubling time from 5.3 mo to 7.7 mo. No grade ≥4 treatment-related toxicity was observed. In the 27 patients eligible and treated for step 2, 20 patients achieved a complete response (CR) at 7 mo (CR rate: 74%; 90% CI, 57-87). Although supportive of larger studies in the cooperative group setting, this study is limited by the small number of patients and the absence of a control group as in a phase 3 study. A viral PSA vaccine can be administered safely in the multi-institutional cooperative group setting to patients with minimal disease volume alone and combined with androgen ablation, supporting the feasibility of future phase 3 studies in this

  1. Ringhals 1 PSA - Evaluation of safety raising measures

    International Nuclear Information System (INIS)

    Hellstroem, P.; Enerholm, A.; Holmgren, P.

    1995-09-01

    A PSA-study of the BWR-reactor has been evaluated, and the following comments are made: The objectives of the study have been reached, but an overview is lacking. Means for verifying the functional demands at primary events should have a very high priority. A deeper analysis is needed to verify that overpressurizing and overfilling not cause HS. The analysis should include a report on dynamic effects at a LOCA. The level of detail in modelling functional dependencies should be increased. The low probabilities for faults caused by the operating personnel should be explained and possible defaults in instructions etc. documented. The results of the study should be analyzed deeper in comparison with other studies. Suggestions for improvement of the plant and priorities for these are missing. The documentation should be improved

  2. ``Losing the Dark:'' A Planetarium PSA about Light Pollution

    Science.gov (United States)

    Productions, L. N.; Walker, D. C.

    2013-04-01

    Losing the Dark is a PSA video being created for fulldome theaters by Loch Ness Productions under the direction of the International Dark Sky Association Education Committee headed by Dr. Constance Walker of the National Optical Astronomy Observatories. It explains the problems with light pollution, its effects on life, and three ways in which people can implement “wise lighting” practices to mitigate light pollution. The show is also being produced in a flat-screen HD format for use in classical planetarium and non-dome theaters, for presentations by IDA speakers when addressing planning boards, etc. and will be posted on the IDA and other web sites. The final length is six minutes for both versions. Funding has been provided by The International Planetarium Society and the International Dark-Sky Association.

  3. Hybrid membrane--PSA system for separating oxygen from air

    Science.gov (United States)

    Staiger, Chad L [Albuquerque, NM; Vaughn, Mark R [Albuquerque, NM; Miller, A Keith [Albuquerque, NM; Cornelius, Christopher J [Blackburg, VA

    2011-01-25

    A portable, non-cryogenic, oxygen generation system capable of delivering oxygen gas at purities greater than 98% and flow rates of 15 L/min or more is described. The system consists of two major components. The first component is a high efficiency membrane capable of separating argon and a portion of the nitrogen content from air, yielding an oxygen-enriched permeate flow. This is then fed to the second component, a pressure swing adsorption (PSA) unit utilizing a commercially available, but specifically formulated zeolite compound to remove the remainder of the nitrogen from the flow. The system is a unique gas separation system that can operate at ambient temperatures, for producing high purity oxygen for various applications (medical, refining, chemical production, enhanced combustion, fuel cells, etc . . . ) and represents a significant advance compared to current technologies.

  4. Flooding risk reduction for the ASCO NPP PSA

    International Nuclear Information System (INIS)

    Nos Llorens, V.; Faig Sureda, J.

    1993-01-01

    Developed within the framework of the UTE (INITEC-INYPSA-Empresarios Agrupados), the Probabilistic Safety Analysis (PSA) of the Asco Nuclear Power Plant has served both as a basic tool in reducing the risk of potential internal flooding at the plant, and as a guideline for studying the optimization and feasibility of necessary plant design modifications and changes to procedures. During execution of the work, and in view of the results, a series of improvements were proposed which gave rise to design modification studies. The paper seeks to describe the effect of these modifications on reducing core damage frequency, it also includes a general description of the methodology used. Finally, it compares the results obtained in the context of similar studies performed in other PSAs. (author)

  5. Ash cloud aviation advisories

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan, T.J.; Ellis, J.S. [Lawrence Livermore National Lab., CA (United States); Schalk, W.W.; Nasstrom, J.S. [EG and G, Inc., Pleasanton, CA (United States)

    1992-06-25

    During the recent (12--22 June 1991) Mount Pinatubo volcano eruptions, the US Air Force Global Weather Central (AFGWC) requested assistance of the US Department of Energy`s Atmospheric Release Advisory Capability (ARAC) in creating volcanic ash cloud aviation advisories for the region of the Philippine Islands. Through application of its three-dimensional material transport and diffusion models using AFGWC meteorological analysis and forecast wind fields ARAC developed extensive analysis and 12-hourly forecast ash cloud position advisories extending to 48 hours for a period of five days. The advisories consisted of ``relative`` ash cloud concentrations in ten layers (surface-5,000 feet, 5,000--10,000 feet and every 10,000 feet to 90,000 feet). The ash was represented as a log-normal size distribution of 10--200 {mu}m diameter solid particles. Size-dependent ``ashfall`` was simulated over time as the eruption clouds dispersed. Except for an internal experimental attempt to model one of the Mount Redoubt, Alaska, eruptions (12/89), ARAC had no prior experience in modeling volcanic eruption ash hazards. For the cataclysmic eruption of 15--16 June, the complex three-dimensional atmospheric structure of the region produced dramatically divergent ash cloud patterns. The large eruptions (> 7--10 km) produced ash plume clouds with strong westward transport over the South China Sea, Southeast Asia, India and beyond. The low-level eruptions (< 7 km) and quasi-steady-state venting produced a plume which generally dispersed to the north and east throughout the support period. Modeling the sequence of eruptions presented a unique challenge. Although the initial approach proved viable, further refinement is necessary and possible. A distinct need exists to quantify eruptions consistently such that ``relative`` ash concentrations relate to specific aviation hazard categories.

  6. Atmospheric release advisory capability

    International Nuclear Information System (INIS)

    Sullivan, T.J.

    1981-01-01

    The ARAC system (Atmospheric Release Advisory Capability) is described. The system is a collection of people, computers, computer models, topographic data and meteorological input data that together permits a calculation of, in a quasi-predictive sense, where effluent from an accident will migrate through the atmosphere, where it will be deposited on the ground, and what instantaneous and integrated dose an exposed individual would receive

  7. Outcomes after radical prostatectomy in the PSA era

    International Nuclear Information System (INIS)

    Scardino, Peter T.

    1996-01-01

    This year 317,000 men will be diagnosed with prostate cancer and 41,400 will die of this disease. Prostate cancer will kill nearly 1 million men alive today who are now over 50 years old. Since the mortality rate from prostate cancer increases more rapidly with age than any other cancer, and the most rapidly growing segment of the population is those > 80 years old, and mortality from other causes is declining, the number of deaths from prostate cancer is expected to increase inexorably for many years. Among the clinical prognostic factors that have been established as important predictors of the natural history of prostate cancer in conservatively treated patients, none is more important than the grade of the tumor. A similar influence of grade has been reported in patients treated surgically. At Baylor we assessed a variety of clinical prognostic factors in 728 men treated with radical prostatectomy and followed with serial PSA levels with no other therapy before proven recurrence of the cancer. While a variety of factors were significant in univariate analyses, in multivariate analysis only grade and serum PSA levels were significant clinical prognostic factors. Once the prostate was removed and pathologic information was available, however, pathologic stage became the most important factor (especially seminal vesicle or lymph node involvement), but Gleason grade was also a powerful independent factor. Surgical margin status and the presence of extracapsular extension were also independent predictors of recurrence, but total tumor volume added little additional information. Once the pathological information is available, none of the prognostic factors known before the operation, including PSA, PSA density, and clinical, have any independent power to predict prognosis. While radical prostatectomy may carry greater risk of complications than radiotherapy, its major advantage is the high probability that the cancer can be completely eradicated, especially if it is

  8. Improvement of Level-1 PSA computer code package -A study for nuclear safety improvement-

    International Nuclear Information System (INIS)

    Park, Chang Kyu; Kim, Tae Woon; Ha, Jae Joo; Han, Sang Hoon; Cho, Yeong Kyun; Jeong, Won Dae; Jang, Seung Cheol; Choi, Young; Seong, Tae Yong; Kang, Dae Il; Hwang, Mi Jeong; Choi, Seon Yeong; An, Kwang Il

    1994-07-01

    This year is the second year of the Government-sponsored Mid- and Long-Term Nuclear Power Technology Development Project. The scope of this subproject titled on 'The Improvement of Level-1 PSA Computer Codes' is divided into three main activities : (1) Methodology development on the under-developed fields such as risk assessment technology for plant shutdown and external events, (2) Computer code package development for Level-1 PSA, (3) Applications of new technologies to reactor safety assessment. At first, in the area of PSA methodology development, foreign PSA reports on shutdown and external events have been reviewed and various PSA methodologies have been compared. Level-1 PSA code KIRAP and CCF analysis code COCOA are converted from KOS to Windows. Human reliability database has been also established in this year. In the area of new technology applications, fuzzy set theory and entropy theory are used to estimate component life and to develop a new measure of uncertainty importance. Finally, in the field of application study of PSA technique to reactor regulation, a strategic study to develop a dynamic risk management tool PEPSI and the determination of inspection and test priority of motor operated valves based on risk importance worths have been studied. (Author)

  9. Development of the fire PSA methodology and the fire analysis computer code system

    International Nuclear Information System (INIS)

    Katsunori, Ogura; Tomomichi, Ito; Tsuyoshi, Uchida; Yusuke, Kasagawa

    2009-01-01

    Fire PSA methodology has been developed and was applied to NPPs in Japan for power operation and LPSD states. CDFs of preliminary fire PSA for power operation were the higher than that of internal events. Fire propagation analysis code system (CFAST/FDS Network) was being developed and verified thru OECD-PRISME Project. Extension of the scope for LPSD state is planned to figure out the risk level. In order to figure out the fire risk level precisely, the enhancement of the methodology is planned. Verification and validation of phenomenological fire propagation analysis code (CFAST/FDS Network) in the context of Fire PSA. Enhancement of the methodology such as an application of 'Electric Circuit Analysis' in NUREG/CR-6850 and related tests in order to quantify the hot-short effect precisely. Development of seismic-induced fire PSA method being integration of existing seismic PSA and fire PSA methods is ongoing. Fire PSA will be applied to review the validity of fire prevention and mitigation measures

  10. Methodologies for uncertainty analysis in the level 2 PSA and their implementation procedures

    International Nuclear Information System (INIS)

    Ahn, Kwang Il; Yang, Joon Eun; Kim, Dong Ha

    2002-04-01

    Main purpose of this report to present standardized methodologies for uncertainty analysis in the Level 2 Probabilistic Safety Assessment (PSA) and their implementation procedures, based on results obtained through a critical review of the existing methodologies for the analysis of uncertainties employed in the Level 2 PSA, especially Accident Progression Event Tree (APET). Uncertainties employed in the Level 2 PSA, quantitative expressions of overall knowledge of analysts' and experts' participating in the probabilistic quantification process of phenomenological accident progressions ranging from core melt to containment failure, their numerical values are directly related to the degree of confidence that the analyst has that a given phenomenological event or accident process will or will not occur, or analyst's subjective probabilities of occurrence. These results that are obtained from Level 2 PSA uncertainty analysis, become an essential contributor to the plant risk, in addition to the Level 1 PSA and Level 3 PSA uncertainties. Uncertainty analysis methodologies and their implementation procedures presented in this report was prepared based on the following criteria: 'uncertainty quantification process must be logical, scrutable, complete, consistent and in an appropriate level of detail, as mandated by the Level 2 PSA objectives'. For the aforementioned purpose, this report deals mainly with (1) summary of general or Level 2 PSA specific uncertainty analysis methodologies, (2) selection of phenomenological branch events for uncertainty analysis in the APET, methodology for quantification of APET uncertainty inputs and its implementation procedure, (3) statistical propagation of uncertainty inputs through APET and its implementation procedure, and (4) formal procedure for quantification of APET uncertainties and source term categories (STCs) through the Level 2 PSA quantification codes

  11. PSA doubling time of prostate carcinoma managed with watchful observation alone

    International Nuclear Information System (INIS)

    Choo, Richard; DeBoer, Gerrit; Klotz, Lawrence; Danjoux, Cyril; Morton, Gerard C.; Rakovitch, Eileen; Fleshner, Neil; Bunting, Peter; Kapusta, Linda; Hruby, George

    2001-01-01

    Purpose: To study prostate-specific antigen (PSA) doubling time of untreated, favorable grade, prostate carcinoma. Methods and Materials: A prospective single-arm cohort study has been in progress to assess the feasibility of a watchful observation protocol with selective delayed intervention using clinical, histologic, or PSA progression as treatment indication in untreated, localized, favorable grade prostate adenocarcinoma (T1b-T2bN0 M0, Gleason Score ≤7, and PSA ≤15 ng/mL). Patients are conservatively managed with watchful observation alone, as long as they do not meet the arbitrarily defined disease progression criteria. Patients are followed regularly and undergo blood tests including PSA at each visit. PSA doubling time (Td) is estimated from a linear regression of ln(PSA) on time, assuming a simple exponential growth model. Results: As of March 2000, 134 patients have been on the study for a minimum of 12 months (median, 24; range, 12-52) and have a median frequency of PSA measurement of 7 times (range, 3-15). Median age is 70 years. Median PSA at enrollment is 6.3 (range, 0.5-14.6). The distribution of Td is as follows: 50 years, 27. The median Td is 5.1 years. In 44 patients (33%), Td is greater than 10 years. There was no correlation between Td and patient age, clinical T stage, Gleason score, or initial PSA level. Conclusion: Td of untreated prostate cancer varies widely. In our cohort, 33% have Td >10 years. Td may be a useful tool to guide treatment intervention for patients managed conservatively with watchful observation alone

  12. Real-life experience of using conventional disease-modifying anti-rheumatic drugs (DMARDs) in psoriatic arthritis (PsA). Retrospective analysis of the efficacy of methotrexate, sulfasalazine, and leflunomide in PsA in comparison to spondyloarthritides other than PsA and literature review of the use of conventional DMARDs in PsA

    Science.gov (United States)

    Roussou, Euthalia; Bouraoui, Aicha

    2017-01-01

    Objective With the aim of assessing the response to treatment with conventional disease-modifying anti-rheumatic drugs (DMARDs) used in patients with psoriatic arthritis (PsA), data on methotrexate, sulfasalazine (SSZ), and leflunomide were analyzed from baseline and subsequent follow-up (FU) questionnaires completed by patients with either PsA or other spondyloarthritides (SpAs). Material and Methods A single-center real-life retrospective analysis was performed by obtaining clinical data via questionnaires administered before and after treatment. The indices used were erythrocyte sedimentation rate (ESR), C-reactive protein (CRP) level, Bath Ankylosing Spondylitis Disease Activity Index (BASDAI), Bath Ankylosing Spondylitis Function Index (BASFI), wellbeing (WB), and treatment effect (TxE). The indices measured at baseline were compared with those measured on one occasion in a FU visit at least 1 year later. Results A total of 73 patients, 51 with PsA (mean age 49.8±12.8 years; male-to-female ratio [M:F]=18:33) and 22 with other SpAs (mean age 50.6±16 years; M:F=2:20), were studied. BASDAI, BASFI, and WB displayed consistent improvements during FU assessments in both PsA patients and controls in comparison to baseline values. SSZ exhibited better efficacy as confirmed by TxE in both PsA patients and controls. ESR and CRP displayed no differences in either the PsA or the SpA group between the cases before and after treatment. Conclusion Real-life retrospective analysis of three DMARDs used in PsA (and SpAs other than PsA) demonstrated that all three DMARDs that were used brought about improvements in BASDAI, BASFI, TxE, and WB. However, the greatest improvements at FU were seen with SSZ use in both PsA and control cohorts. PMID:28293446

  13. Insights of PSA studies made for operating nuclear power stations in Finland

    International Nuclear Information System (INIS)

    Laaksonen, J.; Virolainen, R.

    1991-01-01

    In 1984 the Finnish regulatory authority (STUK) required the utilities to make plant specific probabilistic safety assessment (PSA) studies for each plant. It was also strongly recommended that most of the work be made by plant personnel. This advice was well observed by both utilities. Results of level 1 PSA studies were submitted for regulatory review in June 1989. Only internal initiating events, including loss-of-offsite power and human errors, were considered at this stage. Each study took an effort of 12 to 20 man years. A thorough regulatory review, about two man years per plant, is currently underway, and will cause some changes in the initial results of the studies. The utilities are continuing their PSA work with the fire and flood analysis, and then with the analysis of risks during start-up and shutdown conditions. As soon as a level 1 PSA study has been reviewed, and a common understanding of the models and data has been reached between the utility and the STUK, this basic PSA version will be the first element of a living PSA. The second element is a user friendly PSA code that can rapidly run through the quantitative part of the study and thus easily indicate the influence of any deviation from the basic version. The third element is plant specific data collection and processing system. The living PSA for the first plant is expected to be fully operational sometime next year. The first use of the living PSA will be the safety assessment of proposed plant modifications and a systematic re-evaluation of technical specifications

  14. Best-practices guidelines for L2PSA development and applications. Volume 1 - General

    International Nuclear Information System (INIS)

    Raimond, E.; Pichereau, F.; Durin, T.; Rahni, N.; Loeffler, H.; Roesch, O.; Lajtha, G.; Santamaria, C.S.; Dienstbier, J.; Rydl, A.; Holmberg, J.E.; Lindholm, I.; Maennistoe, I.; Pauli, E.M.; Dirksen, G.; Grindon, L.; Peers, K.; Bassi, C.; Hulqvist, G.; Parozzi, F.; Polidoro, F.; Cazzoli, E.; Vitazkova, J.; Burgazzi, L.; Brinkman, H.; Seidel, A.; Schubert, B.; Wohlstein, R.; Guentay, S.; Oury, L.; Ngatchou, C.; Siltanen, S.; Niemela, I.; Routamo, T.; Vincon, L.; Helstroem, P.

    2010-01-01

    The objective of this coordinated action was to develop best practice guidelines for the performance and application of Level 2 PSA with a view to achieve harmonisation at EU level and to allow a meaningful and practical uncertainty evaluation in a Level 2 PSA. Specific relationships with communities in charge of nuclear reactor safety (utilities, safety authorities, vendors, and research or services companies) have been established in order to define the current needs in terms of guidelines for Level 2 PSA development and application. An international workshop was organised in Hamburg, with the support of VATTENFALL, in November 2008. The Level 2 PSA experts from ASAMPSA2 project partners have proposed some guidelines for the development and application of L2PSA based on their experience, open literature, and on information available from international cooperation (EC Severe Accident network of Excellence - SARNET, IAEA standards, OECD-NEA publications and workshop). There are a large number of technical issues addressed in the guideline which are not all covered with the same level of detail in the first version of the guideline. This version was submitted for external review in November 2010 by severe accident and PSA experts (especially from SARNET and OECD-NEA members). The feedback of the external review will be dis cussed during an international open works hop planned for March 2011 and all outcomes will be taken into consideration in the final version of this guideline (June 2011). The guideline includes 3 volumes: - Volume 1 - General considerations on L2PSA. - Volume 2 - Technical recommendations for Gen II and III reactors. - Volume 3 - Specific considerations for future reactors (Gen IV). The recommendations formulated in the guideline should not be considered as 'mandatory' but should help Level 2 PSA developers to achieve high quality studies with limited time and resources. It may also help Level 2 PSA reviewers by positioning one specific study in

  15. Strain-specific impact of PsaR of Streptococcus pneumoniae on global gene expression and virulence

    OpenAIRE

    Hendriksen, Wouter T.; Bootsma, Hester J.; van Diepen, Angela; Estevao, Silvia; Kuipers, Oscar P.; de Groot, Ronald; Hermans, Peter W. M.

    2009-01-01

    Previous studies have indicated that PsaR of Streptococcus pneumoniae is a manganese-dependent regulator, negatively affecting the expression of at least seven genes. Here, we extended these observations by transcriptome and proteome analysis of psaR mutants in strains D39 and TIGR4. The microarray analysis identified three shared PsaR targets: the psa operon, pcpA and prtA. In addition, we found 31 genes to be regulated by PsaR in D39 only, most strikingly a cellobiose-specific phosphotrains...

  16. A Review of PSA Technology Applications according to the Development of Sodium-cooled Fast Reactors in the World

    International Nuclear Information System (INIS)

    Kim, Tae Woon; Lee, Yong Bum; Jung, Hae Yong; Kim, Sang Ji; Hahn, Do Hee; Yang, Joon Eon

    2008-12-01

    The international nuclear societies request to perform Probabilistic Safety Assessment (PSA) according to the development of Gen IV Sodium-cooled Fast Reactors (SFR). One of the major tasks of the PSA is to identify various sequences of events which could lead to the release of radioactivity. However, due to the limited operating and SFR PSA experiences, it will be difficult to derive and to quantify core damage frequency for SFR under development in Korea, so called KALIMER. Hence, in this report, the foreign PSA results, such as USA and Japan, are analyzed based on the obtained documents. Finally an approach on how to perform PSA for KALIMER is suggested

  17. The low molecular weight protein PsaI stabilizes the light-harvesting complex II docking site of photosystem I

    DEFF Research Database (Denmark)

    Plöchinger, Magdalena; Torabi, Salar; Rantala, Marjaana

    2016-01-01

    PsaI represents one of three low molecular weight peptides of PSI. Targeted inactivation of the plastid PsaI gene in Nicotiana tabacum has no measurable effect on photosynthetic electron transport around PSI or on accumulation of proteins involved in photosynthesis. Instead, the lack of Psa......I destabilizes the association of PsaL and PsaH to PSI, both forming the light-harvesting complex (LHC)II docking site of PSI. These alterations at the LHCII binding site surprisingly did not prevent state transition but led to an increased incidence of PSI-LHCII complexes, coinciding with an elevated...

  18. Mentorship through advisory colleges.

    Science.gov (United States)

    Murr, Andrew H; Miller, Carol; Papadakis, Maxine

    2002-11-01

    Medical students face pressures ranging from the need to create a social network to learning vast amounts of scientific material. Students often feel isolated in this system and lack mentorship. In order to counteract feelings of bureaucratic anonymity and isolation, the University of California San Francisco has created an advisory college to foster the professional and personal growth and well being of students. UCSF has developed a formal structure to advise medical students. A selection committee, chaired by the associate dean of student affairs, appointed five faculty mentors to head advisory colleges. These five colleges serve as the advising and well-being infrastructure for the students. Mentors were chosen from a balanced range of clinical disciplines, both primary and specialty. The disciplines are obstetrics-gynecology, otolaryngology/head and neck surgery, medicine, pediatrics, and psychiatry. The mentors have demonstrated excellence in advising and counseling of students. Mentors meet individually at the beginning of the academic year with incoming first-year and second-year students. They then have bimonthly meetings with eight to ten students within each college throughout the academic year. Curricula for these group sessions include well-being discussions and coping techniques, sessions on the hidden and informal curriculum of professionalism, and discussions on career choices and strategies. For third-year students, advisory college meetings are scheduled during intersessions, which are weeklong courses that occur between the eight-week clerkship blocks. Mentors are available throughout the year to meet with students on an as-needed basis, and advisory colleges may hold group social activities. The dean's office supports each mentor with 20% salary and provides administrative support for the group college activities. Historically, UCSF students feel they receive an excellent education and appropriate job opportunities, but they do not feel they

  19. 75 FR 22757 - Federal Advisory Committee; Army Education Advisory Committee; Charter Renewal

    Science.gov (United States)

    2010-04-30

    ..., school curriculums, educational philosophy and objectives, program effectiveness, facilities, staff and... DEPARTMENT OF DEFENSE Office of the Secretary Federal Advisory Committee; Army Education Advisory... Defense gives notice that it is renewing the charter for the Army Education Advisory Committee (hereafter...

  20. 77 FR 64335 - Notification of a Public Teleconference of the Science Advisory Board; Perchlorate Advisory Panel

    Science.gov (United States)

    2012-10-19

    ... ENVIRONMENTAL PROTECTION AGENCY [FRL--9743-2] Notification of a Public Teleconference of the Science Advisory Board; Perchlorate Advisory Panel AGENCY: Environmental Protection Agency (EPA). ACTION: Notice. SUMMARY: The Environmental Protection Agency (EPA) Science Advisory Board (SAB) Staff Office...

  1. Development of simple immunoradiometric assay kits for measurement of Prostate Specific Antigen (PSA)

    International Nuclear Information System (INIS)

    Najafi, R.; Zarsav, P.; Pourabdi, M.; Moharamzadeh, M.; Mahdiani, B.

    1999-01-01

    The report summarizes our results obtained in the field of PSA IRMA kits development. In these experiments, we used Avidin-Biotin technology for coating of antibodies on beads/tubes and studied various parameters, such as investigation of different types of tubes, incubation time, volume of samples etc., as well as comparing two types of Mabs of PSA (free and total) for coating on the surface of bead/tube and obtaining optimized requirements to achieve reliable and simplified assays of PSA (free and total) in serum. (author)

  2. PSA predicts development of incident lower urinary tract symptoms: results from the REDUCE study.

    Science.gov (United States)

    Patel, Devin N; Feng, Tom; Simon, Ross M; Howard, Lauren E; Vidal, Adriana C; Moreira, Daniel M; Castro-Santamaria, Ramiro; Roehrborn, Claus; Andriole, Gerald L; Freedland, Stephen J

    2018-05-23

    The relationship between baseline prostate-specific antigen (PSA) and development of lower urinary tract symptoms (LUTS) in asymptomatic and mildly symptomatic men is unclear. We sought to determine if PSA predicts incident LUTS in these men. A post-hoc analysis of the 4-year REDUCE study was performed to assess for incident LUTS in 1534 men with mild to no LUTS at baseline. The primary aim was to determine whether PSA independently predicted incident LUTS after adjusting for the key clinical variables of age, prostate size, and baseline International prostate symptom score (IPSS). Incident LUTS was defined as the first report of medical treatment, surgery, or sustained clinically significant symptoms (two IPSS >14). Cox proportional hazards, cumulative incidence curves, and the log-rank test were used to test our hypothesis. A total of 1534 men with baseline IPSS PSA 2.5-4 ng/mL, 589 with PSA 4.1-6 ng/mL, and 610 with PSA 6-10 ng/mL. During the 4-year study, 196 men progressed to incident LUTS (50.5% medical treatment, 9% surgery, and 40.5% new symptoms). As a continuous variable, higher PSA was associated with increased incident LUTS on univariable (HR 1.09, p = 0.019) and multivariable (HR 1.08, p = 0.040) analysis. Likewise, baseline PSA 6-10 ng/mL was associated with increased incident LUTS vs. PSA 2.5-4 ng/mL in adjusted models (HR 1.68, p = 0.016). This association was also observed in men with PSA 4.1-6 ng/mL vs. PSA 2.5-4 ng/mL (HR 1.60, p = 0.032). Men with mild to no LUTS but increased baseline PSA are at increased risk of developing incident LUTS presumed due to benign prostatic hyperplasia.

  3. Key Characteristics of Combined Accident including TLOFW accident for PSA Modeling

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Bo Gyung; Kang, Hyun Gook [KAIST, Daejeon (Korea, Republic of); Yoon, Ho Joon [Khalifa University of Science, Technology and Research, Abu Dhabi (United Arab Emirates)

    2015-05-15

    The conventional PSA techniques cannot adequately evaluate all events. The conventional PSA models usually focus on single internal events such as DBAs, the external hazards such as fire, seismic. However, the Fukushima accident of Japan in 2011 reveals that very rare event is necessary to be considered in the PSA model to prevent the radioactive release to environment caused by poor treatment based on lack of the information, and to improve the emergency operation procedure. Especially, the results from PSA can be used to decision making for regulators. Moreover, designers can consider the weakness of plant safety based on the quantified results and understand accident sequence based on human actions and system availability. This study is for PSA modeling of combined accidents including total loss of feedwater (TLOFW) accident. The TLOFW accident is a representative accident involving the failure of cooling through secondary side. If the amount of heat transfer is not enough due to the failure of secondary side, the heat will be accumulated to the primary side by continuous core decay heat. Transients with loss of feedwater include total loss of feedwater accident, loss of condenser vacuum accident, and closure of all MSIVs. When residual heat removal by the secondary side is terminated, the safety injection into the RCS with direct primary depressurization would provide alternative heat removal. This operation is called feed and bleed (F and B) operation. Combined accidents including TLOFW accident are very rare event and partially considered in conventional PSA model. Since the necessity of F and B operation is related to plant conditions, the PSA modeling for combined accidents including TLOFW accident is necessary to identify the design and operational vulnerabilities.The PSA is significant to assess the risk of NPPs, and to identify the design and operational vulnerabilities. Even though the combined accident is very rare event, the consequence of combined

  4. Age-Specific Cutoff Value for the Application of Percent Free Prostate-Specific Antigen (PSA) in Chinese Men with Serum PSA Levels of 4.0–10.0 ng/ml

    Science.gov (United States)

    Xie, Liping; He, Dalin; Zhou, Liqun; Xu, Chuanliang; Gao, Xu; Ren, Shancheng; Wang, Fubo; Ma, Lulin; Wei, Qiang; Yin, Changjun; Tian, Ye; Sun, Zhongquan; Fu, Qiang; Ding, Qiang; Zheng, Junhua; Ye, Zhangqun; Ye, Dingwei; Xu, Danfeng; Hou, Jianquan; Xu, Kexin; Yuan, Jianlin; Gao, Xin; Liu, Chunxiao; Pan, Tiejun; Sun, Yinghao

    2015-01-01

    Objective The influence of age on the performance of percent free prostate-specific antigen (%fPSA) in diagnosing prostate cancer (PCa) in East Asians is controversial. We tested the diagnostic performance of %fPSA in a multi-center biopsy cohort in China and identified the proper age-specific cutoff values to avoid unnecessary biopsies. Methods Consecutive patients with a prostate-specific antigen (PSA) level of 4.0–10.0 ng/ml or 10.1–20.0 ng/ml who underwent transrectal ultrasound-guided or transperineal prostate biopsy were enrolled from 22 Chinese medical centers from Jan 1, 2010 to Dec 31, 2013. The diagnostic accuracy of PSA and %fPSA was determined using the area under the receiver operating characteristic (ROC) curve (AUC). Age-specific cutoff values were calculated using ROC curve analysis. Results The median %fPSA was much lower in younger patients compared with older patients with a PSA level of 4.0–10.0 ng/ml or 10.1–20.0 ng/ml. The AUC of %fPSA was higher than PSA only in older patients. In patients aged 50 to 59 years, %fPSA failed to improve the diagnosis compared with PSA in these two PSA ranges. Age-specific cutoff values were 24%, 27% and 32% for patients aged 60–69, 70–79 and ≥80 years, respectively, to reduce unnecessary biopsies in men with PSA levels of 4.0–10.0 ng/ml to detect 90% of all PCa. Conclusions The effectiveness of %fPSA is correlated with age in the Chinese population. Age-specific cutoff values would help avoid unnecessary biopsies in the Chinese population. PMID:26091007

  5. Treatment strategy for metastatic prostate cancer with extremely high PSA level: reconsidering the value of vintage therapy.

    Science.gov (United States)

    Yamada, Yasutaka; Sakamoto, Shinichi; Amiya, Yoshiyasu; Sasaki, Makoto; Shima, Takayuki; Komiya, Akira; Suzuki, Noriyuki; Akakura, Koichiro; Ichikawa, Tomohiko; Nakatsu, Hiroomi

    2018-05-04

    The prognostic significance of initial prostate-specific antigen (PSA) level for metastatic prostate cancer remains uncertain. We investigated the differences in prognosis and response to hormonal therapies of metastatic prostate cancer patients according to initial PSA levels. We analyzed 184 patients diagnosed with metastatic prostate cancer and divided them into three PSA level groups as follows: low (PSA progression-free survival (PFS) for first-line ADT and overall survival (OS) within each of the three groups. Furthermore, we analyzed response to antiandrogen withdrawal (AW) and alternative antiandrogen (AA) therapies after development of castration-resistant prostate cancer (CRPC). No significant differences in OS were observed among the three groups (P = 0.654). Patients with high PSA levels had significantly short PFS for first-line ADT (P = 0.037). Conversely, patients in the high PSA level group had significantly longer PFS when treated with AW than those in the low PSA level group (P = 0.047). Furthermore, patients with high PSA levels had significantly longer PFS when provided with AA therapy (P = 0.049). PSA responders to AW and AA therapies had significantly longer survival after CRPC development than nonresponders (P = 0.011 and P PSA level predicted favorable response to vintage sequential ADT and AW. The current data suggest a novel aspect of extremely high PSA value as a favorable prognostic marker after development of CRPC.

  6. Impact of Body Mass Index, Age, Prostate Volume, and Genetic Polymorphisms on Prostate-specific Antigen Levels in a Control Population.

    Science.gov (United States)

    Cornu, Jean-Nicolas; Cancel-Tassin, Geraldine; Cox, David G; Roupret, Morgan; Koutlidis, Nicolas; Bigot, Pierre; Valeri, Antoine; Ondet, Valerie; Gaffory, Cécile; Fournier, Georges; Azzouzi, Abdel-Rahmene; Cormier, Luc; Cussenot, Olivier

    2016-07-01

    Prostate-specific antigen (PSA) is still the cornerstone of prostate cancer (PCa) screening and diagnosis in both research and current clinical practice. Inaccuracy of PSA is partly due to the influence of a number of genetic, clinical, and biological factors modifying PSA blood levels. In the present study, we detailed the respective influence of each factor among age, body mass index (BMI), prostate volume, and five single-nucleotide polymorphisms-rs10788160 (10q26), rs10993994 (10q11), rs11067228 (12q24), rs17632542 (19q13.33), and rs2928679 (8p21)-on PSA values in a cohort of 1374 men without PCa. Our results show that genetic factors, when risk variants are combined, influence PSA levels with an effect size similar to that of BMI. Taken together, the respective correlations of clinical parameters and genetic parameters would make it possible to correct and adjust PSA values more effectively in each individual. These results establish the basis to understand and implement a more personalised approach for the interpretation of PSA blood levels in the context of PCa screening and diagnosis. Prostate-specific antigen (PSA) values in an individual may vary according to genetic predisposition. The effect size of this variation can be significant, comparable with those resulting from clinical characteristics. Personalised PSA testing should take this into account. Copyright © 2016 European Association of Urology. Published by Elsevier B.V. All rights reserved.

  7. Application of PSA techniques to synchrotron radiation source facilities

    International Nuclear Information System (INIS)

    Sanyasi Rao, V.V.S.; Vinod, G.; Vaze, K.K.; Sarkar, P.K.

    2011-01-01

    Synchrotron radiation sources are increasingly being used in research and medical applications. Various instances of overexposure in these facilities have been reported in literature. These instances have lead to the investigation of the risks associated with them with a view to minimise the risks and thereby increasing the level of safety. In nuclear industry, Probabilistic Safety Assessment (PSA) methods are widely used to assess the risk from nuclear power plants. PSA presents a systematic methodology to evaluate the likelihood of various accident scenarios and their possible consequences using fault/event tree techniques. It is proposed to extend similar approach to analyse the risk associated with synchrotron radiation sources. First step for such an analysis is establishing the failure criteria, considering the regulatory stipulations on acceptable limits of dose due to ionization radiation from normal as well as beam loss scenarios. Some possible scenarios considered in this study are (1) excessive Bremsstrahlung in the ring due to loss of vacuum, (2) Target failure due to excessively focused beam (3) mis-directed/mis-steered beam (4) beam loss and sky shine. Hazard analysis needs to cover the beam transfer line, storage ring and experimental beam line areas. Various safety provisions are in place to minimize the hazards from these facilities such as access control interlock systems, radiation shielding for storage ring and beam lines and safety shutters (for beam lines). Experimental beam line area is the most vulnerable locations that need to be critically analysed. There are multiple beam lines, that have different safety provisions and consequences from postulated beam strikes will also be different and this increases the complexity of analysis. Similar studies conducted for such experimental facilities have identified that the radiation safety interlock system, used to control access to areas inside ring and the hutches of beamline facilities has an

  8. A Diet, Physical Activity, and Meditation Intervention in Men With Rising Prostate-Specific Antigen (PSA)

    National Research Council Canada - National Science Library

    Hebert, James R

    2006-01-01

    ... physical activity and mindfulness-based stress reduction. This randomized trial will enroll 60 men with rising PSA levels along with a partner of their choice, half of whom will be randomized to the intervention and half to usual care...

  9. A Diet, Physical Activity, and Meditation Intervention in Men With Rising Prostate-Specific Antigen (PSA)

    National Research Council Canada - National Science Library

    Hebert, James R

    2007-01-01

    ... physical activity and mindfulness-based stress reduction. This randomized trial will enroll 60 men with rising PSA levels along with a partner of their choice, half of whom will be randomized to the intervention and half to usual care...

  10. A Diet, Physical Activity, and Mediation Intervention in Men With Rising Prostate-Specific Antigen (PSA)

    National Research Council Canada - National Science Library

    Hebert, James

    2004-01-01

    ... physical activity and mindfulness-based stress reduction. This randomized trial will enroll 60 men with rising PSA levels along with a partner of their choice, half of whom will be randomized to the intervention and half to usual care...

  11. Patients with Central Lines - What You Need to Know to Avoid a Bloodstream Infection PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    This 60 second PSA is based on the March, 2011 CDC Vital Signs report which indicates bloodstream infections in patients with central lines are largely preventable when healthcare providers use CDC-recommended infection control steps.

  12. Comparison of global sensitivity analysis techniques and importance measures in PSA

    International Nuclear Information System (INIS)

    Borgonovo, E.; Apostolakis, G.E.; Tarantola, S.; Saltelli, A.

    2003-01-01

    This paper discusses application and results of global sensitivity analysis techniques to probabilistic safety assessment (PSA) models, and their comparison to importance measures. This comparison allows one to understand whether PSA elements that are important to the risk, as revealed by importance measures, are also important contributors to the model uncertainty, as revealed by global sensitivity analysis. We show that, due to epistemic dependence, uncertainty and global sensitivity analysis of PSA models must be performed at the parameter level. A difficulty arises, since standard codes produce the calculations at the basic event level. We discuss both the indirect comparison through importance measures computed for basic events, and the direct comparison performed using the differential importance measure and the Fussell-Vesely importance at the parameter level. Results are discussed for the large LLOCA sequence of the advanced test reactor PSA

  13. CDC: Tips from Former Smokers – Jessica PSA (:30)

    Centers for Disease Control (CDC) Podcasts

    Exposure to secondhand smoke can trigger a life-threatening asthma attack. This 30 second PSA features Jessica, a mother with a young son who suffers from asthma attacks triggered by secondhand smoke exposure.

  14. Radiographic progression with nonrising PSA in metastatic castration-resistant prostate cancer

    DEFF Research Database (Denmark)

    Bryce, A H; Alumkal, J J; Armstrong, A

    2017-01-01

    monitoring alone to determine disease status on therapy. This approach has not been adequately tested. METHODS: Chemotherapy-naive asymptomatic or mildly symptomatic men (n=872) with metastatic castration-resistant prostate cancer (mCRPC) who were treated with the androgen receptor inhibitor enzalutamide......BACKGROUND: Advanced prostate cancer is a phenotypically diverse disease that evolves through multiple clinical courses. PSA level is the most widely used parameter for disease monitoring, but it has well-recognized limitations. Unlike in clinical trials, in practice, clinicians may rely on PSA...... treated with enzalutamide. As restaging in advanced prostate cancer patients is often guided by increases in PSA levels, our results demonstrate that disease progression on enzalutamide can occur without rising PSA levels. Therefore, a disease monitoring strategy that includes imaging not entirely reliant...

  15. Making Food Safer to Eat - What You Need to Know PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    This 60 second Public Service Announcement (PSA) is based on the June, 2011 CDC Vital Signs report. One in six Americans gets sick from eating contaminated food each year. To reduce your risk, remember to clean, separate, cook, and chill.

  16. Face-to-face Tobacco Sales: What Retailers Need to Know PSA (:30)

    Centers for Disease Control (CDC) Podcasts

    PSA to help raise retailers' awareness of the new federal tobacco regulations related to the sale of cigarettes and smokeless tobacco products to people under 18 and the requirement to sell products face-to-face.

  17. The significance of the probabilistic safety analysis (PSA) in administrative procedures under nuclear law

    International Nuclear Information System (INIS)

    Berg, H.P.

    1994-01-01

    The probabilistic safety analysis (PSA) is a useful tool for safety relevant evaluation of nuclear power plant designed on the basis of deterministic specifications. The PSA yields data identifying reliable or less reliable systems, or frequent or less frequent failure modes to be taken into account for safety engineering. Performance of a PSA in administrative procedures under nuclear law, e.g. licensing, is an obligation laid down in a footnote to criterion 1.1 of the BMI safety criteria catalogue, which has been in force unaltered since 1977. The paper explains the application and achievements of PSA in the phase of reactor development concerned with the conceptual design basis and design features, using as an example the novel PWR. (orig./HP) [de

  18. utility of prostate specific antigen (psa) in the indigenous african man

    African Journals Online (AJOL)

    diagnosed with Acute Prostatitis, Benign Prostate Hyperplasia (BPH) and Prostate. Cancer in ... Conclusions: The indigenous black African man has high levels of PSA even in benign ... to have other non-prostatic causes of bladder outlet.

  19. New Hope for Stopping HIV - Testing and Medical Care Save Lives PSA (:60)

    Centers for Disease Control (CDC) Podcasts

    This 60 second PSA is based on the December 2011 CDC Vital Signs report, "HIV Prevention through Care and Treatment" that shares new hope for preventing HIV and improving the health of people with HIV.

  20. Evaluating engrailed-2 and cytokines in urine with serum PSA as ...

    African Journals Online (AJOL)

    Evaluating engrailed-2 and cytokines in urine with serum PSA as potential biomarkers in patients with prostatism at Moi Teaching and Referral Hospital, Eldoret, Kenya. B Donald-Buri, K Patel, P Musau, E.N. Fish ...

  1. We Can Stop HIV One Conversation at a Time Radio PSA (:30)

    Centers for Disease Control (CDC) Podcasts

    As part of the We Can Stop HIV One Conversation at a Time campaign, this 30 second PSA encourages Hispanics/Latinos to talk openly about HIV and AIDS with their families, friends, partners, and communities.

  2. Lesson learned from PSA in the design improvement program of KSNP+

    International Nuclear Information System (INIS)

    Kim, M.R.; Lim, H.K.; Kang, S.K.; Park, K.S.

    2001-01-01

    KOPEC (Korea Power Engineering Co.) in conjunction with the client KEPCO (Korea Electric Power Corp.) has been developing a highly competitive Improved Korean Standard Nuclear Power Plant named KSNP+. From the beginning of Design Improvement Program, PSA was carried out to assure that the safety level of KSNP+ is maintained or improved in comparison with that of KSNP, the Korean Standard NPP. To achieve the safety goal of KSNP+, PSA team reviewed all design changes that might affect the plant safety. Design vulnerabilities were identified from the PSA results and safety improvement items were recommended to the system designers. Through the Design Improvement Program, KSNP+ became more reliable, safer and economically competitive than KSNP. This was achieved by systematic approach for design optimization and effective use of PSA technology based on past experience and expertise of nuclear power plant. (author)

  3. Attributes of Full Scope Level 1 Probabilistic Safety Assessment (PSA) for Applications in Nuclear Power Plants

    International Nuclear Information System (INIS)

    2016-10-01

    This publication supersedes IAEA-TECDOC-1511, Determining the Quality of Probabilistic Safety Assessment (PSA) for Applications in Nuclear Power Plants (published in 2006), which provided detailed information on technical features of a restricted scope PSA aimed at analysing only internal initiating events caused by random component failures and human errors, and accident sequences that may lead to reactor core damage during operation. The present publication extends the scope of the PSA to cover a broader range of internal and external hazards, and low power and shutdown modes of nuclear power plant operation. In addition, some PSA aspects relevant to lessons learned from the accident at the Fukushima Daiichi nuclear power plant are also considered

  4. Joint Advisory Appeals Board

    CERN Multimedia

    2013-01-01

    The Joint Advisory Appeals Board has examined the internal appeal lodged by a former member of the personnel, a beneficiary of the CERN Pension Fund, against the calculation of his pension in the framework of the Progressive Retirement Programme.   The person concerned has not objected to the report of the Board and the final decision of the Director-General being brought to the attention of the members of the personnel. In application of Article R VI 1.18 of the Staff Regulations, these documents will therefore be available from 26 July to 11 August 2013 at the following link. HR Department Head Office

  5. JOINT ADVISORY APPEALS BOARD

    CERN Multimedia

    Human Resources Division

    2002-01-01

    The Joint Advisory Appeals Board was convened to examine the appeal lodged by Mr Luc Vos with regard to advancement. As the appellant has not objected, the report of the Board and the final decision of the Director-General are brought to the notice of the personnel in accordance with Article R VI 1.20 of the Staff Regulations. The relevant documents will therefore be posted on the notice boards of the Administration Building (N° 60) from 14 to 28 June 2002. Human Resources Division Tel. 74128

  6. Joint Advisory Appeals Board

    CERN Multimedia

    HR Department

    2008-01-01

    The Joint Advisory Appeals Board has examined the internal appeal lodged by a member of the personnel against the decision to grant him only a periodic one-step advancement for the 2006 reference year. The person concerned has not objected to the report of the Board and the final decision of the Director-General being brought to the attention of the members of the personnel. In application of Article R VI 1.18 of the Staff Regulations, these documents will therefore be posted on the notice board of the Main building (bldg. 500) from 1 September to 14 September 2008. Human Resources Department (73911)

  7. Joint Advisory Appeals Board

    CERN Multimedia

    2003-01-01

    The Joint Advisory Appeals Board was convened to examine the appeal lodged by Mr Poul Frandsen concerning his assimilation into the new career structure. As the appellant has not objected, the report of the Board and the final decision of the Director-General are brought to the notice of the personnel in accordance with Article R VI 1.20 of the Staff Regulations. The relevant documents will therefore be posted on the notice boards of the Administration Building (N° 60) from 13 to 24 January 2003. Human Resources Division Tel. 74128

  8. JOINT ADVISORY APPEALS BOARD

    CERN Multimedia

    Personnel Division

    1999-01-01

    The Joint Advisory Appeals Board was convened to examine the appeal lodged by Mr Joào Bento with regard to residential category. As the appellant has not objected, the recommendations of the Board and the final decision of the Director-General are brought to the notice of the personnel in accordance with Article RÊVIÊ1.20 of the Staff Regulations.The relevant documents will therefore be posted on the notice boards of the Administration Building (N¡ 60) from 29 October to 12 November 1999.Personnel DivisionTel. 74128

  9. Joint Advisory Appeals Board

    CERN Multimedia

    HR Department

    2006-01-01

    The Joint Advisory Appeals Board was convened to examine an appeal lodged by a member of the personnel with regard to advancement. The person concerned has requested that the report of the Board and the final decision of the Director-General be brought to the notice of the personnel in accordance with Article R VI 1.20 of the Staff Regulations. The relevant documents will therefore be posted on the notice boards of the Administration Building (No. 60) from 24 March to 10 April 2006. Human Resources Department Tel. 74128

  10. Joint Advisory Appeals Board

    CERN Multimedia

    HR Department

    2007-01-01

    The Joint Advisory Appeals Board was convened to examine an internal appeal lodged by a member of the personnel with regard to the decision not to grant him an indefinite contract. The person concerned has requested that the report of the Board and the final decision of the Director-General be brought to the notice of the members of the personnel, in accordance with Article R VI 1.18 of the Staff Regulations. The relevant documents will therefore be posted on the notice board of the Main building (Bldg. 60) from 24 September to 7 October 2007. Human Resources Department

  11. JOINT ADVISORY APPEALS BOARD

    CERN Multimedia

    Human Resources Division

    2001-01-01

    The Joint Advisory Appeals Board was convened to examine the appeal lodged by Mr Olivier Francis Martin with regard to indefinite contract. As the appellant has not objected, the report of the Board and the final decision of the Director-General are brought to the notice of the personnel in accordance with Article R VI 1.20 of the Staff Regulations. The relevant documents will therefore be posted on the notice boards of the Administration Building (N° 60) from 8 to 25 June 2001.

  12. JOINT ADVISORY APPEALS BOARD

    CERN Multimedia

    Human Resources Division

    2002-01-01

    The Joint Advisory Appeals Board was convened to examine the appeal lodged by Mr Jack Blanchard with regard to 'non recognition of specific functions'. As the appellant has not objected, the report of the Board and the final decision of the Director-General are brought to the notice of the personnel in accordance with Article R VI 1.20 of the Staff Regulations. The relevant documents will therefore be posted on the notice boards of the Administration Building (N° 60) from 12th to 26th April 2002. Human Resources Division Tel. 74128

  13. Joint Advisory Appeals Board

    CERN Multimedia

    2003-01-01

    The Joint Advisory Appeals Board was convened to examine the appeal lodged by Mrs Judith Igo-Kemenes concerning the application of procedures foreseen by Administrative Circular N§ 26 (Rev. 3). As the appellant has not objected, the report of the Board and the final decision of the Director-General are brought to the notice of the personnel in accordance with Article R VI 1.20 of the Staff Regulations. The relevant documents will therefore be posted on the notice boards of the Administration Building (N° 60) from 6 to 20 June 2003. Human Resources Division Tel. 74128

  14. Joint Advisory Appeals Board

    CERN Multimedia

    2004-01-01

    The Joint Advisory Appeals Board was convened to examine the appeal lodged by Mrs Maria DIMOU with regard to a periodic one-step increase. As the appellant has not objected, the report of the Board and the final decision of the Director-General are brought to the notice of the personnel in accordance with Article R VI 1.20 of the Staff Regulations. The relevant documents will therefore be posted on the notice boards of the Administration Building (N° 60) from 30 April to 14 May 2004. Human Resources Department Tel. 74128

  15. JOINT ADVISORY APPEALS BOARD

    CERN Multimedia

    Human Resources Division

    2001-01-01

    The Joint Advisory Appeals Board was convened to examine the appeal lodged by Mr Joël Lahaye with regard to non-resident allowance. As the appellant has not objected, the report of the Board and the final decision of the Director-General are brought to the notice of the personnel in accordance with Article R VI 1.20 of the Staff Regulations. The relevant documents will therefore be posted on the notice boards of the Administration Building (N° 60) from 18 May to 1st June 2001.

  16. Joint Advisory Appeals Board

    CERN Multimedia

    HR Department

    2008-01-01

    The Joint Advisory Appeals Board has examined the internal appeal lodged by a member of the personnel with regard to the decision not to award him a periodic one-step advancement for the 2006 reference year. The person concerned has not objected to the report of the Board and the final decision of the Director-General being brought to the notice of the members of the personnel. In application of Article R VI 1.18 of the Staff Regulations, these documents will therefore be posted on the notice board of the Main building (Bldg. 500) from 17 March to 30 March 2008. Human Resources Department Tel. 73911

  17. JOINT ADVISORY APPEALS BOARD

    CERN Multimedia

    Human Resources Division

    2002-01-01

    The Joint Advisory Appeals Board was convened to examine the appeal lodged by Mr Bertrand Nicquevert with regard to the non-resident allowance. As the appellant has not objected, the report of the Board and the final decision of the Director-General are brought to the notice of the personnel in accordance with Article R VI 1.20 of the Staff Regulations. The relevant documents will therefore be posted on the notice boards of the Administration Building (N° 60) from 29 November to 13 December 2002. Human Resources Division Tel. 74128

  18. JOINT ADVISORY APPEALS BOARD

    CERN Multimedia

    Human Resources Division

    2002-01-01

    The Joint Advisory Appeals Board was convened to examine the appeal lodged by Mr Antonio Millich with regard to advancement. As the appellant has not objected, the report of the Board and the final decision of the Director-General are brought to the notice of the personnel in accordance with Article R VI 1.20 of the Staff Regulations. The relevant documents will therefore be posted on the notice boards of the Administration Building (N° 60) from 27 September to 11 October 2002. Human Resources Division Tel. 74128

  19. Joint Advisory Appeals Board

    CERN Multimedia

    Human Resources Department

    2005-01-01

    The Joint Advisory Appeals Board was convened to examine an appeal lodged by a member of the personnel with regard to a periodic one-step increase. As the appellant has not objected, the report of the Board and the final decision of the Director-General are brought to the notice of the personnel in accordance with Article R VI 1.20 of the Staff Regulations. The relevant documents will therefore be posted on the notice boards of the Administration Building (N° 60) from 1 to 15 April 2005. Human Resources Department Tel. 74128

  20. Joint Advisory Appeals Board

    CERN Multimedia

    HR Department

    2008-01-01

    The Joint Advisory Appeals Board has examined the internal appeal lodged by a member of the personnel against the decision to grant him only a periodic one-step advancement for the 2006 reference year. The person concerned has not objected to the report of the Board and the final decision of the Director-General being brought to the attention of the members of the personnel. In application of Article R VI 1.18 of the Staff Regulations, these documents will therefore be posted on the notice board of the Main Building (Bldg. 500) from 1 September to 14 September 2008. Human Resources Department (73911)

  1. JOINT ADVISORY APPEALS BOARD

    CERN Multimedia

    Human Resources Division

    2002-01-01

    The Joint Advisory Appeals Board was convened to examine the appeal lodged by Mr Gert Jan Bossen with regard to dependent child allowance. As the appellant has not objected, the report of the Board and the final decision of the Director-General are brought to the notice of the personnel in accordance with Article R VI 1.20 of the Staff Regulations. The relevant documents will therefore be posted on the notice boards of the Administration Building (N° 60) from 1st to 15 March 2002. Human Resources Division Tel. 74128

  2. Joint Advisory Appeals Board

    CERN Multimedia

    HR Department

    2008-01-01

    The Joint Advisory Appeals Board has examined the internal appeal lodged by a member of the personnel with regard to the decision not to grant him an indefinite contract. The person concerned has not objected to the report of the Board and the final decision of the Director-General being brought to the notice of the members of the personnel. In application of Article R VI 1.18 of the Staff Regulations, these documents will therefore be posted on the notice board of the Main Building (Bldg. 500) from 26 May to 6 June 2008. Human Resources Department (73911)

  3. JOINT ADVISORY APPEALS BOARD

    CERN Multimedia

    Human Resources Division

    2002-01-01

    The Joint Advisory Appeals Board was convened to examine the appeal lodged by Mr Serge Peraire with regard to exceptional advancement. As the appellant has not objected, the report of the Board and the final decision of the Director-General are brought to the notice of the personnel in accordance with Article R VI 1.20 of the Staff Regulations. The relevant documents will therefore be posted on the notice boards of the Administration Building (N° 60) from 17 to 31 May 2002. Human Resources Division Tel. 74128

  4. Joint Advisory Appeals Board

    CERN Multimedia

    HR Department

    2008-01-01

    The Joint Advisory Appeals Board was convened to examine an internal appeal lodged by a member of the personnel with regard to the decision not to grant him an indefinite contract. The person concerned has not objected to the report of the Board and the final decision of the Director-General being brought to the notice of the members of the personnel, in accordance with Article R VI 1.18 of the Staff Regulations. These documents will therefore be posted on the notice board of the Main Building (Bldg. 60) from 21 January to 3 February 2008. Human Resources Department (73911)

  5. Joint Advisory Appeals Board

    CERN Multimedia

    2003-01-01

    The Joint Advisory Appeals Board was convened to examine the appeal lodged by Mr Aloïs Girardoz with regard to classification and advancement. As the appellant has not objected, the Board's report and the Director-General's decision will be brought to the notice of the personnel in accordance with Article R VI 1.20 of the Staff Regulations. The relevant documents will therefore be posted on the notice boards of the Administration Building (N° 60) from 15 to 29 August 2003. Human Resources Division Tel. 74128

  6. Prostate Specific Antigen (PSA) as Predicting Marker for Clinical Outcome and Evaluation of Early Toxicity Rate after High-Dose Rate Brachytherapy (HDR-BT) in Combination with Additional External Beam Radiation Therapy (EBRT) for High Risk Prostate Cancer.

    Science.gov (United States)

    Ecke, Thorsten H; Huang-Tiel, Hui-Juan; Golka, Klaus; Selinski, Silvia; Geis, Berit Christine; Koswig, Stephan; Bathe, Katrin; Hallmann, Steffen; Gerullis, Holger

    2016-11-10

    High-dose-rate brachytherapy (HDR-BT) with external beam radiation therapy (EBRT) is a common treatment option for locally advanced prostate cancer (PCa). Seventy-nine male patients (median age 71 years, range 50 to 79) with high-risk PCa underwent HDR-BT following EBRT between December 2009 and January 2016 with a median follow-up of 21 months. HDR-BT was administered in two treatment sessions (one week interval) with 9 Gy per fraction using a planning system and the Ir192 treatment unit GammaMed Plus iX. EBRT was performed with CT-based 3D-conformal treatment planning with a total dose administration of 50.4 Gy with 1.8 Gy per fraction and five fractions per week. Follow-up for all patients was organized one, three, and five years after radiation therapy to evaluate early and late toxicity side effects, metastases, local recurrence, and prostate-specific antigen (PSA) value measured in ng/mL. The evaluated data included age, PSA at time of diagnosis, PSA density, BMI (body mass index), Gleason score, D'Amico risk classification for PCa, digital rectal examination (DRE), PSA value after one/three/five year(s) follow-up (FU), time of follow-up, TNM classification, prostate volume, and early toxicity rates. Early toxicity rates were 8.86% for gastrointestinal, and 6.33% for genitourinary side effects. Of all treated patients, 84.81% had no side effects. All reported complications in early toxicity were grade 1. PSA density at time of diagnosis ( p = 0.009), PSA on date of first HDR-BT ( p = 0.033), and PSA on date of first follow-up after one year ( p = 0.025) have statistical significance on a higher risk to get a local recurrence during follow-up. HDR-BT in combination with additional EBRT in the presented design for high-risk PCa results in high biochemical control rates with minimal side-effects. PSA is a negative predictive biomarker for local recurrence during follow-up. A longer follow-up is needed to assess long-term outcome and toxicities.

  7. Predictive value of [-2]propsa (p2psa and its derivatives for the prostate cancer detection in the 2.0 to 10.0ng/mL PSA range

    Directory of Open Access Journals (Sweden)

    I. Vukovic

    Full Text Available ABSTRACT Introduction To assess predictive value of new tumor markers, precursor of prostate specific antigen (p2PSA and its derivates-%p2PSA and prostate health index (PHI in detection of patients with indolent and aggressive prostate cancer (PC in a subcohort of man whose total PSA ranged from 2 to 10ng/mL. Materials and Methods This cross-sectional study included 129 consecutive male patients aged over 50 years, with no previous history of PC and with normal digital rectal examination findings, but with serum PSA in interval between 2 and 10ng/mL. All patients underwent standard transrectal ultrasonography guided prostate biopsy for the first time. For all patients, serum PSA, free PSA (fPSA and p2PSA were measured and PHI and %p2PSA were calculated. Results PHI and %p2PSA levels were significanlty higher in patients with PC compared to those without this malignancy. The same findings have been observed in group of patients with Gleason score ≥7 compared to those with Gleason score <7. ROC analysis reveled the highest area under the curve with these two markers. Multivariate logistic regression showed significant improvement in PC detection and its agressive form (assumed as Gleason score ≥7. Conclusions New markers, derivates of p2PSA (especially %p2PSA and PHI, represente potentially very important clinical tool for predicting presence of PC, and even more important, to discriminate patients with Gleason score <7 from those with Gleason score ≥7 with total PSA in range from 2 to 10ng/mL.

  8. Predictive value of [-2]propsa (p2psa) and its derivatives for the prostate cancer detection in the 2.0 to 10.0ng/mL PSA range.

    Science.gov (United States)

    Vukovic, I; Djordjevic, D; Bojanic, N; Babic, U; Soldatovic, I

    2017-01-01

    To assess predictive value of new tumor markers, precursor of prostate specific antigen (p2PSA) and its derivates-%p2PSA and prostate health index (PHI) in detection of patients with indolent and aggressive prostate cancer (PC) in a subcohort of man whose total PSA ranged from 2 to 10ng/mL. This cross-sectional study included 129 consecutive male patients aged over 50 years, with no previous history of PC and with normal digital rectal examination findings, but with serum PSA in interval between 2 and 10ng/mL. All patients underwent standard transrectal ultrasonography guided prostate biopsy for the first time. For all patients, serum PSA, free PSA (fPSA) and p2PSA were measured and PHI and %p2PSA were calculated. PHI and %p2PSA levels were significanlty higher in patients with PC compared to those without this malignancy. The same findings have been observed in group of patients with Gleason score ≥7 compared to those with Gleason score <7. ROC analysis reveled the highest area under the curve with these two markers. Multivariate logistic regression showed significant improvement in PC detection and its agressive form (assumed as Gleason score ≥7). New markers, derivates of p2PSA (especially %p2PSA and PHI), represente potentially very important clinical tool for predicting presence of PC, and even more important, to discriminate patients with Gleason score <7 from those with Gleason score ≥7 with total PSA in range from 2 to 10ng/mL. Copyright® by the International Brazilian Journal of Urology.

  9. Developing a Vital Area Identification in Nuclear Power Plants Using PSA Results

    International Nuclear Information System (INIS)

    Kim, Kilyoo; Jung, Woosik; Yang, Juneon

    2008-01-01

    After 9/11, a physical protection and vital area identification (VAI) became important. In the well known VAI methodology, fault trees (FTs) to mitigate the initiating events caused by sabotage or terror should be prepared for the VAI. The KAERI VAI method is to develop FTs by using Probabilistic Safety Assessment (PSA) and Risk Informed In-service Inspection (RI-ISI) results. In this paper, how to develop a VAI model by using PSA and RI-ISI results is described

  10. Improvement of Prostate Cancer Diagnosis by Detecting PSA Glycosylation-Specific Changes.

    Science.gov (United States)

    Llop, Esther; Ferrer-Batallé, Montserrat; Barrabés, Sílvia; Guerrero, Pedro Enrique; Ramírez, Manel; Saldova, Radka; Rudd, Pauline M; Aleixandre, Rosa N; Comet, Josep; de Llorens, Rafael; Peracaula, Rosa

    2016-01-01

    New markers based on PSA isoforms have recently been developed to improve prostate cancer (PCa) diagnosis. However, novel approaches are still required to differentiate aggressive from non-aggressive PCa to improve decision making for patients. PSA glycoforms have been shown to be differentially expressed in PCa. In particular, changes in the extent of core fucosylation and sialylation of PSA N-glycans in PCa patients compared to healthy controls or BPH patients have been reported. The objective of this study was to determine these specific glycan structures in serum PSA to analyze their potential value as markers for discriminating between BPH and PCa of different aggressiveness. In the present work, we have established two methodologies to analyze the core fucosylation and the sialic acid linkage of PSA N-glycans in serum samples from BPH (29) and PCa (44) patients with different degrees of aggressiveness. We detected a significant decrease in the core fucose and an increase in the α2,3-sialic acid percentage of PSA in high-risk PCa that differentiated BPH and low-risk PCa from high-risk PCa patients. In particular, a cut-off value of 0.86 of the PSA core fucose ratio, could distinguish high-risk PCa patients from BPH with 90% sensitivity and 95% specificity, with an AUC of 0.94. In the case of the α2,3-sialic acid percentage of PSA, the cut-off value of 30% discriminated between high-risk PCa and the group of BPH, low-, and intermediate-risk PCa with a sensitivity and specificity of 85.7% and 95.5%, respectively, with an AUC of 0.97. The latter marker exhibited high performance in differentiating between aggressive and non-aggressive PCa and has the potential for translational application in the clinic.

  11. The state of art of internal fire PSA in nuclear power plant

    International Nuclear Information System (INIS)

    Yu Xinli; Zhao Bo; Zheng Xiangyang

    2010-01-01

    The operational experiences of nuclear power plants (NPPs) show that the internal fires challenge effectively the nuclear safety of NPPs. Thus, the authorities having jurisdiction in the world have enhanced the supervision on fire safety in NPPs, asking the licensees to perform fire hazard analysis and evaluate the fire risk. This article mainly describes the state of art of internal fire probabilistic safety assessment (PSA) in the world, and compares the main methods and standards for internal fire PSA. (authors)

  12. The influence of stress, depression, and anxiety on PSA screening rates in a nationally representative sample.

    Science.gov (United States)

    Kotwal, Ashwin A; Schumm, Phil; Mohile, Supriya G; Dale, William

    2012-12-01

    Prostate-specific antigen (PSA) testing for prostate cancer is controversial, with concerning rates of both overscreening and underscreening. The reasons for the observed rates of screening are unknown, and few studies have examined the relationship of psychological health to PSA screening rates. Understanding this relationship can help guide interventions to improve informed decision-making for screening. A nationally representative sample of men 57-85 years old without prostate cancer (N = 1169) from the National Social life, Health and Aging Project was analyzed. The independent relationship of validated psychological health scales measuring stress, anxiety, and depression to PSA testing rates was assessed using multivariable logistic regression analyses. PSA screening rates were significantly lower for men with higher perceived stress [odds ratio (OR) = 0.76, P = 0.006], but not for higher depressive symptoms (OR = 0.89, P = 0.22) when accounting for stress. Anxiety influences PSA screening through an interaction with number of doctor visits (P = 0.02). Among the men who visited the doctor once those with higher anxiety were less likely to be screened (OR = 0.65, P = 0.04). Conversely, those who visited the doctor 10+ times with higher anxiety were more likely to be screened (OR = 1.71, P = 0.04). Perceived stress significantly lowers PSA screening likelihood, and it seems to partly mediate the negative relationship of depression with screening likelihood. Anxiety affects PSA screening rates differently for men with different numbers of doctor visits. Interventions to influence PSA screening rates should recognize the role of the patients' psychological state to improve their likelihood of making informed decisions and improve screening appropriateness.

  13. Estimation Procedure of Common Cause Failure Parameters for CAFE-PSA

    International Nuclear Information System (INIS)

    Kang, Dae Il; Hwang, M. J.; Han, S. H.

    2009-03-01

    Detailed common cause failure (CCF) analysis generally needs the data for CCF events from other nuclear power plants because the CCF events rarely occur. Since 2002, KAERI has participated in the international common cause failure data exchange (ICDE) project to get data for CCF events. The operation office of the ICDE project sent about 400 CCF event data for emergency diesel generators, motor operated valves, check valves, pumps, and breakers to KAERI in 2009. However, there was no program available to analyze the ICDE CCF event data. Therefore, we developed the CAFE-PSA (common CAuse Failure Event analysis program for PSA) to estimate CCF parameters by using the ICDE CCF event data. With CAFE-PSA, the CCF events in the ICDE database can be qualitatively and quantitatively analyzed. The qualitative analysis results of the ICDE CCF data, by using the CAFE-PSA, showed that the major root cause of CCF events, for motor operated valves, check valves, and pumps, was the fault of their internal parts, and that for emergency diesel generators and breakers was the inadequacy of design/manufacture or construction. The quantitative analysis results of the ICDE CCF data, by using the CAFE-PSA, showed that the estimated Alpha Factors of components, mentioned above, were lower than those previously used in the PSA for domestic nuclear power plants, but were higher than those in USNRC 2007 CCF data. Through performing qualitative and quantitative analysis of the ICDE CCF data, by using the CAFE-PSA, a plan for coping with CCF events for design and operation of nuclear power plants can be produced and reasonable values for CCF parameters can be estimated. In addition, it is expected that the technical adequacy of PSA can be improved

  14. Preliminary Development of Regulatory PSA Models for SFR

    International Nuclear Information System (INIS)

    Choi, Yong Won; Shin, Andong; Bae, Moohoon; Suh, Namduk; Lee, Yong Suk

    2013-01-01

    Well developed PRA methodology exists for LWR (Light Water Reactor) and PHWR (Pressurized Heavy Water Reactor). Since KAERI is developing a prototype SFR targeting to apply for a license by 2017, KINS needs to have a PRA models to assess the safety of this prototype reactor. The purpose of this study is to develop the regulatory PSA models for the independent verification of the SFR safety. Since the design of the prototype SFR is not mature yet, we have tried to develop the preliminary models based on the design data of KAERI's previous SFR design. In this study, the preliminary initiating events of level 1 internal event for SFR were selected through reviews of existing PRA (LWR, PRISM, ASTRID and KALIMER-600) models. Then, the event tree for each selected initiating event was developed. The regulatory PRA models of SFR developed are preliminary in a sense, because the prototype SFR design is not mature and provided yet. Still it might be utilized for the forthcoming licensing review in assessing the risk of safety issues and the configuration control of the design

  15. SEPRA - shutdown PSA for the OLKILUOTO nuclear power plant

    International Nuclear Information System (INIS)

    Himanen, R.

    1995-01-01

    The utility TVO has extended the PSA study to the analysis of refueling, shutdown and startup. The Shutdown Event PRA (SEPRA) was reported to the authority in September 1992. The study consists of the analysis of leaks and loss of decay heat removal in the planned shutdown conditions. Special studies were performed for the cold pressurization, for local criticality events, for heavy load transport and for the transients during startup and shutdown. A remarkable effort was put to identify risks, i.e. to the qualitative analysis. The regular preventive maintenance tasks in the refueling outages were analyzed and the important tasks were selected for further studies. Besides the severe core damage risk the utility was interested in less grave consequences, e.g. the economic risks, causing significant extension of outages. The plant specific screening of initiators consisted of a study on the incident history and of interviewing the plant personnel on selected tasks. A number of thermohydraulic calculations were carried out to support the analysis of accident sequences. The operator actions after an initiating event were verified with the operating staff. The annual core damage risk from the refueling outage is about one forth of the total annual risk. The modifications decreased significantly the core damage frequency. It is foreseen that the SEPRA will form a basis of the procedure enhancement for the low power states. (author) 5 figs., 1 tab., 10 refs

  16. PSA application for the scram system of Romanian TRIGA Reactor

    International Nuclear Information System (INIS)

    Laslau, Florica; Negut, Gheorghe

    2008-01-01

    The paper is dedicated to the fault tree analysis of the scram system in TRIGA-INR Pitesti reactor. It is a brief description of the scram system which involves instrumentation, mechanical, electrical,and control devices. The failure criteria considered is fail to drop 5 of 8 control rods. Fault tree was developed using immediate cause principle. The reliability data base used is developed in INR Pitesti based on the IAEA data available. The fault tree was analyzed by an original PC code developed for Romanian PSA program. The dominant for this fault tree appeared to be the human errors. This deserves a sensitivity analysis. If we do not consider the CCF errors contribution, the system computed unavailability is: A = 1.25 · 10 -7 . The failure rate is 1.087 · 10 -2 eV/1000 yr. The mean time between failures is 105 years. Taking in the account roads stuck common cause failure, unavailability will increase by two magnitude orders, A = 3.02 · 10 -5 . We considered this number still provides a reassuring mean time between failures. This value is within the limits accepted by similar scram system studies, but is higher than the value obtained in a similar way for the TRIGA reactor of University of Texas. The reason was the taking into account in our case the human error and CCF

  17. Improved methods for dependent failure analysis in PSA

    International Nuclear Information System (INIS)

    Ballard, G.M.; Games, A.M.

    1988-01-01

    The basic design principle used in ensuring the safe operation of nuclear power plant is defence in depth. This normally takes the form of redundant equipment and systems which provide protection even if a number of equipment failures occur. Such redundancy is particularly effective in ensuring that multiple, independent equipment failures with the potential for jeopardising reactor safety will be rare events. However the achievement of high reliability has served to highlight the potentially dominant role of multiple, dependent failures of equipment and systems. Analysis of reactor operating experience has shown that dependent failure events are the major contributors to safety system failures and reactor incidents and accidents. In parallel PSA studies have shown that the results of a safety analysis are sensitive to assumptions made about the dependent failure (CCF) probability for safety systems. Thus a Westinghouse Analysis showed that increasing system dependent failure probabilities by a factor of 5 led to a factor 4 increase in core. This paper particularly refers to the engineering concepts underlying dependent failure assessment touching briefly on aspects of data. It is specifically not the intent of our work to develop a new mathematical model of CCF but to aid the use of existing models

  18. Survey on Prognostics Techniques for Updating Initiating Event Frequency in PSA

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hyeonmin; Heo, Gyunyoung [Kyung Hee University, Yongin (Korea, Republic of)

    2015-05-15

    One of the applications using PSA is a risk monito. The risk monitoring is real-time analysis tool to decide real-time risk based on real state of components and systems. In order to utilize more effective, the methodologies that manipulate the data from Prognostics was suggested. Generally, Prognostic comprehensively includes not only prognostic but also monitoring and diagnostic. The prognostic method must need condition monitoring. In case of applying PHM to a PSA model, the latest condition of NPPs can be identified more clearly. For reducing the conservatism and uncertainties, we suggested the concept that updates the initiating event frequency in a PSA model by using Bayesian approach which is one of the prognostics techniques before. From previous research, the possibility that PSA is updated by using data more correctly was found. In reliability theory, the Bathtub curve divides three parts (infant failure, constant and random failure, wareout failure). In this paper, in order to investigate the applicability of prognostic methods in updating quantitative data in a PSA model, the OLM acceptance criteria from NUREG, the concept of how to using prognostic in PSA, and the enabling prognostic techniques are suggested. The prognostic has the motivation that improved the predictive capabilities using existing monitoring systems, data, and information will enable more accurate equipment risk assessment for improved decision-making.

  19. Survey on Prognostics Techniques for Updating Initiating Event Frequency in PSA

    International Nuclear Information System (INIS)

    Kim, Hyeonmin; Heo, Gyunyoung

    2015-01-01

    One of the applications using PSA is a risk monito. The risk monitoring is real-time analysis tool to decide real-time risk based on real state of components and systems. In order to utilize more effective, the methodologies that manipulate the data from Prognostics was suggested. Generally, Prognostic comprehensively includes not only prognostic but also monitoring and diagnostic. The prognostic method must need condition monitoring. In case of applying PHM to a PSA model, the latest condition of NPPs can be identified more clearly. For reducing the conservatism and uncertainties, we suggested the concept that updates the initiating event frequency in a PSA model by using Bayesian approach which is one of the prognostics techniques before. From previous research, the possibility that PSA is updated by using data more correctly was found. In reliability theory, the Bathtub curve divides three parts (infant failure, constant and random failure, wareout failure). In this paper, in order to investigate the applicability of prognostic methods in updating quantitative data in a PSA model, the OLM acceptance criteria from NUREG, the concept of how to using prognostic in PSA, and the enabling prognostic techniques are suggested. The prognostic has the motivation that improved the predictive capabilities using existing monitoring systems, data, and information will enable more accurate equipment risk assessment for improved decision-making

  20. Challenges and status of multi-unit PSA development in Canada

    International Nuclear Information System (INIS)

    Yalaoui, Smain

    2015-01-01

    Firstly, this paper discusses the issues and challenges related to the development of a Multi-Unit PSA (MU-PSA) and the general recommendations and conclusions from the MU-PSA Workshop organized by the CNSC in Ottawa, November 2014. This includes a discussion regarding the issue related to the methodological challenges in performing MU-PSA, the site-based risk metrics to be adopted, and the issue of risk aggregation across all hazards and all units. The paper also addresses the challenges for establishing site-based safety goals as the current safety goals were established on a per-unit basis. CNSC Staff efforts, both at the national and international level, on developing whole-site safety goals and guidance on MU-PSA and risk aggregation methodologies will also be discussed. Finally, the paper will provide a summary of the industry effort and road map for completing the pilot Whole-site PSA project for the Pickering Nuclear Generating Station, as requested by the Commission following to the public hearing for licence renewal in February 20 and May 29-31, 2013. (author)