Safety margin evaluation concepts for plant Up rates and life extension. Results of the OECD/NEA/CSNI working group on Safety Margin Action Plan (SMAP)

International Nuclear Information System (INIS)

Belac, J

2006-01-01

This presentation summarizes results of the OECD/NEA/CSNI working group on Safety Margin Action Plan (SMAP) aimed to develop generalized safety margin concept and means of its quantification for the process of evaluating plant safety in the frame of plant life extension and power up rating activities to be used by OECD member countries. (author)

Measuring Safety Culture on Ships Using Safety Climate: A Study among Indian Officers

Directory of Open Access Journals (Sweden)

Yogendra Bhattacharya

2015-12-01

Full Text Available Workplace safety continues to be an area of concern in the maritime industry due to the international nature of the operations. The effectiveness of extensive legislation to manage shipboard safety remains in doubt. The focus must therefore shift towards the human element - seafarers and their perceptions of safety. The study aims to understand the alignment that exists between safety culture and safety climate on board ships as perceived by seafarers. The underlying factors of safety climate were identified using factor analysis which isolated seven factors - Support on Safety, Organizational Support, Resource Availability, Work Environment, Job Demands, ‘Just’ Culture, and Safety Compliance. The perception of safety level of seafarers was found to be low indicating the existence of misalignments between safety culture values and the actual safety climate. The study also reveals that the safety perceptions of officers employed directly by ship owners and those by managers do not differ significantly, nor do they differ between senior and junior officers. A shift in perspective towards how seafarers themselves feel towards safety might provide more effective solutions – instead of relying on regulations - and indeed aid in reducing incidents on board. This paper details practical suggestions on how to identify the factors that contribute towards a better safety climate on board ships.

Safety reassessment and life extension

International Nuclear Information System (INIS)

Gouffon, A.

1992-12-01

The safety reassessment policy implemented in France is a means of ensuring that no important point has been overlooked in the continuous safety reassessment process constituted by the integration of operating feedback. It also provides an opportunity for reappraisal of the basic design of a plant and examination of discrepancies between the safety options prevailing when it was built and those currently adopted. After a ten-year operating period, safety reassessment should enable identification of aging effects on structures and equipment, leading to improvement of component servicing and surveillance programs and provision for replacements which could be necessary

Tolerability and safety of Souvenaid in patients with mild Alzheimer's disease: results of multi-center, 24-week, open-label extension study.

Science.gov (United States)

Olde Rikkert, Marcel G M; Verhey, Frans R; Blesa, Rafael; von Arnim, Christine A F; Bongers, Anke; Harrison, John; Sijben, John; Scarpini, Elio; Vandewoude, Maurits F J; Vellas, Bruno; Witkamp, Renger; Kamphuis, Patrick J G H; Scheltens, Philip

2015-01-01

The medical food Souvenaid, containing the specific nutrient combination Fortasyn Connect, is designed to improve synapse formation and function in patients with Alzheimer's disease (AD). Two double-blind randomized controlled trials (RCT) with Souvenaid of 12 and 24 week duration (Souvenir I and Souvenir II) showed that memory performance was improved in drug-naïve mild AD patients, whereas no effects on cognition were observed in a 24-week RCT (S-Connect) in mild to moderate AD patients using AD medication. Souvenaid was well-tolerated in all RCTs. In this 24-week open-label extension (OLE) study to the 24-week Souvenir II RCT, long-term safety and intake adherence of the medical food Souvenaid was evaluated. Patients with mild AD (n = 201) received Souvenaid once-daily during the OLE. Main outcome parameters were safety and product intake adherence. The memory domain z-score from a revised neuropsychological test battery was continued as exploratory parameter. Compared to the RCT, a similar (low) incidence and type of adverse events was observed, being mainly (68.3%) of mild intensity. Pooled data (RCT and OLE) showed that 48-week use of Souvenaid was well tolerated with high intake adherence (96.1%). Furthermore, a significant increase in the exploratory memory outcome was observed in both the active-active and control-active groups during Souvenaid intervention. Souvenaid use for up to 48-weeks was well tolerated with a favorable safety profile and high intake adherence. The findings in this OLE study warrant further investigation toward the long-term safety and efficacy of Souvenaid in a well-controlled, double-blind RCT.

Extension of CFD Codes Application to Two-Phase Flow Safety Problems - Phase 3

International Nuclear Information System (INIS)

Bestion, D.; Anglart, H.; Mahaffy, J.; Lucas, D.; Song, C.H.; Scheuerer, M.; Zigh, G.; Andreani, M.; Kasahara, F.; Heitsch, M.; Komen, E.; Moretti, F.; Morii, T.; Muehlbauer, P.; Smith, B.L.; Watanabe, T.

2014-11-01

The Writing Group 3 on the extension of CFD to two-phase flow safety problems was formed following recommendations made at the 'Exploratory Meeting of Experts to Define an Action Plan on the Application of Computational Fluid Dynamics (CFD) Codes to Nuclear Reactor Safety Problems' held in Aix-en-Provence, in May 2002. Extension of CFD codes to two-phase flow is significant potentiality for the improvement of safety investigations, by giving some access to smaller scale flow processes which were not explicitly described by present tools. Using such tools as part of a safety demonstration may bring a better understanding of physical situations, more confidence in the results, and an estimation of safety margins. The increasing computer performance allows a more extensive use of 3D modelling of two-phase Thermal hydraulics with finer nodalization. However, models are not as mature as in single phase flow and a lot of work has still to be done on the physical modelling and numerical schemes in such two-phase CFD tools. The Writing Group listed and classified the NRS problems where extension of CFD to two-phase flow may bring real benefit, and classified different modelling approaches in a first report (Bestion et al., 2006). First ideas were reported about the specification and analysis of needs in terms of validation and verification. It was then suggested to focus further activity on a limited number of NRS issues with a high priority and a reasonable chance to be successful in a reasonable period of time. The WG3-step 2 was decided with the following objectives: - selection of a limited number of NRS issues having a high priority and for which two-phase CFD has a reasonable chance to be successful in a reasonable period of time; - identification of the remaining gaps in the existing approaches using two-phase CFD for each selected NRS issue; - review of the existing data base for validation of two-phase CFD application to the selected NRS problems

Efficacy and safety of switching from reference infliximab to CT-P13 compared with maintenance of CT-P13 in ankylosing spondylitis: 102-week data from the PLANETAS extension study.

Science.gov (United States)

Park, Won; Yoo, Dae Hyun; Miranda, Pedro; Brzosko, Marek; Wiland, Piotr; Gutierrez-Ureña, Sergio; Mikazane, Helena; Lee, Yeon-Ah; Smiyan, Svitlana; Lim, Mie-Jin; Kadinov, Vladimir; Abud-Mendoza, Carlos; Kim, HoUng; Lee, Sang Joon; Bae, YunJu; Kim, SuYeon; Braun, Jürgen

2017-02-01

To investigate the efficacy and safety of switching from infliximab reference product (RP) to its biosimilar or maintaining biosimilar treatment in patients with ankylosing spondylitis (AS). This open-label extension study recruited patients with AS who completed a 54-week, randomised controlled study comparing CT-P13 with RP (PLANETAS). CT-P13 (5 mg/kg) was administered intravenously every 8 weeks from week 62 to week 102. Efficacy end points included the proportion of patients achieving Assessment of SpondyloArthritis international Society (ASAS)20. Antidrug antibodies (ADAs) were measured using an electrochemiluminescent method. Data were analysed for patients treated with CT-P13 in the main PLANETAS study and the extension (maintenance group) and those who were switched to CT-P13 during the extension study (switch group). Overall, 174 (82.9%) of 210 patients who completed the first 54 weeks of PLANETAS and agreed to participate in the extension were enrolled. Among these, 88 were maintained on CT-P13 and 86 were switched to CT-P13 from RP. In these maintenance and switch groups, respectively, ASAS20 response rates at week 102 were 80.7% and 76.9%. ASAS40 and ASAS partial remission were also similar between groups. ADA positivity rates were comparable (week 102: 23.3% vs 27.4%). Adverse events led to treatment discontinuation during the extension study in 3 (3.3%) and 4 (4.8%) patients, respectively. This is the first study to show that switching from RP to its biosimilar CT-P13 is possible without negative effects on safety or efficacy in patients with AS. In the maintenance group, CT-P13 was effective and well tolerated over 2 years of treatment. NCT01571206; Results. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/.

NRU licence extension via integrated safety review

Energy Technology Data Exchange (ETDEWEB)

Mantifel, N. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

2014-07-01

The National Research Reactor, NRU at AECL Chalk River Laboratories achieved first criticality in November 1957. The completion of an Integrated Safety Review (ISR) in 2011, and subsequent Global Assessment Report (GAR), and Integrated Implementation Plan (IIP) has given confidence in the safe and reliable operation of NRU, therefore extending the licensing case to safely and reliably operate NRU until 2021 and beyond (64+ years of operation). The key vehicle to achieve this confidence is the IIP, that resulted from the ISR. NRU's IIP is a 10 year plan that addresses the gaps identified in the ISR between modern codes and standards in a prioritized approach. AECL is currently in year 3 of the IIP execution, is on or ahead of schedule to complete the identified improvements. The IIP in conjunction with a License Condition Handbook has replaced the licensing protocol with the Canadian Nuclear Safety Commission, (CNSC). Execution of the IIP to plan supports the continued safe operation of NRU. The ISR was carried out with the recognition that the NRU reactor is a research and isotope producing reactor approaching license renewal and not a power reactor undergoing refurbishment and life extension. Therefore, the IIP is being executed while NRU continues to deliver on its three missions: production of medical isotopes, support for fuels and materials research, and serving as a high flux neutron source in support of research relying on neutron scattering. The IIP is grouped into 5 Global Issue Groups, (GIGs) to support focused execution. The activities and tasks within the five GIGs are being executed via a matrix organization through the use of the Chalk River Laboratories Corrective Action Program to ensure the assignment of actions, completion and evidence to support closure is documented and retained. This paper discusses the approach taken by AECL to license and ensure safe, reliable operation of NRU until 2021 and beyond. (author)

Assessment of extensive surgery for locally advanced lung cancer. Safety and efficacy of induction therapy

International Nuclear Information System (INIS)

Niwa, Hiroshi; Nakamae, Katsumi; Yamada, Takeshi; Kani, Hisanori; Maemoto, Katsutoshi; Mizuno, Takeo

1999-01-01

Locally advanced lung cancer has a poor prognosis, despite extensive surgery conducted in an effort to improve survival. We evaluated the safety and efficacy of induction therapy prior to extensive surgery for locally advanced lung cancer. Primary resection for lung cancer was done in 549 consecutive patients divided into three groups; 446 undergoing standard pulmonary resection (no extensive surgery), 87 undergoing extensive surgery without induction therapy, and 16 undergoing surgery after induction therapy. Morbidity was 23.5%, 28.6%, and 43.8%, respectively. The rate was significantly higher in the induction group compared with the no extensive surgery group (P<0.05). Surgical mortality was 0.67%, 3.4%, and 6.3%, respectively. The difference was statistically significant between the no extensive surgery and extensive surgery groups (P<0.02), and between the no extensive surgery and induction groups (P<0.02). Hospital mortality was 2.2%, 9.2%, and 6.3%, respectively. The rates were significantly higher in the extensive surgery (P<0.01) and induction (P<0.05) groups compared to the no extensive surgery group. Five-year survival was 50.3% for the patients who received induction therapy, and 14.7% for the patients who did not receive induction therapy. Survival differences between the induction and non induction groups were not significant, but some patients with T3 or T4 disease may benefit from induction therapy. The high morbidity of induction treatment should be recognized, and strict candidate selection and careful postoperative care used to help prevent increased mortality. (author)

Study on risk insight for additional ILRT interval extension

International Nuclear Information System (INIS)

Seo, M. R.; Hong, S. Y.; Kim, M. K.; Chung, B. S.; Oh, H. C.

2005-01-01

In U.S., the containment Integrated Leakage Rate Test (ILRT) interval was extended from 3 times per 10 years to once per 10 years based on NUREG-1493 'Performance-Based Containment Leak-Test Program' in 1995. In September, 2001, ILRT interval was extended up to once per 15 years based on Nuclear Energy Industry (NEI) provisional guidance 'Interim Guidance for Performing Risk Impact Assessments In Support of One-Time Extensions for Containment Integrated Leakage Rate Test Surveillance Intervals'. In Korea, the containment ILRT was performed with 5 year interval. But, in MOST(Ministry of Science and Technology) Notice 2004-15 'Standard for the Leak- Rate Test of the Nuclear Reactor Containment', the extension of the ILRT interval to once per 10 year can be allowed if some conditions are met. So, the safety analysis for the extension of Yonggwang Nuclear (YGN) Unit 1 and 2 ILRT interval extension to once per 10 years was completed based on the methodology in NUREG-1493. But, during review process by regulatory body, KINS, it was required that some various risk insight or index for risk analysis should be developed. So, we began to study NEI interim report for 15 year ILRT interval extension. As previous analysis based on NUREG-1493, MACCS II (MELCOR Accident Consequence Code System) computer code was used for the risk analysis of the population, and the population dose was selected as a reference index for the risk evaluation

Extension of Surveillance Test Interval of Safety Injection Pump for APR-1400 Reactors to Improve Reliability and Availability of the Pump

Energy Technology Data Exchange (ETDEWEB)

Osama, A. Rezk; Jung, J. C.; Lee, Yong-Kwan [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2015-10-15

The safety features function to localize, control, mitigate, and terminate such incidents and to hold exposure levels below applicable limits. The safety injection system is comprised of four independent mechanical trains without any tie line among the injection paths and two electrical divisions. Each train has one active Safety Injection Pump (SIP) and one passive Safety Injection Tank (SIT) equipped with a Fluidic Device (FD), each train provides 50% of the minimum injection flow rate for breaks larger than the size of a direct vessel injection line. For breaks equal to or smaller than the size of a direct vessel injection line, each train has 100% of the required capacity. The low pressure injection pumps with common header installed in the conventional design are eliminated, and the functions for safety injection and shutdown cooling are separated. The arrangement of safety injection system for APR-1400 as shown in figure (1). The results obtained in this work show that STI extensions for the SIS feasible without any unacceptable increase in the plant total risk, STI extensions are acceptable for safety injection system to provide plant operational flexibility in the performance of both corrective and preventive maintenance for the safety injection system.

Road safety risk evaluation and target setting using data envelopment analysis and its extensions.

Science.gov (United States)

Shen, Yongjun; Hermans, Elke; Brijs, Tom; Wets, Geert; Vanhoof, Koen

2012-09-01

Currently, comparison between countries in terms of their road safety performance is widely conducted in order to better understand one's own safety situation and to learn from those best-performing countries by indicating practical targets and formulating action programmes. In this respect, crash data such as the number of road fatalities and casualties are mostly investigated. However, the absolute numbers are not directly comparable between countries. Therefore, the concept of risk, which is defined as the ratio of road safety outcomes and some measure of exposure (e.g., the population size, the number of registered vehicles, or distance travelled), is often used in the context of benchmarking. Nevertheless, these risk indicators are not consistent in most cases. In other words, countries may have different evaluation results or ranking positions using different exposure information. In this study, data envelopment analysis (DEA) as a performance measurement technique is investigated to provide an overall perspective on a country's road safety situation, and further assess whether the road safety outcomes registered in a country correspond to the numbers that can be expected based on the level of exposure. In doing so, three model extensions are considered, which are the DEA based road safety model (DEA-RS), the cross-efficiency method, and the categorical DEA model. Using the measures of exposure to risk as the model's input and the number of road fatalities as output, an overall road safety efficiency score is computed for the 27 European Union (EU) countries based on the DEA-RS model, and the ranking of countries in accordance with their cross-efficiency scores is evaluated. Furthermore, after applying clustering analysis to group countries with inherent similarity in their practices, the categorical DEA-RS model is adopted to identify best-performing and underperforming countries in each cluster, as well as the reference sets or benchmarks for those

Status of conceptual safety design study of Japanese sodium-cooled fast reactor

International Nuclear Information System (INIS)

Kubo, Shigenobu; Kurisaka, Kenichi; Niwa, Hajime; Shimakawa, Yoshio

2005-01-01

In this paper, the current conceptual safety design and related evaluation of Japanese Sodium-cooled Fast Reactor which is studied in the framework of the Feasibility Study (FS) on commercialized Fast Reactor Cycle Systems in Japan are described. The purpose of the safety design is to establish a feasible safety concept of FBR which aims at a sustainable energy source of the next generations. The safety targets and the safety design principle are set aiming at realizing worldwide acceptability of the safety level. The basic safety design concept, which can meet the safety targets, was formulated taking along with the defense-in-depth philosophy as the basic safety design principle. In order to cope with wide range of energy and resource demands, there are some various designs both of oxide and metal fuel for JSFR. Some analytical results of typical design basis events, design extension conditions and core damage frequency estimation show the feasibility of the safety design concept for them. (author)

Long-Term Efficacy, Safety, and Pharmacokinetics of Drisapersen in Duchenne Muscular Dystrophy: Results from an Open-Label Extension Study.

Directory of Open Access Journals (Sweden)

Nathalie M Goemans

Full Text Available Drisapersen induces exon 51 skipping during dystrophin pre-mRNA splicing and allows synthesis of partially functional dystrophin in Duchenne muscular dystrophy (DMD patients with amenable mutations.This 188-week open-label extension of the dose-escalation study assessed the long-term efficacy, safety, and pharmacokinetics of drisapersen (PRO051/GSK2402968, 6 mg/kg subcutaneously, in 12 DMD subjects. Dosing was once weekly for 72 weeks. All subjects had a planned treatment interruption (weeks 73-80, followed by intermittent dosing (weeks 81-188.Subjects received a median (range total dose of 5.93 (5.10 to 6.02 mg/kg drisapersen. After 177 weeks (last efficacy assessment, median (mean [SD] six-minute walk distance (6MWD improved by 8 (-24.5 [161] meters for the 10 subjects able to complete the 6MWD at baseline (mean age [SD]: 9.5 [1.9] years. These statistics include 2 subjects unable to complete the test at later visits and who scored "zero". When only the 8 ambulant subjects at week 177 were taken into account, a median (mean [SD] increase of 64 (33 [121] meters in 6MWD was observed. Of 7 subjects walking ≥330 m at extension baseline, 5 walked farther at week 177. Of 3 subjects walking <330 m, 2 lost ambulation, while 1 declined overall but walked farther at some visits. Over the 188 weeks, the most common adverse events were injection-site reactions, raised urinary α1-microglobulin and proteinuria. Dystrophin expression was detected in all muscle biopsies obtained at week 68 or 72.Drisapersen was generally well tolerated over 188 weeks. Possible renal effects, thrombocytopenia and injection-site reactions warrant continued monitoring. Improvements in the 6MWD at 12 weeks were sustained after 3.4 years of dosing for most patients. For a small, uncontrolled study, the outcomes are encouraging, as natural history studies would anticipate a decline of over 100 meters over a 3-year period in a comparable cohort.ClinicalTrials.gov NCT01910649.

Tofacitinib, an oral Janus kinase inhibitor, for the treatment of chronic plaque psoriasis: Long-term efficacy and safety results from 2 randomized phase-III studies and 1 open-label long-term extension study.

Science.gov (United States)

Papp, Kim A; Krueger, James G; Feldman, Steven R; Langley, Richard G; Thaci, Diamant; Torii, Hideshi; Tyring, Stephen; Wolk, Robert; Gardner, Annie; Mebus, Charles; Tan, Huaming; Luo, Yingchun; Gupta, Pankaj; Mallbris, Lotus; Tatulych, Svitlana

2016-05-01

Tofacitinib is an oral Janus kinase inhibitor being investigated for psoriasis. We sought to report longer-term tofacitinib efficacy and safety in patients with moderate to severe psoriasis. Data from 2 identical phase-III studies, Oral-treatment Psoriasis Trial Pivotal 1 and 2, were pooled with data from these patients in an ongoing open-label long-term extension study. Patients (n = 1861) were randomized 2:2:1 to tofacitinib 5 mg, 10 mg, or placebo twice daily (BID). At week 16, placebo patients were rerandomized to tofacitinib. Pivotal study participants could enroll into the long-term extension where they received tofacitinib at 10 mg BID for 3 months, after which dosing could be 5 or 10 mg BID. At week 28, the proportions of patients randomized to tofacitinib 5 and 10 mg BID achieving 75% or greater reduction in Psoriasis Area and Severity Index score from baseline were 55.6% and 68.8%, and achieving Physician Global Assessment of clear or almost clear were 54.7% and 65.9%. Efficacy was maintained in most patients through 24 months. Serious adverse events and discontinuations because of adverse events were reported in less than 11% of patients over 33 months of tofacitinib exposure. There was no dose comparison beyond week 52. Oral tofacitinib demonstrated sustained efficacy in patients with psoriasis through 2 years, with 10 mg BID providing greater efficacy than 5 mg BID. No unexpected safety findings were observed. Copyright © 2016 American Academy of Dermatology, Inc. Published by Elsevier Inc. All rights reserved.

Status of Ignalina's safety analysis reports

International Nuclear Information System (INIS)

Uspuras, E.

1999-01-01

Ignalina NPP is unique among RBMK type reactors in the scope and comprehensiveness of international studies which have been performed to verify its design parameters and analyze risk levels. International assistance took several forms, a very valuable mod of assistance utilized the knowledge of international experts in extensive international studies whose purpose was: collection, systematization and verification of plant design data; analysis of risk levels; recommendations leading to improvements in the safety lave; transfer of state of the art analytical methodology to Lithuanian specialists. The major large scale international studies include: probabilistic risk analysis; extensive international study meant to provide comprehensive overview of plant status with special emphasis on safety aspects; an extensive review of the Safety Analysis Report by an independent group of international experts. In spite of the safety improvements and analyses which have been performed at the Ignalina NPP, much remains to be done in the nearest future

Studies on Labour Safety in Construction Sites

Directory of Open Access Journals (Sweden)

S. Kanchana

2015-01-01

Full Text Available Construction industry has accomplished extensive growth worldwide particularly in past few decades. For a construction project to be successful, safety of the structures as well as that of the personnel is of utmost importance. The safety issues are to be considered right from the design stage till the completion and handing over of the structure. Construction industry employs skilled and unskilled labourers subject to construction site accidents and health risks. A proper coordination between contractors, clients, and workforce is needed for safe work conditions which are very much lacking in Indian construction companies. Though labour safety laws are available, the numerous accidents taking place at construction sites are continuing. Management commitment towards health and safety of the workers is also lagging. A detailed literature study was carried out to understand the causes of accidents, preventive measures, and development of safe work environment. This paper presents the results of a questionnaire survey, which was distributed among various categories of construction workers in Kerala region. The paper examines and discusses in detail the total working hours, work shifts, nativity of the workers, number of accidents, and type of injuries taking place in small and large construction sites.

Studies on Labour Safety in Construction Sites

Science.gov (United States)

Kanchana, S.; Sivaprakash, P.; Joseph, Sebastian

2015-01-01

Construction industry has accomplished extensive growth worldwide particularly in past few decades. For a construction project to be successful, safety of the structures as well as that of the personnel is of utmost importance. The safety issues are to be considered right from the design stage till the completion and handing over of the structure. Construction industry employs skilled and unskilled labourers subject to construction site accidents and health risks. A proper coordination between contractors, clients, and workforce is needed for safe work conditions which are very much lacking in Indian construction companies. Though labour safety laws are available, the numerous accidents taking place at construction sites are continuing. Management commitment towards health and safety of the workers is also lagging. A detailed literature study was carried out to understand the causes of accidents, preventive measures, and development of safe work environment. This paper presents the results of a questionnaire survey, which was distributed among various categories of construction workers in Kerala region. The paper examines and discusses in detail the total working hours, work shifts, nativity of the workers, number of accidents, and type of injuries taking place in small and large construction sites. PMID:26839916

Knowledge Translation and Patient Safety: The Canadian Adverse Events Study

OpenAIRE

Baker, G. Ross; Norton, Peter; Flintoft, Virginia

2006-01-01

The Canadian Adverse Events Study was the first national study of adverse events in Canadian hospitals. Learning from the controversy surrounding similar studies in other countries, the team engaged in extensive knowledge translation activities throughout the life of the project. Using meetings, Web-based communication and other tools, the team successfully prepared most Canadian stakeholders for the study’s release, allowing them to develop anticipatory patient safety initiatives. However, u...

Refurbishment and safety up-gradation of Cirus Reactor

International Nuclear Information System (INIS)

Rao, D.V.H.

2004-01-01

Cirus, a 40 MWth, vertical tank type research reactor, having a wide range of research facilities, was commissioned in 1960. This research facility has been operated and utilized extensively for nearly four decades. With a view to assess the residual life of the reactor, detailed ageing studies were carried out. Based on this, refurbishment work for life extension was undertaken. During this work, additional safety features were incorporated to improve the overall safety of the reactor. This lecture details the methodologies used for ageing studies and refurbishment activities for life extension with enhanced safety. (author)

Systems for the monitoring of working conditions relating to health and safety : extensive descriptions : Belgium, Germany, Luxembourg, The Netherlands

NARCIS (Netherlands)

Prins, R.; Verboon, F.

1991-01-01

This report contains the extensive descriptions of (some of) the monitoring systems on health and safety in use in the Benelux countries and Germany. The project of which this report is a part aimed at gathering information on monitoring systems throughout the EC member states.

ROMANA 3: a phase 3 safety extension study of anamorelin in advanced non-small-cell lung cancer (NSCLC) patients with cachexia.

Science.gov (United States)

Currow, D; Temel, J S; Abernethy, A; Milanowski, J; Friend, J; Fearon, K C

2017-08-01

Cancer anorexia-cachexia is a debilitating condition frequently observed in NSCLC patients, characterized by decreased body weight, reduced food intake, and impaired quality of life. Anamorelin, a novel selective ghrelin receptor agonist, has anabolic and appetite-enhancing activities. ROMANA 3 was a safety extension study of two phase 3, double-blind studies that assessed safety and efficacy of anamorelin in advanced NSCLC patients with cachexia. Patients with preserved Eastern Cooperative Oncology Group ≤2 after completing 12 weeks (w) on the ROMANA 1 or ROMANA 2 trials (0-12 weeks) could enroll in ROMANA 3 and continue to receive anamorelin 100 mg or placebo once daily for an additional 12w (12-24 weeks). The primary endpoint of ROMANA 3 was anamorelin safety/tolerability (12-24 weeks). Secondary endpoints included changes in body weight, handgrip strength (HGS), and symptom burden (0-24 weeks). Of the 703 patients who completed ROMANA 1 and ROMANA 2, 513 patients entered ROMANA 3 (anamorelin, N = 345, mean age 62.0 years; placebo, N = 168; mean age 62.2 years). During ROMANA 3, anamorelin and placebo groups had similar incidences of treatment-emergent adverse events (TEAEs; 52.2% versus 55.7%), grade ≥3 TEAEs (22.4% versus 21.6%), and serious TEAEs (12.8% versus 12.6%). There were 36 (10.5%) and 23 (13.8%) deaths in the anamorelin and placebo groups, respectively; none were drug-related. Improvements in body weight and anorexia-cachexia symptoms observed in the original trials were consistently maintained over 12-24 weeks. Anamorelin, versus placebo, significantly increased body weight from baseline of original trials at all time points (P cachexia symptoms at weeks 3, 6, 9, 12, and 16 (P < 0.05). No significant improvement in HGS was seen in either group. During the 12-24 weeks ROMANA 3 trial, anamorelin continued to be well tolerated. Over the entire 0-24w treatment period, body weight and symptom burden were improved

Adapting Extension Food Safety Programming for Vegetable Growers to Accommodate Differences in Ethnicity, Farming Scale, and Other Individual Factors

Science.gov (United States)

Kline, Terence R.; Kneen, Harold; Barrett, Eric; Kleinschmidt, Andy; Doohan, Doug

2012-01-01

Differences in vegetable production methods utilized by American growers create distinct challenges for Extension personnel providing food safety training to producer groups. A program employing computers and projectors will not be accepted by an Amish group that does not accept modern technology. We have developed an outreach program that covers…

Extension of the nuclear power plant lifetime

International Nuclear Information System (INIS)

Keramsi, Alain

2011-01-01

After a presentation of the French nuclear context (history of the reactor fleet, choice of reactor type, PWR operation principle, competitiveness, environmental performance), this Power Point presentation addresses the context and challenges of the operation lifetime (average fleet age in different countries, examples of extensions, case of the United States, what is at stake with lifetime extension, decennial visits, EDF strategy), discusses the EDF's safety objectives (definition of the three main safety functions, impact of the operation duration and of the coexistence of two generations for the safety functions), discusses how to manage the ageing phenomenon for replaceable and non-replaceable components

In question: the scientific value of preclinical safety pharmacology and toxicology studies with cell-based therapies

Directory of Open Access Journals (Sweden)

Christiane Broichhausen

2014-01-01

Full Text Available A new cell-based medicinal product containing human regulatory macrophages, known as Mreg_UKR, has been developed and conforms to expectations of a therapeutic drug. Here, Mreg_UKR was subjected to pharmacokinetic, safety pharmacology, and toxicological testing, which identified no adverse reactions. These results would normally be interpreted as evidence of the probable clinical safety of Mreg_UKR; however, we contend that, owing to their uncertain biological relevance, our data do not fully support this conclusion. This leads us to question whether there is adequate scientific justification for preclinical safety testing of similar novel cell-based medicinal products using animal models. In earlier work, two patients were treated with regulatory macrophages prior to kidney transplantation. In our opinion, the absence of acute or chronic adverse effects in these cases is the most convincing available evidence of the likely safety of Mreg_UKR in future recipients. On this basis, we consider that safety information from previous clinical investigations of related cell products should carry greater weight than preclinical data when evaluating the safety profile of novel cell-based medicinal products. By extension, we argue that omitting extensive preclinical safety studies before conducting small-scale exploratory clinical investigations of novel cell-based medicinal products data may be justifiable in some instances.

Refurbishment and safety upgradation of research reactor Cirus

International Nuclear Information System (INIS)

Marik, S.K.; Rao, D.V.H.; Bhatnagar, A.; Pant, R.C.; Tikku, A.C.; Sankar, S.

2006-01-01

Cirus, a 40 MW t, vertical tank type research reactor, having wide range of research facilities, was commissioned in the year 1960. This research reactor, situated at Mumbai, India has been operated and utilized extensively for isotope production, material testing and neutron beam research for nearly four decades. With a view to assess the residual life of the reactor, detailed ageing studies were carried out during the early 1990s. Based on these studies, refurbishment of Cirus for its life extension was taken up. During refurbishment, additional safety features were incorporated in various systems to qualify them for the current safety standards. This paper gives the details of the operating experiences, utilization of the reactor along with methodologies followed for carrying out detailed ageing studies, refurbishment and safety upgradation for its life extension

A study on the optimization of plant life extension and decommissioning for the improvement of economy in nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Shin, Jae In; Jung, K. J.; Chung, U. S.; Baik, S. T.; Park, S. K.; Lee, D. G.; Kim, H. R.; Park, B. Y

2000-01-01

Fundamentals on the plan, the national policy, the safety securities for the life extension of the nuclear power plant was established from the domestic/abroad documents and case studies in relation with the life extension and decommissioning of the nuclear power plant. Concerning the decommissioning of the nuclear power plant, the management according to decommissioning stages was analyzed by the investigation of the domestic/abroad standard of the decommissioning (decontamination. dismantling) technology and regulation. Moreover, the study on the cost estimation method has been carried out for the decommissioning of the nuclear power plant. (author)

Establishment of safety verification method for life extension based on periodic safety review

Energy Technology Data Exchange (ETDEWEB)

Kim, Soong Pyung; Yeom, Yu Son; Yoon, In Sik; Lee, Jeo Young [Chosun Univ., Gwangju (Korea, Republic of)

2004-02-15

Safe management of operating lifetimes of Nuclear Power Plants is a subject of prime interests. As the design life of the Nuclear Power Plant will be ended in 2008, an appropriate procedure for the design life re-assessment or lifetime extension is necessary in Korea. Therefore, the objective of this work is to develop procedural requirements which can be applied to the regulation of lifetime management or life extension of Nuclear Power Plants in Korea. Review on the linkage of the PSR with the extension of the operating lifetime of Nuclear Power Plants was performed to enhance the utilization of PSR results and analysis of the insufficiencies in the license rule in Korea.

Open-label 24-week extension study of edaravone (MCI-186) in amyotrophic lateral sclerosis.

Science.gov (United States)

2017-10-01

We aimed to explore the longer-term efficacy and safety of edaravone in an active-treatment extension period following the double-blind period of the second phase III study. Patients who met all the following criteria (scores ≥2 points on all 12 items of the revised amyotrophic lateral sclerosis functional rating scale [ALSFRS-R], forced vital capacity ≥80%, definite or probable ALS, and disease duration ≤2 years) were randomised to 60 mg intravenous edaravone or placebo for six cycles in the double-blind period, and then offered the opportunity to proceed to this 24-week open-label extension period. One hundred and twenty-three of 137 patients continued to the extension period: 65 edaravone-edaravone (E-E group) and 58 placebo-edaravone (P-E group). Change (mean ± standard deviation; SD) in the ALSFRS-R score from baseline in the double-blind period was -4.1 ± 3.4 and -6.9 ± 5.1 in the E-E group and P-E group, respectively, while it was -8.0 ± 5.6 in the E-E group and -10.9 ± 6.9 in the P-E group over the whole 48-week period. The ALSFRS-R score changed almost linearly throughout Cycles 1-12 in the E-E group. The most commonly reported adverse events were constipation, dysphagia, and contusion. There was no sudden deterioration in the ALSFRS-R score of the E-E group. No safety concerns related to edaravone were detected.

Overview of the NKS/RAK-1 project 'Strategies for reactor safety' and linkages to piping reliability studies

International Nuclear Information System (INIS)

Andersson, Kjell

1997-01-01

The NKS/RAK-1 project forms part of a four-year research program (1994-97) in the Nordic countries. The general objective of NKS/RAK-1 project is to explore strategies for reactor safety: to investigate and evaluate the safety work, to increase realism and reliability of safety analysis; and to increase the safety of nuclear installations in selected areas. The project has done extensive interview work at utilities and authorities, and analysed a number of case studies. Brief highlights and overviews of the sub-projects are presented in this paper

Challenges in the Licensing of New Nuclear Power Plant, Service Life Extension of Operating Ones (Safeguards-Safety-Security Aspects)

International Nuclear Information System (INIS)

Horvath, K.

2016-01-01

The Hungarian Atomic Energy Authority (HAEA), as the Hungarian nuclear regulator is faced with dual challenges meant by the licensing of the planned construction of two AES-2006 type nuclear power plant units and the licensing of the service life extension of the existing units that have been operating for more than 30 years. The HAEA has full regulatory competence; its mission is to oversee the safety and security of all the peaceful applications of atomic energy. Accordingly, the licensing scope covers safeguards, safety as well as security. The paper shows the current status of the Hungarian nuclear programme and the future plans, as well as summarizes the regulatory approach followed by HAEA. (author)

Long-term safety and efficacy of etanercept in patients with psoriasis: an open-label study.

NARCIS (Netherlands)

Leonardi, C.; Strober, B.; Gottlieb, A.B.; Elewski, B.E.; Ortonne, J.P.; Kerkhof, P.C.M. van de; Chiou, C.F.; Dunn, M.; Jahreis, A.

2010-01-01

BACKGROUND: In two previous phase 3 studies, up to 60 weeks of etanercept therapy significantly improved the symptoms of psoriasis and was well tolerated. OBJECTIVE: To evaluate the long-term safety of etanercept in an open-label extension study for up to 72 weeks in patients with moderate-to-severe

The programs for lifetime extension by AREVA

International Nuclear Information System (INIS)

Knoche, P.

2014-01-01

In 2011 AREVA launched 2 worldwide programs to meet the demands of its customers: 'AREVA Safety Alliance' that proposes a set of measures for post-Fukushima safety upgrading and 'AREVA Forward Alliance' that is dedicated to lifetime extension projects. Concerning 'AREVA Safety Alliance' about 150 projects have been carried out for 53 customers in 19 countries, as for 'AREVA Forward Alliance' 60% of the lifetime extension projects in the US have been performed by AREVA. In the framework of lifetime extension projects, upgrading measures and services are proposed such as the installation of hydrogen recombiner units, of filtered ventilation systems for severe accidents, or the upgrading of the reactor control system through the implementation of the digital Teleperm XS technology, or recommendations about the methodology to follow for the repair or replacement of important components. The replacement of steam generators and of the pressurizer and with other upgrading works led to a gain of 18.5% on the output power of the Ringhals-4 unit. (A.C.)

Safety aspects of geological studies around nuclear installations sites

International Nuclear Information System (INIS)

Faure, J.

1988-01-01

The experience of geological studies of about forty french nuclear sites allows to set out the objectives, the phases and the geographic extensions of workings to be realized for confirming a site. The data to be collected for the safety analysis are specified; they concern the local and regional geology, the geotechnical characteristics and the essential elements for evaluating the hazards related to the soil liquefaction, the surface fracturing and in some cases the volcanic risks. It is necessary to follow up the geology during the installation construction and life. 8 refs. (F.M.)

Brand Extension: a Case Study of Starbucks

OpenAIRE

Bokii, Artem

2017-01-01

The thesis investigates the topic of brand extension and its importance in the business practice of companies. The theoretical part of the research outlines the key theoretical aspects related to brand and brand extension. The practical part investigates the case study of Starbucks brand extension and compares it with other famous brand extension cases. The paper illustrates how Starbucks brand extension from coffee onto the ice cream market had been successful on the initial stage, and how i...

Long-term tolerability and maintenance of therapeutic response to sodium oxybate in an open-label extension study in patients with fibromyalgia.

Science.gov (United States)

Spaeth, Michael; Alegre, Cayetano; Perrot, Serge; Wang, Youyu; Guinta, Diane R; Alvarez-Horine, Sarah; Russell, Irwin

2013-11-11

The long-term safety and therapeutic response of sodium oxybate (SXB) in fibromyalgia syndrome (FM) patients were assessed for a combined period of up to 1 year in a prospective, multicenter, open-label, extension study in patients completing 1 of 2 phase 3 randomized, double-blind, controlled, 14-week trials that examined the efficacy and safety of SXB 4.5 g, SXB 6 g, and placebo for treatment of FM. This extension study comprised an additional 38 weeks of treatment and was carried out at 130 clinical sites in 7 countries. Initial entry criteria for the previous 2 double-blind clinical trials required that patients aged ≥ 18 years met the American College of Rheumatology 1990 criteria for FM, had a body mass index (BMI) Fibromyalgia Impact Questionnaire (FIQ) total scores, and other measures. Responder analyses showed that 68.8% of patients achieved ≥ 30% reduction in pain VAS and 69.7% achieved ≥ 30% reduction in FIQ total score at study endpoint. The long-term safety profile of SXB in FM patients was similar to that in the previously reported controlled clinical trials. Improvement in pain and other FM clinical domains was maintained during long-term use. ClinicalTrials.gov NCT00423605.

Long-term tolerability and maintenance of therapeutic response to sodium oxybate in an open-label extension study in patients with fibromyalgia

Science.gov (United States)

2013-01-01

Introduction The long-term safety and therapeutic response of sodium oxybate (SXB) in fibromyalgia syndrome (FM) patients were assessed for a combined period of up to 1 year in a prospective, multicenter, open-label, extension study in patients completing 1 of 2 phase 3 randomized, double-blind, controlled, 14-week trials that examined the efficacy and safety of SXB 4.5 g, SXB 6 g, and placebo for treatment of FM. Methods This extension study comprised an additional 38 weeks of treatment and was carried out at 130 clinical sites in 7 countries. Initial entry criteria for the previous 2 double-blind clinical trials required that patients aged ≥ 18 years met the American College of Rheumatology 1990 criteria for FM, had a body mass index (BMI) Fibromyalgia Impact Questionnaire (FIQ) total scores, and other measures. Responder analyses showed that 68.8% of patients achieved ≥ 30% reduction in pain VAS and 69.7% achieved ≥ 30% reduction in FIQ total score at study endpoint. Conclusions The long-term safety profile of SXB in FM patients was similar to that in the previously reported controlled clinical trials. Improvement in pain and other FM clinical domains was maintained during long-term use. Trial registration ClinicalTrials.gov NCT00423605. PMID:24286114

Feedback-Assisted Extension of the Tokamak Operating Space to Low Safety Factor

Science.gov (United States)

Hanson, J. M.

2013-10-01

Recent DIII-D experiments have demonstrated stable operation at very low edge safety factor, q95 instability. The performance of tokamak fusion devices may benefit from increased plasma current, and thus, decreased q. However, disruptive stability limits are commonly encountered in experiments at qedge ~ 2 (limited plasmas) and q95 ~ 2 (diverted plasmas), limiting exploration of low q regimes. In the recent DIII-D experiments, the impact and control of key disruptive instabilities was studied. Locked n = 1 modes with exponential growth times on the order of the wall eddy current decay timescale τw preceded disruptions at q95 = 2 . The instabilities have a poloidal structure that is consistent with VALEN simulations of the RWM mode structure at q95 = 2 . Applying proportional gain magnetic feedback control of the n = 1 mode resulted in stabilized operation with q95 reaching 1.9, and an extension of the discharge lifetime for > 100τw . Loss of feedback control was accompanied by power supply saturation, followed by a rapidly growing n = 1 mode and disruption. Comparisons of the feedback dynamics with VALEN simulations will be presented. The DIII-D results complement and will be discussed alongside recent RFX-MOD demonstrations of RWM control using magnetic feedback in limited tokamak discharges with qedge economical fusion power production. Supported by the US Department of Energy under DE-FG02-04ER54761 and DE-FC02-04ER54698.

Food safety performance indicators to benchmark food safety output of food safety management systems.

Science.gov (United States)

Jacxsens, L; Uyttendaele, M; Devlieghere, F; Rovira, J; Gomez, S Oses; Luning, P A

2010-07-31

There is a need to measure the food safety performance in the agri-food chain without performing actual microbiological analysis. A food safety performance diagnosis, based on seven indicators and corresponding assessment grids have been developed and validated in nine European food businesses. Validation was conducted on the basis of an extensive microbiological assessment scheme (MAS). The assumption behind the food safety performance diagnosis is that food businesses which evaluate the performance of their food safety management system in a more structured way and according to very strict and specific criteria will have a better insight in their actual microbiological food safety performance, because food safety problems will be more systematically detected. The diagnosis can be a useful tool to have a first indication about the microbiological performance of a food safety management system present in a food business. Moreover, the diagnosis can be used in quantitative studies to get insight in the effect of interventions on sector or governmental level. Copyright 2010 Elsevier B.V. All rights reserved.

Consumer food handling in the home: a review of food safety studies.

Science.gov (United States)

Redmond, Elizabeth C; Griffith, Christopher J

2003-01-01

Epidemiological data from Europe, North America, Australia, and New Zealand indicate that a substantial proportion of foodborne disease is attributable to improper food preparation practices in consumers' homes. International concern about consumer food safety has prompted considerable research to evaluate domestic food-handling practices. The majority of consumer food safety studies in the last decade have been conducted in the United Kingdom and Northern Ireland (48%) and in the United States (42%). Surveys (questionnaires and interviews), the most frequent means of data collection, were used in 75% of the reviewed studies. Focus groups and observational studies have also been used. One consumer food safety study examined the relationship between pathogenic microbial contamination from raw chicken and observed food-handling behaviors, and the results of this study indicated extensive Campylobacter cross-contamination during food preparation sessions. Limited information about consumers' attitudes and intentions with regard to safe food-handling behaviors has been obtained, although a substantial amount of information about consumer knowledge and self-reported practices is available. Observation studies suggest that substantial numbers of consumers frequently implement unsafe food-handling practices. Knowledge, attitudes, intentions, and self-reported practices did not correspond to observed behaviors, suggesting that observational studies provide a more realistic indication of the food hygiene actions actually used in domestic food preparation. An improvement in consumer food-handling behavior is likely to reduce the risk and incidence of foodborne disease. The need for the development and implementation of food safety education strategies to improve specific food safety behaviors is reviewed in this paper.

Does lean management improve patient safety culture? An extensive evaluation of safety culture in a radiotherapy institute.

Science.gov (United States)

Simons, Pascale A M; Houben, Ruud; Vlayen, Annemie; Hellings, Johan; Pijls-Johannesma, Madelon; Marneffe, Wim; Vandijck, Dominique

2015-02-01

The importance of a safety culture to maximize safety is no longer questioned. However, achieving sustainable culture improvements are less evident. Evidence is growing for a multifaceted approach, where multiple safety interventions are combined. Lean management is such an integral approach to improve safety, quality and efficiency and therefore, could be expected to improve the safety culture. This paper presents the effects of lean management activities on the patient safety culture in a radiotherapy institute. Patient safety culture was evaluated over a three year period using triangulation of methodologies. Two surveys were distributed three times, workshops were performed twice, data from an incident reporting system (IRS) was monitored and results were explored using structured interviews with professionals. Averages, chi-square, logistical and multi-level regression were used for analysis. The workshops showed no changes in safety culture, whereas the surveys showed improvements on six out of twelve dimensions of safety climate. The intention to report incidents not reaching patient-level decreased in accordance with the decreasing number of reports in the IRS. However, the intention to take action in order to prevent future incidents improved (factorial survey presented β: 1.19 with p: 0.01). Due to increased problem solving and improvements in equipment, the number of incidents decreased. Although the intention to report incidents not reaching patient-level decreased, employees experienced sustained safety awareness and an increased intention to structurally improve. The patient safety culture improved due to the lean activities combined with an organizational restructure, and actual patient safety outcomes might have improved as well. Copyright © 2014 Elsevier Ltd. All rights reserved.

Development of procedural requirements for life extension of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Lee, Sang Hoon; Son, Moon Kyu [Korea Association for Nuclear Technology, Taejon (Korea, Republic of); Jeong, Ji Hwan [Baekseok College, Cheonan (Korea, Republic of); Chang, Keun Sun [Sunmoon Univ., Asan (Korea, Republic of); Ham, Chul Hoon [The Catholic University of Korea, Seoul (Korea, Republic of); Chang, Soon Hong [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

2002-03-15

Technical issues relevant to life extension of NPP were investigated. The GALL report, domestic PSR and periodic inspection rules were reviewed. Technical issues appearing in the safety evaluation reports related to license renewal of Calvert Ciffs 1 and 2 and Qconee 1,2 and 3 NPPs were reviewed. Preliminary study on PSA usage in NPP life extension assessment was performed and further works were suggested. The environment of rules and regulations was analyzed from the viewpoint of plant life extension. Two alternatives are suggested to revise the current domestic nuclear acts.

Development of procedural requirements for life extension of nuclear power plants

International Nuclear Information System (INIS)

Lee, Sang Hoon; Son, Moon Kyu; Jeong, Ji Hwan; Chang, Keun Sun; Ham, Chul Hoon; Chang, Soon Hong

2002-03-01

Technical issues relevant to life extension of NPP were investigated. The GALL report, domestic PSR and periodic inspection rules were reviewed. Technical issues appearing in the safety evaluation reports related to license renewal of Calvert Ciffs 1 and 2 and Qconee 1,2 and 3 NPPs were reviewed. Preliminary study on PSA usage in NPP life extension assessment was performed and further works were suggested. The environment of rules and regulations was analyzed from the viewpoint of plant life extension. Two alternatives are suggested to revise the current domestic nuclear acts

Near-term benefits of life extension planning for nuclear power plants

International Nuclear Information System (INIS)

Pickens, T.; Gregor, F.E.

1988-01-01

Life Extension of Nuclear Power Plants is now viewed as a realistic alternative to construction of new generating facilities. The subject has been under intensive study since 1984 and two comprehensive pilot plant programs have been completed under EPRI, U.S. Department of Energy and utility sponsorship. A major lesson learned from these studies is that planning for life extension must start early and that many activities must be implemented as early in life as possible to enhance the option for life extension through mitigate and preventive actions. It was also determined that achievement of a 40-year licensed life is by no means guaranteed without substantial effort during the remaining plant life. In examining these recommended actions, it becomes obvious that conscientious implementation also leads to realization of significant short-term benefits in the form of availability improvement, outage reduction, maintenance optimization and longer term planning decisions. In addition to the economic benefits, plant safety is also enhanced by reducing challenges to the safety systems and slowly switching from a corrective maintenance to a preventive maintenance program

Nuclear power plant life extension in the United Kingdom

International Nuclear Information System (INIS)

Goodison, D.; Seddon, J.W.; Pape, E.M.

1991-01-01

The safety cases for the United Kingdom's older nuclear power plant have been reviewed by their utilities in order to justify continued operation of the reactors up to an age of at least 30 year. These 'long term safety reviews' have identified worthwhile plant modifications and aspects where further studies or plant inspections are required. As the plants approach the age of 30 years, 'life extension reviews' are now being undertaken, concentrating on management of ageing, to support operation to at least 40 years. (author)

Animal Cloning and Food Safety

Science.gov (United States)

... Products For Consumers Home For Consumers Consumer Updates Animal Cloning and Food Safety Share Tweet Linkedin Pin ... safe to eat as food from conventionally bred animals. This conclusion stems from an extensive study of ...

Safety behavior: Job demands, job resources, and perceived management commitment to safety.

Science.gov (United States)

Hansez, Isabelle; Chmiel, Nik

2010-07-01

The job demands-resources model posits that job demands and resources influence outcomes through job strain and work engagement processes. We test whether the model can be extended to effort-related "routine" safety violations and "situational" safety violations provoked by the organization. In addition we test more directly the involvement of job strain than previous studies which have used burnout measures. Structural equation modeling provided, for the first time, evidence of predicted relationships between job strain and "routine" violations and work engagement with "routine" and "situational" violations, thereby supporting the extension of the job demands-resources model to safety behaviors. In addition our results showed that a key safety-specific construct 'perceived management commitment to safety' added to the explanatory power of the job demands-resources model. A predicted path from job resources to perceived management commitment to safety was highly significant, supporting the view that job resources can influence safety behavior through both general motivational involvement in work (work engagement) and through safety-specific processes.

NPP Mochovce nuclear safety enhancement program

International Nuclear Information System (INIS)

Cech, J.; Baumester, P.

1997-01-01

Nuclear power plant Mochovce is currently under construction and an extensive nuclear safety enhancement programme is under way. The upgrading and modifications are based on IAEA documents and on those of the Nuclear Regulatory Authority of the Slovak Republic. Based on a contract concluded with Riskaudit from the CEC, safety examinations of the Mochovce design were performed. An extensive list of technical specifications of safety measures is given. (M.D.)

Nuclear unit life extension: technico-economic considerations

International Nuclear Information System (INIS)

Bertron, L.

1987-01-01

The outstanding place of PWR power plants among the overall power generating facilities indicates the need for particular attention to be paid to assessing their expected useful life. The more so as they are not, in the medium term, exposed to the risk of becoming financially absolute which might result from more efficient generating tools entering the market. Yet, in no case should plant life extension affect safety in operation. This makes it necessary to ascertain and produce evidence that the various items of equipment remain equal to their function in terms of safety. Components ageing problems should be steadily monitored and ageing indicators adopted, allowing decisions of refurbishing or replacement to be made to avert plant shutdown. The alternative between repair works or shutdown will possibly arise in the case of heavy equipment likely to require protracted repairs and intricate works in radioactive environment. A technico-economic study, making allowance for anticipated savings in life extension through replacement operations, should help make the most appropriate decision [fr

Oral fingolimod (FTY720) in multiple sclerosis: two-year results of a phase II extension study

DEFF Research Database (Denmark)

O'Connor, P; Comi, G; Montalban, X

2009-01-01

OBJECTIVE: To report the results of a 24-month extension of a phase II trial assessing the efficacy, safety, and tolerability of the once-daily oral sphingosine-1-phosphate receptor modulator, fingolimod (FTY720), in relapsing multiple sclerosis (MS). METHODS: In the randomized, double-blind, pla...

An Agent-based Approach for Structured Modeling, Analysis and Improvement of Safety Culture

NARCIS (Netherlands)

Sharpanskykh, O.; Stroeve, S.

2011-01-01

Safety culture is broadly recognized as important for operational safety in various fields, including air traffic management, power plant control and health care. Previous studies addressed characterization and assessment of safety culture extensively. Nevertheless, relations between safety culture

Identifying research priorities for patient safety in mental health: an international expert Delphi study

Science.gov (United States)

Murray, Kevin; Thibaut, Bethan; Ramtale, Sonny Christian; Adam, Sheila; Darzi, Ara; Archer, Stephanie

2018-01-01

Objective Physical healthcare has dominated the patient safety field; research in mental healthcare is not as extensive but findings from physical healthcare cannot be applied to mental healthcare because it delivers specialised care that faces unique challenges. Therefore, a clearer focus and recognition of patient safety in mental health as a distinct research area is still needed. The study aim is to identify future research priorities in the field of patient safety in mental health. Design Semistructured interviews were conducted with the experts to ascertain their views on research priorities in patient safety in mental health. A three-round online Delphi study was used to ascertain consensus on 117 research priority statements. Setting and participants Academic and service user experts from the USA, UK, Switzerland, Netherlands, Ireland, Denmark, Finland, Germany, Sweden, Australia, New Zealand and Singapore were included. Main outcome measures Agreement in research priorities on a five-point scale. Results Seventy-nine statements achieved consensus (>70%). Three out of the top six research priorities were patient driven; experts agreed that understanding the patient perspective on safety planning, on self-harm and on medication was important. Conclusions This is the first international Delphi study to identify research priorities in safety in the mental field as determined by expert academic and service user perspectives. A reasonable consensus was obtained from international perspectives on future research priorities in patient safety in mental health; however, the patient perspective on their mental healthcare is a priority. The research agenda for patient safety in mental health identified here should be informed by patient safety science more broadly and used to further establish this area as a priority in its own right. The safety of mental health patients must have parity with that of physical health patients to achieve this. PMID:29502096

Decision support for life extension of technical systems through virtual age modelling

International Nuclear Information System (INIS)

Pérez Ramírez, Pedro A.; Utne, Ingrid Bouwer

2013-01-01

This article presents a virtual age model for decision support regarding life extension of ageing repairable systems. The aim of the model is to evaluate different life extension decision alternatives and their impact on the future performance of the system. The model can be applied to systems operated continuously (e.g., process systems) and systems operated on demand (e.g., safety systems). Deterioration and efficiency of imperfect maintenance is assessed when there is limited or no degradation data, and only failure and maintenance data is available. Systems that are in operation can be studied, meaning that the systems may be degraded. The current degradation is represented by a “current virtual age”, which is calculated from recorded maintenance data. The model parameters are estimated with the maximum likelihood method. A case study illustrates the application of the model for life extension of two fire water pumps in an oil and gas facility. The performance of the pump system is assessed with respect to number of failures, safety unavailability and costs during the life extension period. -- Highlights: ► Life extension assessment of technical systems using virtual age model is proposed. ► A virtual age model is generalised for systems in stand-by and continuous operation. ► The concept of current virtual age describes technical condition of the system. ► Different decision alternatives for life extension can be easily analysed. ► The decision process is improved even when only scarce failure data is available

Workplace Issues in Extension--A Delphi Study of Extension Educators

Science.gov (United States)

Kroth, Michael; Peutz, Joey

2011-01-01

Using the Delphi technique, expert Extension educators identified and prioritized those workplace issues they believe will be the most important to attract, motivate, and retain Extension educators/agents over the next 5 to 7 years. Obtaining and then utilizing a talented, highly motivated workforce during a period when many will be retiring will…

Improving safety culture through the health and safety organization: a case study.

Science.gov (United States)

Nielsen, Kent J

2014-02-01

International research indicates that internal health and safety organizations (HSO) and health and safety committees (HSC) do not have the intended impact on companies' safety performance. The aim of this case study at an industrial plant was to test whether the HSO can improve company safety culture by creating more and better safety-related interactions both within the HSO and between HSO members and the shop-floor. A quasi-experimental single case study design based on action research with both quantitative and qualitative measures was used. Based on baseline mapping of safety culture and the efficiency of the HSO three developmental processes were started aimed at the HSC, the whole HSO, and the safety representatives, respectively. Results at follow-up indicated a marked improvement in HSO performance, interaction patterns concerning safety, safety culture indicators, and a changed trend in injury rates. These improvements are interpreted as cultural change because an organizational double-loop learning process leading to modification of the basic assumptions could be identified. The study provides evidence that the HSO can improve company safety culture by focusing on safety-related interactions. © 2013. Published by Elsevier Ltd and National Safety Council.

Study on the KALIMER safety approach

International Nuclear Information System (INIS)

Kim, Eui Kwang; Han, Do Hee; Kim, Young Cheol.

1997-01-01

This study describes KALIMER's safety approach, how to establish the safety criteria and temperature limit, how to define safety evaluation events, and some safety research and development needs items. It is recommended that the KALIMER's approach to safety use seven levels of safety design and a defense-in-depth design approach with particular emphasis on inherent passive features. In order to establish as set DBEs for KALIMER safety evaluation, the procedure is explained how to define safety evaluation events. Final selection is to be determined later with the final establishment of design concepts. On the basis of preliminary studies and evaluation of the plant safety related areas, the KALIMER and PRISM have following three main difference that may require special research and development for KALIMER. (author). 7 refs., 6 tabs., 6 figs

Global nuclear safety culture

International Nuclear Information System (INIS)

1997-01-01

As stated in the Nuclear Safety Review 1996, three components characterize the global nuclear safety culture infrastructure: (i) legally binding international agreements; (ii) non-binding common safety standards; and (iii) the application of safety standards. The IAEA has continued to foster the global nuclear safety culture by supporting intergovernmental collaborative efforts; it has facilitated extensive information exchange, promoted the drafting of international legal agreements and the development of common safety standards, and provided for the application of safety standards by organizing a wide variety of expert services

Use of dynamic Bayesian networks for life extension assessment of ageing systems

International Nuclear Information System (INIS)

Ramírez, Pedro A. Pérez; Utne, Ingrid Bouwer

2015-01-01

Extending the operating lifetime of ageing technical systems is of great interest for industrial applications. Life extension requires identifying and selecting decision alternatives which allow for a safe and economic operation of the system beyond its design lifetime. This article proposes a dynamic Bayesian network for assessing the life extension of ageing repairable systems. The main objective of the model is to provide decision support based on the system performance during a finite time horizon, which is defined by the life extension period. The model has three main applications: (i) assessing and selecting optimal decision alternatives for the life extension at present time, based on historical data; (ii) identifying and minimizing the factors that have a negative impact on the system performance; and (iii) reassessing and optimizing the decision alternatives during operation throughout the life extension period, based on updating the model with new operational data gathered. A case study illustrates the application of the model for life extension of a real firewater pump system in an oil and gas facility. The case study analyzes three decision alternatives, where preventive maintenance and functional test policies are optimized, and the uncertainty involved in each alternative is computed. - Highlights: • A dynamic Bayesian network is used for predicting the system performance. • The performance is measured with relevant variables: cost; unavailability; safety. • The model can be used when scarce data is available, no degradation data is needed. • The uncertainty associated to each alternative is computed in the model. • A detailed case study of a real safety system shows the applicability of the model

Safety in offshore engineering an academic course covering safety in offshore wind

NARCIS (Netherlands)

Cerda Salzmann, D.J.

2011-01-01

Offshore projects are known for their challenging conditions, generally leading to high risks. Therefore no offshore project can go without a continuous and extensive assessment on safety issues. The Delft University of Technology is currently developing a course "Safety in Offshore Engineering"

77 FR 16865 - Proposed Extension of Existing Information Collection; Occupational Noise Exposure

Science.gov (United States)

2012-03-22

... harmful physical agent and one of the most pervasive health hazards in mining. Repeated exposure to high... employees working nearby. The Mine Safety and Health Administration (MSHA), the Occupational Safety and... DEPARTMENT OF LABOR Mine Safety and Health Administration Proposed Extension of Existing...

78 FR 65242 - Occupational Exposure to Crystalline Silica; Extension of Comment Period; Extension of Period To...

Science.gov (United States)

2013-10-31

... continue at the same time on subsequent days. Peer reviewers of OSHA's Health Effects Literature Review and... 1926 [Docket No. OSHA-2010-0034] RIN 1218-AB70 Occupational Exposure to Crystalline Silica; Extension...; Scheduling of Public Hearings AGENCY: Occupational Safety and Health Administration (OSHA), Labor. ACTION...

Progress of nuclear safety research, (2)

International Nuclear Information System (INIS)

Amano, Hiroshi; Nakamura, Hiroei; Nozawa, Masao

1981-01-01

The Japan Atomic Energy Research Institute was established in 1956 in conformity with the national policy to extensively conduct the research associated with nuclear energy. Since then, the research on nuclear energy safety has been conducted. In 1978, the Division of Reactor Safety was organized to conduct the large research programs with large scale test facilities. Thereafter, the Divisions of Reactor Safety Evaluation, Environmental Safety Research and Reactor Fuel Examination were organized successevely in the Reactor Safety Research Center. The subjects of research have ranged from the safety of nuclear reactors to that in the recycling of nuclear fuel. In this pamphlet, the activities in JAERI associated with the safety research are reported, which have been carried out in the past two years. Also the international cooperation research program in which JAERI participated is included. This pamphlet consists of two parts and in this Part 2, the environmental safety research is described. The evaluation and analysis of environmental radioactivity, the study on radioactive waste management and the studies on various subjects related to environmental safety are reported. (Kako, I.)

Extension of responsibilities of the State Office for Nuclear Safety

International Nuclear Information System (INIS)

Hrehor, M.

1995-01-01

The responsibilities of the State Office for Nuclear Safety have been extended by Act No. 85/1995 to cover protection against ionizing radiation. The following responsibilities of the State Office for Nuclear Safety are defined by the Act: a) state surveillance over nuclear safety of nuclear facilities, and over radioactive waste and spent fuel management; b) state surveillance over nuclear materials, their record-keeping and accountancy; c) state surveillance over the safeguarding of nuclear facilities and nuclear materials; d) state surveillance over selected materials, facilities and technologies used in the nuclear field, as well as dual-purpose materials and facilities; e) state surveillance over protection against ionizing radiation; f) coordination of the performance of the Radiation Monitoring Network over the Czech Republic and responsibility for international exchange of data on the radiological situation. The Act is reproduced in full, and the organizational structure of the Office is shown in a chart. (J.B.)

77 FR 51943 - Procedures for Safety Investigations

Science.gov (United States)

2012-08-28

... rule, Procedures for Safety Investigations, which published July 27, 2012 in the Federal Register, 77... DEFENSE NUCLEAR FACILITIES SAFETY BOARD 10 CFR Part 1708 Procedures for Safety Investigations AGENCY: Defense Nuclear Facilities Safety Board. ACTION: Proposed rule; extension of comment period...

Principles of electrical safety

CERN Document Server

Sutherland, Peter E

2015-01-01

Principles of Electrical Safety discusses current issues in electrical safety, which are accompanied by series' of practical applications that can be used by practicing professionals, graduate students, and researchers. .  Provides extensive introductions to important topics in electrical safety Comprehensive overview of inductance, resistance, and capacitance as applied to the human body Serves as a preparatory guide for today's practicing engineers

Nordic studies in reactor safety

International Nuclear Information System (INIS)

Pershagen, N.

1993-01-01

The Nordic Nuclear Safety Research Programme SIK programme in reactor safety is part of a major joint Nordic research effort in nuclear safety. The report summarizes the achievements of the SIK programme, which was carried out during 1990-1993 in collaboration between Nordic nuclear utilities, safety authorities, and research institutes. Three main projects were successfully completed dealing with: 1) development and application of a living PSA concept for monitoring the risk of core damage, and of safety indicators for early warning of possible safety problems; 2) review and intercomparison of severe accident codes, case studies of potential core melt accidents in nordic reactors, development of chemical models for the MAAP code, and outline of a system for computerized accident management support; 3) compilation of information about design and safety features of neighbouring reactors in Germany, Lithuania and Russia, and for naval reactors and nuclear submarines. The report reviews the state-of-the-art in each subject matter as an introduction to the individual project summaries. The main findings of each project are highlighted. The report also contains an overview of reactor safety research in the Nordic countries and a summary of fundamental reactor safety principles. (au) (69 refs.)

Implementing and measuring safety goals and safety culture. 2. Extensive Efforts to Learn Lessons from Overseas Nuclear Power Plants

International Nuclear Information System (INIS)

Maki, Nobuo

2001-01-01

The transfer of nuclear power plant (NPP) operating experiences is one of the important measures for the safe operation of NPPs. The Institute of Nuclear Power Operations (INPO),World Association of Nuclear Operators (WANO), and Nuclear Information Center of Central Research Institute of Electric Power Industry are the organizations providing Japanese utilities with useful information on incidents and accidents that have occurred at foreign NPPs. The Kansai Electric Power Company (KEPCO) has established two organizations to make extensive efforts to learn lessons from overseas NPPs: One is the Nuclear Power Plant Maintenance Training Center (MTC), and the other is the Institute of Nuclear Safety System (INSS). This paper describes the function of these organizations in transferring knowledge and expertise to ensure the safe operation of Japanese NPPs as well as recent outcomes. MTC was set up in October 1983. Before its establishment, expertise on NPP maintenance was mainly transferred on an on-the-job basis through daily maintenance work. However, after various NPP incidents and accidents, the importance of off-site training for maintenance personnel was emphasized. MTC possesses full-sized or nearly full sized mockups of Mihama NPP Unit 3 and Takahama NPP Unit 3. Furthermore, many kinds of mechanical, electrical, and instrumental equipment are furnished for training. In 1999, more than 2400 (man/day) maintenance personnel in total had training at MTC. In the tube rupture accident of a steam generator of KEPCO's Mihama Unit 2 on February 9, 1991, the emergency core cooling system actuated for the first time in the history of NPP operation in Japan. The cause of the accident was a fault in the manufacturing process of the steam generator, which was not detected until the accident. After an in-depth evaluation of the accident, many corrective actions were taken to prevent the recurrence of a similar accident. As a part of the actions, KEPCO established INSS in March

Research for enhancing reactor safety

International Nuclear Information System (INIS)

1989-05-01

Recent research for enhanced reactor safety covers extensive and numerous experiments and computed modelling activities designed to verify and to improve existing design requirements. The lectures presented at the meeting report GRS research results and the current status of reactor safety research in France. The GRS experts present results concerning expert systems and their perspectives in safety engineering, large-scale experiments and their significance in the development and verification of computer codes for thermohydraulic modelling of safety-related incidents, the advanced system code ATHLET for analysis of thermohydraulic processes of incidents, the analysis simulator which is a tool for fast evaluation of accident management measures, and investigations into event sequences and the required preventive emergency measures within the German Risk Study. (DG) [de

Considerations for Applying Design Extension Conditions to Domestic Nuclear Power Plants

International Nuclear Information System (INIS)

Ryu, Yongho

2013-01-01

The concept is designed to include more serious accidents than the existing design basis accidents considering additional failures. Design extension conditions can be derived based on engineering judgments, deterministic analysis or probabilistic analysis of the nuclear power plants. They are used to secure practical response capabilities to prevent or mitigate accidents. They may also require the deployment of additional safety equipment for existing nuclear power plants currently in operation. Though the general requirements of design extension conditions are described under the IAEA standards, no specific guidelines have been presented as required for their actual application to the nuclear power plant design. Furthermore, there is great variation between countries in implementing the requirements of design extension conditions. Therefore, for the actual application, considerable effort should be made among relevant organizations to establish detailed requirements of the design extension conditions. Such activities could constitute a part of the efforts of the nuclear community to meet the general public's expectations concerning the safety of nuclear power plants. The introduction of design extension conditions is expected to be a means of systematically enhancing the safety of nuclear power plants. Yet, there exists great differences in terms of the scope of analysis and the acceptance criteria, as no uniform practices have yet been established in applying the specific requirements for design extension conditions. A careful review is required in terms of the technical basis for setting the requirements, including those pertaining to the scope of analysis and the acceptance criteria. The introduction of these new requirements to Korean nuclear power plants may cause unexpected problems. Therefore, it is desirable for the regulatory agency to systematically assess the impact of design extension conditions and to discuss the arising issues with the stake holder

Reliability study: digital engineered safety feature actuation system of Korean Standard Nuclear Power Plant

International Nuclear Information System (INIS)

Sudarno; Kang, H. G.; Jang, S. C.; Eom, H. S.; Ha, J. J.

2003-04-01

The usage of digital Instrumentation and Control (I and C) in a nuclear power plant becomes more extensive, including safety related systems. The PSA application of these new designs are very important in order to evaluate their reliability. In particular, Korean Standard Nuclear Power Plants (KSNPPs), typically Ulchin 5 and 6 (UCN 5 and 6) reactor units, adopted the digital safety-critical systems such as Digital Plant Protection System (DPPS) and Digital Engineered Safety Feature Actuation System (DESFAS). In this research, we developed fault tree models for assessing the unavailability of the DESFAS functions. We also performed an analysis of the quantification results. The unavailability results of different DESFAS functions showed that their values are comprised from 5.461E-5 to 3.14E-4. The system unavailability of DESFAS AFAS-1 is estimated as 5.461E-5, which is about 27% less than that of analog system if we consider the difference of human failure probability estimation between both analyses. The results of this study could be utilized in risk-effect analysis of KSNPP. We expect that the safety analysis result will contribute to design feedback

An open-label extension long-term study of the safety and efficacy of aripiprazole for irritability in children and adolescents with autistic disorder in Japan.

Science.gov (United States)

Ichikawa, Hironobu; Hiratani, Michio; Yasuhara, Akihiro; Tsujii, Noa; Oshimo, Takashi; Ono, Hiroaki; Tadori, Yoshihiro

2018-02-01

The purpose of this study was to evaluate the long-term safety and efficacy of aripiprazole in treating irritability in pediatric patients (6-17 years) with autistic disorder (AD) in Japan. In this open-label extension study, patients who had completed a previous randomized, double-blind, placebo-controlled 8-week study were enrolled and were flexibly dosed with aripiprazole (1-15 mg/day) until the new indication of irritability in pediatric autism spectrum disorder was approved in Japan. Seventy (81%) out of 86 enrolled patients completed week-48 assessments. The mean duration of treatment was 694.9 days. The mean daily dose of aripiprazole over the treatment period was 7.2 mg and the mean of the final dose was 8.5 mg. The most common treatment-emergent adverse events (TEAE; ≥20%) included nasopharyngitis, somnolence, influenza, and increased weight. The majority of these TEAE were mild or moderate in severity, and there were no deaths, and no clinically relevant findings in laboratory values except prolactin decrease, vital signs, height, or ECG parameters. At week 48 (observed case), the mean change from baseline in the Irritability subscale score for the Aberrant Behavior Checklist Japanese Version was -6.3 in prior placebo patients and -2.6 in prior aripiprazole patients. Aripiprazole was generally safe, well tolerated, and effective in the long-term treatment of irritability associated with AD in Japanese pediatric patients. © 2017 The Authors. Psychiatry and Clinical Neurosciences published by John Wiley & Sons Australia, Ltd on behalf of Japanese Society of Psychiatry and Neurology.

The Bus Extension Module Design and Verification of POSAFE-Q Using LVDS

International Nuclear Information System (INIS)

Lee, Youn Sang; Song, Seung Whan; No, Young Hun; Yoo, Kwan Woo

2012-01-01

This paper described the Bus Extension Module using Low Voltage Differential Signal (LVDS). A Bus Extension Module use Safety-Related PLC (Programmable Logic Controller), called POSAFE-Q (made by POSCO ICT), for handling many data (I/O) extension rack. A processor module of POSAFE-Q can control I/O Module installed another rack. This paper explains Bus Extension Module and Data transfer technology using LVDS. (author)

Safety and reliability assessment

International Nuclear Information System (INIS)

1979-01-01

This report contains the papers delivered at the course on safety and reliability assessment held at the CSIR Conference Centre, Scientia, Pretoria. The following topics were discussed: safety standards; licensing; biological effects of radiation; what is a PWR; safety principles in the design of a nuclear reactor; radio-release analysis; quality assurance; the staffing, organisation and training for a nuclear power plant project; event trees, fault trees and probability; Automatic Protective Systems; sources of failure-rate data; interpretation of failure data; synthesis and reliability; quantification of human error in man-machine systems; dispersion of noxious substances through the atmosphere; criticality aspects of enrichment and recovery plants; and risk and hazard analysis. Extensive examples are given as well as case studies

Reliability analysis of Angra I safety systems

International Nuclear Information System (INIS)

Oliveira, L.F.S. de; Soto, J.B.; Maciel, C.C.; Gibelli, S.M.O.; Fleming, P.V.; Arrieta, L.A.

1980-07-01

An extensive reliability analysis of some safety systems of Angra I, are presented. The fault tree technique, which has been successfully used in most reliability studies of nuclear safety systems performed to date is employed. Results of a quantitative determination of the unvailability of the accumulator and the containment spray injection systems are presented. These results are also compared to those reported in WASH-1400. (E.G.) [pt

Recent innovations in IFR safety research

International Nuclear Information System (INIS)

Wade, D.C.

1994-01-01

Recent progress in IFR safety research suggests potential for two extensions of passive features to improve the robustness of safety response. This report provides a discussion of these recent innovations

Clinical Safety and Tolerability of Vildagliptin - Insights from Randomised Trials, Observational Studies and Post-marketing Surveillance.

Science.gov (United States)

Mathieu, Chantal; Kozlovski, Plamen; Paldánius, Päivi M; Foley, James E; Modgill, Vikas; Evans, Marc; Serban, Carmen

2017-08-01

Vildagliptin is one of the most extensively studied dipeptidyl peptidase-4 (DPP-4) inhibitors in terms of its clinical utility. Over the last decade, a vast panorama of evidence on the benefit-risk profile of vildagliptin has been generated in patients with type 2 diabetes mellitus (T2DM). In this article, we review the cumulative evidence on the safety of vildagliptin from the clinical development programme, as well as reports of rare adverse drug reactions detected during the post-marketing surveillance of the drug. Across clinical studies, the overall safety and tolerability profile of vildagliptin was similar to placebo, and it was supported by real-world data in a broad population of patients with T2DM, making DPP-4 inhibitors, like vildagliptin, a safe option for managing patients with T2DM.

Safety studies on Korean fusion DEMO plant using integrated safety assessment methodology

International Nuclear Information System (INIS)

Oh, Kyemin; Kang, Myoung-suk; Heo, Gyunyoung; Kim, Hyoung-chan

2014-01-01

Highlights: •The purpose of this paper is to suggest methodology that can investigate safety issues and provides a case study for Korean fusion DEMO plant. •The concepts of integrated safety assessment methodology (ISAM) that can be applied in addressing regulatory requirements and recognizing safety issues for K-DEMO were emphasized. •Phenomena identification and ranking table (PIRT) was proposed. It can recognize vulnerabilities of systems and identify the gaps in technical areas requiring additional researches. •This work is expected to contribute on the conceptual design of safety features for K-DEMO to design engineers and the guidance for regulatory requirements to licensers. -- Abstract: The purpose of this paper is to suggest methodology that can investigate safety issues and provides a case study for Korean fusion DEMO plant (K-DEMO) as a part of R and D program through the National Fusion Research Institute of Korea. Even though nuclear regulation and licensing framework is well setup due to the operating and design experience of Pressurized Water Reactors (PWRs) since 1970s, the regulatory authority of South Korea has concerns on the challenge of facing new nuclear facilities including K-DEMO due to the differences in systems, materials, and inherent safety feature from conventional PWRs. Even though the follow-up of the ITER license process facilitates to deal with significant safety issues of fusion facilities, a licensee as well as a licenser should identify the gaps between ITER and DEMO in terms of safety issues. First we reviewed the methods of conducting safety analysis for unprecedented nuclear facilities such as Generation IV reactors, particularly very high temperature reactor (VHTR), which is called as integrated safety assessment methodology (ISAM). Second, the analysis for the conceptual design of K-DEMO on the basis of ISAM was conducted. The ISAM consists of five analytical tools to develop the safety requirements from licensee

Safety studies on Korean fusion DEMO plant using integrated safety assessment methodology

Energy Technology Data Exchange (ETDEWEB)

Oh, Kyemin; Kang, Myoung-suk [Kyung Hee University, Youngin-si, Gyeonggi-do 446-701 (Korea, Republic of); Heo, Gyunyoung, E-mail: gheo@khu.ac.kr [Kyung Hee University, Youngin-si, Gyeonggi-do 446-701 (Korea, Republic of); Kim, Hyoung-chan [National Fusion Research Institute, Daejeon-si 305-333 (Korea, Republic of)

2014-10-15

Highlights: •The purpose of this paper is to suggest methodology that can investigate safety issues and provides a case study for Korean fusion DEMO plant. •The concepts of integrated safety assessment methodology (ISAM) that can be applied in addressing regulatory requirements and recognizing safety issues for K-DEMO were emphasized. •Phenomena identification and ranking table (PIRT) was proposed. It can recognize vulnerabilities of systems and identify the gaps in technical areas requiring additional researches. •This work is expected to contribute on the conceptual design of safety features for K-DEMO to design engineers and the guidance for regulatory requirements to licensers. -- Abstract: The purpose of this paper is to suggest methodology that can investigate safety issues and provides a case study for Korean fusion DEMO plant (K-DEMO) as a part of R and D program through the National Fusion Research Institute of Korea. Even though nuclear regulation and licensing framework is well setup due to the operating and design experience of Pressurized Water Reactors (PWRs) since 1970s, the regulatory authority of South Korea has concerns on the challenge of facing new nuclear facilities including K-DEMO due to the differences in systems, materials, and inherent safety feature from conventional PWRs. Even though the follow-up of the ITER license process facilitates to deal with significant safety issues of fusion facilities, a licensee as well as a licenser should identify the gaps between ITER and DEMO in terms of safety issues. First we reviewed the methods of conducting safety analysis for unprecedented nuclear facilities such as Generation IV reactors, particularly very high temperature reactor (VHTR), which is called as integrated safety assessment methodology (ISAM). Second, the analysis for the conceptual design of K-DEMO on the basis of ISAM was conducted. The ISAM consists of five analytical tools to develop the safety requirements from licensee

Review of selected cost drivers for decisions on continued operation of older nuclear reactors. Safety upgrades, lifetime extension, decommissioning

International Nuclear Information System (INIS)

1999-05-01

Lately, the approach to the operation of relatively old NPPs has become an important issue for the nuclear industry for several reasons. First, a large part of operating NPPs will reach the planned end of their lives relatively soon. Replacing these capacities can involve significant investment for the concerned countries and utilities. Second, many operating NPPs while about 30 years old are still in very good condition. Their continued safe operation appears possible and may bring about essential economic gains. Finally, with the costs of new NPPs being rather high at present, continued operation of existing plants and eventually their lifetime extension are viable options for supporting the nuclear share in power generation. This is becoming especially important in view of the growing attention to the issue of global warming and the role of nuclear energy in greenhouse gas mitigation. This report is a review of information related to three cost categories that are part of such cost-benefit analysis: costs of safety upgrades for continued operation of a nuclear unit, costs of lifetime extension and costs of decommissioning. It can serve as a useful reference source for experts and decision makers involved in the economics of operating NPPs

Geological safety aspects of nuclear waste disposalin in Finland

Energy Technology Data Exchange (ETDEWEB)

Ahonen, L; Hakkarainen, V; Kaija, J; Kuivamaki, A; Lindberg, A; Paananen, M; Paulamaki, S; Ruskeeniemi, T

2011-07-01

The management of nuclear waste from Finnish power companies is based on the final geological disposal of encapsulated spent fuel at a depth of several hundreds of metres in the crystalline bedrock. Permission for the licence requires that the safety of disposal is demonstrated in a safety case showing that processes, events and future scenarios possibly affecting the performance of the deep repository are appropriately understood. Many of the safety-related issues are geological in nature. The Precambrian bedrock of Finland has a long history, even if compared with the time span considered for nuclear waste disposal, but the northern location calls for a detailed study of the processes related to Quaternary glaciations. This was manifested in an extensive international permafrost study in northern Canada, coordinated by GTK. Hydrogeology and the common existence of saline waters deep in the bedrock have also been targets of extensive studies, because water chemistry affects the chemical stability of the repository near-field, as well as radionuclide transport. The Palmottu natural analogue study was one of the international high-priority natural analogue studies in which transport phenomena were explored in a natural geological system. Currently, deep biosphere processes are being investigated in support of the safety of nuclear waste disposal. (orig.)

Study of the Working Conditions of Health Extension Workers in ...

African Journals Online (AJOL)

Coverage: 2005-2009” of which “The Health Extension Program (HEP)” is a major component”. Objective: The study focuses on the first batch of Health Extension Workers (HEWs) with the overall objective of assessing the working conditions of HEWs and their job satisfaction. Methods: An in-depth field study was carried ...

Cooperative Agreement on Pesticide Safety Education

Science.gov (United States)

EPA is awarding the eXtension Foundation with a cooperative agreement to establish a system to distribute EPA funds to Pesticide Safety Education Programs (PSEPs) in State Cooperative Extension Services at Land Grant Universities.

Diagnosis function of safety status in the safety parameter display system (SPDS)

International Nuclear Information System (INIS)

Zhang Yuanfang

1993-04-01

An automatic diagnosis function of safety status for nuclear power plant adopted in the SPDS is introduced. To guarantee diagnosis diversification, two diagnosis criteria of a design basis accident monitoring and a critical safety function monitoring used in plant emergency operation are provided. As an extensive function, a parameter deviation monitoring used in plant normal operation is also provided

Railway safety climate: a study on organizational development.

Science.gov (United States)

Cheng, Yung-Hsiang

2017-09-07

The safety climate of an organization is considered a leading indicator of potential risk for railway organizations. This study adopts the perceptual measurement-individual attribute approach to investigate the safety climate of a railway organization. The railway safety climate attributes are evaluated from the perspective of railway system staff. We identify four safety climate dimensions from exploratory factor analysis, namely safety communication, safety training, safety management and subjectively evaluated safety performance. Analytical results indicate that the safety climate differs at vertical and horizontal organizational levels. This study contributes to the literature by providing empirical evidence of the multilevel safety climate in a railway organization, presents possible causes of the differences under various cultural contexts and differentiates between safety climate scales for diverse workgroups within the railway organization. This information can be used to improve the safety sustainability of railway organizations and to conduct safety supervisions for the government.

Sandia Laboratories environment and safety programs

International Nuclear Information System (INIS)

Zak, B.D.; McGrath, P.E.; Trauth, C.A. Jr.

1975-01-01

Sandia, one of ERDA's largest laboratories, is primarily known for its extensive work in the nuclear weapons field. In recent years, however, Sandia's role has expanded to embrace sizeable programs in the energy, resource recovery, and the environment and safety fields. In this latter area, Sandia has programs which address nuclear, fossil fuel, and general environment and safety issues. Here we survey ongoing activities and describe in more detail aa few projects of particular interest. These range from a study of the impact of sealed disposal of radioactive wastes, through reactor safety and fossil fuel plume chemistry, to investigations of the composition and dynamics of the stratosphere

Environmental, Safety, and Health Plan for the remedial investigation/feasibility study at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1993-05-01

This Environmental, Safety, and Health (ES ampersand H) Plan presents the concepts and methodologies to be followed during the remedial investigation/feasibility study (RI/FS) for Oak Ridge National Laboratory (ORNL) to protect the health and safety of employees, the public, and the environment. This ES ampersand H Plan acts as a management extension for ORNL and Martin Marietta Energy Systems, Inc. (Energy Systems) to direct and control implementation of the project ES ampersand H program. The subsections that follow describe the program philosophy, requirements, quality assurance measures, and methods for applying the ES ampersand H program to individual waste area grouping (WAG) remedial investigations. Hazardous work permits (HWPs) will be used to provide task-specific health and safety requirements

Study on safety performance evaluation system of nuclear engineering construction units based on AHP

International Nuclear Information System (INIS)

Xu Yulin; Sun Jian; Shi Xiaofan

2012-01-01

As a very effectual management mean, the performance management has extensively used by many companies of China for staff assessment. The author explored the establishment of the 'Safety Performance Evaluation System' by finding out the similarities in operation between a company and a team of nuclear power projects. Then the author analyzed the principles of the performance management and good practices and summarized safety management experiences. The weight of the system index by using AHP method was calculated in this article. (authors)

Nuclear power and safety

International Nuclear Information System (INIS)

Chidambaram, R.

1992-01-01

Some aspects of safety of nuclear power with special reference to Indian nuclear power programme are discussed. India must develop technology to protect herself from the adverse economic impact arising out of the restrictive regime which is being created through globalization of safety and environmental issues. Though the studies done and experience gained so far have shown that the PHWR system adopted by India has a number of superior safety features, research work is needed in the field of operation and maintenance of reactors and also in the field of reactor life extension through delaying of ageing effects. Public relations work must be pursued to convince the public at large of the safety of nuclear power programme. The new reactor designs in the second stage of evolution are based on either further improvement of existing well-proven designs or adoptions of more innovative ideas based on physical principles to ensure a higher level of safety. The development of Indian nuclear power programme is characterised by a balanced approach in the matter of assuring safety. Safety enforcement is not just looked upon as a pure administrative matter, but experts with independent minds are also involved in safety related matters. (M.G.B.)

Anterior & lateral extension of optic radiation & safety of amygdalohippocampectomy through middle temporal gyrus: a cadaveric study of 11 cerebral hemispheres.

Science.gov (United States)

Chowdhury, F H; Khan, A H

2010-01-01

This is a cadaveric anatomical study on the localization of the optic radiation within the temporal lobe and to find whether surgical intervention to the temporal lobe, especially amygdalohippocampectomy, can damage the optic radiation or not. 11 cadaveric cerebral hemispheres were used for the study. A 2 cm long antero-posterior incision was done with a sharp knife, on middle temporal gyrus, starting 3 cm posterior to temporal pole. The incision was deepened perpendicular to surface of the gyrus to reach the temporal horn. The optic radiation was dissected under operating microscope using Klinger's fiber dissection technique and measurements were taken to define the anterior and lateral extension of optic radiation. The optic radiation in each hemispehere was inspected for any incision related damage. No damage to the optic radiation was found, caused by the 2 cm long anterior-posterior incision on middle temporal gyrus 3 cm posterior to temporal pole. Most anterior 9mm (8-10mm) of the Meyer loop was completely on the roof and there was no extension over lateral wall of the temporal horn. In next posterior 17.5mm (16-20 mm) it extended over lateral wall of temporal horn with gradual progression. The most anterior extension of optic radiation was 26mm (23-31mm) posterior to temporal pole. Amygdalohippocampectomy through a 2 cm long horizontal incision on the middle temporal gyrus, starting 3 cm posterior to the temporal pole, to enter into the temporal horn through the lower aspect of the lateral wall is unlikely to cause damage to the Meyer's loop. Any entry from the superior aspect of the temporal horn and any temporal lobectomy inclusive of the superior temporal gyrus to enter the temporal horn is likely to cause Meyer's loop injury. The findings support the fact that the more inferior the surgical trajectory to the temporal horn of the lateral ventricle, the lover is the risk of visual field damage.

Safety in Agri-food chains

NARCIS (Netherlands)

Luning, P.A.; Vlieghere, de F.; Verhé, R.

2006-01-01

Increasing public demand for adequate and safe food supply has led to extensive development in the field of plant-animal production, food processing, quality and safety procedures, food analysis and control and regulations. However, safety of food can only be guaranteed by the integration of control

The safety of the nuclear fuel cycle

International Nuclear Information System (INIS)

2005-01-01

The procurement and preparation of fuel for nuclear power reactors, followed by its recovery, processing and management subsequent to reactor discharge, are frequently referred to as the ''front end'' and ''back end'' of the nuclear fuel cycle. The facilities associated with these activities have an extensive and well-documented safety record accumulated over the past 50 years by technical experts and safety authorities. This information has enabled an in-depth analysis of the complete fuel cycle. Preceded by two previous editions in 1981 and 1993, this new edition of the Safety of the Nuclear Fuel Cycle represents the most up-to-date analysis of the safety aspects of the nuclear fuel cycle. It will be of considerable interest to nuclear safety experts, but also to those wishing to acquire extensive information about the fuel cycle more generally. (author)

The safety of the nuclear fuel cycle

International Nuclear Information System (INIS)

2005-10-01

The procurement and preparation of fuel for nuclear power reactors, followed by its recovery, processing and management subsequent to reactor discharge, are frequently referred to as the 'front end' and 'back end' of the nuclear fuel cycle. The facilities associated with these activities have an extensive and well-documented safety record accumulated over the past 50 years by technical experts and safety authorities. This information has enabled an in-depth analysis of the complete fuel cycle. Preceded by two previous editions in 1981 and 1993, this new edition of The Safety of the Nuclear Fuel Cycle represents the most up-to-date analysis of the safety aspects of the nuclear fuel cycle. It will be of considerable interest to nuclear safety experts, but also to those wishing to acquire extensive information about the fuel cycle more generally. (author)

Measuring patient safety culture in maternal and child health institutions in China: a qualitative study.

Science.gov (United States)

Wang, Yuanyuan; Liu, Weiwei; Shi, Huifeng; Liu, Chaojie; Wang, Yan

2017-07-12

Patient safety culture (PSC) plays a critical role in ensuring safe and quality care. Extensive PSC studies have been undertaken in hospitals. However, little is known about PSC in maternal and child health (MCH) institutions in China, which provide both population-based preventive services as well as individual care for patients. This study aimed to develop a theoretical framework for conceptualising PSC in MCH institutions in China. The study was undertaken in six MCH institutions (three in Hebei and three in Beijing). Participants (n=118) were recruited through stratified purposive sampling: 20 managers/administrators, 59 care providers and 39 patients. In-depth interviews were conducted with the participants. The interview data were coded using both inductive (based on the existing PSC theory developed by the Agency for Healthcare Research and Quality) and deductive (open coding arising from data) approaches. A PSC framework was formulated through axial coding that connected initial codes and selective coding that extracted a small number of themes. The interviewees considered patient safety in relation to six aspects: safety and security in public spaces, safety of medical services, privacy and information security, financial security, psychological safety and gap in services. A 12-dimensional PSC framework was developed, containing 69 items. While the existing PSC theory was confirmed by this study, some new themes emerged from the data. Patients expressed particular concerns about psychological safety and financial security. Defensive medical practices emerged as a PSC dimension that is associated with not only medical safety but also financial security and psychological safety. Patient engagement was also valued by the interviewees, especially the patients, as part of PSC. Although there are some common features in PSC across different healthcare delivery systems, PSC can also be context specific. In MCH settings in China, the meaning of 'patient safety

Study on safety analysis of VVER-1200/V491 in scenario of Loss of Coolant Accidents along with partly failure of ECCS using RELAP5 code

International Nuclear Information System (INIS)

Hoang Minh Giang; Ha Thi Anh Dao; Hoang Tan Hung; Bui Thi Hoa; Nguyen Thi Tu Oanh; Dinh Anh Tuan; Pham Tuan Nam

2017-01-01

The advanced VVER-1200/V491 reactor designed with passive safety systems to deal with design extension conditions is primarily selected as priority candidate for Ninh Thuan 1 nuclear power plant project. So that, in order to enhance competence of nuclear safety and toward participation on review Safety Analysis Report (SAR) of Ninh Thuan nuclear Power project the study on safety analysis of VVER-1200/V491 in scenario of Loss of Coolant Accidents along with partly failure of ECCS is implemented. As requirement of the study, the input deck file of VVER-1200/V491 for RELAP5 and analysis report for some special case of LOCAs along with partly failure of ECCS are issued. (author)

Home Food Preservation Training for Extension Educators

Science.gov (United States)

Goard, Linnette Mizer; Hill, Melinda; Shumaker, Katharine; Warrix, Marisa

2013-01-01

During times of economic downturn, there has been an increased interest in home food preservation. As the primary resource for current research-based recommendations, a team of Extension Family and Consumer Sciences educators with specialization in food safety and food preservation responded to this demand by developing a standardized food…

23 CFR 1200.31 - Extension of the right to incur costs.

Science.gov (United States)

2010-04-01

... 23 Highways 1 2010-04-01 2010-04-01 false Extension of the right to incur costs. 1200.31 Section... HIGHWAY SAFETY PROGRAMS Closeout § 1200.31 Extension of the right to incur costs. Upon written request by the State, specifying the reasons therefor, the Approving Official may extend the right to incur costs...

Defining safety culture and the nexus between safety goals and safety culture. 1. An Investigation Study on Practical Points of Safety Management

International Nuclear Information System (INIS)

Hasegawa, Naoko; Takano, Kenichi; Hirose, Ayako

2001-01-01

In a report after the Chernobyl accident, the International Atomic Energy Agency indicated the definition and the importance of safety culture and the ideal organizational state where safety culture pervades. However, the report did not mention practical approaches to enhance safety culture. In Japan, although there had been investigations that clarified the consciousness of employees and the organizational climate in the nuclear power and railway industries, organizational factors that clarified the level of organization safety and practical methods that spread safety culture in an organization had not been studied. The Central Research Institute of the Electric Power Industry conducted surveys of organizational culture for the construction, chemical, and manufacturing industries. The aim of our study was to clarify the organizational factors that influence safety in an organization expressed in employee safety consciousness, commitment to safety activities, rate of accidents, etc. If these areas were clarified, the level of organization safety might be evaluated, and practical ways could be suggested to enhance the safety culture. Consequently, a series of investigations was conducted to clarify relationships among organizational climate, employee consciousness, safety management and activities, and rate of accidents. The questionnaire surveys were conducted in 1998-1999. The subjects were (a) managers of the safety management sections in the head offices of the construction, chemical, and manufacturing industries; (b) responsible persons in factories of the chemical and manufacturing industries; and (c) general workers in factories of the chemical and manufacturing industries. The number of collected data was (a) managers in the head office: 48 from the construction industry and 58 from the chemical and manufacturing industries, (b) responsible persons in factories: 567, and (c) general workers: from 29 factories. Items in the questionnaires were selected from

To dimension safety valves. Probabilist study

International Nuclear Information System (INIS)

Noel, Robert; Couvreur, Denis

1982-01-01

The gauge of safety valves of a steam pressure apparatus is usually determined according to an operating situation envelope which it is admitted covers all that can happen in reality. For the safety of the dryer-superheaters of turbines in nuclear power stations, Electricite de France and Alsthom-Atlantique made a reliability study; its method is exposed and the results are discussed. Such a study is heavy going and complex, but in return it permits a better quantitative understanding of the various dimension and operating parameters of an installation which condition its safety. It is therefore a source of progress [fr

Model quality and safety studies

DEFF Research Database (Denmark)

Petersen, K.E.

1997-01-01

The paper describes the EC initiative on model quality assessment and emphasizes some of the problems encountered in the selection of data from field tests used in the evaluation process. Further, it discusses the impact of model uncertainties in safety studies of industrial plants. The model...... that most of these have never been through a procedure of evaluation, but nonetheless are used to assist in making decisions that may directly affect the safety of the public and the environment. As a major funder of European research on major industrial hazards, DGXII is conscious of the importance......-tain model is appropriate for use in solving a given problem. Further, the findings from the REDIPHEM project related to dense gas dispersion will be highlighted. Finally, the paper will discuss the need for model quality assessment in safety studies....

Experience in lifetime extension of the first generation WWER-440 power units

International Nuclear Information System (INIS)

Medvedev, P.

2002-01-01

In connection with the expiration of the lifetime for the first generation WWER-440 reactors in Russian Federation (Novo Voronezh and Kola NPP), the legal procedures and Life Time Extension (LTE) Program are discussed. The LTE Program includes: development of regulation basis; economic efficiency studies; power unit modernization; power unit comprehensive examination and justification od equipment resource; in-dept safety assessment; operational license acquisition. As a result from the LTE Program the safety level of the unit 3 of the Novo Voronezh NPP is significantly increases, the operational period has been justified and a 5-year license has been issued

Nuclear safety in France

International Nuclear Information System (INIS)

Tanguy, P.

1979-01-01

A brief description of the main safety aspects of the French nuclear energy programme and of the general safety organization is followed by a discussion on the current thinking in CEA on some important safety issues. As far as methodology is concerned, the use of probabilistic analysis in the licensing procedure is being extensively developed. Reactor safety research is aimed at a better knowledge of the safety margins involved in the present designs of both PWRs and LMFBRs. A greater emphasis should be put during the next years in the safety of the nuclear fuel cycle installations, including waste disposals. Finally, it is suggested that further international cooperation in the field of nuclear safety should be developed in order to insure for all countries the very high safety level which has been achieved up till now. (author)

Bridging probabilistic safety assessment studies with information Management System

International Nuclear Information System (INIS)

Luanco, E. M.

2010-01-01

Probabilistic Safety Assessment (PSA) is a critical business often known in conjunction with either new build or life extension of nuclear power plant. However, it is not so often referred to the operation phase of the plant, although it could bring a lot of long term benefits to the operator. The purpose of this paper is to discuss the potential contribution of PSA with day to day operation in bridging the deficiencies and specific failures characteristics of critical Structure System and Component (SSC) with the results of PSA studies. From and Information System prospective, the use of Information Management system (IMS) -also known as EAM solution -widely used by the majority of nuclear operators- is the potential vehicle to bridge the 2 worlds of PSA and daily operation. Most EAM solution get reliability management functionalities which are not really integrated with PSA tools and data and thus cannot provide the anticipated benefits of addressing typical aging phenomena beyond the only predictive models used by the PSA studies. The paper will also discuss potential integration scenario between PSA tools and EAM solutions. (authors)

77 FR 27776 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2012-05-11

... Occupational Health Study Section (SOHSS), National Institute for Occupational Safety and Health (NIOSH) In... Services Office, CDC, pursuant to Public Law 92-463. Purpose: The Safety and Occupational Health Study... standard grants review and funding cycles pertaining to research issues in occupational safety and health...

76 FR 18220 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2011-04-01

... Occupational Health Study Section (SOHSS), National Institute for Occupational Safety and Health (NIOSH) In... Services Office, CDC, pursuant to Public Law 92-463. Purpose: The Safety and Occupational Health Study... standard grants review and funding cycles pertaining to research issues in occupational safety and health...

Reactor safety

International Nuclear Information System (INIS)

Meneley, D.A.

The people of Ontario have begun to receive the benefits of a low cost, assured supply of electrical energy from CANDU nuclear stations. This indigenous energy source also has excellent safety characteristics. Safety has been one of the central themes of the CANDU development program from its very beginning. A great deal of work has been done to establish that public risks are small. However, safety design criteria are now undergoing extensive review, with a real prospect of more stringent requirements being applied in the future. Considering the newness of the technology it is not surprising that a consensus does not yet exist; this makes it imperative to discuss the issues. It is time to examine the policies and practice of reactor safety management in Canada to decide whether or not further restrictions are justified in the light of current knowledge

Status and Perspectives of Nuclear Reactor Pressure Vessel Life Extension up to 60 Years Operation in Belgium

Energy Technology Data Exchange (ETDEWEB)

Lucon, E.; Chaouadi, R.; Scibetta, M.; Van Walle, E.

2009-09-15

The scope of this report involves a safety evaluation of the reactor pressure vessel (RPV) against neutron embrittlement, in the most severely irradiation region (belt line) and in the event of a pressurized thermal shock. The irreplaceable RPV is considered to be the most critical component for lifetime considerations of the nuclear power plant. However, an application for operation extension will also depend upon a number of additional considerations, including the technical assessment of other plant components, as well as non-technical arguments (e.g. political, environmental, economical, strategical that are outside the scope this report. In the hypothesis of a request for operation extension, it is the responsibility of the utilities to provide the safety authorities with an exhaustive dossier demonstrating that safe extended operation is guaranteed. The role of the safety authorities is to critically evaluate the safety dossier for eventually granting the operation extension.

Status and Perspectives of Nuclear Reactor Pressure Vessel Life Extension up to 60 Years Operation in Belgium

International Nuclear Information System (INIS)

Lucon, E.; Chaouadi, R.; Scibetta, M.; Van Walle, E.

2009-01-01

The scope of this report involves a safety evaluation of the reactor pressure vessel (RPV) against neutron embrittlement, in the most severely irradiation region (belt line) and in the event of a pressurized thermal shock. The irreplaceable RPV is considered to be the most critical component for lifetime considerations of the nuclear power plant. However, an application for operation extension will also depend upon a number of additional considerations, including the technical assessment of other plant components, as well as non-technical arguments (e.g. political, environmental, economical, strategical that are outside the scope this report. In the hypothesis of a request for operation extension, it is the responsibility of the utilities to provide the safety authorities with an exhaustive dossier demonstrating that safe extended operation is guaranteed. The role of the safety authorities is to critically evaluate the safety dossier for eventually granting the operation extension.

Fusion reactor safety studies, FY 1977

International Nuclear Information System (INIS)

Darby, J.B. Jr.

1978-04-01

This report reviews the technical progress in the fusion reactor safety studies performed during FY 1977 in the Fusion Power Program at the Argonne National Laboratory. The subjects reported on include safety considerations of the vacuum vessel and first-wall design for the ANL/EPR, the thermal responses of a tokamak reactor first wall, the vacuum wall electrical resistive requirements in relationship to magnet safety, and a major effort is reported on considerations and experiments on air detritiation

Tofacitinib, an oral Janus kinase inhibitor, for the treatment of Latin American patients with rheumatoid arthritis: Pooled efficacy and safety analyses of Phase 3 and long-term extension studies.

Science.gov (United States)

Radominski, Sebastião Cezar; Cardiel, Mario Humberto; Citera, Gustavo; Goecke, Annelise; Jaller, Juan Jose; Lomonte, Andrea Barranjard Vannucci; Miranda, Pedro; Velez, Patricia; Xibillé, Daniel; Kwok, Kenneth; Rojo, Ricardo; García, Erika Gabriela

Tofacitinib is an oral Janus kinase inhibitor for the treatment of rheumatoid arthritis (RA). We assessed tofacitinib efficacy and safety in the Latin American (LA) subpopulation of global Phase 3 and long-term extension (LTE) studies. Data from LA patients with RA and inadequate response to disease-modifying antirheumatic drugs (DMARDs) were pooled across five Phase 3 studies. Phase 3 patients received tofacitinib 5 or 10mg twice daily (BID), adalimumab or placebo; patients in the single LTE study received tofacitinib 5 or 10mg BID; treatments were administered alone or with conventional synthetic DMARDs. Efficacy was reported up to 12 months (Phase 3) and 36 months (LTE) by American College of Rheumatology (ACR) 20/50/70 response rates, Disease Activity Score (DAS)28-4(erythrocyte sedimentation rate [ESR]) and Health Assessment Questionnaire-Disability Index (HAQ-DI). Incidence rates (IRs; patients with event/100 patient-years) of adverse events (AEs) of special interest were reported. The Phase 3 studies randomized 496 LA patients; the LTE study enrolled 756 LA patients from Phase 2 and Phase 3. In the Phase 3 studies, patients who received tofacitinib 5 and 10mg BID showed improvements vs placebo at Month 3 in ACR20 (68.9% and 75.7% vs 35.6%), ACR50 (45.8% and 49.7% vs 20.7%) and ACR70 (17.5% and 23.1% vs 6.9%) responses, mean change from baseline in HAQ-DI (-0.6 and -0.8 vs -0.3) and DAS28-4(ESR) score (-2.3 and -2.4 vs -1.4). The improvements were sustained up to Month 36 in the LTE study. In the Phase 3 studies, IRs with tofacitinib 5 and 10mg BID and placebo were 7.99, 6.57 and 9.84, respectively, for SAEs, and 3.87, 5.28 and 3.26 for discontinuation due to AEs. IRs of AEs of special interest in tofacitinib-treated LA patients were similar to the global population. In Phase 3 and LTE studies in LA patients with RA, tofacitinib demonstrated efficacy up to 36 months with a manageable safety profile up to 60 months, consistent with the overall tofacitinib

75 FR 26266 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2010-05-11

... Occupational Health Study Section (SOHSS), National Institute for Occupational Safety and Health (NIOSH) In...) Public Law 92-463. Purpose: The Safety and Occupational Health Study Section will review, discuss, and... cycles pertaining to research issues in occupational safety and health, and allied areas. It is the...

Randomized Phase III and Extension Studies of Naldemedine in Patients With Opioid-Induced Constipation and Cancer.

Science.gov (United States)

Katakami, Nobuyuki; Harada, Toshiyuki; Murata, Toru; Shinozaki, Katsunori; Tsutsumi, Masakazu; Yokota, Takaaki; Arai, Masatsugu; Tada, Yukio; Narabayashi, Masaru; Boku, Narikazu

2017-12-01

Purpose Opioid-induced constipation (OIC) is a frequent and debilitating adverse effect (AE) of opioids-common analgesics for cancer pain. We investigated the efficacy and safety of a peripherally acting μ-opioid receptor antagonist, naldemedine (S-297995), for OIC, specifically in patients with cancer. Patients and Methods This phase III trial consisted of a 2-week, randomized, double-blind, placebo-controlled study (COMPOSE-4) and an open-label, 12-week extension study (COMPOSE-5). In COMPOSE-4, eligible adults with OIC and cancer were randomly assigned on a 1:1 basis to receive once-daily oral naldemedine 0.2 mg or placebo. The primary end point was the proportion of spontaneous bowel movement (SBM) responders (≥ 3 SBMs/week and an increase of ≥ 1 SBM/week from baseline). The primary end point of COMPOSE-5 was safety. Results In COMPOSE-4, 193 eligible patients were randomly assigned to naldemedine (n = 97) or placebo (n = 96). The proportion of SBM responders in COMPOSE-4 was significantly greater with naldemedine than with placebo (71.1% [69 of 97 patients] v 34.4% [33 of 96 patients]; P opioid withdrawal and had no notable impact on opioid-mediated analgesia. Conclusion Once-daily oral naldemedine 0.2 mg effectively treated OIC and was generally well tolerated in patients with OIC and cancer.

Westinghouse Advances in Passive Plant Safety

International Nuclear Information System (INIS)

Bruschi, H. J.; Manager, General; Gerstenhaber, E.

1993-01-01

On June 26, 1992, Westinghouse submitted the Ap600 Standard Safety Analysis Report and comprehensive PIRA results to the U. S. NRC for review as part of the Ap600 design certification program. This major milestone was met on time on a schedule set more than 3 years before submittal and is the result of the cooperative efforts of the U. S. Department of Energy (DOE), the Electric Power Requirements Program, and the Westinghouse Ap600 design team. These efforts were initiated in 1985 to develop a 600 MW advanced light water reactor plant design based on specific technical requirements established to provide the safety, simplicity, reliability, and economics necessary for the next generation of nuclear power plants. The Ap600 design achieves the ALRR safety requirements through ample design margins, simplified safety systems based on natural driving forces, and on a human-engineered man-machine interface system. Extensive Probabilistic Risk evolution, have recently shown that even if none of the active defense-in-depth safety systems are available, the passive systems alone meet safety goals. Furthermore, many tests in an extensive test program have begun or have been completed. Early tests show that passive safety perform well and meet design expectations

The use of SIPA 2 simulator for safety studies experience feedbacks and future developments

International Nuclear Information System (INIS)

Dumas, J.M.; Leteinturier, D.

1999-01-01

SIPA 2 experience feedbacks from the beginning of its use at IPSN in 1991 and trends for the next five years are presented. The simulator has been used for three applications: training of engineers working in safety analysis, preparation of national crisis drills, safety studies. In each application, experience feedbacks are analysed to show encountered advantages and difficulties. Trends for the next five years are: extension of the engineer training program (new training courses about normal operating conditions or about beyond design basis accidents), improvements in the validation of simulation configurations (in particular comparison with Cathare 2 new version results) increase of the simulation scope in connection with the SCAR project (taking into account the current power plant datapackage, the improvement of thermalhydraulic models, the extent of the system representation, new neutronic models and description of severe accident conditions). For each trend above, a detail of the planned actions is given. (author)

Safety of gadobutrol in more than 1,000 pediatric patients: subanalysis of the GARDIAN study, a global multicenter prospective non-interventional study

International Nuclear Information System (INIS)

Glutig, Katja; Bhargava, Ravi; Hahn, Gabriele; Hirsch, Wolfgang; Kunze, Christian; Mentzel, Hans-Joachim; Schaefer, Juergen F.; Willinek, Winfried; Palkowitsch, Petra

2016-01-01

Gadobutrol is a gadolinium-based contrast agent, uniquely formulated at 1.0 mmol/ml. Although there is extensive safety evidence on the use of gadobutrol in adults, few studies have addressed the safety and tolerability of gadobutrol in pediatric patients. This subanalysis of data from the GARDIAN study evaluated the safety and use of gadobutrol in pediatric patients (age <18 years). The GARDIAN study was a large phase IV non-interventional prospective multicenter post-authorization safety study performed in Europe, Asia, North America and Africa. A total of 23,708 patients were included who were scheduled to undergo cranial or spinal MRI, liver or kidney MRI, or MR angiography with gadobutrol enhancement. The primary study endpoint was the overall incidence of adverse drug reactions (ADRs) and serious adverse events (SAEs) following gadobutrol administration. The GARDIAN study included 1,142 children (age <18 years) who received gadobutrol at a mean dose of 0.13 (range 0.04-0.50) mmol/kg body weight. Gadobutrol was well tolerated in these children, with low rates of ADRs (0.5%) and no SAEs, consistent with results in adults enrolled in the GARDIAN study. Rates of adverse events and ADRs were unrelated to pediatric age or gadobutrol weight-adjusted dose. There were no symptoms suggestive of nephrogenic systemic fibrosis. Investigators rated the contrast quality of gadobutrol-enhanced images as good or excellent in 97.8% of pediatric patients, similar to the main study population. Gadobutrol is very well tolerated and provides excellent contrast quality at the recommended weight-adjusted dose in children (age <18 years), similar to the profile in adults. (orig.)

Seismic safety of Paks nuclear power plant

International Nuclear Information System (INIS)

Katona, T.

1993-01-01

An extensive program is underway at Paks NPP for evaluation of the seismic safety and for development of the necessary safety increasing measures. This program includes the following five measures: investigation of methods, regulations and techniques utilized for reassessment of seismic safety of operating NPPs and promoting safety; investigation of earthquake hazards; development of concepts for creating the seismic safety location of earthquake warning system; determination of dynamic features of systems and facilities determined by the concept, and preliminary evaluation of the seismic safety

AN OPEN-LABEL EXTENSION STUDY OF PARATHYROID HORMONE RHPTH(1-84) IN ADULTS WITH HYPOPARATHYROIDISM.

Science.gov (United States)

Lakatos, Peter; Bajnok, Laszlo; Lagast, Hjalmar; Valkusz, Zsuzsanna

2016-05-01

Hypoparathyroidism is characterized by inadequate parathyroid hormone (PTH), resulting in hypocalcemia, hyperphosphatemia, and bone abnormalities. Adults with hypoparathyroidism treated with recombinant human PTH, rhPTH(1-84), in the 24-week, phase III REPLACE study maintained serum calcium despite reductions in oral calcium and active vitamin D. This study assessed the long-term efficacy and safety of rhPTH(1-84) for hypoparathyroidism. This was a 24-week, open-label, flexible-dose extension study of REPLACE (REPEAT) conducted in 3 outpatient centers in Hungary. Patients who previously completed or enrolled in REPLACE received 50 μg/day rhPTH(1-84), escalated to 75 and then to 100 μg/day, if needed, to reduce active vitamin D and oral calcium. The primary endpoint was ≥50% reduction in oral calcium (or ≤500 mg/day) and active vitamin D (or calcitriol ≤0.25 μg/day or alfacalcidol ≤0.50 μg/day) with normocalcemia. Twenty-four patients (n = 16 previously treated with rhPTH[1-84]; n = 8 rhPTH[1-84]-naïve) were enrolled and completed the study. At Week 24, 75% of patients (95% confidence interval [CI], 53.3-90.2%) achieved the study endpoint; 58% eliminated oral calcium and active vitamin D. Urinary calcium, serum phosphate, and calcium × phosphate (Ca × P) product decreased by Week 24. Mean serum bone turnover markers increased with rhPTH(1-84). Treatment-emergent adverse events (TEAEs) were reported by 92% of patients. No serious adverse events (AEs) occurred. This study used a simplified treatment algorithm intended to better mimic typical clinical practice and demonstrated the extended efficacy and safety of rhPTH(1-84) in patients with hypoparathyroidism and confirmed the REPLACE findings. Sustained rhPTH(1-84) efficacy up to 48 weeks was observed despite treatment interruption between studies.

Center for Maritime Safety and Health Studies

Data.gov (United States)

Federal Laboratory Consortium — Established in November 2015, the Center for Maritime Safety and Health Studies (CMSHS) promotes safety and health for all maritime workers, including those employed...

On the extension of Importance Measures to complex components

International Nuclear Information System (INIS)

Dutuit, Yves; Rauzy, Antoine

2015-01-01

Importance Measures are indicators of the risk significance of the components of a system. They are widely used in various applications of Probabilistic Safety Analyses, off-line and on-line, in decision making for preventive and corrective purposes, as well as to rank components according to their contribution to the global risk. They are primarily defined for the case the support model is a coherent fault tree and failures of components are described by basic events of this fault tree. In this article, we study their extension to complex components, i.e. components whose failures are modeled by a gate rather than just a basic event. Although quite natural, such an extension has not received much attention in the literature. We show that it raises a number of problems. The Birnbaum Importance Measure and the notion of Critical States concentrate these difficulties. We present alternative solutions for the extension of these notions. We discuss their respective advantages and drawbacks. This article gives a new point of view on the mathematical foundations of Importance Measures and helps us to clarify their physical meaning. - Highlights: • We propose an extension of Importance Measures to complex components. • We define our extension in term minterms, i.e. states of the system. • We discuss the physical interpretation of Importance Measures in light of this interpretation

Using C Language Extensions for Developing Embedded Software : A Case Study

NARCIS (Netherlands)

Voelter, M.; Van Deursen, A.; Kolb, B.; Eberle, S.

2015-01-01

We report on an industrial case study on developing the embedded software for a smart meter using the C programming language and domain-specific extensions of C such as components, physical units, state machines, registers and interrupts. We find that the extensions help significantly with managing

Characterization of in-containment cables for nuclear plant life extension

International Nuclear Information System (INIS)

DuCharme, A.R.; Bustard, L.D.

1988-01-01

Electrical cable is made by a large number of manufacturers and used for a variety of applications in nuclear plants. cables have been identified in the Monticello and Surry Pilot Plant life extension studies and the NRC Nuclear Plant Aging Research Program as components important to the economic and safety aspects of life extension. Currently, fitness for service is largely determined by preoperational testing. The US Department of Energy is supporting work at Sandia National Laboratories to assess the technical basis for the life extension of cables found inside containment at US nuclear plants. The work is being performed in coordination with the Nuclear Management and Resource Council's (NUMARC) NUPLEX Working Group. The initial task of this effort is to characterize the design attributes of in-containment cables. This has been completed via development of a data base depicting the manufacturer, type, material composition, use, qualification, and relative popularity of cables installed in containment. Other ongoing work is focused on a review of cable operational experience and assessment of the issues affecting cable life extension. In the long term, the work aims to identify the technical criteria and life extension strategies needed to support continued cable qualification by nuclear plant owner/operators. 7 refs., 4 tabs

Study on Fusion Safety Infrastructure using ISAM

International Nuclear Information System (INIS)

Oh, Kyemin; Kang, Myungsuk; Heo, Gyunyoung; Kim, Hyoungchan

2013-01-01

The regulation of nuclear facilities have checked and managed safety throughout the entire process from design, construction, operation and decommissioning. Also, the same meaning as the regulatory requirements and design requirements, it will be important indicators for detailed design of K-DEMO. K-DEMO has many uncertainties because it is in conceptual design phase. Also, there is no reference material because demonstration scale fusion power plants were not operated yet in overseas. So, hazard that threaten the integrity of K-DEMO have to be defined preferentially to define regulatory or design requirements. This study proposed method that educe regulatory or design requirements and introduce web-based cloud infrastructure to perform renewal and sharing of information related with safety that is required in the study rapidly as a part of the R and D program funded by National Fusion Research Institute of Korea (NFRI). We have been performing QSR and PIRT in accordance with development of fusion DEMO plant, and preparing OPT, PSA and DPA for regulation requirements. This study introduces our recent research activities about ISAM for fusion and CCI built for expert and extant safety related information. Unlike fission, nuclear fusion's safety goal is non-evacuation of the public during an accident. To satisfy this goal not only various safety issues should be analyzed, but safety objectives, regulatory requirements, and design variables should also be established in detailed design phase. The web-based cloud infrastructure proposed in this paper will be able to offer input data of future studies and, it is expected to contribute on general and technical safety principles for national fusion power plant technology plan

Exploratory double-blind, parallel-group, placebo-controlled extension study of edaravone (MCI-186) in amyotrophic lateral sclerosis.

Science.gov (United States)

2017-10-01

Following the first phase III study of edaravone for amyotrophic lateral sclerosis (ALS), this extension study was performed to evaluate longer-term efficacy and safety. Patients given edaravone in the first 24-week phase III study (Cycles 1-6) were randomised to edaravone (E-E) or placebo (E-P) in the subsequent 24-week double-blind period (Cycles 7-12). Patients given placebo in phase III were switched to edaravone (P-E). Subsequently, all patients received edaravone for 12 weeks (Cycles 13-15). Efficacy endpoints included revised ALS Functional Rating Scale (ALSFRS-R) score. Analysis populations were the full analysis set (FAS) and the efficacy-expected subpopulation (EESP) defined by post-hoc analysis of the first phase III study. The least-squares mean and standard error of the intergroup difference (E-E vs. E-P) of change in the ALSFRS-R score from Cycles 7-12 was 1.16 ± 0.93 (p = 0.2176) in the FAS, and 1.85 ± 1.14 (p = 0.1127) in the EESP. The ALSFRS-R score changed almost linearly in the E-E group throughout Cycles 1-15 (60 weeks). The incidence of serious adverse events associated with ALS progression was higher in E-E than in E-P. Edaravone might have potential efficacy for up to 15 cycles when used to treat patients in the EESP with careful safety monitoring.

Risk-adapted monitoring is not inferior to extensive on-site monitoring: Results of the ADAMON cluster-randomised study.

Science.gov (United States)

Brosteanu, Oana; Schwarz, Gabriele; Houben, Peggy; Paulus, Ursula; Strenge-Hesse, Anke; Zettelmeyer, Ulrike; Schneider, Anja; Hasenclever, Dirk

2017-12-01

Background According to Good Clinical Practice, clinical trials must protect rights and safety of patients and make sure that the trial results are valid and interpretable. Monitoring on-site has an important role in achieving these objectives; it controls trial conduct at trial sites and informs the sponsor on systematic problems. In the past, extensive on-site monitoring with a particular focus on formal source data verification often lost sight of systematic problems in study procedures that endanger Good Clinical Practice objectives. ADAMON is a prospective, stratified, cluster-randomised, controlled study comparing extensive on-site monitoring with risk-adapted monitoring according to a previously published approach. Methods In all, 213 sites from 11 academic trials were cluster-randomised between extensive on-site monitoring (104) and risk-adapted monitoring (109). Independent post-trial audits using structured manuals were performed to determine the frequency of major Good Clinical Practice findings at the patient level. The primary outcome measure is the proportion of audited patients with at least one major audit finding. Analysis relies on logistic regression incorporating trial and monitoring arm as fixed effects and site as random effect. The hypothesis was that risk-adapted monitoring is non-inferior to extensive on-site monitoring with a non-inferiority margin of 0.60 (logit scale). Results Average number of monitoring visits and time spent on-site was 2.1 and 2.7 times higher in extensive on-site monitoring than in risk-adapted monitoring, respectively. A total of 156 (extensive on-site monitoring: 76; risk-adapted monitoring: 80) sites were audited. In 996 of 1618 audited patients, a total of 2456 major audit findings were documented. Depending on the trial, findings were identified in 18%-99% of the audited patients, with no marked monitoring effect in any of the trials. The estimated monitoring effect is -0.04 on the logit scale with two-sided 95

The first symposium of Research Center for Radiation Safety, NIRS. Perspective of future studies of radiation safety

International Nuclear Information System (INIS)

Shimo, Michikuni

2002-03-01

This paper summarizes presentations given in the title symposium, held at the Conference Room of National Institute of Radiological Sciences (NIRS) on November 29 and 30, 2001. Contained are Introductory remarks: Basic presentations concerning exposure dose in man; Environmental levels of radiation and radioactivity, environmental radon level and exposure dose, and radiation levels in the specific environment (like in the aircraft): Special lecture (biological effects given by space environment) concerning various needs for studies of radiation safety; Requirement for open investigations, from the view of utilization, research and development of atomic energy, from the clinical aspect, and from the epidemiological aspect: Special lecture (safety in utilization of atomic energy and radiation-Activities of Nuclear Safety Commission of Japan) concerning present state and perspective of studies of radiation safety; Safety of radiation and studies of biological effects of radiation-perspective, and radiation protection and radiation safety studies: Studies in the Research Center for Radiation Safety; Summary of studies in the center, studies of the biological effects of neutron beam, carcinogenesis by radiation and living environmental factors-complicated effects, and studies of hereditary effects: Panel discussion (future direction of studies of radiation safety for the purpose of the center's direction): and concluding remarks. (N.I.)

Consumer perception of safety in the agri-food chain

DEFF Research Database (Denmark)

Verbeke, Wim; Scholderer, Joachim; Frewer, Lynn J.

2006-01-01

, former real or perceived food safety problems extended into food scares after extensive mass media coverage. A wide diversity of studies consistently report declining consumer confidence, deteriorating perception and decreasing consumption rates after exposure to adverse food-health communication. After......Introduction: The aim of this section is to describe the scope and objectives of this chapter on consumer perception of safety in the agri-food chain. Furthermore, the rationale for taking consumer behavioural issues into account in agri-food safety debates is provided. In order to shed some light...... on consumer behaviour with respect to food safety issues, this chapter both provides some basic principles of consumer behaviour and a selection of topical case studies. First, this chapter envisages introducing basic principles of consumer behaviour and consumer decision-making that are applicable in food...

77 FR 46739 - Proposed Extension of Approval of Information Collection; Comment Request-Baby Bouncers and...

Science.gov (United States)

2012-08-06

... CONSUMER PRODUCT SAFETY COMMISSION Proposed Extension of Approval of Information Collection; Comment Request--Baby Bouncers and Walker-Jumpers AGENCY: Consumer Product Safety Commission. ACTION... information collection requirements for manufacturers and importers of children's articles known as baby...

Nuclear power plant ageing and life extension: Safety aspects

International Nuclear Information System (INIS)

Novak, S.; Podest, M.

1987-01-01

Experience with large fossil-fired electrical generating units, as well as in all process industries, shows that plants begin to deteriorate with age after approximately 10 years of operation. Similar phenomena will prevail for nuclear plants, and it is reasonable to postulate that their availability will be affected, as will their safety, if appropriate measures are not taken. It is evident that the average age of power reactors in the IAEA's Member States is increasing. By 2000, more than 50 nuclear plants will have been providing electricity for 25 years or longer. Most nuclear power plants have operating lifetimes of between 20 and 40 years. Ageing is defined as a continuing time-dependent degradation of material due to service conditions, including normal operation and transient conditions. It is common experience that over long periods of time, there is a gradual change in the properties of materials. These changes can affect the capability of engineered components, systems, or structures to perform their required function. Not all changes are deleterious, but it is commonly observed that ageing processes normally involve a gradual reduction in performance capability. All materials in a nuclear power plant can suffer from ageing and can partially or totally lose their designed function. Ageing is not only of concern for active components (for which the probability of malfunction increases with time) but also for passive ones, since the safety margin is being reduced towards the lowest allowable level

Sustained weight loss in patients treated with mifepristone for Cushing's syndrome: a follow-up analysis of the SEISMIC study and long-term extension.

Science.gov (United States)

Fein, Henry G; Vaughan, T Brooks; Kushner, Harvey; Cram, David; Nguyen, Dat

2015-10-27

Overweight and obesity are common among patients with Cushing's syndrome (CS) and may persist in some patients even after ostensibly curative surgery, contributing to cardiometabolic dysfunction and increased cardiovascular risk. Mifepristone, a selective glucocorticoid receptor antagonist, was effective in controlling hyperglycemia in a 24-week trial of adults (N = 50) with endogenous CS and associated type 2 diabetes mellitus/impaired glucose tolerance or hypertension who had failed or were not candidates for surgery (SEISMIC, Study of the Efficacy and Safety of Mifepristone in the Treatment of Endogenous Cushing's Syndrome). This analysis examines long-term weight change among patients who received mifepristone in SEISMIC and enrolled in a long-term safety extension (LTE) study. Patients completing the 24-week SEISMIC study and subsequent 6-week off-drug safety evaluation were invited to enroll in the LTE study. Mifepristone doses at the end of SEISMIC were the LTE starting doses. Body weight measures were reviewed at baseline and week 24 of SEISMIC and at LTE month 6, 12, 18, 24, and final visit (last observation collected during the LTE study). Of the 30 patients enrolled in the LTE, evaluable weight data were available for 29 (20/29 female; mean age of 44.7 ± 11.2 years). These patients received mifepristone for a median of 29.2 months (range 8.4-41.9). Mean ± SD weight from SEISMIC baseline to LTE final visit decreased by 10.3 ± 16.3 kg (mean 105.4 ± 34.3 kg to 95.1 ± 32.9 kg), a 9.3 % decrease from baseline weight (P = 0.0008). Of the 29 LTE patients, 18 (62.1 %) lost ≥ 5 % of body weight by the end of the initial 24-week treatment period; this ≥5 % weight loss persisted in 83.3 % (15/18) at LTE final visit. Ten patients (34.5 %) lost ≥ 10 % of initial body weight by week 24 of SEISMIC, which persisted in 80 % at LTE final visit. No new safety signals were detected with long-term mifepristone use. Clinically meaningful weight loss achieved during

Structural safety - Is the safety margin measurable

International Nuclear Information System (INIS)

Rintamaa, R.

1992-01-01

In ensuring the structural safety of the nuclear components one must be aware of the uncertainties related to the material deorientation, loadings and other operational conditions, geometrical dimensions as well as the service environment. Furthermore, the validation of the analysis tools and procedures is of great importance in overall safety assessment of a pressure retaining component. In order to identify and quantify the concerns and risks arising from the uncertainties in the safety related issue intensive research is being carried out all over the world, in particular, on the ageing, plant life extension and management of old nuclear power plants. The presentation includes a general survey of the factors relevant to the assessment of safe and reliable operation of a nuclear component throughout its planned service life. Certain aspects are outlined based on the research work being carried out at the Technical Research Centre of Finland (VTT)(orig.)

Safety lock for radiography exposure device

International Nuclear Information System (INIS)

Gaines, T.M.

1982-01-01

A safety lock for securing a radiation source in a radiography exposure device is disclosed. The safety lock prevents the inadvertent extension of the radiation source from the exposure device. The exposure devices are used extensively in industry for nondestructive testing of metal materials for defect. Unnecessary exposure of the radiographer or operator occurs not infrequently due to operator's error in believing that the radiation source is secured in the exposure device when, in fact, it is not. The present invention solves this problem of unnecessary exposure by releasingly trapping the radiation source in the shield of the radiography exposure device each time the source is retracted therein so that it is not inadvertently extended therefrom without the operator resetting the safety lock, thereby releasing the radiation source. Further, the safety lock includes an indicator which indicates when the source is trapped in the exposure device and also when it is untrapped. The safety lock is so designed that it does not prevent the return of the source to the trapped, shielded position in the exposure device. Further the safety lock includes a key means for locking the radiation source in the trapped position. The key means cannot be actuated until said radiation source is in said trapped position to further insure the safety lock cannot be inadvertently locked with the source untrapped and thus still extendable from the exposure device

Lessons learned from measuring safety culture: an Australian case study.

Science.gov (United States)

Allen, Suellen; Chiarella, Mary; Homer, Caroline S E

2010-10-01

adverse events in maternity care are relatively common but often avoidable. International patient safety strategies advocate measuring safety culture as a strategy to improve patient safety. Evidence suggests it is necessary to fully understand the safety culture of an organisation to make improvements to patient safety. this paper reports a case study examining the safety culture in one maternity service in Australia and considers the benefits of using surveys and interviews to understand safety culture as an approach to identify possible strategies to improve patient safety in this setting. the study took place in one maternity service in two public hospitals in NSW, Australia. Concurrently, both hospitals were undergoing an organisational restructure which was part of a major health reform agenda. The priorities of the reform included improving the quality of care and patient safety; and, creating a more efficient health system by reducing administration inefficiencies and duplication. a descriptive case study using three approaches: the safety culture was identified to warrant improvement across all six safety culture domains. There was reduced infrastructure and capacity to support incident management activities required to improve safety, which was influenced by instability from the organisational restructure. There was a perceived lack of leadership at all levels to drive safety and quality and improving the safety culture was neither a key priority nor was it valued by the organisation. the safety culture was complex as was undertaking this study. We were unable to achieve a desired 60% response rate highlighting the limitations of using safety culture surveys in isolation as a strategy to improve safety culture. Qualitative interviews provided greater insight into the factors influencing the safety culture. The findings of this study provide evidence of the benefits of including qualitative methods with quantitative surveys when examining safety culture

Japan reforms its nuclear safety

International Nuclear Information System (INIS)

Anon.

2013-01-01

The Fukushima Daiichi NPP accident deeply questioned the bases of nuclear safety and nuclear safety regulation in Japan. It also resulted in a considerable loss of public confidence in the safety of nuclear power across the world. Although the accident was caused by natural phenomena, institutional and human factors also largely contributed to its devastating consequences, as shown by the Japanese Diet's and Government's investigation reports. 'Both regulators and licensees were held responsible and decided to fully reconsider the existing approaches to nuclear safety. Consequently, the regulatory system underwent extensive reform based on the lessons learned from the accident,' Yoshihiro Nakagome, the President of Japan Nuclear Energy Safety Organisation, an ETSON member TSO, explains. (orig.)

A service life extension (SLEP) approach to operating aging aircraft beyond their original design lives

Science.gov (United States)

Pentz, Alan Carter

With today's uncertain funding climate (including sequestration and continuing budget resolutions), decision makers face severe budgetary challenges to maintain dominance through all aspects of the Department of Defense (DoD). To meet war-fighting capabilities, the DoD continues to extend aircraft programs beyond their design service lives by up to ten years, and occasionally much more. The budget requires a new approach to traditional extension strategies (i.e., reuse, reset, and reclamation) for structural hardware. While extending service life without careful controls can present a safety concern, future operations planning does not consider how much risk is present when operating within sound structural principles. Traditional structural hardware extension methods drive increased costs. Decision makers often overlook the inherent damage tolerance and fatigue capability of structural components and rely on simple time- and flight-based cycle accumulation when determining aircraft retirement lives. This study demonstrates that decision makers should consider risk in addition to the current extension strategies. Through an evaluation of eight military aircraft programs and the application and simulation of F-18 turbine engine usage data, this dissertation shows that insight into actual aircraft mission data, consideration of fatigue capability, and service extension length are key factors to consider. Aircraft structural components, as well as many critical safety components and system designs, have a predefined level of conservatism and inherent damage tolerance. The methods applied in this study would apply to extensions of other critical structures such as bridges. Understanding how much damage tolerance is built into the design compared to the original design usage requirements presents the opportunity to manage systems based on risk. The study presents the sensitivity of these factors and recommends avenues for further research.

Nuclear safety. Improvement programme

International Nuclear Information System (INIS)

2000-01-01

In this brochure the improvement programme of nuclear safety of the Mochovce NPP is presented in detail. In 1996, a 'Mochovce NPP Nuclear Safety Improvement Programme' was developed in the frame of unit 1 and 2 completion project. The programme has been compiled as a continuous one, with the aim to reach the highest possible safety level at the time of commissioning and to establish good preconditions for permanent safety improvement in future. Such an approach is in compliance with the world's trends of safety improvement, life-time extension, modernisation and nuclear station power increase. The basic document for development of the 'Programme' is the one titled 'Safety Issues and their Ranking for WWER 440/213 NPP' developed by a group of IAEA experts. The following organisations were selected for solution of the safety measures: EUCOM (Consortium of FRAMATOME, France, and SIEMENS, Germany); SKODA Prague, a.s.; ENERGOPROJEKT Prague, a.s. (EGP); Russian organisations associated in ATOMENERGOEXPORT; VUJE Trnava, a.s

Randomized controlled trials and real-world observational studies in evaluating cardiovascular safety of inhaled bronchodilator therapy in COPD

Directory of Open Access Journals (Sweden)

Kardos P

2016-11-01

Full Text Available Peter Kardos,1 Sally Worsley,2 Dave Singh,3 Miguel Román-Rodríguez,4 David E Newby,5 Hana Müllerová2 1Group Practice and Respiratory, Allergy and Sleep Unit, Red Cross Maingau Hospital, Frankfurt, Germany; 2GSK, Stockley Park, Middlesex, 3University of Manchester, Medicines Evaluation Unit, University Hospital of South Manchester NHS Foundation Trust, Manchester, UK; 4Primary Care Respiratory Research Unit, Instituto de Investigación Sanitaria de Palma IdisPa, Palma de Mallorca, Spain; 5BHF Centre for Cardiovascular Science, University of Edinburgh, The Queen’s Medical Research Institute, Edinburgh, UK Abstract: Long-acting muscarinic antagonist (LAMA or long-acting β2-agonist (LABA bronchodilators and their combination are recommended for the maintenance treatment of chronic obstructive pulmonary disease (COPD. Although the efficacy of LAMAs and LABAs has been well established through randomized controlled trials (RCTs, questions remain regarding their cardiovascular (CV safety. Furthermore, while the safety of LAMA and LABA monotherapy has been extensively studied, data are lacking for LAMA/LABA combination therapy, and the majority of the studies that have reported on the CV safety of LAMA/LABA combination therapy were not specifically designed to assess this. Evaluation of CV safety for COPD treatments is important because many patients with COPD have underlying CV comorbidities. However, severe CV and other comorbidities are often exclusion criteria for RCTs, contributing to a lack in external validity and generalizability. Real-world observational studies are another important tool to evaluate the effectiveness and safety of COPD therapies in a broader population of patients and can improve upon the external validity limitations of RCTs. We examine what is already known regarding the CV and cerebrovascular safety of LAMA/LABA combination therapy from RCTs and real-world observational studies, and explore the advantages and

77 FR 55812 - Proposed Extension of Approval of Information Collection; Comment Request-Baby Bouncers and...

Science.gov (United States)

2012-09-11

... CONSUMER PRODUCT SAFETY COMMISSION [Docket No. CPSC-2012-0038] Proposed Extension of Approval of Information Collection; Comment Request--Baby Bouncers and Walker-Jumpers AGENCY: Consumer Product Safety... collection requirements for manufacturers and importers of children's articles known as baby-bouncers and...

National Nuclear Safety Department Experience of Supervision over Safety Culture of BNPP-1

International Nuclear Information System (INIS)

Sepanloo, K.; Ardeshir, A.T.

2016-01-01

The analysis of the past major NPPs accidents, TMI, Chernobyl and Fukushima Daiichi shows that causes of these accidents can be explained by a complex combination of human, technological and organizational factors. One of the findings of accident investigations and risk assessments is the growing recognition of the impact of cultural context of work practices on safety. The assumed link between culture and safety, epitomized through the concept of safety culture, has been the subject of extensive research in recent years. The term “safety culture” was first introduced into the nuclear industry by the IAEA in INSAG-1 to underline the role and importance of the organizational factors. The objective of this paper is to conduct an assessment of some safety culture indicators of Bushehr Nuclear Power Plant (BNPP-1).

Experimental facilities for gas-cooled reactor safety studies. Task group on Advanced Reactor Experimental Facilities (TAREF)

International Nuclear Information System (INIS)

2009-01-01

In 2007, the NEA Committee on the Safety of Nuclear Installations (CSNI) completed a study on Nuclear Safety Research in OECD Countries: Support Facilities for Existing and Advanced Reactors (SFEAR) which focused on facilities suitable for current and advanced water reactor systems. In a subsequent collective opinion on the subject, the CSNI recommended to conduct a similar exercise for Generation IV reactor designs, aiming to develop a strategy for ' better preparing the CSNI to play a role in the planned extension of safety research beyond the needs set by current operating reactors'. In that context, the CSNI established the Task Group on Advanced Reactor Experimental Facilities (TAREF) in 2008 with the objective of providing an overview of facilities suitable for performing safety research relevant to gas-cooled reactors and sodium fast reactors. This report addresses gas-cooled reactors; a similar report covering sodium fast reactors is under preparation. The findings of the TAREF are expected to trigger internationally funded CSNI projects on relevant safety issues at the key facilities identified. Such CSNI-sponsored projects constitute a means for efficiently obtaining the necessary data through internationally co-ordinated research. This report provides an overview of experimental facilities that can be used to carry out nuclear safety research for gas-cooled reactors and identifies priorities for organizing international co-operative programmes at selected facilities. The information has been collected and analysed by a Task Group on Advanced Reactor Experimental Facilities (TAREF) as part of an ongoing initiative of the NEA Committee on the Safety of Nuclear Installations (CSNI) which aims to define and to implement a strategy for the efficient utilisation of facilities and resources for Generation IV reactor systems. (author)

Angra-1 probabilistic safety study-phase B

International Nuclear Information System (INIS)

Fernandes Filho, T.L.; Gibelli, S.M.O.

1988-05-01

This study represents the Phase B of the Angra-1 Probabilistic Safety Study and is the the final report prepared for the IAEA under Research Contract No. 3423/R2/RB. The three main items covered in this report are the establishment of interim safety goals, analysis of Angra-1 operational experience and development of emergency procedures to address severe accidents. For establishment of interim safety goals a methodology for calculating consequences and risks associated to the Angra-1 operation was developed based on the available data and codes. The proposed safety goals refer to the individual risk of early fatality for people living in the vicinity of the plant, colective risk of cancer fatalities for people living near the plant, the propobability of core melt occurrence and the probability of dominant accident sequences. (author) [pt

Environmental, Safety, and Health Plan for the remedial investigation/feasibility study at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Revision 1, Environmental Restoration Program

Energy Technology Data Exchange (ETDEWEB)

Davis, C. M.; El-Messidi, O. E.; Cowser, D. K.; Kannard, J. R.; Carvin, R. T.; Will, III, A. S.; Clark, Jr., C.; Garland, S. B.

1993-05-01

This Environmental, Safety, and Health (ES&H) Plan presents the concepts and methodologies to be followed during the remedial investigation/feasibility study (RI/FS) for Oak Ridge National Laboratory (ORNL) to protect the health and safety of employees, the public, and the environment. This ES&H Plan acts as a management extension for ORNL and Martin Marietta Energy Systems, Inc. (Energy Systems) to direct and control implementation of the project ES&H program. The subsections that follow describe the program philosophy, requirements, quality assurance measures, and methods for applying the ES&H program to individual waste area grouping (WAG) remedial investigations. Hazardous work permits (HWPs) will be used to provide task-specific health and safety requirements.

Behavioral integrity for safety, priority of safety, psychological safety, and patient safety : a team-level study

NARCIS (Netherlands)

Leroy, H.; Dierynck, B.; Anseel, F.; Simons, T.; Halbesleben, J.R.; McCaughey, D.; Savage, G.T.; Sels, L.

2012-01-01

This article clarifies how leader behavioral integrity for safety helps solve follower's double bind between adhering to safety protocols and speaking up about mistakes against protocols. Path modeling of survey data in 54 nursing teams showed that head nurse behavioral integrity for safety

A study on safety climate at nuclear power plants

International Nuclear Information System (INIS)

Fukui, Hirokazu; Yoshida, Michio; Yoshiyama, Naohiro

2001-01-01

In the current study, we define safety climate as an organizational environment that induces members of the organization to give consideration to safety or take safety actions. It is of utmost importance that people holding managerial positions in an organization have a good understanding of the characteristics of the safety climate of the organization and implement safety promotion activities effectively. In the current research, we studied the rating scales and the characteristics of a safety climate. A survey was conducted, targeting technical engineers who belong to the three power stations of Kansai Electric Power Co., Inc. The questionnaire mainly consisted of questions concerning safety measures taken by individuals and questions concerning safety measures taken by the organization, to which the individuals belong. As a result of a factor analysis of the responses, we extracted five factors, namely, 'confidence in knowledge and skill', attitude of supervisors,' 'safety education in workplace', 'clarity of tasks' and 'safety confirmation/report'. In studying the rating scales of the safety climate, we selected five items from each of the above five factors, and used the total scores of the ratings of the five items as scores of each factor. Then, we examined the correlation between scores of personal factors and scores of organizational environment factors. We treated the scores of safety confirmation/report' and 'confidence in knowledge and skill', which are personal factors, as criterion variables, and the scores of 'attitude of supervisors', 'safety education in workplace' and 'clarity of tasks', which are organizational environment factors, as predictor variables. As a result, we found that levels of 'safety confirmation/report' and 'confidence in knowledge and skill' can be deduced from the scores of 'attitude of supervisors', 'safety education in workplace' and 'clarity of tasks.' Hence, we have decided to use these three organizational environment

Risk-based evaluation of allowed outage time and surveillance test interval extensions for nuclear power plants

International Nuclear Information System (INIS)

Gibelli, Sonia Maria Orlando

2008-03-01

The main goal of this work is, through the use of Probabilistic Safety Analysis (PSA), to evaluate Technical Specification (TS) Allowed Outage Times (AOT) and Surveillance Test Intervals (STI) extensions for Angra 1 nuclear power plant. PSA has been incorporated as an additional tool, required as part of NPP licensing process. The risk measure used in this work is the Core Damage Frequency (CDF), obtained from the Angra 1 PSA Level 1. AOT and STI extensions are calculated for the Safety Injection System (SIS), Service water System (SAS) and Auxiliary Feedwater System (AFS) through the use of SAPHIRE code. In order to compensate for the risk increase caused by the extensions, compensatory measures as test of redundant train prior to entering maintenance and staggered test strategy are proposed. Results have shown that the proposed AOT extensions are acceptable for the SIS and SAS with the implementation of compensatory measures. The proposed AOT extension is not acceptable for the AFS. The STI extensions are acceptable for all three systems. (author)

Safety stock placement in supply chains with demand forecast updates

Directory of Open Access Journals (Sweden)

Youssef Boulaksil

2016-01-01

Full Text Available Supply chains are exposed to many types of risks and it may not be obvious where to keep safety stocks in the supply chain to hedge against those risks, while maintaining a high customer service level. In this paper, we develop an approach to determine the safety stock levels in supply chain systems that face demand uncertainty. We model customer demand following the Martingale Model of Forecast Evolution (MMFE. An extensive body of literature discusses the safety stock placement problem in supply chains, but most studies assume independent and identically distributed demand. Our approach is based on a simulation study in which mathematical models are solved in a rolling horizon setting. It allows determining the safety stock levels at each stage of the supply chain. Based on a numerical study, we find that a big portion of the safety stocks should be placed downstream in the supply chain to achieve a high customer service level.

Criticality safety basics, a study guide

Energy Technology Data Exchange (ETDEWEB)

V. L. Putman

1999-09-01

This document is a self-study and classroom guide, for criticality safety of activities with fissile materials outside nuclear reactors. This guide provides a basic overview of criticality safety and criticality accident prevention methods divided into three parts: theory, application, and history. Except for topic emphasis, theory and history information is general, while application information is specific to the Idaho National Engineering and Environmental Laboratory (INEEL). Information presented here should be useful to personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. However, the guide's primary target audience is fissile material handler candidates.

Criticality safety basics, a study guide

International Nuclear Information System (INIS)

Putman, V.L.

1999-01-01

This document is a self-study and classroom guide, for criticality safety of activities with fissile materials outside nuclear reactors. This guide provides a basic overview of criticality safety and criticality accident prevention methods divided into three parts: theory, application, and history. Except for topic emphasis, theory and history information is general, while application information is specific to the Idaho National Engineering and Environmental Laboratory (INEEL). Information presented here should be useful to personnel who must know criticality safety basics to perform their assignments safely or to design critically safe equipment or operations. However, the guide's primary target audience is fissile material handler candidates

Lifetime-management and lifetime-extension at PAKS nuclear power plant

International Nuclear Information System (INIS)

Katona, Tamas; Ratkai, Sandor; Janosi, Agnes Biro

2002-01-01

Paks Nuclear Power Plant provides 38-40% of domestic generation at lowest price. It has an important energy-policy role in Hungary. NPP Paks shall be a decisive and perspectively permanent element of the domestic electricity generation during the next two decades, which shall be ensured by plant safe operation, the lifetime extension and power uprating. Paks Nuclear Power Plant investigated the nuclear power plant's lifetime extension possibilities and alternatives, as well as technical and business feasibility of such alternatives. The feasibility study is based on the evaluation of a representative set of systems, structures and components, operational, test, in-service inspection and maintenance practice, experience and findings of the Periodic Safety Review. The most important results of this study showing the feasibility of 20 years lifetime extension is summarised in the paper. It was found that there are no technical or safety issues or limits, which may inhibit the operation of the Nuclear Power Plant Paks up to 50 years. In case of most systems and equipment the recent monitoring, maintenance and regular reconstruction practice of the NPP Paks allows the lifetime extension without outstanding cost. Replacement or reconstruction of a few equipment and systems requires significant investment costs. Material of reactor vessels of VVER/213 incorporated at Paks, compared to vessels of the similar units, is less sensitive to the embrittlement. At units 3-4 reactor vessels do not require any measure, consequently, any additional cost, even in case of a lifetime of 50 years. At unit 2 to extend the lifetime of the reactor vessel, only heating-up of emergency core cooling tanks is needed in order to decrease thermal stress levels caused by pressure thermal shock (PST) transients. For this purpose cost-effective technical solutions are available. At unit 1, beside the heating-up of the emergency core cooling tanks annealing of the welded joint No. 5/6 close to the

The 40 year deadline for the French nuclear stock. Decision process, strengthening option and costs associated with a possible lifetime extension beyond 40 years of EDF reactors

International Nuclear Information System (INIS)

Marignac, Yves

2014-01-01

This report first proposes an overview of the lifetime extension problematic (PLEX) for nuclear plants in a general context (strategy of lifetime extension, and uncertainty and lack of return on experience), and in the case of France (emergence of a strategy of lifetime extension, economic challenges of an extension, uncertainty on investments required by an extension, risk of imposed implicit decisions). It gives a rather detailed overview of the French nuclear reactor fleet, of the status of EDF-operated reactors (construction stages, main lifetime events, regulatory situation of currently exploited reactors) and of their characteristics (common operation principle, main components, main safety functions, main considered severe accidents). It addresses safety issues related to ageing and to the post-Fukushima re-assessment (problematic, robustness increase, limits and weaknesses of additional safety assessments). It presents the currently performed improvements (safety referential, applicable strengthening requirements like safety re-examinations and requirements introduced after Fukushima, applied strengthening prescriptions drawn from additional safety assessments or from the third decennial inspection, with their limitations and perspectives). It proposes strengthening scenarios along with their challenges (in terms of requirement level, procedure and agenda). Three scenarios are proposed (degraded safety, preserved safety, strengthened safety) and analysed in terms of protection against aggressions, diffuse robustness, prevention and management of reactor accident, prevention and management of pool accidents, ultimate control and assistance means. Scenarios are finally compared in terms of costs

Design and safety aspects of nuclear district heating reactors

International Nuclear Information System (INIS)

Brogli, R.; Mathews, D.; Pelloni, S.

1989-01-01

Extensive studies on the rationale, the potential and the technology of nuclear district heating have been performed in Switzerland. Beside economics the safety aspects were of primary importance. Due to the high costs to transport heat the heating reactor tend to be small and therefore, minimally staffed and located close to population centers. Stringed safety rules are therefore applying. Gas cooled reactors are well suited as district heating reactors since they have due to their characteristics several inherent features, significant safety margins and a remarkable radioactivity retention potential. Some ways to mitigate the effects of water ingress and graphite corrosion are under investigation. (author). 5 refs, 3 figs

Life extension decision making of safety critical systems: An overview

OpenAIRE

Shafiee, Mahmood; Animah, I.

2017-01-01

In recent years, the concept of “asset life extension” has become increasingly important to safety critical industries including nuclear power, offshore oil and gas, petrochemical, renewable energy, rail transport, aviation, shipping, electricity distribution and transmission, etc. Extending the service life of industrial assets can offer a broad range of economic, technical, social and environmental benefits as compared to other end-of-life management strategies such as decommissioning and r...

Life prediction study of reactor pressure vessel as essential technical foundation for plant life extension

International Nuclear Information System (INIS)

Nakajima, H.; Nakajima, N.; Kondo, T.

1987-01-01

The life of a LWR plant is determined essentially by the limit of reliable performance of the components which are difficult to replace without high economic and/or safety risks. Typical of such a component is the reactor pressure vessel (RPV). The engineering life of a RPV of a given quality of steel is considered to be a complex function of factors such as the resistance to fracture, which has deteriorated due to neutron irradiation and thermal aging, and generation of surface flaws by environmental effects such as corrosion and their growth under operational load that varies during steady state operation and transients. In an attempt to evaluate the engineering life of a RPV of a LWR, a preliminary survey was made by applying a set of knowledge accumulated primarily in the field of subcritical crack growth behavior of RPV steels in reactor water environments. The major conclusions drawn are: (1) the life of a RPV is dependent on the quality of steel used, particularly with respect to any minor impurities it contains. (2) The issue of plant life extension in RPV aspect is found to be optimistic for cases where the steels used satisfy a reasonable level of quality control. (3) The importance of providing sound scientific foundation is stressed for the implementation of a practicable life extension scheme: this can be established through intensified studies of flaw growth and fracture behaviours in well defined testings under reasonably simulated service conditions

Safety certification of airborne software: An empirical study

International Nuclear Information System (INIS)

Dodd, Ian; Habli, Ibrahim

2012-01-01

Many safety-critical aircraft functions are software-enabled. Airborne software must be audited and approved by the aerospace certification authorities prior to deployment. The auditing process is time-consuming, and its outcome is unpredictable, due to the criticality and complex nature of airborne software. To ensure that the engineering of airborne software is systematically regulated and is auditable, certification authorities mandate compliance with safety standards that detail industrial best practice. This paper reviews existing practices in software safety certification. It also explores how software safety audits are performed in the civil aerospace domain. The paper then proposes a statistical method for supporting software safety audits by collecting and analysing data about the software throughout its lifecycle. This method is then empirically evaluated through an industrial case study based on data collected from 9 aerospace projects covering 58 software releases. The results of this case study show that our proposed method can help the certification authorities and the software and safety engineers to gain confidence in the certification readiness of airborne software and predict the likely outcome of the audits. The results also highlight some confidentiality issues concerning the management and retention of sensitive data generated from safety-critical projects.

A literature review of safety culture.

Energy Technology Data Exchange (ETDEWEB)

Cole, Kerstan Suzanne; Stevens-Adams, Susan Marie; Wenner, Caren A.

2013-03-01

Workplace safety has been historically neglected by organizations in order to enhance profitability. Over the past 30 years, safety concerns and attention to safety have increased due to a series of disastrous events occurring across many different industries (e.g., Chernobyl, Upper Big-Branch Mine, Davis-Besse etc.). Many organizations have focused on promoting a healthy safety culture as a way to understand past incidents, and to prevent future disasters. There is an extensive academic literature devoted to safety culture, and the Department of Energy has also published a significant number of documents related to safety culture. The purpose of the current endeavor was to conduct a review of the safety culture literature in order to understand definitions, methodologies, models, and successful interventions for improving safety culture. After reviewing the literature, we observed four emerging themes. First, it was apparent that although safety culture is a valuable construct, it has some inherent weaknesses. For example, there is no common definition of safety culture and no standard way for assessing the construct. Second, it is apparent that researchers know how to measure particular components of safety culture, with specific focus on individual and organizational factors. Such existing methodologies can be leveraged for future assessments. Third, based on the published literature, the relationship between safety culture and performance is tenuous at best. There are few empirical studies that examine the relationship between safety culture and safety performance metrics. Further, most of these studies do not include a description of the implementation of interventions to improve safety culture, or do not measure the effect of these interventions on safety culture or performance. Fourth, safety culture is best viewed as a dynamic, multi-faceted overall system composed of individual, engineered and organizational models. By addressing all three components of

Quality management of pharmacology and safety pharmacology studies

DEFF Research Database (Denmark)

Spindler, Per; Seiler, Jürg P

2002-01-01

to safety pharmacology studies, and, when indicated, to secondary pharmacodynamic studies, does not influence the scientific standards of studies. However, applying formal GLP standards will ensure the quality, reliability and integrity of studies, which reflect sound study management. It is important...... to encourage a positive attitude among researchers and academics towards these lines, whenever possible. GLP principles applied to the management of non-clinical safety studies are appropriate quality standards when studies are used in the context of protecting public health, and these quality standards...... of pharmacology studies (ICH S7A): primary pharmacodynamic, secondary pharmacodynamic and safety pharmacology studies, and guidance on the quality standards (expectations for GLP conformity) for these study types have been provided. Primary pharmacodynamic studies are the only study types that are fully exempt...

Effectiveness and safety of imipenem/clavulanate and linezolid to treat multidrug and extensively drug-resistant tuberculosis at a referral hospital in Brazil

Directory of Open Access Journals (Sweden)

M.A. Arbex

2016-11-01

Full Text Available Evidence on effectiveness, safety, and tolerability of imipenem/clavulanate (IC and linezolid containing regimens to treat multidrug-resistant (MDR- and extensively drug-resistant tuberculosis (XDR-TB is scarce. The aim of this observational study is to evaluate the therapeutic contribution of IC and linezolid to manage MDR/XDR-TB cases at the reference centre of São Paulo state, Brazil. Twelve patients (9 males, 1 HIV positive in antiretroviral treatment, 4 MDR, 8 XDR were treated with IC, 11 of them within linezolid-containing regimens. They all were previously treated with treatment failure, for a median (IQR, interquartile range of 4.5 (2–6.5 times, having a severe resistance pattern (median number of resistances: 7 (5–8 and being sputum smear and culture positive. IC and linezolid were prescribed at the dose of 1000 mg/day and 600 mg/day, respectively. The overall exposure was (median (IQR 419 (375.5–658 days for IC and 678 (392–720 days for linezolid. All of them converted their sputum (time to sputum conversion; 60 (37.5–90 days and culture (75 (60–135 days, and 7 were cured while 5 are still on treatment with a gradually improving clinical picture.While no adverse events were reported for IC, 2 minor side effects, only, were attributed to linezolid (17%; in both cases the drug was re-started without further problems. Our study suggests that IC and linezolid-containing regimens can be used safely and with satisfactory outcomes in reference centres to treat MDR/XDR-TB patients. Keywords: MDR-TB, XDR-TB, Imipenem, Linezolid, Effectiveness, Safety, Tolerability

Effect of electronic device use on pedestrian safety : a literature review.

Science.gov (United States)

2016-04-01

This literature review on the effect of electronic device use on pedestrian safety is part of a research project sponsored by the Office of Behavioral Safety Research in the National Highway Traffic Safety Administration (NHTSA). An extensive literat...

A study on safety climate at nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Fukui, Hirokazu [Institute of Nuclear Safety System Inc., Mihama, Fukui (Japan); Yoshida, Michio; Yoshiyama, Naohiro [Japan Institute for Group Dynamics, Fukuoka (Japan)

2001-09-01

In the current study, we define safety climate as an organizational environment that induces members of the organization to give consideration to safety or take safety actions. It is of utmost importance that people holding managerial positions in an organization have a good understanding of the characteristics of the safety climate of the organization and implement safety promotion activities effectively. In the current research, we studied the rating scales and the characteristics of a safety climate. A survey was conducted, targeting technical engineers who belong to the three power stations of Kansai Electric Power Co., Inc. The questionnaire mainly consisted of questions concerning safety measures taken by individuals and questions concerning safety measures taken by the organization, to which the individuals belong. As a result of a factor analysis of the responses, we extracted five factors, namely, 'confidence in knowledge and skill', attitude of supervisors,' 'safety education in workplace', 'clarity of tasks' and 'safety confirmation/report'. In studying the rating scales of the safety climate, we selected five items from each of the above five factors, and used the total scores of the ratings of the five items as scores of each factor. Then, we examined the correlation between scores of personal factors and scores of organizational environment factors. We treated the scores of safety confirmation/report' and 'confidence in knowledge and skill', which are personal factors, as criterion variables, and the scores of 'attitude of supervisors', 'safety education in workplace' and 'clarity of tasks', which are organizational environment factors, as predictor variables. As a result, we found that levels of 'safety confirmation/report' and 'confidence in knowledge and skill' can be deduced from the scores of 'attitude of supervisors', 'safety

Operational safety at the FFTF

International Nuclear Information System (INIS)

Baird, Q.L.; Hagan, J.W.; Seeman, S.E.; Baker, S.M.

1981-02-01

An extensive operational nuclear safety program has been an integral part of the design, startup, and initial operating phases of the Fast Flux Test Facility (FFTF). During the design and construction of the facility, a program of independent safety overviews and analyses assured the provision of responsible safety margins within the plant, protective systems, and engineered safety features for protection of the public, operating staff, and the facility. The program is continuing through surveillance of operations to verify continued adherence to the established operating envelope and for timely identification of any trends potentially adverse to those margins. Experience from operation of FFTF is being utilized in the development of enhanced operational nuclear safety aids for application in follow-on breeder reactor power systems. The commendable plant and personnel safety experiences of FFTF through its startup and ascension to full power demonstrate the overall effectiveness of the FFTF operational nuclear safety program

The necessity of periodic fire safety review

International Nuclear Information System (INIS)

Mowrer, D.S.

1998-01-01

Effective fire safety requires the coordinated integration of many diverse elements. Clear fire safety objectives are defined by plant management and/or regulatory authorities. Extensive and time-consuming systematic analyses are performed. Fire safety features (both active and passive) are installed and maintained, and administrative programs are established and implemented to achieve the defined objectives. Personnel are rigorously trained. Given the time, effort and monetary resources expended to achieve a specific level of fire safety, conducting periodic assessments to verify that the specified level of fire safety has been achieved and is maintained is a matter of common sense. Periodic fire safety reviews and assessment play an essential role in assuring continual nuclear safety in the world's power plants

Evaluation of neutronic characteristics of in-pile test reactor for fast reactor safety research

Energy Technology Data Exchange (ETDEWEB)

Uto, N.; Ohno, S.; Kawata, N. [Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center

1996-09-01

An extensive research program has been carried out at the Power Reactor and Nuclear Fuel Development Corporation for the safety of future liquid-metal fast breeder reactors to be commercialized. A major part of this program is investigation and planning of advanced safety experiments conducted with a new in-pile safety test facility, which is larger and more advanced than any of the currently existing test reactors. Such a transient safety test reactor generally has unique neutronic characteristics that require various studies from the reactor physics point of view. In this paper, the outcome of the neutronics study is highlighted with presenting a reference core design concept and its performance in regard to the safety test objectives. (author)

Development of safety related technology and infrastructure for safety assessment

International Nuclear Information System (INIS)

Venkat Raj, V.

1997-01-01

Development and optimum utilisation of any technology calls for the building up of the necessary infrastructure and backup facilities. This is particularly true for a developing country like India and more so for an advanced technology like nuclear technology. Right from the inception of its nuclear power programme, the Indian approach has been to develop adequate infrastructure in various areas such as design, construction, manufacture, installation, commissioning and safety assessment of nuclear plants. This paper deals with the development of safety related technology and the relevant infrastructure for safety assessment. A number of computer codes for safety assessment have been developed or adapted in the areas of thermal hydraulics, structural dynamics etc. These codes have undergone extensive validation through data generated in the experimental facilities set up in India as well as participation in international standard problem exercises. Side by side with the development of the tools for safety assessment, the development of safety related technology was also given equal importance. Many of the technologies required for the inspection, ageing assessment and estimation of the residual life of various components and equipment, particularly those having a bearing on safety, were developed. This paper highlights, briefly, the work carried out in some of the areas mentioned above. (author)

Study on 'Safety qualification of process computers used in safety systems of nuclear power plants'

International Nuclear Information System (INIS)

Bertsche, K.; Hoermann, E.

1991-01-01

The study aims at developing safety standards for hardware and software of computer systems which are increasingly used also for important safety systems in nuclear power plants. The survey of the present state-of-the-art of safety requirements and specifications for safety-relevant systems and, additionally, for process computer systems has been compiled from national and foreign rules. In the Federal Republic of Germany the KTA safety guides and the BMI/BMU safety criteria have to be observed. For the design of future computer-aided systems in nuclear power plants it will be necessary to apply the guidelines in [DIN-880] and [DKE-714] together with [DIN-192]. With the aid of a risk graph the various functions of a system, or of a subsystem, can be evaluated with regard to their significance for safety engineering. (orig./HP) [de

Competency Modeling in Extension Education: Integrating an Academic Extension Education Model with an Extension Human Resource Management Model

Science.gov (United States)

Scheer, Scott D.; Cochran, Graham R.; Harder, Amy; Place, Nick T.

2011-01-01

The purpose of this study was to compare and contrast an academic extension education model with an Extension human resource management model. The academic model of 19 competencies was similar across the 22 competencies of the Extension human resource management model. There were seven unique competencies for the human resource management model.…

Characteristics of the safety climate in teams with world-class safety ...

African Journals Online (AJOL)

Accidents and incidents in the construction environment are not reduced or eliminated effectively, despite numerous efforts made to improve health and safety in the industry. An extensive field of research has been conducted on how teams in the construction environment interact to deliver a project successfully in terms of ...

Institutionalization of safety re-assessment system for operating nuclear power plants

International Nuclear Information System (INIS)

Kim, H. J.; Cho, J. C.; Min, B. K.; Park, J. S.; Jung, H. D.; Oh, K. M.; Kim, W. K.; Lim, J. H.

1999-01-01

In this study, in-depth reviews of the foreign countries' experiences and practices in applications of the periodic safety review (PSR), backfitting and license renewal systems as well as the current status of nuclear power safety assurance programs and activities in Korea have been performed to investigate the necessity and feasibility of the application of the systems for the domestic operating nuclear power plants and to establish effective strategy and methodology for the institutionalization of a periodic safety re-assessment system appropriate to both the domestic and international nuclear power environments by incorporating the PSR with the backfitting and license renewal systems. For these purposes, the regulatory policy, fundamental principles and detailed requirements for the institutionalization of the safety re-assessment system and the effective measures for active implementation of the backfitting program have been developed and then a comparative study of benefits and shortcomings has been conducted for the three different models of the periodic safety re-assessment system incorporated with either the license renewal or life extension process, which have been considered as practicable ones in the domestic situation. The model chosen in this study as the most appropriate safety re-assessment system is the one that the re-assessments are performed at the interval of ten years throughout the service life of nuclear power plant and the ten-year license renewal or life extension after the expiration of design life can be permitted based on the regulatory review of the re-assessment results and follow-up measures. Finally, this paper has discussed on the details of the requirements, approach and procedures established for the institutionalization of the periodic safety re-assessment system chosen as the most appropriate one for domestic applications

TAPS safety evaluation criteria for reload fueling

International Nuclear Information System (INIS)

Mahendra Nath; Veeraraghavan, N.

1976-01-01

To improve operating performance of Tarapur reactors, several proposals are under consideration such as core expansion, change-over to an improved fuel design with lower heat rating, extension of fuel cycle lengths etc., which have a bearing on overall plant operating characteristics and reactor safety. For evaluating safety implications of the various proposals, it is necessary to formulate safety evaluation criteria for reload fuelling. Salient features of these criteria are discussed. (author)

Environmental Regulation and Food Safety: Studies of Protection ...

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

Environmental Regulation and Food Safety: Studies of Protection and Protectionism. Book cover Environmental Regulation and Food Safety: Studies of Protection and Protectionism. Directeur(s) : Veena Jha. Maison(s) d'édition : Edward Elgar, IDRC. 1 janvier 2006. ISBN : 184542512X. 250 pages. e-ISBN : 155250185X.

75 FR 79030 - Proposed Extension of Existing Information Collection; Training Plans and Records of Training

Science.gov (United States)

2010-12-17

... Extension of Existing Information Collection; Training Plans and Records of Training AGENCY: Mine Safety and... extension of the information collection for Training Plans and Records of Training, 30 CFR 48.3, 48.9, 48.23... require training plans for underground and surface mines, respectively. The standards are intended to...

Nitrogen-system safety study: Portsmouth Gaseous Diffusion Plant

International Nuclear Information System (INIS)

1982-07-01

The Department of Energy has primary responsibility for the safety of operations at DOE-owned nuclear facilities. The guidelines for the analysis of credible accidents are outlined in DOE Order 5481.1. DOE has requested that existing plant facilities and operations be reviewed for potential safety problems not covered by standard industrial safety procedures. This review is being conducted by investigating individual facilities and documenting the results in Safety Study Reports which will be compiled to form the Existing Plant Final Safety Analysis Report which is scheduled for completion in September, 1984. This Safety Study documents the review of the Plant Nitrogen System facilities and operations and consists of Section 4.0, Facility and Process Description, and Section 5.0, Accident Analysis, of the Final Safety Analysis Report format. The existing nitrogen system consists of a Superior Air Products Company Type D Nitrogen Plant, nitrogen storage facilities, vaporization facilities and a distribution system. The system is designed to generate and distribute nitrogen gas used in the cascade for seal feed, buffer systems, and for servicing equipment when exceptionally low dew points are required. Gaseous nitrogen is also distributed to various process auxiliary buildings. The average usage is approximately 130,000 standard cubic feet per day

Tofacitinib, an oral Janus kinase inhibitor, as monotherapy or with background methotrexate, in Japanese patients with rheumatoid arthritis: an open-label, long-term extension study.

Science.gov (United States)

Yamanaka, Hisashi; Tanaka, Yoshiya; Takeuchi, Tsutomu; Sugiyama, Naonobu; Yuasa, Hirotoshi; Toyoizumi, Shigeyuki; Morishima, Yosuke; Hirose, Tomohiro; Zwillich, Samuel

2016-01-28

Tofacitinib is an oral Janus kinase inhibitor for the treatment of rheumatoid arthritis. Here, tofacitinib safety and efficacy data from a long-term extension study in Japanese patients are presented. Study A3921041 was a multi-centre, open-label, long-term extension study that included Japanese patients who had participated in a prior Phase 2 or Phase 3 study of tofacitinib as monotherapy or with background methotrexate. Patients received tofacitinib 5 mg twice daily (BID) or tofacitinib 10 mg BID. Dose adjustment of tofacitinib during treatment period, and concomitant usage of disease-modifying antirheumatic drugs including methotrexate after week 12 were permitted. Primary endpoints were adverse events, laboratory parameters and vital signs. Secondary efficacy endpoints included American College of Rheumatology (ACR)20/50/70 response rates, Disease Activity Score (DAS)28-4(erythrocyte sedimentation rate (ESR))tofacitinib-treated patients, the incidence rate (patients with events per 100 patient-years) was 10.7 for serious adverse events, 3.3 for serious infections, 7.4 for herpes zoster (serious and non-serious) and 1.2 for malignancies (excluding non-melanoma skin cancer). Mean changes from baseline (start of the index study) in laboratory parameters were consistent with those seen in previously reported studies of tofacitinib. ACR20/50/70 response rates, DAS-defined remission rates and HAQ-DI scores were sustained through to study completion. Tofacitinib (with or without background methotrexate) demonstrated a stable safety profile and sustained efficacy in Japanese patients with active rheumatoid arthritis. The risk of herpes zoster appears to be higher in Japanese patients treated with tofacitinib than in the global population. Clinicaltrials.gov NCT00661661 . Registered 7 February 2008.

Ventilatory function assessment in safety pharmacology: Optimization of rodent studies using normocapnic or hypercapnic conditions

International Nuclear Information System (INIS)

Goineau, Sonia; Rompion, Sonia; Guillaume, Philippe; Picard, Sandra

2010-01-01

Although the whole body plethysmography for unrestrained animals is the most widely used method to assess the respiratory risk of new drugs in safety pharmacology, non-appropriate experimental conditions may mask deleterious side effects of some substances. If stimulant or bronchodilatory effects can be easily evidenced in rodents under standard experimental conditions, i.e. normal air breathing and diurnal phase, drug-induced respiratory depression remains more difficult to detect. This study was aimed at comparing the responsiveness of Wistar rats, Duncan Hartley guinea-pigs or BALB/c mice to the respiratory properties of theophylline (50 or 100 mg/kg p.o.) or morphine (30 mg/kg i.p.) under varying conditions (100% air versus 5% CO 2 -enriched air, light versus dark day phase), in order to select the most appropriate experimental conditions to each species for safety airway investigations. Our results showed that under normocapnia the ventilatory depressant effects of morphine can be easily evidenced in mice, slightly observed in guinea-pigs and not detected in rats in any day phase. Slight hypercapnic conditions enhanced the responsiveness of rats to morphine but not that of guinea-pigs and importantly they did not blunt the airway responsiveness of rats to the stimulation and bronchodilation evoked by theophylline, the most widely used reference agent in safety pharmacology studies. In conclusion, hypercapnic conditions associated with the non-invasive whole body plethysmography should be considered for optimizing the assessment of both the ventilatory depressant potential of morphine-like substances or the respiratory stimulant effects of new drugs in the rat, the most extensively used species in rodent safety and toxicological investigations.

Needs for evidence-based road safety decision making in Europe.

NARCIS (Netherlands)

Dupont, E. Muhlrad, N. Buttler, I. Gitelman, V. Giustiniani, G. Jähi, H. Machata, K. Martensen, H. Papadimitriou, E. Persia, L. Talbot, R. Vallet, G. Wijnen, W. & Yannis, G.

2012-01-01

The objective of this research is the assessment of current needs for evidence-based road safety decision making in Europe, through the consultation of a panel of road safety experts. The members of this Experts Panel have extensive knowledge of road safety management processes and needs in their

On Safety Management. A Frame of Reference for Studies of Safety Management with Examples From Non-Nuclear Contexts of Relevance for Nuclear Safety

International Nuclear Information System (INIS)

Svensson, Ola; Salo, Ilkka; Allwin, Pernilla

2004-11-01

A good knowledge about safety management from risk technologies outside the area of nuclear power may contribute to both broaden the perspectives on safety management in general, and point at new opportunities for improving safety measures within the nuclear industry. First, a theoretical framework for the study of safety management in general is presented, followed by three case studies on safety management from different non-nuclear areas with potential relevance for nuclear safety. The chapters are written as separate reports and can be read independently of each other. The nuclear industry has a long experience about the management of risky activities, involving all the stages from planing to implementation, both on a more generalized level and in the specific branches of activities (management, administration, operation, maintenance, etc.). Here, safety management is a key concept related to these areas of activities. Outside the field of nuclear power there exist a number of different non-nuclear risk technologies, each one with their own specific needs and experiences about safety management. The differences between the areas consist partly of the different experiences caused by the different technologies. Besides using own experiences in safety practices within the own areas of activities, it may be profitable to take advantage in knowledge and experiences from one area and put it in practice in another area. In order to facilitate knowledge transfer from one technological area to another it may be possible to adapt a common theoretical model, for descriptions and explanations, to the different technologies. Such a model should admit that common denominators for safety management across the areas might be identified and described with common concepts. Systems theory gives the opportunity to not only create models that are descriptive for events within the limits of a given technology, but also to generate knowledge that can be transferred to other

Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. General Safety Requirements. Pt. 3 (Chinese Edition)

International Nuclear Information System (INIS)

2014-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Radiation protection and safety of radiation sources: International basic safety standards. General safety requirements. Pt. 3 (French Edition)

International Nuclear Information System (INIS)

2016-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. General Safety Requirements. Pt. 3 (Arabic Edition)

International Nuclear Information System (INIS)

2015-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Safety and Toxicology of Cannabinoids

OpenAIRE

Sachs, Jane; McGlade, Erin; Yurgelun-Todd, Deborah

2015-01-01

There is extensive research on the safety, toxicology, potency, and therapeutic potential of cannabis. However, uncertainty remains facilitating continued debate on medical and recreational cannabis policies at the state and federal levels. This review will include a brief description of cannabinoids and the endocannabinoid system; a summary of the acute and long-term effects of cannabis; and a discussion of the therapeutic potential of cannabis. The conclusions about safety and efficacy will...

Food Safety for Transplant Recipients

Science.gov (United States)

... became ill from food you ate in a restaurant or other food establishment. • The health department staff ... to 4 p.m. Eastern Time. • An extensive selection of timely food safety messages is also available ...

NPP Evaluation, backfitting and life extension. An engineering viewpoint

Energy Technology Data Exchange (ETDEWEB)

Gonzalez Lopez, A [Empresarios Agrupados, A.I.E., Madrid (Spain)

1993-12-15

During the decade of the 80s, the Owners of the two oldest operating plants in Spain designed and built during the 60s - namely, Jose Cabrera NPP, a Westinghouse PWR, and Santa Maria de Garona NPP, a GE BWR- undertook the following important programs: 1. A far-reaching Systematic Evaluation Program (SEP) for the Jose Cabrera NPP consisting in the systematic safety review of the plant design, followed by the necessary hardware modifications, to upgrade it and make it comply with current safety criteria, and a Plant Upgrading Program for the Garona Nuclear Station focusing on specific topics affecting GE BWR Mark-I type plants of the same vintage. 2. A Remaining Life Management Program to ensure that the units, after extensive backfittings and high capital investment, would complete their design life, leaving open the option for plant life extension. These two units are today considered by the Spanish nuclear industry as the pilot plants for Plant Life Extension (PLEX) programs for PWRs and BWRs in our country The purpose of this paper is to summarize the principal lessons learned from EMPRESARIOS AGRUPADOS' participation as an architect-engineering organization in the engineering, design and implementation of these Programs. They are practical examples of positive experience which could be considered as a reference when carrying out similar programs for other plants. (author)

NPP Evaluation, backfitting and life extension. An engineering viewpoint

International Nuclear Information System (INIS)

Gonzalez Lopez, A.

1993-01-01

During the decade of the 80s, the Owners of the two oldest operating plants in Spain designed and built during the 60s - namely, Jose Cabrera NPP, a Westinghouse PWR, and Santa Maria de Garona NPP, a GE BWR- undertook the following important programs: 1. A far-reaching Systematic Evaluation Program (SEP) for the Jose Cabrera NPP consisting in the systematic safety review of the plant design, followed by the necessary hardware modifications, to upgrade it and make it comply with current safety criteria, and a Plant Upgrading Program for the Garona Nuclear Station focusing on specific topics affecting GE BWR Mark-I type plants of the same vintage. 2. A Remaining Life Management Program to ensure that the units, after extensive backfittings and high capital investment, would complete their design life, leaving open the option for plant life extension. These two units are today considered by the Spanish nuclear industry as the pilot plants for Plant Life Extension (PLEX) programs for PWRs and BWRs in our country The purpose of this paper is to summarize the principal lessons learned from EMPRESARIOS AGRUPADOS' participation as an architect-engineering organization in the engineering, design and implementation of these Programs. They are practical examples of positive experience which could be considered as a reference when carrying out similar programs for other plants. (author)

Studying the Safety Impact of Autonomous Vehicles Using Simulation-Based Surrogate Safety Measures

Directory of Open Access Journals (Sweden)

Mark Mario Morando

2018-01-01

Full Text Available Autonomous vehicle (AV technology has advanced rapidly in recent years with some automated features already available in vehicles on the market. AVs are expected to reduce traffic crashes as the majority of crashes are related to driver errors, fatigue, alcohol, or drugs. However, very little research has been conducted to estimate the safety impact of AVs. This paper aims to investigate the safety impacts of AVs using a simulation-based surrogate safety measure approach. To this end, safety impacts are explored through the number of conflicts extracted from the VISSIM traffic microsimulator using the Surrogate Safety Assessment Model (SSAM. Behaviours of human-driven vehicles (HVs and AVs (level 4 automation are modelled within the VISSIM’s car-following model. The safety investigation is conducted for two case studies, that is, a signalised intersection and a roundabout, under various AV penetration rates. Results suggest that AVs improve safety significantly with high penetration rates, even when they travel with shorter headways to improve road capacity and reduce delay. For the signalised intersection, AVs reduce the number of conflicts by 20% to 65% with the AV penetration rates of between 50% and 100% (statistically significant at p<0.05. For the roundabout, the number of conflicts is reduced by 29% to 64% with the 100% AV penetration rate (statistically significant at p<0.05.

Safety of steel vessel Magnox pressure circuits

International Nuclear Information System (INIS)

Stokoe, T.Y.; Bolton, C.J.; Heffer, P.J.H.

1991-01-01

The maintenance of pressure circuit integrity is fundamental to nuclear safety at the steel vessel Magnox stations. To confirm continued pressure circuit integrity the CEGB, as part of the Long Term Safety Review, has carried out extensive assessment and inspection in recent years. The assessment methods and inspection techniques employed are based on the most modern available. Reactor pressure vessel integrity is confirmed by a combination of arguments including safety factors inferred from the successful pre-service overpressure test, leak-before-break analysis and probabilistic assessment. In the case of other parts of the pressure circuits that are more accessible, comprising the boiler shells and interconnecting gas duct work, in-service inspection is a major element of the safety substantiation. The assessment and inspection techniques and the materials property data have been underpinned for many years by extensive research and development programmes and in-reactor monitoring of representative samples has also been undertaken. The paper summarises the work carried out to demonstrate the long term integrity of the Magnox pressure circuits and provides examples of the results obtained. (author)

Contribution of operating feedback to probabilistic safety studies

International Nuclear Information System (INIS)

Guio, J.M. de; Lannoy, A.

1992-03-01

This paper presents the method used for PWR unit operation feedback analysis and its contribution to probabilistic safety studies. The targets were as follows: - use of failure data banks to assess reliability parameters, - use of event data banks to identify and quantify main system initiating events, - determination of a standard operating profile. These studies, performed in the context of nuclear power plant safety programs, prove useful not only to safety engineers but also to equipment experts, designers, operators and maintenance specialists. They constitute basic data for studies in all these areas or the departure point for new investigations. (authors). 3 figs., 3 tabs., 3 refs

Disposal safety

International Nuclear Information System (INIS)

Bartlett, J.W.

International consensus does not seem to be necessary or appropriate for many of the issues concerned with the safety of nuclear waste disposal. International interaction on the technical aspects of disposal has been extensive, and this interaction has contributed greatly to development of a consensus technical infrastructure for disposal. This infrastructure provides a common and firm base for regulatory, political, and social actions in each nation

Extension of HCDA safety analysis to large PCRV containment structures

International Nuclear Information System (INIS)

Marchertas, A.H.; Fistedis, S.H.; Bazant, A.P.; Belytschko, T.

1977-01-01

The introduction of PCRV as part of LMFBR containment also brings in the need for dynamic analysis. The conventional design would not be adequate for designing PCRVs subject to highly transient loading. The PCRV models described provide a valuable illustration of the design arrived at by conventional means and loaded dynamically by means of the transient computer code. In particular the value of the computer code is realized in the case of the loop-type model. The original pressure-volume source used for the illustrative examples corresponds to a total available energy of 2720 MW-s, if the expansion were continued down to one bar. Thus the energy source is considerably larger than the energy releases utilized in the currently prevailing LMFBR safety evaluations. Although the resultant pressure acting on the walls of the PCRV varies with the particular design, the two sample cases indicate that no apparent difficulty is encountered in designing the PCRV to sustain those higher loads. The computer code is established as a valuable tool to study the PCRV response. It serves as a means to locate critical areas of the particular design. Parameter- or sensitivity studies could thus be made with great efficiency. As an example, one interesting and somewhat unexpected result of the illustrations presented is the occurrence of circumferential cracks through the walls of the PCRV

Criticality safety studies at VTT Energy

International Nuclear Information System (INIS)

Roine, T.; Anttila, M.

1995-01-01

At VTT Energy a compact reactor physics calculation system is applied in many kind of problems. Generation of group constants for static and dynamic core calculations, flux and dose rate calculations as well as criticality safety studies are performed basically with the same codes. In the presentation a short overview of the wide variety of criticality safety problems analyzed at VTT Energy is given. The calculation system with some illustrative examples is also described. (12 refs., 1 tab.)

The German nuclear power plant safety study

International Nuclear Information System (INIS)

1979-01-01

With this study a new approach has been chosen, taking nuclear power plants as an example to assess and to describe the risks arising from the use of modern technology, including those hazards emanating from the rather hypothetical possibility of occurrence of very serious accidents. Following the definition of basic concepts and methods to be applied in risk assessment studied, as well as a brief account of the design and operating mode of nuclear power plants with PWRs', accidents and failures to be considered in a safety study are described. Using the course-of-event and fault tree analysis, the probability of fission product release as a consequence of failures in safety systems or of core meltdown is evaluated. Subsequently, the theoretical model for assessment of reactor accident consequences is presented, discussing such aspects as the dispersion of radioactivity in the atmosphere, the radiation dose model, safety and countermeasures, the model for the evaluation of health hazards as well as methods and calculations for estimating the reliability of risk assessments together with the remaining uncertainties. In an appendix to this study, the analyses presented in the study are discussed in the light of the TMI-2 event. This safety study showing the possibilities of detecting, keeping in check and minimizing harmful effects, can be regarded as a contribution to a better understanding of our modern, highly industrialised society, and eventually to an improvement of the quality of life. (GL) 891 GL/GL 892 MB [de

On Safety Management. A Frame of Reference for Studies of Safety Management with Examples From Non-Nuclear Contexts of Relevance for Nuclear Safety

Energy Technology Data Exchange (ETDEWEB)

Svensson, Ola; Salo, Ilkka; Allwin, Pernilla (Risk Analysis, Social and Decision Research Unit, Dept. of Psychology, Stockholm Univ., Stockholm (Sweden))

2004-11-15

A good knowledge about safety management from risk technologies outside the area of nuclear power may contribute to both broaden the perspectives on safety management in general, and point at new opportunities for improving safety measures within the nuclear industry. First, a theoretical framework for the study of safety management in general is presented, followed by three case studies on safety management from different non-nuclear areas with potential relevance for nuclear safety. The chapters are written as separate reports and can be read independently of each other. The nuclear industry has a long experience about the management of risky activities, involving all the stages from planing to implementation, both on a more generalized level and in the specific branches of activities (management, administration, operation, maintenance, etc.). Here, safety management is a key concept related to these areas of activities. Outside the field of nuclear power there exist a number of different non-nuclear risk technologies, each one with their own specific needs and experiences about safety management. The differences between the areas consist partly of the different experiences caused by the different technologies. Besides using own experiences in safety practices within the own areas of activities, it may be profitable to take advantage in knowledge and experiences from one area and put it in practice in another area. In order to facilitate knowledge transfer from one technological area to another it may be possible to adapt a common theoretical model, for descriptions and explanations, to the different technologies. Such a model should admit that common denominators for safety management across the areas might be identified and described with common concepts. Systems theory gives the opportunity to not only create models that are descriptive for events within the limits of a given technology, but also to generate knowledge that can be transferred to other

Operational Safety Performance Indicators and Balanced Scorecard in HANARO

International Nuclear Information System (INIS)

Wu, Jong-Sup; Jung, Hoan-Sung; Ahn, Guk-Hoon; Lee, Kye-Hong; Lim, In-Cheol; Kim, Hark-Rho

2007-01-01

Research reactors need an extensive basis for ensuring their safety. The importance of a safety management in nuclear facilities and activities has been emphasized. The safety activities in HANARO have been continuously conducted to enhance its safe operation. Last year, HANARO prepared two indicator sets to measure and assess the safety status of the reactor's operation and utilization. One is Safety Performance Indicators (SPI) and the other is Balanced Scorecard (BSC). Through reviewing these indicators, we can obtain the following information; - Plant safety status - Safety parameter trends - Safety information, for example, reactor operation status and radiation safety HANARO will continuously pursue the trends of SPI and BSC

Laboratory safety handbook

Science.gov (United States)

Skinner, E.L.; Watterson, C.A.; Chemerys, J.C.

1983-01-01

Safety, defined as 'freedom from danger, risk, or injury,' is difficult to achieve in a laboratory environment. Inherent dangers, associated with water analysis and research laboratories where hazardous samples, materials, and equipment are used, must be minimized to protect workers, buildings, and equipment. Managers, supervisors, analysts, and laboratory support personnel each have specific responsibilities to reduce hazards by maintaining a safe work environment. General rules of conduct and safety practices that involve personal protection, laboratory practices, chemical handling, compressed gases handling, use of equipment, and overall security must be practiced by everyone at all levels. Routine and extensive inspections of all laboratories must be made regularly by qualified people. Personnel should be trained thoroughly and repetitively. Special hazards that may involve exposure to carcinogens, cryogenics, or radiation must be given special attention, and specific rules and operational procedures must be established to deal with them. Safety data, reference materials, and texts must be kept available if prudent safety is to be practiced and accidents prevented or minimized.

Esmeralda project for studying extensive sodium fire

International Nuclear Information System (INIS)

Sophy, Y.M.; Roy, D.; Bentz, A.; Gerosa, A.; Noel, H.

1979-01-01

This paper describes the Esmeralda Project for studying extensive fires involving up to 70 metric tons of sodium. The motivations which prompted the decision to create this research facility are related to construction of the Super-Phenix breeder reactor and to the scale effect problems posed by the use of very large quantities of sodium. Information is included on the dimensions of the installation, the objectives of the project, the means to be employed, the timetable to be followed, and the organization which was created for this project within the context of Franco-Italian cooperation

78 FR 65429 - Pipeline Safety: Request for Special Permit

Science.gov (United States)

2013-10-31

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2010-0041] Pipeline Safety: Request for Special Permit AGENCY: Pipeline and Hazardous Materials...-0041 Williams Gas Pipeline 49 CFR 192.150........ To authorize the extension Company, LLC (WGP). of a...

Preliminary study on improving safety culture in Malaysian nuclear industries

International Nuclear Information System (INIS)

Ibrahim, Sabariah Kader; Lee, Y. E.

2012-01-01

This paper presents preliminary study on safety culture and its implementation in Malaysian nuclear industries by realizing the importance of safety culture; identification of important safety culture attributes; safety culture assessment and the practices to incorporate the identified safety culture attributes in organization. The first section of this paper explains the terms and definitions related to safety culture. Second, for the realization of importance of safety culture in organization, the international operational experiences emphasizing the importance of safety culture are described. Third, important safety culture attributes which are frequently cited in literature are provided. Fourth, methods to assess safety culture in operating organization are described. Finally, the practices to enhance the safety culture in an organization are discussed

Preliminary study on improving safety culture in Malaysian nuclear industries

Energy Technology Data Exchange (ETDEWEB)

Ibrahim, Sabariah Kader [KAIST, Daejeon (Korea, Republic of); Lee, Y. E. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2012-10-15

This paper presents preliminary study on safety culture and its implementation in Malaysian nuclear industries by realizing the importance of safety culture; identification of important safety culture attributes; safety culture assessment and the practices to incorporate the identified safety culture attributes in organization. The first section of this paper explains the terms and definitions related to safety culture. Second, for the realization of importance of safety culture in organization, the international operational experiences emphasizing the importance of safety culture are described. Third, important safety culture attributes which are frequently cited in literature are provided. Fourth, methods to assess safety culture in operating organization are described. Finally, the practices to enhance the safety culture in an organization are discussed.

Application and Assessment of Extension of Time Claim: Findings of Case Studies Conducted in Malaysia

Directory of Open Access Journals (Sweden)

M.S. Mohd Danuri,

2006-12-01

Full Text Available It is a common phenomenon for construction projects to have applications for extension of time. Many problems are encountered in practice in the application and preparation of extension of time claims. A study was conducted to identify the main problems encountered in the application and assessment of extension of time claim in selected construction projects in Malaysia. Three (3 case studies have been used 10 investigate the extension of time issues. Findings from the study revealed that local contractors usually fail to comply with the contract procedural requirements to submit timely notification of delay and have difficulty in demonstrating their entitlement for extension of time. The main problem faced by contract administrators is that contractors tend to "inflate" their extension of time entitlement with the intention to maximise their claims. Adherence to the agreed procedure in preparing and evaluating of delay claims and the implementation of a set of agreed standardised delay analysis may help to minimize the frequency and impact of such problems.

Review of studies on criticality safety evaluation and criticality experiment methods

International Nuclear Information System (INIS)

Naito, Yoshitaka; Yamamoto, Toshihiro; Misawa, Tsuyoshi; Yamane, Yuichi

2013-01-01

Since the early 1960s, many studies on criticality safety evaluation have been conducted in Japan. Computer code systems were developed initially by employing finite difference methods, and more recently by using Monte Carlo methods. Criticality experiments have also been carried out in many laboratories in Japan as well as overseas. By effectively using these study results, the Japanese Criticality Safety Handbook was published in 1988, almost the intermediate point of the last 50 years. An increased interest has been shown in criticality safety studies, and a Working Party on Nuclear Criticality Safety (WPNCS) was set up by the Nuclear Science Committee of Organisation Economic Co-operation and Development in 1997. WPNCS has several task forces in charge of each of the International Criticality Safety Benchmark Evaluation Program (ICSBEP), Subcritical Measurement, Experimental Needs, Burn-up Credit Studies and Minimum Critical Values. Criticality safety studies in Japan have been carried out in cooperation with WPNCS. This paper describes criticality safety study activities in Japan along with the contents of the Japanese Criticality Safety Handbook and the tasks of WPNCS. (author)

Plutonium ocean shipment safety between Europe and Japan

International Nuclear Information System (INIS)

Pierce, J.D.; Hohnstreiter, G.F.; McClure, J.D.; Smith, J.D.; Dukart, R.J.; Koski, J.A.; Braithwate, J.W.; Sorenson, N.R.; Yamamoto, K.; Kitamura, T.; Shibata, K.; Ouchi, Y.; Ito, T.

2004-01-01

Sandia National Laboratories (SNL) and Japan Nuclear Cycle Development Institute (JNC) have conducted an extensive emergency response planning study of the safety of the sea transport of plutonium for JNC. This study was conducted in response to international concerns about the safety of the marine transport of PuO2 powder that began with the sea transport of plutonium powder from France to Japan in 1992 using a purposebuilt ship. This emergency response planning study addressed four topics to better define the accident environment for long-range sea transport of nuclear materials. The first topic is a probabilistic safety analysis that evaluates the technical issues of transporting plutonium between Europe and Japan. An engine-room fire aboard a purposebuilt ship is evaluated as the second topic to determine the vulnerability and safety margin of radioactive material packaging for plutonium designed to meet International Atomic Energy Agency (IAEA) standards. The third topic is a corrosion study performed for generic plutonium packaging to estimate the time required to breach the containment boundary in the event of submersion in seawater. The final study topic is a worldwide survey of information on high-value cargo salvage capabilities from sunken ships. The primary purpose of this overall emergency response planning study is to describe and analyze the safety of radioactive material transportation operations for the international transportation of radioactive materials by maritime cargo vessels

Plutonium ocean shipment safety between Europe and Japan

Energy Technology Data Exchange (ETDEWEB)

Pierce, J D; Hohnstreiter, G F; McClure, J D; Smith, J D; Dukart, R J; Koski, J A; Braithwate, J W; Sorenson, N R [Sandia National Labs., Albuquerque, NM (United States); Yamamoto, K; Kitamura, T; Shibata, K; Ouchi, Y; Ito, T [Japan Nuclear Cycle Development Inst., Tokai-mura (Japan)

2004-07-01

Sandia National Laboratories (SNL) and Japan Nuclear Cycle Development Institute (JNC) have conducted an extensive emergency response planning study of the safety of the sea transport of plutonium for JNC. This study was conducted in response to international concerns about the safety of the marine transport of PuO2 powder that began with the sea transport of plutonium powder from France to Japan in 1992 using a purposebuilt ship. This emergency response planning study addressed four topics to better define the accident environment for long-range sea transport of nuclear materials. The first topic is a probabilistic safety analysis that evaluates the technical issues of transporting plutonium between Europe and Japan. An engine-room fire aboard a purposebuilt ship is evaluated as the second topic to determine the vulnerability and safety margin of radioactive material packaging for plutonium designed to meet International Atomic Energy Agency (IAEA) standards. The third topic is a corrosion study performed for generic plutonium packaging to estimate the time required to breach the containment boundary in the event of submersion in seawater. The final study topic is a worldwide survey of information on high-value cargo salvage capabilities from sunken ships. The primary purpose of this overall emergency response planning study is to describe and analyze the safety of radioactive material transportation operations for the international transportation of radioactive materials by maritime cargo vessels.

On safety management and nuclear safety - A frame of reference for studies of safety management with examples from non-nuclear contects of relevance for nuclear safety

International Nuclear Information System (INIS)

Svenson, O.; Allwin, P.; Salo, I.

2004-03-01

The report includes three case studies of safety management. The studies are presented as chapters, but are written in a format that makes them easy to read separately. Two of the studies cover regulators (the Swedish Civil Aviation Safety Authority, Luftfartsinspektionen) and the Norwegian Petroleum Directorate) and one a regulated activity/industry (a car manufacturer, Volvo Car). The introduction outlines a living system framework and relates this to concepts used in organizational management. The report concludes with some findings with potential relevance for safety management in the nuclear power domain. In the next phase of the work, the regulated counterparts of the regulators here will be investigated in addition to a fourth case study of a regulated activity/industry. (au)

A study of passive safety conditions for fast reactor core

International Nuclear Information System (INIS)

Shimizu, Akinao

1991-01-01

A study has been made for passive safety conditions of fast reactor cores. Objective of the study is to develop a concept of a core with passive safety as well as a simple safety philosophy. A simple safety philosophy, which is wore easy to explain to the public, is needed to enhance the public acceptance for nuclear reactors. The present paper describes a conceptual plan of the study including the definition of the problem a method of approach and identification of tasks to be solved

Study of industry safety management

International Nuclear Information System (INIS)

Park, Pil Su

1987-06-01

This book deals with general remarks, industrial accidents, statistics of industrial accidents, unsafe actions, making machinery and facilities safe, safe activities, having working environment safe, survey of industrial accidents and analysis of causes, system of safety management and operations, safety management planning, safety education, human engineering such as human-machines system, system safety, and costs of disaster losses. It lastly adds individual protective equipment and working clothes including protect equipment for eyes, face, hands, arms and feet.

Nuclear safety guide TID-7016 Revision 2

International Nuclear Information System (INIS)

Thomas, J.T.

1980-01-01

The present revision of TID-7016 Nuclear Safety Guide is discussed. This Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams, experienced in the field. The reader will find a significant change in the character of information presented in this version. Nuclear Criticality Safety has matured in the past twelve years. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available, information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the former Guides by employing appropriate safety factors. In fact, it becomes incumbent on the Criticality Safety Specialist to necessarily impose safety factors consistent with the possible normal and abnormal credible contingencies of an operation as revealed by his evaluation. In its present form the Guide easily becomes a suitable module in any compendium or handbook tailored for internal use by organizations. It is hoped the Guide will continue to serve immediate needs and will encourage continuing and more comprehensive efforts toward organizing nuclear criticality safety information

Safety Culture Enhancement Project. Final Report. A Field Study on Approaches to Enhancement of Safety Culture

Energy Technology Data Exchange (ETDEWEB)

Lowe, Andrew; Hayward, Brent (Dedale Asia Pacific, Albert Park VIC 3206 (Australia))

2006-08-15

This report documents a study with the objective of enhancing safety culture in the Swedish nuclear power industry. A primary objective of this study was to ensure that the latest thinking on human factors principles was being recognised and applied by nuclear power operators as a means of ensuring optimal safety performance. The initial phase of the project was conducted as a pilot study, involving the senior management group at one Swedish nuclear power-producing site. The pilot study enabled the project methodology to be validated after which it was repeated at other Swedish nuclear power industry sites, providing a broad-ranging analysis of opportunities across the industry to enhance safety culture. The introduction to this report contains an overview of safety culture, explains the background to the project and sets out the project rationale and objectives. The methodology used for understanding and analysing the important safety culture issues at each nuclear power site is then described. This section begins with a summary of the processes used in the information gathering and data analysis stage. The six components of the Management Workshops conducted at each site are then described. These workshops used a series of presentations, interactive events and group exercises to: (a) provide feedback to site managers on the safety culture and safety leadership issues identified at their site, and (b) stimulate further safety thinking and provide 'take-away' information and leadership strategies that could be applied to promote safety culture improvements. Section 3, project Findings, contains the main observations and output from the project. These include: - a brief overview of aspects of the local industry operating context that impinge on safety culture; - a summary of strengths or positive attributes observed within the safety culture of the Swedish nuclear industry; - a set of identified opportunities for further improvement; - the aggregated

Progress of nuclear safety research, (1)

International Nuclear Information System (INIS)

Amano, Hiroshi; Nakamura, Hiroei; Nozawa, Masao

1981-01-01

The Japan Atomic Energy Research Institute was established in 1956 in conformity with the national policy to extensively conduct the research associated with nuclear energy. Since then, the research on nuclear energy safety has been conducted. In 1978, the Division of Reactor Safety was organized to conduct the large research programs with large scale test facilities. Thereafter, the Divisions of Reactor Safety Evaluation, Environmental Safety Research and Reactor Fuel Examination were organized successively in the Reactor Safety Research Center. The subjects of research have ranged from the safety of nuclear reactors to that in the recycling of nuclear fuel. In this pamphlet, the activities in JAERI associated with the safety research are reported, which have been carried out in the past two years. Also, the international cooperation research program in which JAERI participated is included. This pamphlet consists of two parts, and in this Part 1, the reactor safety research is described. The safety of nuclear fuel, the integrity and safety of pressure boundary components, the engineered safety in LOCA, fuel behavior in accident and others are reported. (Kako, I.)

Nuclear plant life extension

International Nuclear Information System (INIS)

Negin, C.A.

1989-01-01

The nuclear power industry's addressing of life extension is a natural trend in the maturation of this technology after 20 years of commercial operation. With increasing emphasis on how plants are operated, and less on how to build them, attention is turning on to maximizing the use of these substantial investments. The first studies of life extension were conducted in the period from 1978 and 1982. These were motivated by the initiation, by the Nuclear Regulatory Commission (NRC), of studies to support decommissioning rulemaking. The basic conclusions of those early studies that life extension is feasible and worth pursuing have not been changed by the much more extensive investigations that have since been conducted. From an engineering perspective, life extension for nuclear plants is fundamentally the same as for fossil plants

49 CFR 190.319 - Petitions for extension of time to comment.

Science.gov (United States)

2010-10-01

... the time for petitioner's comments. A petition is granted only if the petitioner shows good cause for... 49 Transportation 3 2010-10-01 2010-10-01 false Petitions for extension of time to comment. 190... AND HAZARDOUS MATERIALS SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION (CONTINUED) PIPELINE...

Probabilistic studies for a safety assurance program

International Nuclear Information System (INIS)

Iyer, S.S.; Davis, J.F.

1985-01-01

The adequate supply of energy is always a matter of concern for any country. Nuclear power has played, and will continue to play an important role in supplying this energy. However, safety in nuclear power production is a fundamental prerequisite in fulfilling this role. This paper outlines a program to ensure safe operation of a nuclear power plant utilizing the Probabilistic Safety Studies

Activities on safety culture study. Study status in public and private sectors

International Nuclear Information System (INIS)

Makino, Maomi; Takano, Kenichi

2004-01-01

Around after entering in the 21st century, organizational accidents had occurred in Japan at various industries including nuclear industry, which were caused directly by unsafe action, human error and illegal conduct of personnel but there were problems in safety culture of organization such as slow retreat of safety system stimulated by management, schedule control and procedure management becoming a dead letter, lack of safety education, and workplace climate of schedule priority. This article referred to organizational factors common to many severe accidents and introduced safety culture study in public and private sectors to overcome those factors. Safety Culture Evaluation Support Tool (SCEST) was developed for self-evaluation of safety culture of organization as well as Organizational Reliability model (OR model) for analysis of initiation and propagation process of risk event. Safety diagnosis system and feedback type risk assessment system for promoting safe organizational climate and culture were also developed. (T. Tanaka)

A PIP chart for nuclear plant safety

International Nuclear Information System (INIS)

Suzuki, Tatsujiro; Yamaoka, Taiji

1992-01-01

While it is known that social and political aspects of nuclear safety issues are important, little study has been done on identifying the breadth of stakeholders whose policies have important influences over nuclear plant safety in a comprehensive way. The objectives of this study are to develop a chart that visually identifies important stakeholders and their policies and illustrates these influences in a hierarchical representation so that the relationship between stakeholders and nuclear safety will be better understood. This study is based on a series of extensive interviews with major stakeholders, such as nuclear plant managers, corporate planning vice presidents, state regulators, news media, and public interest groups, and focuses on one US nuclear power plant. Based on the interview results, the authors developed a conceptual policy influence paths (PIP) chart. The PIP chart illustrates the hierarchy of influence among stakeholders. The PIP chart is also useful in identifying possible stakeholders who can be easily overlooked without the PIP chart. In addition, it shows that influence flow is circular rather than linear in one direction

Food Safety for People with Cancer

Science.gov (United States)

... became ill from food you ate in a restaurant or other food establishment. The health department staff ... to 4 p.m. Eastern Time. An extensive selection of timely food safety messages is also available ...

Irradiation of prepared meals for microbiological safety and shelf-life extension

Energy Technology Data Exchange (ETDEWEB)

Nketsia-Tabiri, J; Adu-Gyamfi, A; Owusu-Biney, Alex; Apea Bah, F; Akomeah-Adjei, F [Biotechnology and Nuclear Agriculture Research Institute, Ghana Atomic Energy Commission, Legon (Ghana)

2004-07-01

Current trends suggest increasing world-wide demand for convenience foods such as prepared meals and those that require minimum preparation before consumption. In Ghana, the trend is the same with ready-to-eat or prepared meals mostly sold in the informal sector, playing a major role in meeting the nutritional needs of the people these meals are prepared on daily basis as in most developing countries. With increasing urbanization and rapid adoption of refrigeration for food preservation in developing countries, the demand for such foods in supermarkets should be expected. Over 90% of ready-to-eat meals prepared in Ghana are marketed under ambient conditions and have shelf-life of less than 12 hours. However, there are a few caterers who prepare cook-chill meals using hygienic and preventative approach (e.g. HACCP) in order to enhance the safety of their meals. Preliminary investigations have demonstrated that these cook-chill meals are potential sources of pathogenic bacteria and have been implicated in food-borne disease outbreaks. There is therefore the need to ensure the safety of ready-to-eat meals through effective processing such as irradiation.

IAEA programme on research reactor safety

International Nuclear Information System (INIS)

Alcala, F.; Di Meglio, A.F.

1995-01-01

This paper describes the IAEA programme on research reactor safety and includes the safety related areas of conversions to the use of low enriched uranium (LEU) fuel. The program is based on the IAEA statutory responsibilities as they apply to the requirements of over 320 research reactors operating around the world. The programme covers four major areas: (a) the development of safety documents; (b) safety missions to research reactor facilities; (c) support of research programmes on research reactor safety; (d) support of Technical Cooperation projects on research reactor safety issues. The demand for these activities by the IAEA member states has increased substantially in recent years especially in developing countries with increasing emphasis being placed on LEU conversion matters. In response to this demand, the IAEA has undertaken an extensive programme for each of the four areas above. (author)

Safety Culture Enhancement Project. Final Report. A Field Study on Approaches to Enhancement of Safety Culture

International Nuclear Information System (INIS)

Lowe, Andrew; Hayward, Brent

2006-08-01

This report documents a study with the objective of enhancing safety culture in the Swedish nuclear power industry. A primary objective of this study was to ensure that the latest thinking on human factors principles was being recognised and applied by nuclear power operators as a means of ensuring optimal safety performance. The initial phase of the project was conducted as a pilot study, involving the senior management group at one Swedish nuclear power-producing site. The pilot study enabled the project methodology to be validated after which it was repeated at other Swedish nuclear power industry sites, providing a broad-ranging analysis of opportunities across the industry to enhance safety culture. The introduction to this report contains an overview of safety culture, explains the background to the project and sets out the project rationale and objectives. The methodology used for understanding and analysing the important safety culture issues at each nuclear power site is then described. This section begins with a summary of the processes used in the information gathering and data analysis stage. The six components of the Management Workshops conducted at each site are then described. These workshops used a series of presentations, interactive events and group exercises to: (a) provide feedback to site managers on the safety culture and safety leadership issues identified at their site, and (b) stimulate further safety thinking and provide 'take-away' information and leadership strategies that could be applied to promote safety culture improvements. Section 3, project Findings, contains the main observations and output from the project. These include: - a brief overview of aspects of the local industry operating context that impinge on safety culture; - a summary of strengths or positive attributes observed within the safety culture of the Swedish nuclear industry; - a set of identified opportunities for further improvement; - the aggregated results of the

SRP reactor safety evolution

International Nuclear Information System (INIS)

Rankin, D.B.

1984-01-01

The Savannah River Plant reactors have operated for over 100 reactor years without an incident of significant consequence to on or off-site personnel. The reactor safety posture incorporates a conservative, failure-tolerant design; extensive administrative controls carried out through detailed operating and emergency written procedures; and multiple engineered safety systems backed by comprehensive safety analyses, adapting through the years as operating experience, changes in reactor operational modes, equipment modernization, and experience in the nuclear power industry suggested. Independent technical reviews and audits as well as a strong organizational structure also contribute to the defense-in-depth safety posture. A complete review of safety history would discuss all of the above contributors and the interplay of roles. This report, however, is limited to evolution of the engineered safety features and some of the supporting analyses. The discussion of safety history is divided into finite periods of operating history for preservation of historical perspective and ease of understanding by the reader. Programs in progress are also included. The accident at Three Mile Island was assessed for its safety implications to SRP operation. Resulting recommendations and their current status are discussed separately at the end of the report. 16 refs., 3 figs

Nanotechnology Safety Self-Study

Energy Technology Data Exchange (ETDEWEB)

Grogin, Phillip W. [Los Alamos National Laboratory

2016-03-29

Nanoparticles are near-atomic scale structures between 1 and 100 nanometers (one billionth of a meter). Engineered nanoparticles are intentionally created and are used in research and development at Sandia National Laboratories (SNL) and Los Alamos National Laboratory (LANL). This course, Nanotechnology Safety Self-Study, presents an overview of the hazards, controls, and uncertainties associated with the use of unbound engineered nanoscale particles (UNP) in a laboratory environment.

Food Safety Posters for Safe Handling of Leafy Greens

Science.gov (United States)

Rajagopal, Lakshman; Arendt, Susan W.; Shaw, Angela M.; Strohbehn, Catherine H.; Sauer, Kevin L.

2016-01-01

This article describes food safety educational tools depicting safe handling of leafy greens that are available as downloadable posters to Extension educators and practitioners (www.extension.iastate.edu). Nine visual-based minimal-text colored posters in English, Chinese, and Spanish were developed for use when formally or informally educating…

Nuclear safety guide: TID--7016, Revision 2

International Nuclear Information System (INIS)

Thomas, J.T.

1978-01-01

The Nuclear Safety Guide was first issued in 1956 as classified AEC report LA-2063 and was reprinted the next year, unclassified, as TID-7016. Revision 1, published in 1961, extended the scope and refined the guiding information. Revision 2 of the Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams experienced in the field. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the former Guides by employing appropriate safety factors

Study of Scenarios Related to Design Extension Conditions of PHWR Using PSA Methodology

Energy Technology Data Exchange (ETDEWEB)

Kim, H. Y.; Yi, S. D.; Kim, S. R. [NESS, Daejeon (Korea, Republic of)

2016-05-15

Studies to establish the event classification framework and acceptance criteria for an event that exceeds the existing DBAs in order to enhance the safety operation of nuclear power plants in accordance with the domestic nuclear safety laws amended recently have been doing briskly in the country. In this perspective, a study of DECs for domestic PWRs has already begun, and accordingly, studies to cope with BDBAs including DECs for domestic CANDU plants also are required. In this paper, a postulated event which might be included into DECs for domestic CANDU is analyzed by CATHENA code, and Probabilistic Safety Assessment(PSA) data needed for selecting events for DECs are drawn. In this paper, based on the assumption that all the heat sinks and power are not available, countermeasure capability against loss of safety functions such as power supply system in domestic CANDU are assessed. The results and available power and heat sink source which are the required coping facilities for mitigating the accident are presented and the available limited time also are assessed. Provided that ways of long-term core cooling are secured later, it is expected that the safety functions of a plant can be secured even in the extremely severe natural disasters.

78 FR 64504 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2013-10-29

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety and Health (NIOSH or..., Number 177, Pages 56235-56236. Contact Person for More Information: Price Connor, Ph.D., NIOSH Health...

Nuclear Safety Bureau: safety objectives and principles for the proposed ANSTO reactor

International Nuclear Information System (INIS)

Westall, D.

1993-01-01

Siting criteria and safety assessment principles were previously promulgated by the Australian Atomic Energy Commission (AAEC), and have been applied by ANSTO and the Nuclear Safety Bureau (NSB). The NSB is revising these criteria and principles to take account of evolving nuclear safety standards and practices. The NSB Safety and Siting Assessment Principles (SSAP) are presented and it is estimated that it will provide a comprehensive basis for the safety assessment of research reactors in Australia, and be applicable to all stages of a reactor project: siting: design and construction; operation; modification; and decommissioning. The SSAP are similar to the principles promulgated by the AAEC, in that probabilistic safety criteria are set for assessment of design, however these criteria are complimentary to a deterministic design basis approach. This is a similar approach to that recently published by the UK Nuclear Installations Inspectorate 4 . Siting principles are now also included, where they were previously separate, and require a consideration of the consequences of severe accidents which are an extension of accidents catered for by the design of the plant. Criteria for radiation doses due to normal operations and design basis accidents are included in the principles for safety assessment. 9 refs

Canadian Consumer Food Safety Practices and Knowledge: Foodbook Study.

Science.gov (United States)

Murray, Regan; Glass-Kaastra, Shiona; Gardhouse, Christine; Marshall, Barbara; Ciampa, Nadia; Franklin, Kristyn; Hurst, Matt; Thomas, M Kate; Nesbitt, Andrea

2017-10-01

Understanding consumers' food safety practices and knowledge supports food safety education for the prevention of foodborne illness. The objective of this study was to describe Canadian consumer food safety practices and knowledge. This study identifies demographic groups for targeted food safety education messaging and establishes a baseline measurement to assess the effectiveness of food safety interventions over time. Questions regarding consumer food safety practices and knowledge were included in a population-based telephone survey, Foodbook, conducted from November 2014 to March 2015. The results were analyzed nationally by age group and by gender. The results showed that approximately 90% of Canadians reported taking the recommended cleaning and separating precautions when handling raw meat to prevent foodborne illness. Only 29% of respondents reported using a food thermometer when cooking any meat, and even fewer (12%) reported using a food thermometer for small cuts of meat such as chicken pieces. The majority (>80%) of Canadians were aware of the foodborne illness risks related to chicken and hamburger, but fewer (poultry.

Extension of operation of nuclear plants. Synthesis of the qualitative study and of the citizen committee

International Nuclear Information System (INIS)

Suteau, Regis

2014-01-01

The author comments the results of a survey which was based on 20 interviews with French citizens of different ages, political opinions, geographical locations and also different opinions on nuclear energy. The objective was to obtain their perception and feeling about the issue of nuclear plant service life extension, in order to assess whether they were aware of this issue, could understand it, and what was their opinion about it. Then, these citizens have been gathered three weeks later and met three experts (a representative of a NGO, a member of the ASN and a representative of EDF) who answered their questions and discussed their arguments. These citizens then made statements and recommendations. It appeared that the issue of lifetime extension is hardly known by the public, and is therefore not a topic of public debate but a modality within the important debate about nuclear energy. However, the citizen committee accepts this lifetime extension for different reasons (no known alternatives; economic aspects; safety, nuclear energy is non polluting energy; jobs will be saved) but under some conditions which depend on the opinion on nuclear energy (rather for or rather against). The opinion may change negatively in relationship with some issues: the future of radioactive wastes and dismantled installations, quality and traceability of subcontracted components. This survey is an opportunity to question the general relationship of French people with nuclear energy. In this respect, five profiles are identified: confident, resigned, realistic and reasonable, realistic and anxious, and opponent

Food Safety for People with Diabetes

Science.gov (United States)

... became ill from food you ate in a restaurant or other food establishment. • The health department staff ... to 4 p.m. Eastern Time. • An extensive selection of timely food safety messages is also available ...

Flammable Gas Safety Self-Study 52827

Energy Technology Data Exchange (ETDEWEB)

Glass, George [Los Alamos National Laboratory

2016-03-17

This course, Flammable Gas Safety Self-Study (COURSE 52827), presents an overview of the hazards and controls associated with commonly used, compressed flammable gases at Los Alamos National Laboratory (LANL).

Modeling the Relationship between Safety Climate and Safety Performance in a Developing Construction Industry: A Cross-Cultural Validation Study.

Science.gov (United States)

Zahoor, Hafiz; Chan, Albert P C; Utama, Wahyudi P; Gao, Ran; Zafar, Irfan

2017-03-28

This study attempts to validate a safety performance (SP) measurement model in the cross-cultural setting of a developing country. In addition, it highlights the variations in investigating the relationship between safety climate (SC) factors and SP indicators. The data were collected from forty under-construction multi-storey building projects in Pakistan. Based on the results of exploratory factor analysis, a SP measurement model was hypothesized. It was tested and validated by conducting confirmatory factor analysis on calibration and validation sub-samples respectively. The study confirmed the significant positive impact of SC on safety compliance and safety participation , and negative impact on number of self-reported accidents/injuries . However, number of near-misses could not be retained in the final SP model because it attained a lower standardized path coefficient value. Moreover, instead of safety participation , safety compliance established a stronger impact on SP. The study uncovered safety enforcement and promotion as a novel SC factor, whereas safety rules and work practices was identified as the most neglected factor. The study contributed to the body of knowledge by unveiling the deviations in existing dimensions of SC and SP. The refined model is expected to concisely measure the SP in the Pakistani construction industry, however, caution must be exercised while generalizing the study results to other developing countries.

Neonatal pearls : safety and efficacy of medication use in fetus and neonate

NARCIS (Netherlands)

Lugt, Neeltje Margaretha van der

2013-01-01

Neonatal health care is provided with medication and protocols for almost all morbidities. Before the use of these medicines is allowed, they are extensively studied and tested for efficacy and safety. As patient population and knowledge on specific diseases changes with time, repeated evaluation

Studies of vehicle lane-changing dynamics and its effect on traffic efficiency, safety and environmental impact

Science.gov (United States)

Li, Xiang; Sun, Jian-Qiao

2017-02-01

Drivers often change lanes on the road to maintain desired speed and to avoid slow vehicles, pedestrians, obstacles and lane closure. Understanding the effect of lane-changing on the traffic is an important topic in designing optimal traffic control systems. This paper presents a comprehensive study of this topic. We review the theory of microscopic dynamic car-following models and the lane-changing models, propose additional lane-changing rules to deal with moving bottleneck and lane reduction, and investigate the effects of lane-changing on the traffic efficiency, traffic safety and fuel consumption as a function of different variables including the distance of the emergency sign ahead of the lane closure, speed limit, traffic density, etc. Extensive simulations of the traffic system have been carried out in different scenarios. A number of important findings of the effect of various factors on the traffic are reported. These findings provide guidance on the traffic management and are important to the designers and engineers of modern highway or inner city roads to achieve high traffic efficiency and safety with minimum environmental impact.

Carbapenems to Treat Multidrug and Extensively Drug-Resistant Tuberculosis: A Systematic Review.

Science.gov (United States)

Sotgiu, Giovanni; D'Ambrosio, Lia; Centis, Rosella; Tiberi, Simon; Esposito, Susanna; Dore, Simone; Spanevello, Antonio; Migliori, Giovanni Battista

2016-03-12

Carbapenems (ertapenem, imipenem, meropenem) are used to treat multidrug-resistant (MDR-) and extensively drug-resistant tuberculosis (XDR-TB), even if the published evidence is limited, particularly when it is otherwise difficult to identify the recommended four active drugs to be included in the regimen. No systematic review to date has ever evaluated the efficacy, safety, and tolerability of carbapenems. A search of peer-reviewed, scientific evidence was carried out, aimed at evaluating the efficacy/effectiveness, safety, and tolerability of carbapenem-containing regimens in individuals with pulmonary/extra-pulmonary disease which was bacteriologically confirmed as M/XDR-TB. We used PubMed to identify relevant full-text, English manuscripts up to the 20 December 2015, excluding editorials and reviews. Seven out of 160 studies satisfied the inclusion criteria: two on ertapenem, one on imipenem, and four on meropenem, all published between 2005 and 2016. Of seven studies, six were retrospective, four were performed in a single center, two enrolled children, two had a control group, and six reported a proportion of XDR-TB cases higher than 20%. Treatment success was higher than 57% in five studies with culture conversion rates between 60% and 94.8%. The safety and tolerability is very good, with the proportion of adverse events attributable to carbapenems below 15%.

ENTREPRENEURSHIP ECONOMIC SAFETY AND DEVELOPMENT OF SECURITY SERVICES

Directory of Open Access Journals (Sweden)

G. V. Goudkov

2011-01-01

Full Text Available Successful functioning of the industry that provides for safety of organizations and physical entities exercises strategic impacts on development of society and economics of any state including Russia. Economic safety of Russia is directly linked with economic and information safety of itsbusiness structures. Extension of the scope and use of services offered by experienced state and private security enterprises including licensed individuals is one of most important directions of business safety perfection. Further improvement of Russian legislation on non-governmentalsecurity structures and coordination of their activities with those of state law enforcement bodies is obligatory condition of attaining higherpublic and economic safety levels.

Safety and efficacy of gadoteric acid in pediatric magnetic resonance imaging: overview of clinical trials and post-marketing studies

Energy Technology Data Exchange (ETDEWEB)

Balassy, Csilla [Medical University of Vienna, Vienna General Hospital, Department of Radiology, Division of General and Pediatric Radiology, Vienna (Austria); Roberts, Donna [Medical University of South Carolina, Department of Radiology, Charleston, SC (United States); Miller, Stephen F. [LeBonheur Children' s Hospital, Department of Radiology, Memphis, TN (United States)

2015-11-15

Gadoteric acid is a paramagnetic gadolinium macrocyclic contrast agent approved for use in MRI of cerebral and spinal lesions and for body imaging. To investigate the safety and efficacy of gadoteric acid in children by extensively reviewing clinical and post-marketing observational studies. Data were collected from 3,810 children (ages 3 days to 17 years) investigated in seven clinical trials of central nervous system (CNS) imaging (n = 141) and six post-marketing observational studies of CNS, musculoskeletal and whole-body MR imaging (n = 3,669). Of these, 3,569 children were 2-17 years of age and 241 were younger than 2 years. Gadoteric acid was generally administered at a dose of 0.1 mmol/kg. We evaluated image quality, lesion detection and border delineation, and the safety of gadoteric acid. We also reviewed post-marketing pharmacovigilance experience. Consistent with findings in adults, gadoteric acid was effective in children for improving image quality compared with T1-W unenhanced sequences, providing diagnostic improvement, and often influencing the therapeutic approach, resulting in treatment modifications. In studies assessing neurological tumors, gadoteric acid improved border delineation, internal morphology and contrast enhancement compared to unenhanced MR imaging. Gadoteric acid has a well-established safety profile. Among all studies, a total of 10 children experienced 20 adverse events, 7 of which were thought to be related to gadoteric acid. No serious adverse events were reported in any study. Post-marketing pharmacovigilance experience did not find any specific safety concern. Gadoteric acid was associated with improved lesion detection and delineation and is an effective and well-tolerated contrast agent for use in children. (orig.)

Safety and efficacy of gadoteric acid in pediatric magnetic resonance imaging: overview of clinical trials and post-marketing studies.

Science.gov (United States)

Balassy, Csilla; Roberts, Donna; Miller, Stephen F

2015-11-01

Gadoteric acid is a paramagnetic gadolinium macrocyclic contrast agent approved for use in MRI of cerebral and spinal lesions and for body imaging. To investigate the safety and efficacy of gadoteric acid in children by extensively reviewing clinical and post-marketing observational studies. Data were collected from 3,810 children (ages 3 days to 17 years) investigated in seven clinical trials of central nervous system (CNS) imaging (n = 141) and six post-marketing observational studies of CNS, musculoskeletal and whole-body MR imaging (n = 3,669). Of these, 3,569 children were 2-17 years of age and 241 were younger than 2 years. Gadoteric acid was generally administered at a dose of 0.1 mmol/kg. We evaluated image quality, lesion detection and border delineation, and the safety of gadoteric acid. We also reviewed post-marketing pharmacovigilance experience. Consistent with findings in adults, gadoteric acid was effective in children for improving image quality compared with T1-W unenhanced sequences, providing diagnostic improvement, and often influencing the therapeutic approach, resulting in treatment modifications. In studies assessing neurological tumors, gadoteric acid improved border delineation, internal morphology and contrast enhancement compared to unenhanced MR imaging. Gadoteric acid has a well-established safety profile. Among all studies, a total of 10 children experienced 20 adverse events, 7 of which were thought to be related to gadoteric acid. No serious adverse events were reported in any study. Post-marketing pharmacovigilance experience did not find any specific safety concern. Gadoteric acid was associated with improved lesion detection and delineation and is an effective and well-tolerated contrast agent for use in children.

Safety and efficacy of gadoteric acid in pediatric magnetic resonance imaging: overview of clinical trials and post-marketing studies

International Nuclear Information System (INIS)

Balassy, Csilla; Roberts, Donna; Miller, Stephen F.

2015-01-01

Gadoteric acid is a paramagnetic gadolinium macrocyclic contrast agent approved for use in MRI of cerebral and spinal lesions and for body imaging. To investigate the safety and efficacy of gadoteric acid in children by extensively reviewing clinical and post-marketing observational studies. Data were collected from 3,810 children (ages 3 days to 17 years) investigated in seven clinical trials of central nervous system (CNS) imaging (n = 141) and six post-marketing observational studies of CNS, musculoskeletal and whole-body MR imaging (n = 3,669). Of these, 3,569 children were 2-17 years of age and 241 were younger than 2 years. Gadoteric acid was generally administered at a dose of 0.1 mmol/kg. We evaluated image quality, lesion detection and border delineation, and the safety of gadoteric acid. We also reviewed post-marketing pharmacovigilance experience. Consistent with findings in adults, gadoteric acid was effective in children for improving image quality compared with T1-W unenhanced sequences, providing diagnostic improvement, and often influencing the therapeutic approach, resulting in treatment modifications. In studies assessing neurological tumors, gadoteric acid improved border delineation, internal morphology and contrast enhancement compared to unenhanced MR imaging. Gadoteric acid has a well-established safety profile. Among all studies, a total of 10 children experienced 20 adverse events, 7 of which were thought to be related to gadoteric acid. No serious adverse events were reported in any study. Post-marketing pharmacovigilance experience did not find any specific safety concern. Gadoteric acid was associated with improved lesion detection and delineation and is an effective and well-tolerated contrast agent for use in children. (orig.)

Nuclear safety review requirements for launch approval

International Nuclear Information System (INIS)

Sholtis, J.A. Jr.; Winchester, R.O.

1992-01-01

Use of nuclear power systems in space requires approval which is preceded by extensive safety analysis and review. This careful study allows an informed risk-benefit decision at the highest level of our government. This paper describes the process as it has historically been applied to U.S. isotopic power systems. The Ulysses mission, launched in October 1990, is used to illustrate the process. Expected variations to deal with reactor-power systems are explained

Safety considerations of PWR's

International Nuclear Information System (INIS)

Arnold, W.H. Jr.

1977-01-01

The safety of the central station pressurized water reactor is well established and substantiated by its excellent operating record. Operating data from 55 reactors of this type have established a record of safe operating history unparalleled by any modern large scale industry. The 186 plants under construction require a continuing commitment to maintain this outstanding record. The safety of the PWR has been further verified by the recently completed Reactor Safety Study (''Rasmussen'' Report). Not only has this study confirmed the exceptionally low risk associated with PWR operation, it has also introduced a valuable new tool in the decision making process. PWR designs, utilizing the philosophy of defense in depth, provide the bases for evaluating margins of safety. The design of the reactor coolant system, the containment system, emergency core cooling system and other related systems and components provide substantial margins of safety under both normal and postulated accident conditions even considering simultaneous effects of earthquakes and other environmental phenomena. Margins of safety in the assessment of various postulated accident conditions, with emphasis on the postulated loss of reactor coolant accident (LOCA), have been evaluated in depth as exemplified by the comprehensive ECCS rulemaking hearings followed by imposition of very conservative Nuclear Regulatory Commission requirements. When evaluated on an engineering best estimate approach, the significant margins to safety for a LOCA become more apparent. Extensive test programs have also substantiated margins to safety limits. These programs have included both separate effects and systems tests. Component testing has also been performed to substantiate performance levels under adverse combinations of environmental stress. The importance of utilizing past experience and of optimizing the deployment of incremental resources is self evident. Recent safety concerns have included specific areas such

Case study: the Argentina Road Safety Project: lessons learned for the decade of action for road safety, 2011-2020.

Science.gov (United States)

Raffo, Veronica; Bliss, Tony; Shotten, Marc; Sleet, David; Blanchard, Claire

2013-12-01

This case study of the Argentina Road Safety Project demonstrates how the application of World Bank road safety project guidelines focused on institution building can accelerate knowledge transfer, scale up investment and improve the focus on results. The case study highlights road safety as a development priority and outlines World Bank initiatives addressing the implementation of the World Report on Road Traffic Injury's recommendations and the subsequent launch of the Decade of Action for Road Safety, from 2011-2020. The case study emphasizes the vital role played by the lead agency in ensuring sustainable road safety improvements and promoting the shift to a 'Safe System' approach, which necessitated the strengthening of all elements of the road safety management system. It summarizes road safety performance and institutional initiatives in Argentina leading up to the preparation and implementation of the project. We describe the project's development objectives, financing arrangements, specific components and investment staging. Finally, we discuss its innovative features and lessons learned, and present a set of supplementary guidelines, both to assist multilateral development banks and their clients with future road safety initiatives, and to encourage better linkages between the health and transportation sectors supporting them.

Safety analysis and related studies

International Nuclear Information System (INIS)

Lelievre, J.

1979-12-01

Several examples of reactor safety studies are given. For light water reactors, the consequences of loss of coolant, the disposition of the fuel elements and the behaviour under irradiation of the steels used for containment are described. For fast reactors, the disposition of fuel elements in the case of cooling accidents and sodium fies are described. Examples given of studies not specific to a particular reactor type include studies of non-destructive testing and those of reliability

Utilization pattern of extension tools and methods by Agricultural Extension Agents

Directory of Open Access Journals (Sweden)

M Surudhi

2018-05-01

Full Text Available A study was conducted in Krishnagiri district of Tamil Nadu state to understand the utilization pattern of extension tools and methods by the agricultural extension agents. As ICT revolution is slowly conquering the rural sector, it becomes imperative that the agricultural extension agents transform themselves to the changing times and develop competencies in utilizing these ICTs.  The study explored the usage of various extension tools and methods by the change agents and the constraints faced in utilizing them. The findings revealed that the extension functionaries frequently used the individual contact methods viz., telephone, office calls and farm and home visits in the process of transfer of technology. Least efforts were shown in sending SMS based communication. Meetings were the common and frequently adopted group contact method. Demonstrations, farmer field school, farmer’s interest groups, field trips and farmer training programmes were moderately adopted. Posters, leaflets and pre-season campaigns were the widely adopted mass contact methods. They possess least skill in utilizing farm magazines, presenting television and radio programmes, which are among the most popular and most efficient mass contact methods. The extension functionaries need to be trained adequately on the wider use of electronic communication methods like e mails, and SMS in the local language. Efforts should be taken up to sensitize the importance and train the extension agents in the usage of different group and mass contact methods.

The advanced neutron source facility: Safety philosophy and studies

International Nuclear Information System (INIS)

Greene, S.R.; Harrington, R.M.

1988-01-01

The Advanced Neutron Source (ANS) is currently the only new civilian nuclear reactor facility proposed for construction in the United States. Even though the thermal power of this research-oriented reactor is a relatively low 300 MW, the design will undoubtedly receive intense scrutiny before construction is allowed to proceed. Safety studies are already under way to ensure that the maximum degree of safety in incorporated into the design and that the design is acceptable to the Department of Energy (DOE) and can meet the Nuclear Regulatory Commission regulations. This document discusses these safety studies

Patient safety: Safety culture and patient safety ethics

DEFF Research Database (Denmark)

Madsen, Marlene Dyrløv

2006-01-01

,demonstrating significant, consistent and sometimes large differences in terms of safety culture factors across the units participating in the survey. Paper 5 is the results of a study of the relation between safety culture, occupational health andpatient safety using a safety culture questionnaire survey......Patient safety - the prevention of medical error and adverse events - and the initiative of developing safety cultures to assure patients from harm have become one of the central concerns in quality improvement in healthcare both nationally andinternationally. This subject raises numerous...... challenging issues of systemic, organisational, cultural and ethical relevance, which this dissertation seeks to address through the application of different disciplinary approaches. The main focus of researchis safety culture; through empirical and theoretical studies to comprehend the phenomenon, address...

Concrete component aging and its significance relative to life extension of nuclear power plants

International Nuclear Information System (INIS)

Naus, D.J.

1986-09-01

The objectives of this study are to (1) expand upon the work that was initiated in the first two Electric Power Research Institute studies relative to longevity and life extension considerations of safety-related concrete components in light-water reactor (LWR) facilities and (2) provide background that will logically lead to subsequent development of a methodology for assessing and predicting the effects of aging on the performance of concrete-based materials and components. These objectives are consistent with Nuclear Plant Aging Research (NPAR) Program goals: (1) to identify and characterize aging and service wear effects that, if unchecked, could cause degradation of structures, components, and systems and, thereby, impair plant safety; (2) to identify methods of inspection, surveillance, and monitoring or of evaluating residual life of structures, components, and systems that will ensure timely detection of significant aging effects before loss of safety function; and (3) to evaluate the effectiveness of storage, maintenance, repair, and replacement practices in mitigating the rate and extent of degradation caused by aging and service wear

An approach to review design bases and safety analysis of earlier generation atomic power plants; a case study of TAPS

International Nuclear Information System (INIS)

Malhotra, P.K.; Bajaj, S.S.

2002-01-01

The twin unit boiling water reactor (BWR) station at TAPS has completed 30 years of power operation and for further extending plant operating life, a fresh extensive exercise involving review of plant operating performance, aging management and review of design bases and safety analysis has been carried out. The review exercise resulted in assessment of acceptability of identified non-conformances and recommendation for compensatory measures in the form of design modification or plant operating procedures. The second part of the exercise is related to safety analysis, which is carried out in view of the plant modifications done and advances taken place in methodologies of analytical techniques. Chiefly, it involves LOCA analysis done for various break sizes at different locations and plant transient studies. It also includes the fatigue analysis of the reactor pressure vessel. The related review approach adopted is presented here

Preliminary Study on the Revision of Nuclear Safety Policy Statement

International Nuclear Information System (INIS)

Lee, Y. E.; Lee, S. H.; Chang, H. S.; Choi, K. S.; Jung, S. J.

2011-01-01

Nuclear safety policy in Korea is currently declared in the Nuclear Safety Charter as the highest tier document and safety principles and directions are announced in the Nuclear Safety Policy Statement. As the circumstances affecting on the nuclear safety policy change, it needs to revise the Statement. This study aims to develop the revised Nuclear Safety Policy Statement to declare that securing safety is a prerequisite to the utilization of nuclear energy, and that all workers in nuclear industry and regulatory body must adhere to the principle of priority to safety. As a result, two different types of revision are being prepared as of August. One is based on the spirit of Nuclear Safety Charter as well as the direction of future-oriented safety policies including the changes in the environment after declaration of the Statement. The other is to declare the fundamental safety objective and safety principles as the top philosophy of national nuclear safety policy by adopting the '10 Safety Principles in IAEA Safety Fundamental' instead of the current Charter. Both versions of revision are subject to further in-depth discussion. However once the revision is finalized and declared, it would be useful to accomplish effectively the organizational responsibilities and to enhance the public confidence in nuclear safety by performing the regulatory activities in a planned and systematic manner and promulgating the government's dedication to priority to safety

Progress in the development of methodology for fusion safety systems studies

International Nuclear Information System (INIS)

Ho, S.K.; Cambi, G.; Ciattaglia, S.; Fujii-e, Y.; Seki, Y.

1994-01-01

The development of fusion safety systems-study methodology, including the aspects of schematic classification of overall fusion safety system, qualitative assessment of fusion system for identification of critical accident scenarios, quantitative analysis of accident consequences and risk for safety design evaluation, and system-level analysis of accident consequences and risk for design optimization, by a consortium of international efforts is presented. The potential application of this methodology into reactor design studies will facilitate the systematic assessment of safety performance of reactor designs and enhance the impacts of safety considerations on the selection of design configurations

Project safety studies - nuclear waste management (PSE)

International Nuclear Information System (INIS)

1981-10-01

The project 'Safety Studies-Nuclear Waste Management' (PSE) is a research project performed by order of the Federal Minister for Research and Technology, the general purpose of which is to deepen and ensure the understanding of the safety aspects of the nuclear waste management and to prepare a risk analysis which will have to be established in the future. Owing to this the project is part of a series of projects which serve the further development of the concept of nuclear waste management and its safety, and which are set up in such a way as to accompany the realization of that concept. This report contains the results of the first stage of the project from 1978 to mid-1981. (orig./RW) [de

12 CFR 1710.16 - Prohibition of extensions of credit to board members and executive officers.

Science.gov (United States)

2010-01-01

... ENTERPRISE OVERSIGHT, DEPARTMENT OF HOUSING AND URBAN DEVELOPMENT SAFETY AND SOUNDNESS CORPORATE GOVERNANCE Corporate Practices and Procedures § 1710.16 Prohibition of extensions of credit to board members and...

Safety and Toxicology of Cannabinoids.

Science.gov (United States)

Sachs, Jane; McGlade, Erin; Yurgelun-Todd, Deborah

2015-10-01

There is extensive research on the safety, toxicology, potency, and therapeutic potential of cannabis. However, uncertainty remains facilitating continued debate on medical and recreational cannabis policies at the state and federal levels. This review will include a brief description of cannabinoids and the endocannabinoid system; a summary of the acute and long-term effects of cannabis; and a discussion of the therapeutic potential of cannabis. The conclusions about safety and efficacy will then be compared with the current social and political climate to suggest future policy directions and general guidelines.

Trends in Control Area of PLC Reliability and Safety Parameters

Directory of Open Access Journals (Sweden)

Juraj Zdansky

2008-01-01

Full Text Available Extension of the PLC application possibilities is closely related to increase of reliability and safety parameters. If the requirement of reliability and safety parameters will be suitable, the PLC could by implemented to specific applications such the safety-related processes control. The goal of this article is to show the way which producers are approaching to increase PLC`s reliability and safety parameters. The second goal is to analyze these parameters for range of present choice and describe the possibility how the reliability and safety parameters can be affected.

A study on optimization of the nuclear safety system

International Nuclear Information System (INIS)

Lee, Sang Hoon; Koh, Byung Joon; Kim, Jin Soo; Kim, Byoung Do; Cho, Seong Won; Kwon, Seog Kwon; Choi, Kwang Sik

1986-12-01

The number of nuclear facilities (nuclear power plants, research reactors, nuclear fuel facilities) under construction or in operation in Korea continues to increase and this has brought about increased importance and concerns toward nuclear safety in Korea. Also, domestic nuclear related organizations are increasingly carrying out the design/construction of nuclear power plants and the development /supply of nuclear fuels. In order to flexibly respond to these changes and to suggest direction to take, it is necessary to re-examine the current nuclear safety regulation system. This study is carried out in two stages and this report describes the results of the analysis and the assessment of the nuclear licencing system of such foreign countries as sweden and German, as the first of the two. In this regard, this study includes the analysis on the backgrounds on the choice of nuclear licensing system, the analysis on the licensing procedures, the analysis on the safety inspection system and the enforcement laws, the analysis on the structure and function of the regulatory, business and research organizations as well as the analysis on the relationship between the safety research and the regulatory duties. In this study, the German safety inspection system and the enforcement procedures and the Swedish nuclear licensing system are analyzed in detail. By comparing and assessing the finding with the current Korea Nuclear Licensing System, this study points out some reform measures of the Korean system that needs to improved. With the changing situations in mind, this study aims to develop the nuclear safety regulation system optimized for Korean situation by re-examining the current regulation system. (Author)

Discussion on life extension of nuclear power plant around the world

International Nuclear Information System (INIS)

Chen Ming; Zhang Yuansi

2010-01-01

The very Paper introduces the concept, basic working flow and fundamental elements of the life extension of nuclear power plant (NPP) around the world; and it generally collects and summarizes the status datum of life extension of NPPs. Afterwards, the Paper analyses the present status of life extension of NPP in various countries with strong nuclear power industry, i.e. the United States, France, Germany, Russia Federation, Japan, South Korea and Canada. At the end, the Paper make a conclusion that whether an operating NPP will adopt life extension at the end of its design life, this issue depends on the factor of economy, safety and technical feasibility of life extension on the NPP. According to latest datum collected in 2009, the nuclear power units around the world, which have exceeded the design lives or are close to design life ends, most of them (about 64%) have selected to extend their service lives; based on this statistical data, we concludes that when an operating nuclear unit is facing with the issue of to extend life or to retire itself, it will be apt to make life extension. (authors)

Study on some safety-related aspects of tyre use

NARCIS (Netherlands)

Jansen, S.T.H.; Schmeitz, A.J.C.; Maas, S.; Rodarius, C.; Akkermans, L.

2014-01-01

The tyre is a key component that affects road safety. The European commission has posted a tender aimed to study what measures on a European level can be taken in relation to the use of tyres to improve road safety. The results of this study, supported by a cost benefit analyses and carried out by

Runtime extension and nuclear safety. On the legal and technological context of the 11th and 12th amendment of the Atomic Energy Act; Laufzeitverlaengerung und nukleare Sicherheit. Zum rechtlichen und technischen Zusammenhang von 11. und 12. AtG Novelle

Energy Technology Data Exchange (ETDEWEB)

Renneberg, Wolfgang [Renneberg Consult UG, Alfter (Germany)

2011-04-15

The 11th and 12 Amendment of the Atomic Energy Act with which on the one hand the runtime is extended and on the other hand the safety requirements have been renormalized, formally are independent legislative projects. Concerning to the contents, the 12th Amendment appears as an essential element for securing the extension of operation periods. At the same time it constitutes censorship in the safety assessment of nuclear power plants which is equivalent to a modification in the existing security philosophy. The relationships allowing this interpretation go beyond purely legal issues. Therefore the contribution under consideration reports on the legal, safety related and safety political genesis of the actual legal situation following the contributions of Rossnagel/Hentschel and Ziehm.

Nuclear safety guide. TID-7016, Revision 2

International Nuclear Information System (INIS)

Thomas, J.T.

1978-01-01

The Nuclear Safety Guide was first issued in 1956 as classified AEC report LA-2063 and was reprinted the next year, unclassified, as TID-7016. Revision 1, published in 1961, extended the scope and refined the guiding information. The present revision of the Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams, experienced in the field. The reader will find a significant change in the character of information presented in this version. Nuclear Criticality Safety has matured in the past twelve years. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the formerGuides by employing appropriate safety factors. In fact, it becomes incumbent on the Criticality Safety Specialist to necessarily impose safety factors consistent with the possible normal and abnormal credible contingencies of an operation as revealed by his evaluation. In its present form the Guide easily becomes a suitable module in any compendium or handbook tailored for internal use by organizations. It is hoped the Guide will continue to serve immediate needs and will encourage continuing and more comprehensive efforts toward organizing nuclear criticality safety information

Nuclear safety guide. TID-7016, Revision 2

Energy Technology Data Exchange (ETDEWEB)

Thomas, J T [ed.

1978-05-01

The Nuclear Safety Guide was first issued in 1956 as classified AEC report LA-2063 and was reprinted the next year, unclassified, as TID-7016. Revision 1, published in 1961, extended the scope and refined the guiding information. The present revision of the Guide differs significantly from its predecessor in that the latter was intentionally conservative in its recommendations. Firmly based on experimental evidence of criticality, the original Guide and the first revision were considered to be of most value to organizations whose activities with fissionable materials were not extensive and, secondarily, that it would serve as a point of departure for members of established nuclear safety teams, experienced in the field. The reader will find a significant change in the character of information presented in this version. Nuclear Criticality Safety has matured in the past twelve years. The advance of calculational capability has permitted validated calculations to extend and substitute for experimental data. The broadened data base has enabled better interpolation, extension, and understanding of available information, especially in areas previously addressed by undefined but adequate factors of safety. The content has been thereby enriched in qualitative guidance. The information inherently contains, and the user can recapture, the quantitative guidance characteristic of the formerGuides by employing appropriate safety factors. In fact, it becomes incumbent on the Criticality Safety Specialist to necessarily impose safety factors consistent with the possible normal and abnormal credible contingencies of an operation as revealed by his evaluation. In its present form the Guide easily becomes a suitable module in any compendium or handbook tailored for internal use by organizations. It is hoped the Guide will continue to serve immediate needs and will encourage continuing and more comprehensive efforts toward organizing nuclear criticality safety information.

A study of software safety analysis system for safety-critical software

International Nuclear Information System (INIS)

Chang, H. S.; Shin, H. K.; Chang, Y. W.; Jung, J. C.; Kim, J. H.; Han, H. H.; Son, H. S.

2004-01-01

The core factors and requirements for the safety-critical software traced and the methodology adopted in each stage of software life cycle are presented. In concept phase, Failure Modes and Effects Analysis (FMEA) for the system has been performed. The feasibility evaluation of selected safety parameter was performed and Preliminary Hazards Analysis list was prepared using HAZOP(Hazard and Operability) technique. And the check list for management control has been produced via walk-through technique. Based on the evaluation of the check list, activities to be performed in requirement phase have been determined. In the design phase, hazard analysis has been performed to check the safety capability of the system with regard to safety software algorithm using Fault Tree Analysis (FTA). In the test phase, the test items based on FMEA have been checked for fitness guided by an accident scenario. The pressurizer low pressure trip algorithm has been selected to apply FTA method to software safety analysis as a sample. By applying CASE tool, the requirements traceability of safety critical system has been enhanced during all of software life cycle phases

CYP2D6 predicted metabolizer status and safety in adult patients with attention-deficit hyperactivity disorder participating in a large placebo-controlled atomoxetine maintenance of response clinical trial.

Science.gov (United States)

Fijal, Bonnie A; Guo, Yingying; Li, Si G; Ahl, Jonna; Goto, Taro; Tanaka, Yoko; Nisenbaum, Laura K; Upadhyaya, Himanshu P

2015-10-01

Atomoxetine, which is indicated for treatment of attention-deficit hyperactivity disorder (ADHD), is predominantly metabolized by genetically polymorphic cytochrome P450 2D6 (CYP2D6). Based on identified CYP2D6 genotypes, individuals can be categorized into 4 phenotypic metabolizer groups as ultrarapid, extensive, intermediate, and poor. Previous studies have focused on observed differences between poor and extensive metabolizers, but it is not well understood whether the safety profile of intermediate metabolizers differs from that of ultrarapid and extensive metabolizers. This study compared safety and tolerability among the different CYP2D6 metabolizer groups in the 12-week open-label phase of an atomoxetine study in adult patients with ADHD. Genotyping identified 1039 patients as extensive/ultrarapid metabolizers, 780 patients as intermediate metabolizers, and 117 patients as poor metabolizers. Common (≥5% frequency) treatment-emergent adverse events did not significantly differ between extensive/ultrarapid and intermediate metabolizers (odds ratios were 0.5). Poor metabolizers had higher frequencies of dry mouth, erectile dysfunction, hyperhidrosis, insomnia, and urinary retention compared with the other metabolizer groups. There were no significant differences between extensive/ultrarapid and intermediate metabolizers in changes from baseline in vital signs. These results suggest that data from CYP2D6 intermediate and extensive/ultrarapid metabolizers can be combined when considering safety analyses related to atomoxetine. © 2015, The American College of Clinical Pharmacology.

COLD-SAT feasibility study safety analysis

Science.gov (United States)

Mchenry, Steven T.; Yost, James M.

1991-01-01

The Cryogenic On-orbit Liquid Depot-Storage, Acquisition, and Transfer (COLD-SAT) satellite presents some unique safety issues. The feasibility study conducted at NASA-Lewis desired a systems safety program that would be involved from the initial design in order to eliminate and/or control the inherent hazards. Because of this, a hazards analysis method was needed that: (1) identified issues that needed to be addressed for a feasibility assessment; and (2) identified all potential hazards that would need to be controlled and/or eliminated during the detailed design phases. The developed analysis method is presented as well as the results generated for the COLD-SAT system.

Long-term, interventional, open-label extension study evaluating the safety of tocilizumab treatment in patients with polyarticular-course juvenile idiopathic arthritis from Poland and Russia who completed the global, international CHERISH trial.

Science.gov (United States)

Opoka-Winiarska, Violetta; Żuber, Zbigniew; Alexeeva, Ekaterina; Chasnyk, Vyacheslav; Nikishina, Irina; Dębowska, Grażyna; Smolewska, Elżbieta

2018-04-13

Efficacy and safety of tocilizumab (TCZ), an interleukin-6 receptor inhibitor, were demonstrated in juvenile idiopathic arthritis (JIA) with polyarticular course (pJIA) in the CHERISH trial. This observational, III phase study evaluated long-term treatment of TCZ in pJIA patients was conducted by members of the Pediatric Rheumatology International Trials Organization (PRINTO) from Poland and Russia. Forty-one patients, who had completed the CHERISH core study (104 weeks), were extensionally treated with TCZ (8 mg/kg, intravenous infusion every 4 weeks). Total treatment time was from 131 to 193 weeks. The long-term safety (the primary endpoint) and efficacy were evaluated. All patients achieved ACR70 response in the core study and continued to achieve at least ACR50 response up to week 24 of this study. The safety population comprised 46.41 patient-years (PY). Rates per 100 PY of adverse (AEs) and serious events (SAEs) were 181.0 and 6.46, respectively. Pharyngitis and respiratory tract infections were the most common AEs. Except one AE (severe neutropenia), all others were classified as mild (24.4%) or moderate (29.3%). The incidence of SAEs was low (7.3%). No new safety findings were observed. The safety profile of over 2.5-year treatment with TCZ is consistent with the pre-marketing CHERISH clinical trial. Presented data and continued efficacy response support the use of TCZ in pJIA. EUDRACT No: 2011-001607-12. https://clinicaltrials.gov/ct2/show/study/NCT01575769?term=ML27783.

Experimental Studies of quantitative evaluation using HPLC and safety of Bee Venom Acupuncture

Directory of Open Access Journals (Sweden)

Seong Bong Jang

2006-02-01

Full Text Available Objectives : This study was conducted to carry out quantitative evaluation and safety of Bee Venom Acupuncture. Methods : Content analysis was done using HPLC, measurement of , and histological observations were made on the skin and muscles. Results : 1. According to HPLC analysis, each BVA-1 contained approximately , and BVA-2 contained approximately . But the volume of coating was so minute, slight difference exists between each needle. 2. LD50 of mouse with BVA-1 was 16 counts and this is equivalent to 640 needles/kg, making Bee Venom Acupuncture safe treatment apparatus. 3. Regardless of the number of needles, there was no sign of blood stasis or inflammation detected on the skin and muscle tissues. Conclusion : Above results indicate that the Bee Venom Acupuncture can complement shortcomings of syringe usage as a part of Oriental medicine treatment, but extensive researches should be done for further verification.

Safety and relief valves in light water reactors

International Nuclear Information System (INIS)

Singh, A.

1985-12-01

Information is presented to: provide an introduction to and descriptions of various types of safety and relief valves in both PWR and BWR plants; describe anticipated operating conditions for these valves; describe the test facilities, procedures, and major results for both types of valves; present an extensive discussion of modeling and analysis of safety and relief valve performance, including the prediction of flow capacity and stability during operation; deal with the analyses related to the prediction of thermal-hydraulic loads on discharge piping and comparison against test data; discuss results of small-scale valve tests and flow visualization studies through transparent valve models; and describe an EPRI study for optimizing a typical PWR over-pressure protection system to enhance the availability and reliability of plant operation and thus reduce operation costs

International Conference of Ukrainian Nuclear Society ''NPP's safety and protection''(annotations)

International Nuclear Information System (INIS)

Barbashev, S.V.

1997-01-01

The abstracts of reports submitted to the Conference include: - New developments of the safe nuclear installations; - NPP ecological safety; - Methods of personnel and population protection; - Waste management safety (at transportation, processing and storage); - Spent nuclear fuel management; - NPP life extension and decommissioning; - Public opinion as an element of NPP safety; - Training of personnel, scientific support and safety culture; - Forecasting of nuclear power and industry safe development; - Development of international cooperation in nuclear power

Bohunice Nuclear Power Plant Safety Upgrading Program

International Nuclear Information System (INIS)

Toth, A.; Fagula, L.

1996-01-01

Bohunice nuclear Power Plant generation represents almost 50% of the Slovak republic electric power production. Due to such high level of commitment to nuclear power in the power generation system, a special attention is given to safe and reliable operation of NPPs. Safety upgrading and operational reliability improvement of Bohunice V-1 NPP was carried out by the Bohunice staff continuously since the plant commissioning. In the 1990 - 1993 period extensive projects were realised. As a result of 'Small Reconstruction of the Bohunice V-1 NPP', the standards of both the nuclear safety and operational reliability have been significantly improved. The implementation of another modifications that will take place gradually during extended refuelling outages and overhauls in the course of 1996 through 1999, is referred to as the Gradual Reconstruction of the Bohunice V-1 Plant. The general goal of the V-1 NPP safety upgrading is the achievement of internationally acceptable level of nuclear safety. Extensive and financially demanding modification process of Bohunice V-2 NPP is likely to be implemented after a completion of the Gradual Reconstruction of the Bohunice V-1 NPP, since the year 1999. With this in mind, a first draft of the strategy of the Bohunice V-2 NPP upgrading program based on Probabilistic Safety assessment consideration was developed. A number of actions with a general effect on Bohunice site safety is evident. All these activities are aimed at reaching the essential objective of Bohunice NPP Management - to ensure a safe, reliable and effective electric energy and heat generation at the Bohunice site. (author)

The ESMERALDA project for studying extensive sodium fire

International Nuclear Information System (INIS)

Sophy, Y.M.; Roy, D.; Noel, H.; Gerosa, A.

1979-08-01

This paper describes the Esmeralda Project for studying extensive fires involving up to 70 metric tons of sodium. The motivations which prompted the decision to create this research facility are related to construction of the Super-Phenix breeder reactor and to the scale effect problems posed by the use of very large quantities of sodium. Information is included on the dimensions of the installation, the objectives of the project, the means to be employed, the timetable to be followed, and the organization which was created for this project within the context of Franco-Italian cooperation

CONSUMER WILLINGNESS TO PAY FOR SAFETY LABELS IN NIGERIA: A CASE STUDY OF POTASSIUM BROMATE IN BREAD

Directory of Open Access Journals (Sweden)

O Oni

2006-05-01

Full Text Available The study analysed consumer willingness to pay for safety labels in Nigeria by a case study of potassium bromate in bread” in Benin City, Edo State. It specifi cally investigates factors that promote willingness to pay for label among consumers of bread in Benin City, Edo State. Data used for the study were obtained through a well-structured questionnaire from 200 respondents. Both descriptive analytical methods and probit regression models were used for the analysis. The study revealed that 73% of the respondents are in their active working age with 50 percent of the respondent being male and female respectively. 67 percent of the respondents are married with 55 percent having an average of 5 members per household. 99 percent of the respondents are educated i.e. they have the capability of being able to read and write. Respondents purchased bread mainly from hawkers (60% with about 60% of them being aware of the presence of bromate in bread. 40% of the consumers used labeling as a way of identifying bromate free bread. Other methods reported deal with differences in price of bread with same weight, aroma and taste. Result also revealed that 60% of the respondents got to know about the negative effect of bromate from news (both print and mass media. Econometric results show that variables like education, gender, income, prior knowledge of bromate and perception held by respondents of negative implications of bromate signifi cantly infl uence the willingness to pay for safety labels. Education, gender, income and prior knowledge of bromate positively infl uence the probability of consumers’ decision to pay for safety label, while price of bread and confi dence and perception held by respondents of negative implications of bromate on human health infl uence consumers willingness to pay more for safety labels. The study, thus, suggests a defi ned market for bread purchases, community based awareness programme and extension of National Agency

Behavior-based safety on construction sites: a case study.

Science.gov (United States)

Choudhry, Rafiq M

2014-09-01

This work presents the results of a case study and describes an important area within the field of construction safety management, namely behavior-based safety (BBS). This paper adopts and develops a management approach for safety improvements in construction site environments. A rigorous behavioral safety system and its intervention program was implemented and deployed on target construction sites. After taking a few weeks of safety behavior measurements, the project management team implemented the designed intervention and measurements were taken. Goal-setting sessions were arranged on-site with workers' participation to set realistic and attainable targets of performance. Safety performance measurements continued and the levels of performance and the targets were presented on feedback charts. Supervisors were asked to give workers recognition and praise when they acted safely or improved critical behaviors. Observers were requested to have discussions with workers, visit the site, distribute training materials to workers, and provide feedback to crews and display charts. They were required to talk to operatives in the presence of line managers. It was necessary to develop awareness and understanding of what was being measured. In the process, operatives learned how to act safely when conducting site tasks using the designed checklists. Current weekly scores were discussed in the weekly safety meetings and other operational site meetings with emphasis on how to achieve set targets. The reliability of the safety performance measures taken by the company's observers was monitored. A clear increase in safety performance level was achieved across all categories: personal protective equipment; housekeeping; access to heights; plant and equipment, and scaffolding. The research reveals that scores of safety performance at one project improved from 86% (at the end of 3rd week) to 92.9% during the 9th week. The results of intervention demonstrated large decreases in

The safety of the nuclear fuel cycle

International Nuclear Information System (INIS)

1993-01-01

The nuclear fuel cycle covers the procurement and preparation of fuel for nuclear power reactors, its recovery and recycling after use and the safe storage of all wastes generated through these operations. The facilities associated with these activities have an extensive and well documented safety record accumulated over the past 40 years by technical experts and safety authorities. This report constitutes an up-to-date analysis of the safety of the nuclear fuel cycle, based on the available experience in OECD countries. It addresses the technical aspects of fuel cycle operations, provides information on operating practices and looks ahead to future activities

Safety evaluation status report for the prototype license application safety analysis report

International Nuclear Information System (INIS)

1989-07-01

The US Nuclear Regulatory Commission (NRC) staff and consultants reviewed a Prototype License Application Safety Analysis Report (PLASAR) submitted by the US Department of Energy (DOE) for the earth-mounded concrete bunker (EMCB) alternative method of low-level radioactive waste disposal. The NRC reviewers relied extensively on the Standard Review Plan (SRP), Rev.1 (NUREG-1200), to evaluate the acceptability of the information provided in the EMCB PLASAR. The NRC staff selected certain review areas in the PLASAR for development of safety evaluation report input to provide examples of safety assessments that are necessary as part of a licensing review. Because of the fictitious nature of the assumed disposal site, and the decision to limit the review to essentially first-round review status, the NRC staff report is labeled a ''Safety Evaluation Status Report'' (SESR). Appendix A comprises the NRC review comments and questions on the information that DOE submitted in the PLASAR. The NRC concentrated its review on the design and operations-related portions of the EMCB PLASAR

Age and workers' perceptions of workplace safety: a comparative study.

Science.gov (United States)

Gyekye, Seth Ayim; Salminen, Simo

2009-01-01

The study examined the relationship between age and (i) safety perception; (ii) job satisfaction; (iii) compliance with safety management policies; and (iv) accident frequency. Participants were Ghanaian industrial workers (N=320) categorized into 4 age groups: 19-29 years; 30-39 years; 40-50 years; and 51 years and above. Workplace safety perception was assessed with Hayes, Perander, Smecko, and Trask's (1998) 50-item Work Safety Scale (WSS): a scale that effectively captures the dimensions identified by safety experts to influence perceptions of workplace safety. ANOVA was used to test for differences in the mean scores of the 4 groups. Post Hoc analysis revealed differences of statistical significance between the 2 younger cohorts and the 2 older cohorts. The results indicated a positive association between age and safety perception. Older workers had the best perceptions on safety, indicated the highest level of job satisfaction, were the most compliant with safety procedures, and recorded the lowest accident involvement rate. From a practical perspective, understanding age-related perceptions of workplace safety would benefit management's decisions regarding workers' adaptability, general work effectiveness, accident frequency, implementation of safety management policies, and handling of age-related accident characteristics.

Improving safety margin of LWRs by rethinking the emergency core cooling system criteria and safety system capacity

Energy Technology Data Exchange (ETDEWEB)

Lee, Youho, E-mail: euo@kaist.ac.kr; Kim, Bokyung, E-mail: bkkim2@kaist.ac.kr; NO, Hee Cheon, E-mail: hcno@kaist.ac.kr

2016-10-15

Highlights: • Zircaloy embrittlement criteria can increase to 1370 °C for CP-ECR lower than 13%. • The draft ECCS criteria of U.S. NRC allow less than 5% in power margin. • The Japanese fracture-based criteria allow around 5% in power margin. • Increasing SIT inventory is effective in assuring safety margin for power uprates. - Abstract: This study investigates the engineering compatibility between emergency core cooling system criteria and safety water injection systems, in the pursuit of safety margin increase of light water reactors. This study proposes an acceptable temperature increase to 1370 °C as long as equivalent cladding reacted calculated by the Cathcart–Pawel equation is below 13%, after an extensive literature review. The influence of different ECCS criteria on the safety margin during large break loss of coolant accident is investigated for OPR-1000 by the system code MARS-KS, implemented with the KINS-REM method. The fracture-based emergency core cooling system (ECCS) criteria proposed in this study are shown to enable power margins up to 10%. In the meantime, the draft U.S. NRC’s embrittlement criteria (burnup-sensitive) and Japanese fracture-based criteria are shown to allow less than 5%, and around 5% of power margins, respectively. Increasing safety injection tank (SIT) water inventory is the key, yet convenient, way of assuring safety margin for power increase. More than 20% increase in the SIT water inventory is required to allow 15% power margins, for the U.S. NRC’s burnup-dependent embrittlement criteria. Controlling SIT water inventory would be a useful option that could allow the industrial desire to pursue power margins even under the recent atmosphere of imposing stricter ECCS criteria for the considerable burnup effects.

Regulatory aspects of NPP safety

International Nuclear Information System (INIS)

Kastchiev, G.

1999-01-01

Extensive review of the NPP Safety is presented including tasks of Ministry of Health, Ministry of Internal Affairs, Ministry of Environment and Waters, Ministry of Defense in the field of national system for monitoring the nuclear power. In the frame of national nuclear safety legislation Bulgaria is in the process of approximation of the national legislation to that of EC. Detailed analysis of the status of regulatory body, its functions, organisation structure, responsibilities and future tasks is included. Basis for establishing the system of regulatory inspections and safety enforcement as well as intensification of inspections is described. Assessment of safety modifications is concerned with complex program for reconstruction of Units 1-4 of Kozloduy NPP, as well as for modernisation of Units 5 and 6. Qualification and licensing of the NPP personnel, Year 2000 problem, priorities and the need of international assistance are mentioned

Risk reduction category (RRC-A) accident studies in the safety analysis report of the EPR trademark reactor

International Nuclear Information System (INIS)

Poehlmann, M.; Bleher, G.; Ismaier, A.; Knoll, A.; Levi, P.; Garcia, E. Vera; Schels, A.; Seitz, H.; Lima Campos, L.

2013-01-01

The Risk Reduction Category (RRC-A) is considered in the safety demonstration of nuclear reactors in addition to design basis operating conditions (Plant Condition Category, PCC), in order to analyze with a risk reduction approach any operating conditions with multiple failures. As extending the operating conditions of the plant 'beyond design basis', the Risk Reduction Category (RRC-A) is also denoted as Design Extension Condition (DEC-A). In the German licensing framework, the RRCA (or DEC-A) transients correspond to safety assessment level '4b' of the 'Sicherheitsanforderungen an Kernkraftwerke' (Safety Requirements for Nuclear Power Plants), Az. RS I 5 - 13303/01 of the German Federal Ministry for the Environment, Nature Conservation and Nuclear Safety. These RRC-A (or DEC-A) operating conditions require specific design provisions (implemented by manual or automatic action), known as RRC-A measures, intended to render consequences of accumulated failures admissible. In contrast, RRC-B constitute severe accidents that lead to core melt. Identification of RRC-A operating conditions and corresponding RRC-A measures is based on the use of results of probabilistic safety assessments. After the Fukushima accident the RRC-A accidents like Station Black Out (SBO) or Loss of Ultimate Heat Sink (LUHS) are of particular interest in the safety assessment of nuclear new builds. In several chapters of the Safety Analysis Report it is demonstrated that the AREVA EPRTM design is resistant at RRC-A accident conditions. (orig.)

Main lessons for FBR safety study from the CABRI experiments

International Nuclear Information System (INIS)

Sato, Ikken

2006-01-01

CABRI project has been carried out FBR safety study with international cooperation of five nations since 1978. The project consists of four periods such as CABRI-1, CABRI-2, CABRI-FAST and CABRI-RAFT. The objects and the main information for hypothetical core decay accident and safety study of fuel are described. The behavior of core decay accident was studied in the first period (CABRI-1), the safety study of fuel was investigated after the second period (CABRI-2). Change of phenomena at the initial process of core decay accident, comparison between analysis and data of fuel diffusion behavior of neutron horoscope by CABRI-2 experiment, representative in-core experiment under slow TOP conditions, the damaged and undamaged pin under slow TOP conditions, the exterior of CABRI and TREAT and the upper part of CABRI and TREAT reactor are shown. CABRI experiments changed to LWR safety study and a part of TREAT is stated. (S.Y.)

Reliability Centered Maintenance as a tool for plant life extension

International Nuclear Information System (INIS)

Elliott, J.O.; Mulay, J.N.; Nakahara, Y.

1991-01-01

Currently in the nuclear industry there is a growing interest in lowering the cost and complexity of maintenance activities while at the same time improving plant reliability and safety in an effort to prepare for the technical and regulatory challenges of life extension. This seemingly difficult task is being aided by the introduction of a maintenance philosophy developed originally by the airline industry and subsequently applied with great success both in that industry and the U.S. military services. Reliability Centered Maintenance (RCM), in its basic form, may be described as a consideration of reliability and maintenance problems from a systems level approach, allowing a focus on preservation of system function as the aim of a maintenance program optimized for both safety and economics. It is this systematic view of plant maintenance, with the emphasis on overall functions rather than individual parts and components which sets RCM apart from past nuclear plant maintenance philosophies. It is also the factor which makes application of RCM an ideal first step in development of strategies for life extension, both for aging plants, and for plants just beginning their first license term. (J.P.N.)

Establishment of Safety Analysis System and Technology for CANDU Reactors

International Nuclear Information System (INIS)

Park, Joo Hwan; Rhee, B. W.; Min, B. J.; Kim, H. T.; Kim, W. Y.; Yoon, C.; Chun, J. S.; Cho, M. S.; Jeong, J. Y.; Kang, H. S.

2007-06-01

The following 4 research items have been studied to establish a CANDU safety analysis system and to develop the relevant elementary technology for CANDU reactors. First, to improve and validate the CANDU design and operational safety analysis codes, the CANDU physics cell code WIMS-CANDU was improved, and validated, and an analysis of the moderator subcooling and pressure tube integrity has been performed for the large break LOCAs without ECCS. Also a CATHENA model and a CFD model for a post-blowdown fuel channel analysis have been developed and validated against two high temperature thermal-chemical experiments, CS28-1 and 2. Second, to improve the integrated operating system of the CANDU safety analysis codes, an extension has been made to them to include the core and fuel accident analyses, and a web-based CANDU database, CANTHIS version 2.0 was completed. Third, to assess the applicability of the ACR-7 safety analysis methodology to CANDU-6 the ACR-7 safety analysis methods were reviewed and the safety analysis methods of ACR-7 applicable to CANDU-6 were recommended. Last, to supplement and improve the existing CANDU safety analysis procedures, detailed analysis procedures have been prepared for individual accident scenarios. The results of this study can be used to resolve the CANDU safety issues, to improve the current design and operational safety analysis codes, and to technically support the Wolsong site to resolve their problems

The safety relief valve handbook design and use of process safety valves to ASME and International codes and standards

CERN Document Server

Hellemans, Marc

2009-01-01

The Safety Valve Handbook is a professional reference for design, process, instrumentation, plant and maintenance engineers who work with fluid flow and transportation systems in the process industries, which covers the chemical, oil and gas, water, paper and pulp, food and bio products and energy sectors. It meets the need of engineers who have responsibilities for specifying, installing, inspecting or maintaining safety valves and flow control systems. It will also be an important reference for process safety and loss prevention engineers, environmental engineers, and plant and process designers who need to understand the operation of safety valves in a wider equipment or plant design context. . No other publication is dedicated to safety valves or to the extensive codes and standards that govern their installation and use. A single source means users save time in searching for specific information about safety valves. . The Safety Valve Handbook contains all of the vital technical and standards informat...

A correlation for safety valve blowdown and ring settings

International Nuclear Information System (INIS)

Singh, A.; Shak, D.

1982-01-01

The blowdown of a spring loaded safety valve is defined as the difference between the pressure at which the valve opens and the pressure at which the valve fully closes under certain fluid flow conditions. Generally, the blowdown is expressed in terms of percentage of the opening pressure. An extensive series of tests carried out in the EPRI/PWR Utilities Valve Test Program has shown that the blowdown of safety valves can in general be strongly dependent upon the valve geometry and other parameters such as ring adjustments, spring stiffness, backpressure etc. In the present study, correlations have been developed using the EPRI safety valve test data to predict the expected blowdown as a function of adjustment ring settings for geometrically similar valves under steam discharge conditions. The correlation is validated against two different size Dresser valves

Safety culture: the perspective of a lawyer on its necessity and weaknesses

International Nuclear Information System (INIS)

Favini, J.M.

1998-01-01

A reflection is presented on the acceptance and extension of the concept of safety culture in radiation protection. Safety culture, a basic attitude to guard against nuclear accidents, radiological hazards or radiological accidents, is predicated on the prevention of complacency. (author)

76 FR 3175 - Proposed Extension of Existing Information Collection; Hoist Operators' Physical Fitness

Science.gov (United States)

2011-01-19

... Extension of Existing Information Collection; Hoist Operators' Physical Fitness AGENCY: Mine Safety and... fitness. DATES: All comments must be received by midnight Eastern Standard Time on March 21, 2011... 56.19057 and 57.19057 require the annual examination and certification of hoist operators' fitness by...

Long-Term Effectiveness and Safety of Dexmethylphenidate Extended-Release Capsules in Adult ADHD

Science.gov (United States)

Adler, Lenard A.; Spencer, Thomas; McGough, James J.; Jiang, Hai; Muniz, Rafael

2009-01-01

Objective: This study evaluates dexmethylphenidate extended release (d-MPH-ER) in adults with ADHD. Method: Following a 5-week, randomized, controlled, fixed-dose study of d-MPH-ER 20 to 40 mg/d, 170 adults entered a 6-month open-label extension (OLE) to assess long-term safety, with flexible dosing of 20 to 40 mg/d. Exploratory effectiveness…

A New Method to Measure Crack Extension in Nuclear Graphite Based on Digital Image Correlation

Directory of Open Access Journals (Sweden)

Shigang Lai

2017-01-01

Full Text Available Graphite components, used as moderators, reflectors, and core-support structures in a High-Temperature Gas-Cooled Reactor, play an important role in the safety of the reactor. Specifically, they provide channels for the fuel elements, control rods, and coolant flow. Fracture is the main failure mode for graphite, and breaching of the above channels by crack extension will seriously threaten the safety of a reactor. In this paper, a new method based on digital image correlation (DIC is introduced for measuring crack extension in brittle materials. Cross-correlation of the displacements measured by DIC with a step function was employed to identify the advancing crack tip in a graphite beam specimen under three-point bending. The load-crack extension curve, which is required for analyzing the R-curve and tension softening behaviors, was obtained for this material. Furthermore, a sensitivity analysis of the threshold value employed for the cross-correlation parameter in the crack identification process was conducted. Finally, the results were verified using the finite element method.

Explicit Precedence Constraints in Safety-Critical Java

DEFF Research Database (Denmark)

Puffitsch, Wolfgang; Noulard, Eric; Pagetti, Claire

2013-01-01

Safety-critical Java (SCJ) aims at making the amenities of Java available for the development of safety-critical applications. The multi-rate synchronous language Prelude facilitates the specification of the communication and timing requirements of complex real-time systems. This paper combines...... to provide explicit support for precedence constraints. We present the considerations behind the design of this extension and discuss our experiences with a first prototype implementation based on the SCJ implementation of the Java Optimized Processor....

48 CFR 2052.235-71 - Safety, health, and fire protection.

Science.gov (United States)

2010-10-01

... extension of time or for compensation or damages by reason of, or in connection with, this type of work... performance of the work under this contract to protect the health and safety of its employees and of members... hazards to life and property. The contractor shall comply with all applicable health, safety, and fire...

Irradiation of prepared meals for microbiological safety and shelf life extension

International Nuclear Information System (INIS)

Nketsia-Tabiri, K.; Adu-Gyamfi, A.; Apea Bah, F.

2009-01-01

Fourteen international ready meals prepared under the approved hazard analysis critical control point (HACCP) plan and two Ghanaian ready meals, waakye (co-boiled rice and cowpeas served with gravy, minimally processed vegetable salad, hydrated gari, fried fish and macaroni) and jollof rice (rice cooked in tomato sauce and served with gravy and beef tripe), were investigated with the view to enhancing microbiological safety and extending shelf life under chilled conditions. The microbiological count of the complete waakye meal exceeded the microbiological standard. The microbiological counts on meals prepared under the HACCP plan and the jollof rice meals were within the microbiological standards. The D 10 values for potential pathogens on waakye were 0.271 kGy for Escherichia coli, 0.325 kGy for Salmonella aureus and 0.440 kGy for Salmonella spp. while the D 10 values on jollof rice meal were 0.173 kGy, 0.260 kGy and 0.285 kGy, respectively. Challenge tests with the pathogens on one of the HACCP meals (poached chicken) or jollof rice suggested that the 3 kGy dose was sufficient for the elimination of the pathogens to ensure the microbiological safety of the meals and extended their shelf life under chilled storage for 28 days without significant effects on their sensory quality. Doses of 1 and 2 kGy did not affect the sensory quality of the rice and chicken/gravy but boiled carrots were unable to withstand a dose of more than 1 kGy. (author)

Fusion-reactor blanket-material safety-compatibility studies

International Nuclear Information System (INIS)

Jeppson, D.W.; Muhlestein, L.D.; Keough, R.F.; Cohen, S.

1982-11-01

Blanket material selection for fusion reactors is strongly influenced by the desire to minimize safety and environmental concerns. Blanket material safety compatibility studies are being conducted to identify and characterize blanket-coolant-material interactions under postulated reactor accident conditions. Recently completed scoping compatibility tests indicate that : (1) ternary oxides (LiAlO 2 , Li 2 ZrO 3 , Li 2 SiO 3 , Li 4 SiO 4 and LiTiO 3 ) at postulated blanket operating temperatures are compatible with water coolant, while liquid lithium and Li 7 Pb 2 alloy reactions with water generate heat, aerosol and hydrogen; (2) lithium oxide and Li 17 Pb 83 alloy react mildly with water requiring special precautions to control hydrogen release; (3) liquid lithium reacts substantially, while Li 17 Pb 83 alloy reacts mildly with concrete to produce hydrogen; and (4) liquid lithium-air reactions present some major safety concerns

Life extension of the St. Lucie unit 1 reactor vessel

International Nuclear Information System (INIS)

Rowan, G.A.; Sun, J.B.; Mott, S.L.

1991-01-01

In late 1989, Florida Power and Light Company (FP and L) established the policy that St. Lucie unit 1 should not be prevented from achieving a 60-yr operating life by reactor vessel embrittlement. A 60-yr operating life means that the plant would be allowed to operate until the year 2036, which is 20 years beyond the current license expiration date of 2016. Since modifications to the reactor vessel and its components are projected to be expensive, the desire of FP and L management was to achieve this lifetime extension through the use of fuel management and proven technology. The following limitations were placed on any acceptable method for achieving this lifetime extension capability: low fuel cycle cost; low impact on safety parameters; very little or no operations impact; and use of normal reactor materials. A task team was formed along with the Advanced Nuclear Fuels Company (ANF) to develop a vessel-life extension program

Review of light--water reactor safety studies. Volume 3 of health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California

International Nuclear Information System (INIS)

Nero, A.V.; Farnaam, M.R.K.

1977-01-01

This report summarizes and compares important studies of light-water nuclear reactor safety, emphasizing the Nuclear Regulatory Commission's Reactor Safety Study, work on risk assessment funded by the Electric Power Research Institute, and the Report of the American Physical Society study group on light-water reactor safety. These reports treat risk assessment for nuclear power plants and provide an introduction to the basic issues in reactor safety and the needs of the reactor safety research program. Earlier studies are treated more briefly. The report includes comments on the Reactor Safety Study. The manner in which these studies may be used and alterations which would increase their utility are discussed

RSAS: a Reactor Safety Assessment System

International Nuclear Information System (INIS)

Sebo, D.E.; Dixon, B.W.; Bray, M.A.

1985-01-01

The Reactor Safety Assessment System (RSAS) is an expert system under development for the United States Nuclear Regulatory Commission (NRC). RSAS is being developed for use at the NRC's Operations Center in the event of a serious incident at a licensed nuclear power plant. The system generates situation assessments for the NRC Reactor Safety Team based on a limited number of plant parameters, known operator actions, and plant status data. The RSAS rule base currently covers one reactor type. The extension of the rule base to other reactor types is also discussed

10 years of denosumab treatment in postmenopausal women with osteoporosis: results from the phase 3 randomised FREEDOM trial and open-label extension.

Science.gov (United States)

Bone, Henry G; Wagman, Rachel B; Brandi, Maria L; Brown, Jacques P; Chapurlat, Roland; Cummings, Steven R; Czerwiński, Edward; Fahrleitner-Pammer, Astrid; Kendler, David L; Lippuner, Kurt; Reginster, Jean-Yves; Roux, Christian; Malouf, Jorge; Bradley, Michelle N; Daizadeh, Nadia S; Wang, Andrea; Dakin, Paula; Pannacciulli, Nicola; Dempster, David W; Papapoulos, Socrates

2017-07-01

Long-term safety and efficacy of osteoporosis treatment are important because of the chronic nature of the disease. We aimed to assess the long-term safety and efficacy of denosumab, which is widely used for the treatment of postmenopausal women with osteoporosis. In the multicentre, randomised, double-blind, placebo-controlled, phase 3 FREEDOM trial, postmenopausal women aged 60-90 years with osteoporosis were enrolled in 214 centres in North America, Europe, Latin America, and Australasia and were randomly assigned (1:1) to receive 60 mg subcutaneous denosumab or placebo every 6 months for 3 years. All participants who completed the FREEDOM trial without discontinuing treatment or missing more than one dose of investigational product were eligible to enrol in the open-label, 7-year extension, in which all participants received denosumab. The data represent up to 10 years of denosumab exposure for women who received 3 years of denosumab in FREEDOM and continued in the extension (long-term group), and up to 7 years for women who received 3 years of placebo and transitioned to denosumab in the extension (crossover group). The primary outcome was safety monitoring, comprising assessments of adverse event incidence and serious adverse event incidence, changes in safety laboratory analytes (ie, serum chemistry and haematology), and participant incidence of denosumab antibody formation. Secondary outcomes included new vertebral, hip, and non-vertebral fractures as well as bone mineral density (BMD) at the lumbar spine, total hip, femoral neck, and one-third radius. Analyses were done according to the randomised FREEDOM treatment assignments. All participants who received at least one dose of investigational product in FREEDOM or the extension were included in the combined safety analyses. All participants who enrolled in the extension with observed data were included in the efficacy analyses. The FREEDOM trial (NCT00089791) and its extension (NCT00523341) are both

Preliminary Study on the Development of Quantitative Safety Culture Index

International Nuclear Information System (INIS)

Lee, Young Eal; Kim, Hun Sil; Ahn, Nam Sung

2005-01-01

Safety culture is that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance. Because it needs to be recognized as the most significant consciousness to achieve the nuclear safety performance, Korean government and nuclear power generation company have tried to develop the practical method to improve the safety culture from the long term point view. In this study, based on the site interviews to define the potential issues on organizational behavior for the safe operation and the survey on the level of safety culture of occupied workers are conducted. Survey results are quantified as a few indicators of nuclear safety by the statistical method and it can be simulated by the dynamic modeling as time goes on. Currently index and dynamic modeling are still being developed, however, results can be used to suggest the long term strategy which safety is clearly integrated into all activities in the nuclear organization

Definitive closure of nuclear power plants. Aspects concerning physical safety

International Nuclear Information System (INIS)

Rodriguez, C.; Puntarulo, L.; Canibano, J.

1988-01-01

This paper analyzes the various safety requirements that must be fulfilled by nuclear power plants for their operation without restrictions, such as safeguards, nuclear safety and physical protection. Physical protection, the subject most extensively dealt by the authors, is defined as safety measures aimed at providing protection against deliberate hostile deeds, such as robberies or non-authorized transport of radioactive materials or sabotage in nuclear facilities, performed either by individuals or by groups of individuals. (Author)

Study Of Safety Management By Using Gis In Coimbatore

Directory of Open Access Journals (Sweden)

S. Kanchana

2015-08-01

Full Text Available The safety management is very important in the process of construction .The traditional methods of construction safety control cannot meet the construction of big project. To ensure the safety of construction and reduce accidents in the process of construction the current situation and problems we face in construction safety management should be studied first. And then the project risk warning mechanism based on the GIS is constructed according to the problems we faced to achieve visual monitoring and warning of construction safety risk management and to provide decision support for construction. This project aims to develop a web-based spatial decision support system model for proactive health and safety management in linear construction projects. 5 Currently health and safety management is usually performed reactively instead of proactive management since hazard identification and risk assessment is mostly performed on paper based documents that are not effectively used at site. An information system relates to a chain of operations lead to planning the observation and collection of data to storage and analysis of data to the use of derived information in decision-making processes. To create a web-based free and open sourced GIS that can work with different data formats by exchanging and presenting data as a real-time map on web.

Efficacy and safety of saxagliptin in combination with insulin in Japanese patients with type 2 diabetes mellitus: a 16-week double-blind randomized controlled trial with a 36-week open-label extension.

Science.gov (United States)

Kadowaki, Takashi; Muto, Satsuki; Ouchi, Yoshiumi; Shimazaki, Ryutaro; Seino, Yutaka

2017-12-01

We examined the efficacy and safety of saxagliptin as an add-on to insulin in Japanese patients with type 2 diabetes mellitus. We randomized 240 patients with type 2 diabetes mellitus on insulin monotherapy to 5-mg saxagliptin or placebo as add-on therapy for a 16-week, double-blind period. All patients received 5-mg saxagliptin and insulin for an additional 36 weeks (open-label extension). Change in hemoglobin A1c (HbA1c) at Week 16 was the main endpoint. At Week 16, the adjusted change in HbA1c from baseline increased by 0.51% with placebo and decreased by 0.40% with saxagliptin (difference -0.92% [95% confidence interval -1.07%, -0.76%; p 1]). In patients receiving saxagliptin, reductions in HbA1c at Week 16 were maintained to Week 52, while switching from placebo to saxagliptin resulted in a similar reduction in HbA1c. The incidence of hypoglycemia was not markedly increased with saxagliptin versus placebo in the double-blind period and did not increase substantially during the open-label extension period. The efficacy and safety of saxagliptin was similar between the elderly and non-elderly patient groups. Adding saxagliptin to ongoing insulin therapy improved glycemic control and was well tolerated in Japanese patients with type 2 diabetes.

78 FR 59725 - Construction Fall Protection Systems Criteria and Practices, and Training Requirements; Extension...

Science.gov (United States)

2013-09-27

...- 1648. Mail, hand delivery, express mail, messenger, or courier service: When using this method, you... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2010-0008] Construction Fall Protection Systems Criteria and Practices, and Training Requirements; Extension of the Office...

Food safety and quality assurance : foods of animal origin

National Research Council Canada - National Science Library

Hughes, Keith L; Hinton, Michael H; Hubbert, William T; Hagstad, Harry V; Spangler, Elizabeth

1996-01-01

The second edition of Food Safety and Quality Assurance is a basic reference for veterinarians, extension specialists, and others who help food-animal producers throughout the food chain to provide...

Developing a Contemporary Dairy Foods Extension Program: A Training and Technical Resource Needs Assessment of Pennsylvania Dairy Foods Processors

Science.gov (United States)

Syrko, Joseph; Kaylegian, Kerry E.

2015-01-01

Growth in the dairy industry and the passage of the Food Safety Modernization Act have renewed interest in dairy foods processing extension positions. A needs assessment survey was sent to Pennsylvania dairy processors and raw milk providers to guide priorities for a dairy foods extension program. The successful development and delivery of…

Safety research needs for Russian-designed reactors. Requirements situation

International Nuclear Information System (INIS)

Brown, R. Allan; Holmstrom, Heikki; Reocreux, Michel; Schulz, Helmut; Liesch, Klaus; Santarossa, Giampiero; Hayamizu, Yoshitaka; Asmolov, Vladimir; Bolshov, Leonid; Strizhov, Valerii; Bougaenko, Sergei; Nikitin, Yuri N.; Proklov, Vladimir; Potapov, Alexandre; Kinnersly, Stephen R.; Voronin, Leonid M.; Honekamp, John R.; Frescura, Gianni M.; Maki, Nobuo; Reig, Javier; ); Bekjord, Eric S.; Rosinger, Herbert E.

1998-01-01

In June 1995, an OECD Support Group was set up to perform a broad study of the safety research needs of Russian-designed reactors. The emphasis of the study is on the VVER-type reactors in part because of the larger base of knowledge within the NEA Member countries related to LWRs. For the RBMKs, the study does not make the judgement that such reactors can be brought to acceptable levels of safety but focuses on near term efforts that can contribute to reducing the risk to the public. The need for the safety research must be evaluated in context of the lifetime of the reactors. The principal outcome of the work of the Support Group is the identification of a number of research topics which the members believe should receive priority attention over the next several years if risk levels are to be reduced and public safety enhanced. These appear in the Conclusions and Recommendations section of the report, and are the following: - The most important near-term need for VVER and RBMK safety research is to establish a sound technical basis for the emergency operating procedures used by the plant staff to prevent or halt the progression of accidents (i.e., Accident Management) and for plant safety improvements. - Co-operation of Western and Eastern experts should help to avoid East-West know-how gaps in the future, as safety technology continues to improve. - Safety research in Eastern countries will make an important contribution to public safety as it has in OECD countries. - RBMK safety research, including verification of codes, starts from a smaller base of experience than VVER, and is at an earlier stage of development. Technical Conclusions: - Research to improve human performance and operational safety of VVER and RBMK plants is extremely important. - VVER thermal-hydraulic and reactor physics research should focus on full validation of codes to VVER-specific features, and on extension of experimental data base. - Methods of assessing VVER pressure boundary

Blueprint for nuclear safety - a nonregulatory strategy

International Nuclear Information System (INIS)

Knight, J.P.

1989-01-01

The Department of Energy operates a nuclear complex that now numbers over 250 facilities nationwide, many of which date back to the 1940s and 1950s. In 1985, Secretary Herrington moved to establish the Office of Environment, Safety and Health, give it needed resources and authorities, and begin extensive environmental protection and safety evaluations of all major DOE sites and facilities. On the nuclear safety side this necessitates an integrated program that not only strengthens oversight but also builds DOE-wide technical capabilities and promotes safety performance. This has led up to focus our attention on three areas: (1) the DOE safety oversight system -- its resources, technical capabilities, and effectiveness; (2) the safety policy development and review; and (3) the Department's capabilities to foster technical inquisitiveness and overall excellence in safety performance. The essence of this approach is found in this last term -- performance. Performance that is results-oriented; founded on realized safety enhancements and risk reduction, not merely regulation for its own sake. Performance not merely in terms of hardware fixes, but also focusing on the human part of the safety equation

Summary of ORNL work on NRC-sponsored HTGR safety research, July 1974-September 1980

International Nuclear Information System (INIS)

Ball, S.J.; Cleveland, J.C.; Conklin, J.C.; Delene, J.G.; Harrington, R.M.; Hatta, M.; Hedrick, R.A.; Johnson, L.G.; Sanders, J.P.

1982-03-01

A summary is presented of the major accomplishments of the Oak Ridge National Laboratory (ORNL) research program on High-Temperature Gas-Cooled Reactor (HTGR) safety. This report is intended to help the nuclear Regulatory Commission establish goals for future research by comparing the status of the work here (as well as at other laboratories) with the perceived safety needs of the large HTGR. The ORNL program includes extensive work on dynamics-related safety code development, use of codes for studying postulated accident sequences, and use of experimental data for code verification. Cooperative efforts with other programs are also described. Suggestions for near-term and long-term research are presented

Identification of potential safety-related incidents applicable to a breeder fuel reprocessing plant

International Nuclear Information System (INIS)

Perkins, W.C.

1980-01-01

The current emphasis on safety in all phases of the nuclear fuel cycle requires that safety features be identified and included in designs of nuclear facilities at the earliest possible stage. A popular method for the early identification of these safety features is the Preliminary Hazards Analysis. An extension of this analysis is to illustrate the nature of a hazard by its effects in accident situations, that is, to identify what are called safety-related incidents. Some useful tools are described which have been used at the Savannah River Laboratory, SRL, to make Preliminary Hazards Analyses as well as safety analyses of facilities for processing spent nuclear fuels from both power and production reactors. These tools have also been used in safety studies of waste handling operations at the Savannah River Plant. The tools are the SRL Incidents Data Bank and the What If meeting. The application of this methodology to a proposed facility which has breeder fuel reprocessing capability, the Hot Experimental Facility (HEF) is illustrated

ENHANCING FOOD SAFETY AND STABILITY THROUGH IRRADIATION: A REVIEW

Directory of Open Access Journals (Sweden)

Manzoor Ahmad Shah

2014-04-01

Full Text Available Food irradiation is one of the non thermal food processing methods. It is the process of exposing food materials to the controlled amounts of ionizing radiations such as gamma rays, X-rays and accelerated electrons, to improve microbiological safety and stability. Irradiation disrupts the biological processes that lead to decay of food quality. It is an effective tool to reduce food-borne pathogens, spoilage microorganisms and parasites; to extend shelf-life and for insect disinfection. The safety and consumption of irradiated foods have been extensively studied at national levels and in international cooperations and have concluded that foods irradiated under appropriate technologies are both safe and nutritionally adequate. Specific applications of food irradiation have been approved by national legislations of more than 55 countries worldwide. This review aims to discuss the applications of irradiation in food processing with the emphasis on food safety and stability.

On application of CFD codes to problems of nuclear reactor safety

International Nuclear Information System (INIS)

Muehlbauer, Petr

2005-01-01

The 'Exploratory Meeting of Experts to Define an Action Plan on the Application of Computational Fluid Dynamics (CFD) Codes to Nuclear Reactor Safety Problems' held in May 2002 at Aix-en-Province, France, recommended formation of writing groups to report the need of guidelines for use and assessment of CFD in single-phase nuclear reactor safety problems, and on recommended extensions to CFD codes to meet the needs of two-phase problems in nuclear reactor safety. This recommendations was supported also by Working Group on the Analysis and Management of Accidents and led to formation oaf three Writing Groups. The first writing Group prepared a summary of existing best practice guidelines for single phase CFD analysis and made a recommendation on the need for nuclear reactor safety specific guidelines. The second Writing Group selected those nuclear reactor safety applications for which understanding requires or is significantly enhanced by single-phase CFD analysis, and proposed a methodology for establishing assesment matrices relevant to nuclear reactor safety applications. The third writing group performed a classification of nuclear reactor safety problems where extension of CFD to two-phase flow may bring real benefit, a classification of different modeling approaches, and specification and analysis of needs in terms of physical and numerical assessments. This presentation provides a review of these activities with the most important conclusions and recommendations (Authors)

Safety of pressurized water reactors: problems and corresponding studies

International Nuclear Information System (INIS)

Cogne, F.

1976-01-01

The author recalls the safety problems subject to researches in the CEA, either because of their importance or because studies made abroad were not sufficiently developed or were classified or in order to acquire an independent judgement when safety is concerned. Those problems and studies are submitted referring to the 3 existing shields between man and dangerous materials: fuel element can, thermal shield, (pressure vessel and pipes), biological shield of which the behaviour is studied in connection with outside aggressions such as earthquakes, plane crashes, chemical explosions.. [fr

75 FR 5333 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2010-02-02

...) Place: Embassy Suites Hotel, 1900 Diagonal Road, Alexandria, Virginia 22314, Telephone (703) 684-5900... matters related to the conduct of Study Section business and for the study section to consider safety and...

Nuclear health and safety

International Nuclear Information System (INIS)

1991-08-01

This paper is a review of environmental and safety programs at facilities in the Naval Reactors Program which shows no basis for allegations that unsafe conditions exist there or that the environment is being harmed by activities conducted there. The prototype reactor design provides safety measures that are consistent with commercial nuclear power plants. Minor incidents affecting safety and the environment have occurred, however, and dents affecting safety and the environment have occurred, however, and as with other nuclear facilities, past activities have caused environmental problems that require ongoing monitoring and vigilance. While the program has historically been exempt from most oversight, some federal and state environmental oversight agencies have recently been permitted access to Naval Reactors facilities for oversight purposes. The program voluntarily cooperates with the Nuclear Regulatory Commission regarding reactor modifications, safety improvements, and component reliability. In addition, the program and its contractors have established an extensive internal oversight program that is geared toward reporting the slightest deviations from requirements or procedures. Given the program's classification policies and requirements, it does not appear that the program routinely overclassifies information to prevent its release to the public or to avoid embarrassment. However, GAO did not some instances in which documents were improperly classified

Abstract of results of safety study. Nuclear fuel cycle field in fiscal 2003

International Nuclear Information System (INIS)

2004-11-01

This report descried the results of studies of nuclear fuel cycle field (nuclear fuel facilities, seismic design, all subjects of environmental radiation and waste disposal, and subjects on nuclear fuel cycle in probabilistic safety assessment) in fiscal 2003 on the basis of the principle project of safety study (from fiscal 2001 to 2005). It consists of four chapters; the first chapter is outline of the principle of project, the second is objects and subjects of safety study in the nuclear fuel cycle field, the third list of questionnaire of results of safety study and the forth investigation of results of safety study in fiscal 2003. There are 49 lists, which include 22 reports on the nuclear fuel facility, one on the seismic design, 4 on the probabilistic safety assessment, 7 on the environmental radiation and 15 on the waste disposal. (S.Y.)

A feasibility study for Arizona's roadway safety management process using the Highway Safety Manual and SafetyAnalyst : final report.

Science.gov (United States)

2016-07-01

To enable implementation of the American Association of State Highway Transportation (AASHTO) Highway Safety Manual using : SaftetyAnalyst (an AASHTOWare software product), the Arizona Department of Transportation (ADOT) studied the data assessment :...

Safety study of PCC 2140 and ALILOG 21 used as part of safety measurement systems

International Nuclear Information System (INIS)

Meriaux, Pierre; Adnot, Serge; Rayrolles, Catherine.

1978-03-01

The PCC 2140 and ALILOG 21 equipment may be used at C.E.A. or E.D.F., as part of safety measurement systems. In a study of a similar, but earlier equipment, it was noticed that certain types of failures caused the system to switch to the least sensitive measurement range, which was detrimental to safety. This report analyses failure modes leading to unsafe failures and evaluates the risks ran into taking in account tests during use [fr

Critical experiments facility and criticality safety programs at JAERI

International Nuclear Information System (INIS)

Kobayashi, Iwao; Tachimori, Shoichi; Takeshita, Isao; Suzaki, Takenori; Miyoshi, Yoshinori; Nomura, Yasushi

1985-10-01

The nuclear criticality safety is becoming a key point in Japan in the safety considerations for nuclear installations outside reactors such as spent fuel reprocessing facilities, plutonium fuel fabrication facilities, large scale hot alboratories, and so on. Especially a large scale spent fuel reprocessing facility is being designed and would be constructed in near future, therefore extensive experimental studies are needed for compilation of our own technical standards and also for verification of safety in a potential criticality accident to obtain public acceptance. Japan Atomic Energy Research Institute is proceeding a construction program of a new criticality safety experimental facility where criticality data can be obtained for such solution fuels as mainly handled in a reprocessing facility and also chemical process experiments can be performed to investigate abnormal phenomena, e.g. plutonium behavior in solvent extraction process by using pulsed colums. In FY 1985 detail design of the facility will be completed and licensing review by the government would start in FY 1986. Experiments would start in FY 1990. Research subjects and main specifications of the facility are described. (author)

Deterministic and probabilistic approach to safety analysis

International Nuclear Information System (INIS)

Heuser, F.W.

1980-01-01

The examples discussed in this paper show that reliability analysis methods fairly well can be applied in order to interpret deterministic safety criteria in quantitative terms. For further improved extension of applied reliability analysis it has turned out that the influence of operational and control systems and of component protection devices should be considered with the aid of reliability analysis methods in detail. Of course, an extension of probabilistic analysis must be accompanied by further development of the methods and a broadening of the data base. (orig.)

Study on the safety and on international developments of small modular reactors (SMR). Final report; Studie zur Sicherheit und zu internationalen Entwicklungen von Small Modular Reactors (SMR). Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Buchholz, Sebastian; Kruessenberg, Anne; Schaffrath, Andreas; Zipper, Reinhard

2015-05-15

This report documents the work and results of the project RS1521 Study of Safety and International Development of Small Modular Reactors (SMR). The aims of this study can be summarized as - setting-up of a sound overview on SMR, - identification of essential issues of reactor safety research and future R and D projects, - identification of needs for adaption of system codes of GRS used in reactor safety research. The sound overview consists of the descriptions of in total 69 SMR (Small and Medium Sized Rector) concepts (32 light water reactors (LWR), 22 liquid metal cooled reactors (LMR), 2 heavy water reactors, 9 gas cooled reactors (GCR) and 4 molten salt reactors (MSR)). It provides information about the core, the cooling circuits and the safety systems. The quality of the given specifications depends on their availability and public accessibility. Using the safety requirements for nuclear power plants and the fundamental safety functions, the safety relevant issues of the described SMR concepts were identified. The systems and measures used in the safety requirements were summarized in table form. Finally it was evaluated whether these systems and measures can be already simulated with the nuclear simulation chain of GRS and where further code development and validation is necessary. The results of this study can be summarized as follows: Many of the current SMR concepts are based on integral design. Here the main components like steam generators, intermediate heat exchangers or - in case of forced convection core cooling - main cooling pumps are located within the reactor pressure vessel. Most of the SMR fulfil highest safety standards and their safety concepts are mainly based on passive safety systems. The safety of theses reactors is achieved indefinitely without energy supply or additional measures of the operators. Since SMR's aim is not only to produce electricity but also couple them with chemical or physical process plants, the safety aspects of

Empirical Analysis of Construction Safety Climate - A Study

OpenAIRE

S.V.S.RAJA PRASAD; K.P.REGHUNATH

2010-01-01

Safety in the construction industry has always been a major issue. Though much improvement in construction safety has been achieved, the industry still continues to lag behind most other industries with regard to safety. The safety climate of any organization consists of employee’s attitudes towards and perceptions of, health and safety behavior. Construction workers attitudes towards safety are influenced by their perceptions of risk, management, safety rulesand procedures. A measure of safe...

Economic evaluation of Kori and Wolsong Unit 1 plant life extension

International Nuclear Information System (INIS)

Song, T. H.; Jeong, I. S.

2002-01-01

24 years have been passed since Kori Unit 1 began its commercial operation, and 19 years have been passed since Wolsong Unit 1 began its commercial operation. As the end point of design life become closer, plant life extension and periodic safety assessment is paid more and more attention to by the utility company. In this paper, the methodologies and results of plant lifetime management economic evaluations of both units have been presented in comparison with Korean standard nuclear power plant 10, 20 and 30 year life extension cases respectively. In addition to that, sensitivity analysis and break even point analysis results are presented with the variables of capacity factor, operation and maintenance cost, and discount rate

Why Work for Extension? An Examination of Job Satisfaction and Motivation in a Statewide Employee Retention Study

Science.gov (United States)

Harder, Amy; Gouldthorpe, Jessica; Goodwin, Jeff

2014-01-01

Understanding motivation and job satisfaction is important for increasing rates of employee retention within Extension. The purpose of the study reported here was to explore factors positively affecting the motivation of Extension professionals in their careers. An online survey of Extension professionals in Colorado was conducted. Factors such as…

77 FR 24992 - OSHA Strategic Partnership Program for Worker Safety and Health (OSPP); Extension of the Office...

Science.gov (United States)

2012-04-26

... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2011-0861] OSHA... and Health Administration (OSHA), Labor. ACTION: Request for public comments. SUMMARY: OSHA solicits... specified in the OSHAs Strategic Partnership Program for Worker Safety and Health (OSPP). DATES: Comments...

Contractors’ Attitude towards Enhancing Safety Performance: Case Study on Construction Firms in Penang

Directory of Open Access Journals (Sweden)

Ulang N. Md

2014-01-01

Full Text Available A qualitative study was conducted to investigate the contractors’ attitude towards enhancing the safety performance in construction site. Despite the fact that there are many safety initiatives established by the government, the rates of accidents are still in a critically high condition. Thus the purpose of this research is to study the contractors’ attitude towards enhancing the implementation of safety management system in construction site in order to increase the safety awareness of construction practitioners in construction site and improve the safety condition of construction sites. This study is conducted through oral interviews with the construction practitioners, and visual inspection of construction sites. The attitudes of contractors are evaluated from 3 aspects: Contractors’ efforts in implement and enforce the safety rules, Contractors efforts in overcoming the rate of accidents, and Reasons given by the contractors for not implement safety law.

Studying the Safety Impact of Autonomous Vehicles Using Simulation-Based Surrogate Safety Measures

OpenAIRE

Morando, Mark Mario; Tian, Qingyun; Truong, Long T.; Vu, Hai L.

2018-01-01

Autonomous vehicle (AV) technology has advanced rapidly in recent years with some automated features already available in vehicles on the market. AVs are expected to reduce traffic crashes as the majority of crashes are related to driver errors, fatigue, alcohol, or drugs. However, very little research has been conducted to estimate the safety impact of AVs. This paper aims to investigate the safety impacts of AVs using a simulation-based surrogate safety measure approach. To this end, safety...

Safety of pandemic H1N1 vaccines in children and adolescents

NARCIS (Netherlands)

E.G. Wijnans (Leonoor); S. de Bie (Sandra); J.P. Dieleman (Jeanne); J. Bonhoeffer (Jan); M.C.J.M. Sturkenboom (Miriam)

2011-01-01

textabstractDuring the 2009 influenza A (H1N1) pandemic several pandemic H1N1 vaccines were licensed using fast track procedures, with relatively limited data on the safety in children and adolescents. Different extensive safety monitoring efforts were put in place to ensure timely detection of

77 FR 75633 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2012-12-21

... (Closed). 8:00 a.m.-5:00 p.m., February 22, 2013 (Closed). Place: Embassy Suites, 1900 Diagonal Road... conduct of Study Section business and for the study section to consider safety and occupational health...

Solutions to Burnout and Retention as Perceived by County Extension Agents of the Colorado State University Extension System

Directory of Open Access Journals (Sweden)

Matt Benge

2015-02-01

Full Text Available This study explored solutions to the issue of burnout and retention of Extension agents. Extension agents experience burnout for reasons such as long hours, stress, and organizational factors. As Extension administration addresses job satisfaction and performance of Extension employees, burnout and retention issues identified in this study can facilitate efforts to enhance the effectiveness of a statewide Extension program. Herzberg’s Motivation-Hygiene Theory was the theoretical framework for this study. Researchers used the constant-comparative method of analysis to identify recurring themes from the open-ended items of an online-administered survey. Twelve primary themes emerged, including (a compensation, (b hiring practices, (c promotion and advancement within Extension, (d organizational support regarding agent development, (e organizational support regarding administration, (f organizational support regarding colleagues, (g reporting, (h recognition, (i resources, (j personnel and staffing, (k evaluation of administration and specialists, and (l workload. Results suggest that Extension administration should focus on the maintenance factors of compensation, workload, and internal promotion and advancement, as well as motivating factors, to improve retention of Extension agents.

RURAL EXTENSION EPISTEMOLOGY AND THE TIME OF TOTAL EXTENSION

Directory of Open Access Journals (Sweden)

Silvio Calgaro Neto

2016-09-01

Full Text Available This article is dedicated to explore the field of knowledge related to rural extension. In general, a three complementary perspective is used as theoretical strategy to present this epistemological study. The first perspective, seeks to accomplish a brief archeology of rural extension, identifying the remarkable historical passages. At the second, we look to some theoretical models through the modern epistemological platform. Finally, the third perspective, aims to present a methodological proposal that contemplate this epistemic characteristics, relating with the contemporary transformations observed in the knowledge construction and technological transference for a rural development. Keywords: Total institutions. University.

Why is patient safety so hard? A selective review of ethnographic studies.

Science.gov (United States)

Dixon-Woods, Mary

2010-01-01

Ethnographic studies are valuable in studying patient safety. This is a narrative review of four reports of ethnographic studies of patient safety in UK hospitals conducted as part of the Patient Safety Research Programme. Three of these studies were undertaken in operating theatres and one in an A&E Department. The studies found that hospitals were rarely geared towards ensuring perfect performances. The coordination and mobilization of the large number of inter-dependent processes and resources needed to support the achievement of tasks was rarely optimal. This produced significant strain that staff learned to tolerate by developing various compensatory strategies. Teamwork and inter-professional communication did not always function sufficiently well to ensure that basic procedural information was shared or that the required sequence of events was planned. Staff did not always do the right things, for a wide range of different reasons, including contestations about what counted as the right thing. Structures of authority and accountability were not always clear or well-functioning. Patient safety incidents were usually not reported, though there were many different reasons for this. It can be concluded that securing patient safety is hard. There are multiple interacting influences on safety, and solutions need to be based on a sound understanding of the nature of the problems and which approaches are likely to be best suited to resolving them. Some solutions that appear attractive and straightforward are likely to founder. Addressing safety problems requires acknowledgement that patient safety is not simply a technical issue, but a site of organizational and professional politics.

Advances made in French safety studies on pressurized water reactors

International Nuclear Information System (INIS)

Pelce, J.

1979-01-01

The programme of French safety studies on reactors is supposed to be known in its main outlines. A few recent results, obtained in different fields are presented. They concern the safety margins evaluation, the contamination transfer and the effect of external aggressions

Energy policy, economic and engineering issues of the extension of Paks Nuclear Power Plant

International Nuclear Information System (INIS)

Aszodi, Attila; Boros, Ildiko; Kovacs, Arnold

2014-01-01

The four operating blocks of the Paks Nuclear Power Plant are of Russian design. They entered into operation three decades ago, between 1982 and 1987. In 2013 they produced 15 TWh out of the 42 TWh energy consumption of Hungary, that is they produced 36% of the energy demand. In the beginning of 2014 the Hungarian and the Russian governments signed the agreement on the extension of Paks site with building two new blocks, producing 1200 MW each. The paper summarizes the energy policy, engineering, safety and economic aspects of the extension. (TRA)

Safety design study of fast breeder reactors in Japan

International Nuclear Information System (INIS)

Miura, M.; Inagaki, T.

1992-01-01

This paper reports on two fast breeder reactor (FBR) concepts, the tank type and the loop type, that have been studied as possible reactor designs to be used for a demonstration FBR (DFBR). The basic principle fo the DFBR design is to ensure plant safety through a defense-in-depth methodology. Improvements in the seismic and thermal stress designs have been attempted for both reactor concepts. The system design study strives to maximize the reliability of the safety-related systems and to rationalize commercialization of the plant

Design extension conditions

Energy Technology Data Exchange (ETDEWEB)

Bujor, A.; Harwood, C.; Lei, Q.; Viktorov, A., E-mail: christopher.harwood@cnsc-ccsn.gc.ca [Canadian Nuclear Safety Commission, Ottawa, Ontario (Canada)

2013-07-01

The CNSC has introduced the term Design Extension Conditions (DEC) in regulatory document RD-337 version 2, 'Design of New Nuclear Power Plants' which was issued for public consultation in July 2012. The primary drivers for this change compared with the earlier version of RD-337 are to maintain alignment with the equivalent International Atomic Energy Agency (IAEA) safety standard and to introduce changes resulting from lessons learned from the Fukushima Daiichi accident. RD-337 version 2 and the accompanying guidance document GD-337 establish high level design requirements and expectations for new Nuclear Power Plants (NPPs), including those pertaining to DEC. Other regulatory documents provide requirements for safety analysis and accident management as well as other aspect relevant to DEC. Nevertheless, the currently available guidance specific to DEC is not comprehensive, while the practices just begin to emerge. CNSC and industry stakeholders are actively discussing how the high level requirements and expectations will be applied in various fields. This paper is a summary of a CNSC discussion paper that is being developed to encourage substantive stakeholder discussions. The topic of DEC is being advanced rapidly both nationally and internationally. With this in mind, this paper does not intend to provide a final established position, but rather to stimulate discussion on the subject of DEC. This paper provides the definition of DEC, gives background information relating to the adoption of the term, describes the identification of DECs and the underlying principles associated with design, analysis, operational and procedural requirements. As described in this paper, DEC and associated requirements apply to new NPPs. Applicability to existing NPPs is also discussed. (author)

Study on safety subsidiary objective of nuclear power plant in USA

International Nuclear Information System (INIS)

Chen Yan; Zhang Chunming; Fu Zhiwei; Song Wei; Li Chaojun; Wang Zhe; Zuo Jiaxu

2013-01-01

This paper reviewed the development of the quantitative safety objective and subsidiary objective in USA. The expressions of CDF and LERF were obtained according to NUREG-1150. The relationship between the subsidiary objective and the quantitative safety objective was derived. The method was compared with that used in NUREG-1860. The requirements of safety objective for the future nuclear power plant and the development of probabilistic safety analysis (PSA) technology in USA were studied and can be used as reference in China. (authors)

EXTENSION EDUCATION SYMPOSIUM: reinventing extension as a resource--what does the future hold?

Science.gov (United States)

Mirando, M A; Bewley, J M; Blue, J; Amaral-Phillips, D M; Corriher, V A; Whittet, K M; Arthur, N; Patterson, D J

2012-10-01

The mission of the Cooperative Extension Service, as a component of the land-grant university system, is to disseminate new knowledge and to foster its application and use. Opportunities and challenges facing animal agriculture in the United States have changed dramatically over the past few decades and require the use of new approaches and emerging technologies that are available to extension professionals. Increased federal competitive grant funding for extension, the creation of eXtension, the development of smartphone and related electronic technologies, and the rapidly increasing popularity of social media created new opportunities for extension educators to disseminate knowledge to a variety of audiences and engage these audiences in electronic discussions. Competitive grant funding opportunities for extension efforts to advance animal agriculture became available from the USDA National Institute of Food and Agriculture (NIFA) and have increased dramatically in recent years. The majority of NIFA funding opportunities require extension efforts to be integrated with research, and NIFA encourages the use of eXtension and other cutting-edge approaches to extend research to traditional clientele and nontraditional audiences. A case study is presented to illustrate how research and extension were integrated to improve the adoption of AI by beef producers. Those in agriculture are increasingly resorting to the use of social media venues such as Facebook, YouTube, LinkedIn, and Twitter to access information required to support their enterprises. Use of these various approaches by extension educators requires appreciation of the technology and an understanding of how the target audiences access information available on social media. Technology to deliver information is changing rapidly, and Cooperative Extension Service professionals will need to continuously evaluate digital technology and social media tools to appropriately integrate them into learning and

Turning an Extension Aide into an Extension Agent

Science.gov (United States)

Seevers, Brenda; Dormody, Thomas J.

2010-01-01

For any organization to remain sustainable, a renewable source of faculty and staff needs to be available. The Extension Internship Program for Juniors and Seniors in High School is a new tool for recruiting and developing new Extension agents. Students get "hands on" experience working in an Extension office and earn college credit…

Microbiological food safety: a dilemma of developing societies.

Science.gov (United States)

Akhtar, Saeed; Sarker, Mahfuzur R; Hossain, Ashfaque

2014-11-01

Current food safety issues are deleteriously reshaping the life style of the population in the developing world. Socioeconomic status of the population in poorer economies is one of the major determinants to delineate the availability of safe food to the vulnerable population. Assessment of the prevalence of foodborne illness in developing world is the most neglected area to control disease. Botulism, Shigellosis, Campylobacteriosis, Escherichia coli infection, Staphylococcus aureus infection, Salmonellosis, Listeriosis and Cholerae are extensively prevalent and pose a major threat to human health in underdeveloped communities. The existing food safety status of many African, South Asian, Central, and South American developing countries is distressing therefore; it seems much timely to highlight the areas for the improvement to ensure the supply of safe food to the population in these regions. Extensive literature search at PubMed, Science Direct and Medline was carried out during the current year to catch on relevant data from 1976 to date, using selective terms like food safety, South East Asia, Africa, Central and South America, and foodborne illness etc. Efforts were made to restrict the search to low income countries of these regions with reference to specific foodborne pathogens. This report briefly discusses the present food safety situation in these developing countries and associated consequences as prime issues, suggesting foodborne illness to be the most distressing threat for human health and economic growth.

Patient safety challenges in a case study hospital--of relevance for transfusion processes?

Science.gov (United States)

Aase, Karina; Høyland, Sindre; Olsen, Espen; Wiig, Siri; Nilsen, Stein Tore

2008-10-01

The paper reports results from a research project with the objective of studying patient safety, and relates the finding to safety issues within transfusion medicine. The background is an increased focus on undesired events related to diagnosis, medication, and patient treatment in general in the healthcare sector. The study is designed as a case study within a regional Norwegian hospital conducting specialised health care services. The study includes multiple methods such as interviews, document analysis, analysis of error reports, and a questionnaire survey. Results show that the challenges for improved patient safety, based on employees' perceptions, are hospital management support, reporting of accidents/incidents, and collaboration across hospital units. Several of these generic safety challenges are also found to be of relevance for a hospital's transfusion service. Positive patient safety factors are identified as teamwork within hospital units, a non-punitive response to errors, and unit manager's actions promoting safety.

The reactor safety study of experimental multi-purpose VHTR design

International Nuclear Information System (INIS)

Yasuno, T.; Mitake, S.; Ezaki, M.; Suzuki, K.

1981-01-01

Over the past years, the design works of the Experimental Very High Temperature Reactor (VHTR) plant have been conducted at Japan Atomic Energy Research Institute. The conceptual design has been completed and the more detailed design works and the safety analysis of the experimental VHTR plant are continued. The purposes of design studies are to show the feasibility of the experimental VHTR program, to specify the characteristics and functions of the plant components, to point out the R and D items necessary for the experimental VHTR plant construction, and to analyze the feature of the plant safety. In this paper the summary of system design and safety features of the experimental reactor are indicated. Main issues are the safety philosophy for the design basis accident, the accidents assumed and the engineered safety systems adopted in the design works

Escitalopram in the Treatment of Adolescent Depression: A Randomized, Double-Blind, Placebo-Controlled Extension Trial

Science.gov (United States)

Robb, Adelaide; Bose, Anjana

2013-01-01

Abstract Objective The purpose of this study was to evaluate the extended efficacy, safety, and tolerability of escitalopram relative to placebo in adolescents with major depressive disorder (MDD). Methods Adolescents (12–17 years) who completed an 8-week randomized, double-blind, flexible-dose, placebo-controlled, lead-in study of escitalopram 10–20 mg versus placebo could enroll in a 16–24-week, multisite extension trial; patients maintained the same lead-in randomization (escitalopram or placebo) and dosage (escitalopram 10 or 20 mg/day, or placebo) during the extension. The primary efficacy was Children's Depression Rating Scale-Revised (CDRS-R) change from the lead-in study baseline to treatment week 24 (8-week lead-in study plus 16-week extension); the secondary efficacy was Clinical Global Impressions-Improvement (CGI-I) score at week 24. All efficacy analyses used the last observation carried forward (LOCF) approach; sensitivity analyses used observed cases (OC) and mixed-effects model for repeated measures (MMRM). Safety was evaluated via adverse event (AE) reports and the clinician-rated Columbia-Suicide Severity Rating Scale (C-SSRS). Results Following lead-in, 165 patients enrolled in the double-blind extension (82 placebo; 83 escitalopram); 40 (48.8%) placebo and 37 (44.6%) escitalopram patients completed treatment. CDRS-R total score improvement was significantly greater for escitalopram than for placebo (p=0.005, LOCF; p=0.014; MMRM). Response rates (CDRS-R ≥40% reduction from baseline [adjusted and unadjusted] and CGI-I ≤2) were significantly higher for escitalopram than for placebo (LOCF); remission rates (CDRS-R ≤28) were 50.6% for escitalopram and 35.7% for placebo (p=0.002). OC analyses were not significantly different between groups. The most frequent escitalopram AEs (≥5% and more frequent than placebo) were headache, nausea, insomnia, vomiting, influenza-like symptoms, diarrhea, and urinary tract infection. Most AEs were

Standardization of doctoral study in agricultural and extension education: is the field of study mature enough for achievement of the optimum degree of order?

Science.gov (United States)

Briers, G E; Lindner, J R; Shinn, G C; Wingenbach, G W; Baker, M T

2010-01-01

Agricultural and extension education--or some derivative name--is a field of study leading to the doctoral degree in universities around the world. Is there are body of knowledge or a taxonomy of the knowledge--e.g., a knowledge domain--that one should possess with a doctorate in agricultural and extension education? The purpose of this paper was to synthesize the work of researchers who attempted to define the field of study, with a taxonomy comprising the knowledge domains (standards) and knowledge objects--structured interrelated sets of data, knowledge, and wisdom--of the field of study. Doctoral study in agricultural and extension education needs a document that provides for rules and guidelines--rules and guidelines that in turn provide for common and repeated use--all leading to achievement of an optimum degree of order in the context of academic, scholarly, and professional practice in agricultural and extension education. Thus, one would know in broad categories the knowledge, skills, and abilities possessed by one who holds a doctoral degree in agricultural and extension education. That is, there would exist a standard for doctoral degrees in agricultural and extension education. A content analysis of three previous attempts to categorize knowledge in agricultural and extension education served as the primary technique to create a new taxonomy--or to confirm an existing taxonomy--for doctoral study in agricultural and extension education. The following coalesced as nine essential knowledge domains for a doctorate in agricultural and extension education: (1) history, philosophy, ethics, and policy; (2) agricultural/rural development; (3) organizational development and change management; (4) planning, needs assessment, and evaluation; (5) learning theory; (6) curriculum development and instructional design; (7) teaching methods and delivery strategies; (8) research methods and tools; and, (9) scholarship and communications.

Characteristics and Motivational Factors of Effective Extension Advisory Leaders: Implications for Building Strong Extension Advisory Councils

Directory of Open Access Journals (Sweden)

Joy Kish

2014-10-01

Full Text Available The purpose of this study was to determine the characteristics and motivational factors of effective Extension advisory leaders. This Delphi study was conducted with a selected group of County Extension Directors and a group of Extension State Advisory Leaders. The study identified 10 characteristics that distinguish an effective Extension advisory leader. Some of these characteristics are explicit and easy to observe, while others are implicit and difficult to directly observe. Therefore, it is practical to use directly observable characteristics of effective advisory leaders when selecting volunteers. Once potential volunteers are spotted in the community, implicit characteristics of effective advisory leaders should be used to further screen them before they are selected. The study also identified the eight most important factors motivating individuals to volunteer as effective advisory leaders. Understanding these motivational factors is helpful for creating an environment for attracting and retaining effective volunteers. Understanding their motivation for volunteer work and creating an environment for them to meet the motivating factors for volunteering will lead to volunteer satisfaction and retention. The findings of this study can be used to build strong Extension advisory councils.

Safety and efficacy of pregabalin in adolescents with fibromyalgia: a randomized, double-blind, placebo-controlled trial and a 6-month open-label extension study.

Science.gov (United States)

Arnold, Lesley M; Schikler, Kenneth N; Bateman, Lucinda; Khan, Tahira; Pauer, Lynne; Bhadra-Brown, Pritha; Clair, Andrew; Chew, Marci L; Scavone, Joseph

2016-07-30

Fibromyalgia (FM) is a common pain condition characterized by widespread musculoskeletal pain and tenderness. Pregabalin is an approved treatment for adults in the United States, but there are no approved treatments for adolescents with FM. This was a 15-week, randomized, double-blind, placebo-controlled study and 6-month open-label safety trial of flexible-dose pregabalin (75-450 mg/day) for the treatment of adolescents (12-17 years) with FM. Primary outcome was change in mean pain score at endpoint (scored from 0-10, with 24-h recall). Secondary outcomes included global assessments and measures of pain, sleep, and FM impact. A total of 107 subjects were randomized to treatment (54 pregabalin, 53 placebo) and 80 completed the study (44 pregabalin, 36 placebo). Improvement in mean pain score at endpoint with pregabalin versus placebo was not statistically significant, treatment difference (95 % CI), -0.66 (-1.51, 0.18), P = 0.121. There were significant improvements with pregabalin versus placebo in secondary outcomes of change in pain score by week (P recall), treatment difference (95 % CI), -0.87 (-1.68, -0.05), P = 0.037; and patient global impression of change, 53.1 % versus 29.5 % very much or much improved (P = 0.013). Trends toward improvement with pregabalin in other secondary outcomes measuring pain, sleep, and FM impact were not significant. Safety was consistent with the known profile of pregabalin in adults with FM. Pregabalin did not significantly improve the mean pain score in adolescents with FM. There were significant improvements in secondary outcomes measuring pain and impression of change. NCT01020474 ; NCT01020526 .

A study of RFID application impacts on medical safety.

Science.gov (United States)

Chang, She-I; Ou, Chin-Shyh; Ku, Cheng-Yuan; Yang, Morris

2008-01-01

With the international reform in medical management systems gaining ground worldwide, hospital management has gradually begun to shift its focus from providing expensive medical treatment to improving medical service quality and patient safety. In this study, we discuss the application of Radio Frequency Identification (RFID) and data integrating technology with the medical service, and examine whether or not this technology can enhance medical safety. We also discuss the possible benefits following the application of the RFID system. The findings show that the application of RFID to hospitals can actually generate benefits, which can be further divided into operational structure benefits, users' structure benefits, and organisational and environmental benefits. However, not all these benefits can achieve medical safety. Among them, only the operator and environmental benefits can play such roles. Nevertheless, the application of RFID can bring hospitals towards the integration of technology benefits and improved medical safety.

Bus safety study : a report to Congress.

Science.gov (United States)

2013-11-01

Section 20021(b) of the Moving Ahead for Progress for the 21st Century (MAP-21) legislation requires the Secretary of Transportation : to submit a report of the results of a Bus Safety Study to the Committee on Banking, Housing, and Urban Affai...

Measuring Best Practices for Workplace Safety, Health, and Well-Being: The Workplace Integrated Safety and Health Assessment.

Science.gov (United States)

Sorensen, Glorian; Sparer, Emily; Williams, Jessica A R; Gundersen, Daniel; Boden, Leslie I; Dennerlein, Jack T; Hashimoto, Dean; Katz, Jeffrey N; McLellan, Deborah L; Okechukwu, Cassandra A; Pronk, Nicolaas P; Revette, Anna; Wagner, Gregory R

2018-05-01

To present a measure of effective workplace organizational policies, programs, and practices that focuses on working conditions and organizational facilitators of worker safety, health and well-being: the workplace integrated safety and health (WISH) assessment. Development of this assessment used an iterative process involving a modified Delphi method, extensive literature reviews, and systematic cognitive testing. The assessment measures six core constructs identified as central to best practices for protecting and promoting worker safety, health and well-being: leadership commitment; participation; policies, programs, and practices that foster supportive working conditions; comprehensive and collaborative strategies; adherence to federal and state regulations and ethical norms; and data-driven change. The WISH Assessment holds promise as a tool that may inform organizational priority setting and guide research around causal pathways influencing implementation and outcomes related to these approaches.

Safety in the ARIES Tokamak Design Study

International Nuclear Information System (INIS)

Herring, J.S.; Wong, C.P.-C.; Cheng, E.T.; Grotz, S.

1989-01-01

Safety is one of the primary goals of the ARIES Tokamak Design Study. Public safety goals are the achievement passive safety which is demonstrable in tests that could precede operation and the assurance that releases from accidents be passively limited such that no evacuation plan in necessary. Strategies for safety of the plant investment are factory fabrication, short construction times and a design such that no off-normal operational transient results in damage which could not be repaired in routine maintenance. ARIES-I, the first of three 'visions' of potential tokamak reactors, will use He at 5 MPa as a blanket coolant and SiC/composite ceramic for the first wall and blanket materials. Both the coolant and the structural material were chosen for their low activation, both in the short term after accidents and for long term waste management. The breeder, Li 4 SiO 4 , was also chosen for low activation. Contemporary plasma physics and aggressive technology are used in ARIES-I, which results in very high toroidal fields (24 T maximum at the coil). The stored TF energy will be about 130 GJ. A central concern is the safe discharge of this stored energy under electrical fault conditions and prevention of a failure in the magnet set from propagating into systems containing radioactive inventories. The TF coil system consists of 16 coils, each containing two separate windings powered by two independent power supplies. Arcs and shorts between the two power supply systems and across individual windings have been modeled. In addition, delay or failure in circuit breaker opening has been modeled. The safety impacts of LOCA, LOFA and disruptive events have also been evaluated. 8 refs., 4 figs., 7 tabs

77 FR 43090 - Safety and Occupational Health Study Section: Notice of Charter Renewal

Science.gov (United States)

2012-07-23

... Committee Act (Pub. L. 92-463) of October 6, 1972, that the Safety and Occupational Health Study Section... Secretary, Safety and Occupational Health Study Section, Department of Health and Human Services, 1600... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Safety and...

75 FR 42455 - Safety and Occupational Health Study Section: Notice of Charter Renewal

Science.gov (United States)

2010-07-21

... Committee Act (Pub. L. 92-463) of October 6, 1972, that the Safety and Occupational Health Study Section... Secretary, Safety and Occupational Health Study Section, Department of Health and Human Services, 1600... DEPARTMENT OF HEALTH AND HUMAN SERVICES Centers for Disease Control and Prevention Safety and...

Microprocessor-based data acquisition system for extensive air shower studies

International Nuclear Information System (INIS)

Mazumdar, G.K.D.; Kalita, P.M.; Bordoloi, T.C.; Pathak, K.M.

1989-01-01

Studies on electromagnetic radiation from large extensive air showers (Esub(p) ≥> 10 16 eV) have been of recent importance in the investigation of properties of EAS in problems involving mass composition, arrival time, radio emission. Cerenkov radiation etc. Such studies need fast electronic circuitry preferably for digitisation. A microprocessor based data acquisition system having scintillation counters, PA, MA, Pd, S/H and control unit has been developed and is being used in the EAS studies at Gauhati University Cosmic Ray Research Laboratory. Description of the different units along with their functioning and method of standardisation is presented in this paper. (author). 3 figs

EPR safety. Consideration of the internal and external hazards in the safety studies

International Nuclear Information System (INIS)

Gueguin, H.

2008-04-01

The author presents the main points of the Preliminary Safety Report of EDF on the EPR reactor safety. It concerns the considerations of the internal (fire, flood, explosions, pipes failures) and external (earthquakes, airplane falls, explosions, exceptional natural disasters, extreme meteorological conditions) damages. It presents how the safety report takes into account the aggression. (A.L.B.)

Fire safety study of Dodewaard and Borssele nuclear power plants

International Nuclear Information System (INIS)

1988-03-01

From the nuclear and conventional fire safety audits of both Dutch nuclear power plants performed under supervision of the Nuclear Safety Inspectorate and the Inspectorate for the Fire Services it turns out that the fire safety is sufficient however amenable for improvement. Besides a detailed description of the method of examination, the study 'Fire Safety' contains the results of the audit and 14 respectively 15 recommendations for improvement of the fire safety in Dodewaard and Borssele. The suggested recommendations which are applicable to both power plants are the following: fire fighting training for operators and guards, a complete emergency ventilation system of the control room, increase in the number of detectors and alarms, an increase in the quantity of water available for high-pressure fire fighting, improvement of fire barriers between several redundancies of nuclear safety systems, an investigation and possible improvement of the heat and radiation protection offered by presently used fire fighting suits. For Dodewaard a closed emergency staircase in the reactor building (secondary containment) is deemed necessary for personnel emergency escape routes and continued fire fighting if required

78 FR 24751 - Safety and Occupational Health Study Section (SOHSS), National Institute for Occupational Safety...

Science.gov (United States)

2013-04-26

... 14, 2013 (Closed) Place: Embassy Suites, 1900 Diagonal Road, Alexandria, Virginia 22314, Telephone... business and for the study section to consider safety and occupational health-related grant applications...

International exchange of safety and licensing information

International Nuclear Information System (INIS)

Lafleur, J.D. Jr.; Hauber, R.D.; Chenier, D.M.

1977-01-01

A network of formal and informal bilateral arrangements for the exchange of nuclear safety information is being established by the U.S. Nuclear Regulatory Commission. For developing countries, such arrangements can provide ready access to the extensive, fully documented safety analyses and safety research results that NRC has accumulated. NRC has been receiving foreign visitors at a rate of about 500 per year, largely for discussions of safety and licensing questions related to light water reactors. Exchanges also are taking place on the safety of advanced reactors. A special interest of the NRC is in providing for reciprocal communicaion, at the earliest possible time, of important problems, decisions and other actions on nuclear safety matters. For example, it is essential that a newly-discovered problem in a nuclear reactor be brought immediately to the attention of other governments which are responsible for the safety of similar reactors. Definite progress has been made in the U.S. Freedom of Information Act. Certain exchanges have taken place on this basis. Experience in the establishment and operation of NRC's bilateral exchange arrangements is summarized. A typical exchange with the regulatory authority of country building its first power reactor is described

Knowledge Assessment of Food Safety Managers in Utah and Its Implications on the Exam and Instruction

Science.gov (United States)

Nummer, Brian A.; Guy, Stanley M.; Bentley, Joanne P. H.

2010-01-01

Food Safety Manager's Certification is offered through a state-local Extension partnership in Utah using an online course management system. Exams and course materials were created by an Extension Specialist at Utah State Univ. Extension Agents provide exam and curriculum facilitation in each county. This form of distance education enables access…

International requirements for life extension of nuclear power plants

International Nuclear Information System (INIS)

Wernicke, Robert

2009-01-01

Lifetime extension or long-term operation of nuclear facilities are topics of great international significance against the backdrop of a fleet of nuclear power plants of which many have reached 2/3 of their planned life. The article deals with the conditions for, and the specific requirements of, seeking long-term operation of nuclear power plants as established internationally and on the basis of IAEA collections. Technically, long-term operation is possible for many of the nuclear power plants in the world because, normally, they were built on the basis of conservative rules and regulations and, as a consequence, incorporate significant additional safety. Application of requirements to specific plants implies assessments of technical safety which show that conservative design philosophies created reserves and, as a consequence, there is an adequate level of safety also in long-term plant operation. For this purpose, the technical specifications must be revised, necessary additions made, and (international) operating experience taken into account and management of aging established. Two examples are presented to show how the approach to long-term plant operation is put into practice on a national level. (orig.)

Cross-comparison of three surrogate safety methods to diagnose cyclist safety problems at intersections in Norway.

Science.gov (United States)

Laureshyn, Aliaksei; Goede, Maartje de; Saunier, Nicolas; Fyhri, Aslak

2017-08-01

Relying on accident records as the main data source for studying cyclists' safety has many drawbacks, such as high degree of under-reporting, the lack of accident details and particularly of information about the interaction processes that led to the accident. It is also an ethical problem as one has to wait for accidents to happen in order to make a statement about cyclists' (un-)safety. In this perspective, the use of surrogate safety measures based on actual observations in traffic is very promising. In this study we used video data from three intersections in Norway that were all independently analysed using three methods: the Swedish traffic conflict technique (Swedish TCT), the Dutch conflict technique (DOCTOR) and the probabilistic surrogate measures of safety (PSMS) technique developed in Canada. The first two methods are based on manual detection and counting of critical events in traffic (traffic conflicts), while the third considers probabilities of multiple trajectories for each interaction and delivers a density map of potential collision points per site. Due to extensive use of microscopic data, PSMS technique relies heavily on automated tracking of the road users in video. Across the three sites, the methods show similarities or are at least "compatible" with the accident records. The two conflict techniques agree quite well for the number, type and location of conflicts, but some differences with no obvious explanation are also found. PSMS reports many more safety-relevant interactions including less severe events. The location of the potential collision points is compatible with what the conflict techniques suggest, but the possibly significant share of false alarms due to inaccurate trajectories extracted from video complicates the comparison. The tested techniques still require enhancement, with respect to better adjustment to analysis of the situations involving cyclists (and vulnerable road users in general) and further validation. However, we

Experiences from the LNPP-P and DSA review. Lessons learned from RBMK safety studies

International Nuclear Information System (INIS)

Mankamo, T.; Marttila, J.; Reponen, H.

2000-09-01

RBMK is the Russian acronym for 'Channelized Large Power Reactor'. The Soviet-designed RBMK plants deviate substantially from typical Western BWR or PWR plants. The safety of the RBMK plants has raised severe concerns since the major accident at Chernobyl Unit 4 in 1986. In addition, a fire destroyed the turbine hall of Chernobyl Unit 2 in 1991 resulting in a near-accident: the reactor cooling could only be maintained through improvised measures. Another well-known fire event is the control cable room fire at Ignalina Unit 2 in 1989, which led to a partial loss of the main control room functions. After the collapse of Soviet Union several multilateral safety programs were started to evaluate and improve the safety of the RBMK plants. A Probabilistic and Deterministic Safety Assessment (P and DSA) of the Leningrad Nuclear Power Plant (LNPP) Unit 2 was started in 1996. Phase 2 of the project was completed in January 1999. A Peer Review was performed by Russian and Western experts. This report describes the insights from the RBMK risk studies, especially from the LNPP P and DSA with emphasis on the deeper understanding of the risk-important design factors and identification of possible ways to increase safety. LNPP P and DSA has meant a significant progress in this respect. Despite of its certain limitations P and DSA Phase 2 could point out short-term measures, which substantially reduced the risk of identified weaknesses, mostly related to the reliability of the emergency feedwater function and its support systems. The findings of LNPP P and DSA and the review recommendations emphasise the extensions needed to the analysis scope. The spreading and other influences of fires and floods between connected spaces should be analysed because of incomplete separation and protection in these regards in the 16st generation RBMK plants. High priority should be given to the analysis of external hazards, which were found important at the Loviisa NPP on the Northern side of the

Experiences from the LNPP-P and DSA review. Lessons learned from RBMK safety studies

Energy Technology Data Exchange (ETDEWEB)

Mankamo, T. [Avaplan Oy (Finland); Marttila, J.; Reponen, H. [Radiation and Nuclear Safety Authority, Helsinki (Finland)

2000-09-01

RBMK is the Russian acronym for 'Channelized Large Power Reactor'. The Soviet-designed RBMK plants deviate substantially from typical Western BWR or PWR plants. The safety of the RBMK plants has raised severe concerns since the major accident at Chernobyl Unit 4 in 1986. In addition, a fire destroyed the turbine hall of Chernobyl Unit 2 in 1991 resulting in a near-accident: the reactor cooling could only be maintained through improvised measures. Another well-known fire event is the control cable room fire at Ignalina Unit 2 in 1989, which led to a partial loss of the main control room functions. After the collapse of Soviet Union several multilateral safety programs were started to evaluate and improve the safety of the RBMK plants. A Probabilistic and Deterministic Safety Assessment (P and DSA) of the Leningrad Nuclear Power Plant (LNPP) Unit 2 was started in 1996. Phase 2 of the project was completed in January 1999. A Peer Review was performed by Russian and Western experts. This report describes the insights from the RBMK risk studies, especially from the LNPP P and DSA with emphasis on the deeper understanding of the risk-important design factors and identification of possible ways to increase safety. LNPP P and DSA has meant a significant progress in this respect. Despite of its certain limitations P and DSA Phase 2 could point out short-term measures, which substantially reduced the risk of identified weaknesses, mostly related to the reliability of the emergency feedwater function and its support systems. The findings of LNPP P and DSA and the review recommendations emphasise the extensions needed to the analysis scope. The spreading and other influences of fires and floods between connected spaces should be analysed because of incomplete separation and protection in these regards in the 16st generation RBMK plants. High priority should be given to the analysis of external hazards, which were found important at the Loviisa NPP on the Northern

Safety evaluation of Elixir Paregorico in healthy volunteers: a phase I study.

Science.gov (United States)

de Moraes, Mea; Bezerra, Mm; Bezerra, Faf; de Moraes, Ra; Cavalcanti, Pp; Uchoa, Cra; Lima, Fav; Odorico de Moraes, M

2008-10-01

A liquid alcoholic extract of Papaver somniferum named Elixir Paregorico is extensively used for diarrheal diseases in Brazil. Its increased popularity has brought concerns and fears over the safety of this herbal product. Given the lack of investigative clinical studies, in this regard, this study investigated whether Elixir Paregorico administration causes any noticeable toxic effects in healthy volunteers. In all, 28 middle-aged healthy male (n = 14) and female (n = 14) were enrolled. After screening and a washout period, eligible subjects received four oral doses per day of Elixir Paregorico (3 mL diluted in 30 mL of water) over a 10-day period. Altogether, all 28 participants completed the study. The results of hematological and biochemical tests performed pre and post-treatment were within the normal range. In both male and female volunteers, there were no statistical differences (P > 0.05) in the results of clinical and laboratory tests performed at screening, on 5th and 10th day visits, and at final assessment. Although mild adverse events were related, which subsided spontaneously, no serious untoward reactions were reported following Elixir Paregorico administration. To our knowledge, this is the first demonstration that Elixir Paregorico administered four times a day for 10 days is safe and does not cause any noticeable toxic effect in healthy volunteers.

Longitudinal extensive transverse myelitis (LETM) in children: A twenty-year study from Oman.

Science.gov (United States)

Koul, Roshan; Alfutaisi, Amna M; Mani, Renjith; Abdel Rahim, Rana A; Sankhla, Dilip K; Al Azri, Faisal M

2017-04-01

The data on children with diagnosis of idiopathic transverse myelitis (ITM) was searched to find the pattern of myelitis in Oman. A retrospective study was carried out from January1995 to December 2014. Electronic medical records and patient medical files were seen to get the complete data of the children with ITM. This work was carried out at Sultan Qaboos University hospital, Muscat, Oman. The ethical committee of the hospital had approved the study. The diagnosis was based on the established criteria. Other causes of myelopathy were excluded. 19 children with idiopathic transverse myelitis were found. There were 18 out of 19 (94.6%) children with longitudinal extensive transverse myelitis (LETM). Longitudinal transverse extensive myelitis is the most common form of ITM in Oman.

Simulation study of coal mine safety investment based on system dynamics

Institute of Scientific and Technical Information of China (English)

Tong Lei; Dou Yuanyuan

2014-01-01

To generate dynamic planning for coal mine safety investment, this study applies system dynamics to decision-making, classifying safety investments by accident type. It validates the relationship between safety investments and accident cost, by structurally analyzing the causality between safety investments and their influence factors. Our simulation model, based on Vensim software, conducts simulation anal-ysis on a series of actual data from a coalmine in Shanxi Province. Our results indicate a lag phase in safety investments, and that increasing pre-phase safety investment reduces accident costs. We found that a 24%increase in initial safety investment could help reach the target accident costs level 14 months earlier. Our simulation test included nine kinds of variation trends of accident costs brought by different investment ratios on accident prevention. We found an optimized ratio of accident prevention invest-ments allowing a mine to reach accident cost goals 4 months earlier, without changing its total investment.

Safety of pandemic H1N1 vaccines in children and adolescents.

Science.gov (United States)

Wijnans, Leonoor; de Bie, Sandra; Dieleman, Jeanne; Bonhoeffer, Jan; Sturkenboom, Miriam

2011-10-06

During the 2009 influenza A (H1N1) pandemic several pandemic H1N1 vaccines were licensed using fast track procedures, with relatively limited data on the safety in children and adolescents. Different extensive safety monitoring efforts were put in place to ensure timely detection of adverse events following immunization. These combined efforts have generated large amounts of data on the safety of the different pandemic H1N1 vaccines, also in children and adolescents. In this overview we shortly summarize the safety experience with seasonal influenza vaccines as a background and focus on the clinical and post marketing safety data of the pandemic H1N1 vaccines in children. We identified 25 different clinical studies including 10,505 children and adolescents, both healthy and with underlying medical conditions, between the ages of 6 months and 23 years. In addition, large monitoring efforts have resulted in large amounts of data, with almost 13,000 individual case reports in children and adolescents to the WHO. However, the diversity in methods and data presentation in clinical study publications and publications of spontaneous reports hampered the analysis of safety of the different vaccines. As a result, relatively little has been learned on the comparative safety of these pandemic H1N1 vaccines - particularly in children. It should be a collective effort to give added value to the enormous work going into the individual studies by adhering to available guidelines for the collection, analysis, and presentation of vaccine safety data in clinical studies and to guidance for the clinical investigation of medicinal products in the pediatric population. Importantly the pandemic has brought us the beginning of an infrastructure for collaborative vaccine safety studies in the EU, USA and globally. Copyright © 2011 Elsevier Ltd. All rights reserved.

Towards a Formal Basis for Modular Safety Cases

Science.gov (United States)

Denney, Ewen; Pai, Ganesh

2015-01-01

Safety assurance using argument-based safety cases is an accepted best-practice in many safety-critical sectors. Goal Structuring Notation (GSN), which is widely used for presenting safety arguments graphically, provides a notion of modular arguments to support the goal of incremental certification. Despite the efforts at standardization, GSN remains an informal notation whereas the GSN standard contains appreciable ambiguity especially concerning modular extensions. This, in turn, presents challenges when developing tools and methods to intelligently manipulate modular GSN arguments. This paper develops the elements of a theory of modular safety cases, leveraging our previous work on formalizing GSN arguments. Using example argument structures we highlight some ambiguities arising through the existing guidance, present the intuition underlying the theory, clarify syntax, and address modular arguments, contracts, well-formedness and well-scopedness of modules. Based on this theory, we have a preliminary implementation of modular arguments in our toolset, AdvoCATE.

Assessment of policy issues in nuclear safety regulation according to circumstantial changes

Energy Technology Data Exchange (ETDEWEB)

Chang, Soon Heung; Lee, Byong Ho; Baek, Won Pil; Lee, Kwang Gu; Huh, Gyun Young; Hahn, Young Tae [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

2000-03-15

The objective of the work is to assess various issues in nuclear safety regulation in consideration of circumstantial changes. Emphasis is given to the safety of operating NPPs. It is concluded that the Periodic Safety Review (PSR) should be implemented in Korea as soon as possible, in harmonization with the regulation for life extension of NPPs. The IAEA guidelines, including 10 year intervals and 11 safety factors, should be used as the basic guidelines. The approach to improve regulatory effectiveness is also reviewed and a transition to 'knowledge-based regulation' is suggested.

Assessment of policy issues in nuclear safety regulation according to circumstantial changes

Energy Technology Data Exchange (ETDEWEB)

Chang, Soon Heung; Chang, Soon Heung; Lee, Byong Ho; Baek, Won Pil; Roh, Chang Hyun; Lee, Kwang Gu; Kim, Hong Chae; Lee, Yong Ho [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

1999-03-15

The objective of the work is to assess various issues in nuclear safety regulation in consideration of circumstantial changes. Emphasis is given to the safety of operating NPPs. It is concluded that the Periodic Safety Review (PSR) should be implemented in Korea as soon as possible, in harmonization with the regulation for life extension of NPPs. The IAEA guidelines, including 10 year intervals and 11 safety factors, should be used as the basic guidelines. Efforts are also required to cope with other circumstantial changes such as the establishment of International Nuclear Regulators Association (INRA)

Safety and Tolerability of Atomoxetine over 3 to 4 Years in Children with ADHD

Science.gov (United States)

Donnelly, Craig; Bangs, Mark; Trzepacz, Paula; Jin, Ling; Zhang, Shuyu; Witte, Michael M.; Ball, Susan G.; Spencer, Thomas J.

2009-01-01

Data from 13 double-blind, placebo-controlled trials and three open-label extension studies were pooled to examine the safety of atomoxetine for treating attention deficit hyperactivity disorder in children and adolescents for less than or equal to three or four years. Results show that atomoxetine is safe and well tolerated in the subjects.

Pilot Study on Harmonisation of Reactor Safety in WENRA Countries

International Nuclear Information System (INIS)

2003-03-01

Most of the objectives, set for the Pilot Study, were met. It can be concluded that the methodology was adequate for its purpose. National requirements on selected safety issues have been systematically compared and the major gaps and differences have been identified. Convenient overviews have been provided of differences and similarities between the countries. Furthermore, the conclusions are based on a safety justification and are detailed enough to provide input to a further more detailed analysis on the national level. It was not possible, however, to provide fully verified conclusions about the implementation of the reference levels in the different countries. This has to do with the following constraints on the study: In line with the Terms of Reference, the comparison of formal requirements did not address the more detailed use of criteria and methods to verify compliance. The same requirement could be enforced differently in different regulatory systems, and hence lead to different implementation. The Pilot Study also assessed the implementation, but it was not possible to do this in sufficient detail to identify such differences. The implementation was assessed on the basis of current knowledge of the respective regulatory body, but it was not possible to provide the panels with evidence of the implementation. For these reasons, conclusions about implemented safety provisions in the different countries should be drawn with precaution. The introduction of the panel assessments greatly improved the quality and consistency of the comparison assessments. Uncertainties in the assessments are mainly connected with lack of time to make a detailed analysis in some cases. The reliability of the assessments seems to be sufficient for the objectives of the Pilot Study. The introduction of the IAEA safety standards in the study proved to be helpful and provided confidence in the scope and strictness of the reference levels. This Pilot Study has contributed to

Land-Grant University Employee Perceptions of eXtension: A Baseline Descriptive Study

Science.gov (United States)

Kelsey, Kathleen D.; Stafne, Eric T.; Greer, Lane

2011-01-01

eXtension was publicly launched in 2008 as an online resource; however, adoption rates have been disappointing. The research reported here measured adoption of eXtension, willingness to participate in a Community of Practice, and adoption barriers among Oklahoma Extension employees. The adoption rate was 49%, and 43% of employees were willing to…

KIT safety management. Annual report 2012

International Nuclear Information System (INIS)

Frank, Gerhard

2013-01-01

The KIT Safety Management Service Unit (KSM) guarantees radiological and conventional technical safety and security of Karlsruhe Institute of Technology and controls the implementation and observation of legal environmental protection requirements. KSM is responsible for - licensing procedures, - industrial safety organization, - control of environmental protection measures, - planning and implementation of emergency preparedness and response, - operation of radiological laboratories and measurement stations, - extensive radiation protection support and the - the execution of security tasks in and for all organizational units of KIT. Moreover, KSM is in charge of wastewater and environmental monitoring for all facilities and nuclear installations all over the KIT campus. KSM is headed by the Safety Commissioner of KIT, who is appointed by the Presidential Committee. Within his scope of procedure for KIT, the Safety Commissioner controls the implementation of and compliance with safety-relevant requirements. The KIT Safety Management is certified according to DIN EN ISO 9001, its industrial safety management is certified by the VBG as ''AMS-Arbeitsschutz mit System'' and, hence, fulfills the requirements of NLF / ISO-OSH 2001. KSM laboratories are accredited according to DIN EN ISO/IEC 17025. To the extent possible, KSM is committed to maintaining competence in radiation protection and to supporting research and teaching activities. The present reports lists the individual tasks of the KIT Safety Management and informs about the results achieved in 2012. Status figures in principle reflect the status at the end of the year 2012. The processes described cover the areas of competence of KSM.

On the safety of conceptual fusion-fission hybrid reactors

International Nuclear Information System (INIS)

Kastenberg, W.E.; Okrent, D.; Badham, V.; Caspi, S.; Chan, C.K.; Ferrell, W.J.; Frederking, T.H.K.; Grzesik, J.; Lee, J.Y.; McKone, T.E.; Pomraning, G.C.; Ullman, A.Z.; Ting, T.D.; Kim, Y.I.

1979-01-01

A preliminary examination of some potential safety questions for conceptual fusion-fission hybrid reactors is presented in this paper. The study and subsequent analysis was largely based upon one design, a conceptual mirror fusion-fission reactor, operating on the deuterium-tritium plasma fusion fuel cycle and the uranium-plutonium fission fuel cycle. The major potential hazards were found to be: (a) fission products, (b) actinide elements, (c) induced radioactivity, and (d) tritium. As a result of these studies, it appears that highly reliable and even redundent decay heat removal must be provided. Loss of the ability to remove decay heat results in melting of fuel, with ultimate release of fission products and actinides to the containment. In addition, the studies indicate that blankets can be designed which will remain subcritical under extensive changes in both composition and geometry. Magnet safety and the effects of magnetic fields on thermal parameters were also considered. (Auth.)

Meeting Extension Programming Needs with Technology: A Case Study of Agritourism Webinars

Science.gov (United States)

Rich, Samantha Rozier; Komar, Stephen; Schilling, Brian; Tomas, Stacy R.; Carleo, Jenny; Colucci, Susan J.

2011-01-01

As clientele needs diversify, Extension educators are examining new technologies, including online tools, to deliver educational programming and resources. Using agritourism as the educational topic, the study reported here sought to evaluate participants' acceptance of online educational programming (webinars) and the effectiveness of the…

Study on operational safety issues in the Japanese disposal concept

International Nuclear Information System (INIS)

Suzuki, Satoru; Kitagawa, Yoshito; Hyodo, Hideaki; Kubota, Shigeru; Iijima, Masayoshi; Tamura, Akio; Ishiguro, Katsuhiko; Fujihara, Hiroshi

2014-01-01

In Japan, vitrified high-level radioactive waste (HLW) and certain types of low-level radioactive waste that results from the reprocessing of spent fuel and classified as TRU waste will be disposed of in deep geological formations. NUMO aims to ensure the safety of local residents and workers during the operational phase and after repository closure and will therefore establish a safety case for the geological disposal programme at the end of each stage of the stepwise siting process. Although the Japanese programme is still in the stage before initiation of the siting process, updating the generic (non-site-specific) safety case is required for building confidence among stakeholders. This study focuses on operational safety issues for the Japanese HLW disposal concept. (authors)

Preliminary study on functional performance of compound type multistage safety injection tank

International Nuclear Information System (INIS)

Bae, Youngmin; Kim, Young In; Kim, Keung Koo

2015-01-01

Highlights: • Functional performance of compound type multistage safety injection tanks is studied. • Effects of key design parameters are scrutinized. • Distinctive flow features in compound type safety injection tanks are explored. - Abstract: A parametric study is carried out to evaluate the functional performance of a compound type multistage safety injection tank that would be considered one of the components for the passive safety injection systems in nuclear power plants. The effects of key design parameters such as the initial volume fraction and charging pressure of gas, tank elevation, vertical location of a sparger, resistance coefficient, and operating condition on the injection flow rate are scrutinized along with a discussion of the relevant flow features. The obtained results indicate that the compound type multistage safety injection tank can effectively control the injection flow rate in a passive manner, by switching the driving force for the safety injection from gas pressure to gravity during the refill and reflood phases, respectively

Tritium safety study using Caisson Assembly (CATS) at TPL/JAEA

International Nuclear Information System (INIS)

Hayashi, T.; Kobayashi, K.; Iwai, Y.; Isobe, K.; Nakamura, H.; Kawamura, Y.; Shu, W.; Suzuki, T.; Yamada, M.; Yamanishi, T.

2008-01-01

Tritium confinement is required as the most important safety Junction for a fusion reactor. In order to demonstrate the confinement performance experimentally, an unique equipment, called CATS: Caisson Assembly for Tritium Safety study, was installed in Tritium Process Laboratory of Japan Atomic Energy Agency and operated for about 10 years. Tritium confinement and migration data in CATS have been accumulated and dynamic simulation code was accumulated using these data. Contamination and decontamination behavior on various materials and new safety equipment functions have been investigated under collaborations with a lot of laboratories and universities. (authors)

Quotient semigroups and extension semigroups

Indian Academy of Sciences (India)

Introduction. Abelian groups and semigroups play an important role in the classification of C. ∗. -algebras and their extensions. ... -algebra extension theory and K K-theory, it is crucial to study the theory of quotient semigroups from the ...

Sizewell 'B' PWR pre-construction safety report

International Nuclear Information System (INIS)

1982-04-01

The Pre-Construction Safety Report (PCSR) for a PWR power station to be constructed as Sizewell 'B' is presented in 13 volumes containing 16 chapters. The PCSR has been submitted to the Nuclear Installations Inspectorate in support of the Central Electricity Generating Board's application for consent to the extension at Sizewell. It describes the design and provides the safety case for the proposed station, which comprises a 4-loop pressurized water reactor with associated generating plant and supporting auxiliary equipment. A general description of the station and its site is given. The strategy for ensuring nuclear safety is set out and the general design aspects of systems and plant outlined. The plant and systems, including their safety design bases and the fault analyses carried out for the design are described. Finally the way in which the plant will be decommissioned at the end of its useful life is outlined. (U.K.)

Effectiveness and safety of imipenem/clavulanate and linezolid to treat multidrug and extensively drug-resistant tuberculosis at a referral hospital in Brazil.

Science.gov (United States)

Arbex, M A; Bonini, E H; Kawakame Pirolla, G; D'Ambrosio, L; Centis, R; Migliori, G B

Evidence on effectiveness, safety, and tolerability of imipenem/clavulanate (IC) and linezolid containing regimens to treat multidrug-resistant (MDR-) and extensively drug-resistant tuberculosis (XDR-TB) is scarce. The aim of this observational study is to evaluate the therapeutic contribution of IC and linezolid to manage MDR/XDR-TB cases at the reference centre of São Paulo state, Brazil. Twelve patients (9 males, 1 HIV positive in antiretroviral treatment, 4 MDR, 8 XDR) were treated with IC, 11 of them within linezolid-containing regimens. They all were previously treated with treatment failure, for a median (IQR, interquartile range) of 4.5 (2-6.5) times, having a severe resistance pattern (median number of resistances: 7 (5-8)) and being sputum smear and culture positive. IC and linezolid were prescribed at the dose of 1000mg/day and 600mg/day, respectively. The overall exposure was (median (IQR)) 419 (375.5-658) days for IC and 678 (392-720) days for linezolid. All of them converted their sputum (time to sputum conversion; 60 (37.5-90) days) and culture (75 (60-135) days), and 7 were cured while 5 are still on treatment with a gradually improving clinical picture. While no adverse events were reported for IC, 2 minor side effects, only, were attributed to linezolid (17%); in both cases the drug was re-started without further problems. Our study suggests that IC and linezolid-containing regimens can be used safely and with satisfactory outcomes in reference centres to treat MDR/XDR-TB patients. Copyright © 2016 Sociedade Portuguesa de Pneumologia. Published by Elsevier España, S.L.U. All rights reserved.

Safety related studies on the accident behaviour of the HTR-100

International Nuclear Information System (INIS)

Wolters, J.; Mertens, J.; Altes, J.; Bongartz, R.; Breitbach, G.; David, P.H.; Degen, G.; Ehrlich, H.G.; Escherich, K.H.; Frank, E.; Hennings, W.; Jahn, W.; Koschmieder, R.; Marx, J.; Meister, G.; Moormann, R.; Rehm, W.; Verfondern, K.

1991-10-01

The aim of investigations was to verify the safety concept of the plant for balance and to quantify the radiological risk to be expected in operating an HTR-100 double unit system. Moreover, aspects of the investment risk were considered. The spectrum of initiating events ranged from so-called transients to leaks in the primary circuit and steam generator and even included earthquakes. Some of the event trees derived were highly complex and extensive due to the situation of the steam generator above the core and with regard to the double unit plant concept with increased possibilities of accident control, but also with respect to potential accident propagation. Correspondingly sophisticated analyses were required to identify risk-relevant event sequences. Environmental exposure for all risk-relevant accidents is so low that accident consequence calculations do not reveal any lethal radiation doses and practically no stochastic fatal injuries. These calculations neither assumed acute protective measures nor long-term resettlement or decontamination. The radiological risk caused by an HTR-100 plant is therefore to be classified as very low. The initiating events selected as representative and the event sequences studied in detail cover the risk-relevant event spectrum well into the hypothetical range. (orig./HP) [de

Safety benefits from CANDU reactor replacement - a case study

International Nuclear Information System (INIS)

Mottram, R.; Millard, J.W.F.; Purdy, P.

2011-01-01

Both total core replacement and core retubing have been used in the CANDU industry. For future plant refurbishments, based on experience both in new construction and in recent refurbishments, the concept of total core replacement has been revisited. This builds on practices for replacement of other large plant equipment like boilers. The Bruce CANDU reactors, with their local shield tanks built around the Calandria and containment closely located around that Calandria Shield Tank Assembly (CSTA), are believed to be good candidates for core replacement. A structured process was used to design a replacement CSTA suitable for Bruce A use. The work started with a study of opportunities for safety enhancements in the core. This progressed into design studies and related design assist safety analysis on the reactor. A key element of the work involved consideration of how verified features from later CANDU designs, and from our new reactor design work, could be tailored to fit this replacement core. The replacement reactor core brings in structural improvements in both calandria and end shield, and safety improvements like the natural circulation enhancing moderator cooling layout and further optimized reactivity layouts to improve shutdown system performance. Bruce Power are currently studying the business implications of this and retube techniques as part of preparation for future refurbishments. The work explained in this paper is in the context of the safety related changes and the work to choose and quantify them. (author)

Safety benefits from CANDU reactor replacement. A case study

International Nuclear Information System (INIS)

Mottram, R.; Millard, J.W.F.; Purdy, P.

2011-01-01

Both total core replacement and core retubing have been used in the CANDU industry. For future plant refurbishments, based on experience both in new construction and in recent refurbishments, the concept of total core replacement has been revisited. This builds on practices for replacement of other large plant equipment like boilers. The Bruce CANDU reactors, with their local shield tanks built around the Calandria and containment closely located around that Calandria Shield Tank Assembly (CSTA), are believed to be good candidates for core replacement. A structured process was used to design a replacement CSTA suitable for Bruce A use. The work started with a study of opportunities for safety enhancements in the core. This progressed into design studies and related design assist safety analysis on the reactor. A key element of the work involved consideration of how verified features from later CANDU designs, and from our new reactor design work, could be tailored to fit this replacement core. The replacement reactor core brings in structural improvements in both calandria and end shield, and safety improvements like the natural circulation enhancing moderator cooling layout and further optimized reactivity layouts to improve shutdown system performance. Bruce Power are currently studying the business implications of this and retube techniques as part of preparation for future refurbishments. The work explained in this paper is in the context of the safety related changes and the work to choose and quantify them. (author)

Ferrocyanide safety project ferrocyanide aging studies. Final report

International Nuclear Information System (INIS)

Lilga, M.A.; Hallen, R.T.; Alderson, E.V.

1996-06-01

This final report gives the results of the work conducted by Pacific Northwest National Laboratory (PNNL) from FY 1992 to FY 1996 on the Ferrocyanide Aging Studies, part of the Ferrocyanide Safety Project. The Ferrocyanide Safety Project was initiated as a result of concern raised about the safe storage of ferrocyanide waste intermixed with oxidants, such as nitrate and nitrite salts, in Hanford Site single-shell tanks (SSTs). In the laboratory, such mixtures can be made to undergo uncontrolled or explosive reactions by heating dry reagents to over 200 degrees C. In 1987, an Environmental Impact Statement (EIS), published by the U.S. Department of Energy (DOE), Final Environmental Impact Statement, Disposal of Hanford Defense High-Level Transuranic and Tank Waste, Hanford Site, Richland, Washington, included an environmental impact analysis of potential explosions involving ferrocyanide-nitrate mixtures. The EIS postulated that an explosion could occur during mechanical retrieval of saltcake or sludge from a ferrocyanide waste tank, and concluded that this worst-case accident could create enough energy to release radioactive material to the atmosphere through ventilation openings, exposing persons offsite to a short-term radiation dose of approximately 200 mrem. Later, in a separate study (1990), the General Accounting Office postulated a worst-case accident of one to two orders of magnitude greater than that postulated in the DOE EIS. The uncertainties regarding the safety envelope of the Hanford Site ferrocyanide waste tanks led to the declaration of the Ferrocyanide Unreviewed Safety Question (USQ) in October 1990

Purdue Extension: Employee Engagement and Leadership Style

Science.gov (United States)

Abbott, Angela R.

2017-01-01

The purpose of this quantitative study was to assess the Purdue Extension county directors' level of engagement and leadership style and to examine the relationship between these two variables. The study aimed to inform a professional development training program for all Purdue Extension county extension directors. Survey data were collected from…

Efficacy and safety profile of linezolid in the treatment of multidrug-resistant (MDR) and extensively drug-resistant (XDR) tuberculosis: a systematic review and meta-analysis.

Science.gov (United States)

Agyeman, Akosua Adom; Ofori-Asenso, Richard

2016-06-22

Treatment options for drug-resistant tuberculosis are still limited. Linezolid has been recommended for treatment of patients with multidrug-resistant (MDR) or extensively-drug-resistant (XDR) tuberculosis, although uncertainties remain regarding its safety and tolerability in these circumstances. To systematically evaluate the existing evidence regarding the efficacy and tolerability of linezolid in the treatment of MDR or XDR tuberculosis. We conducted a systematic review and meta-analysis in accordance with the PRISMA guidelines. Searches were conducted in PubMed, Web of Science and EMBASE followed by direct search of abstracts in the International Journal of Tuberculosis and Lung Disease to retrieve primary studies published between January 2000 and January 2016 assessing linezolid efficacy and safety in the treatment of drug-resistant TB. We evaluated the occurrence of outcomes including culture conversion, treatment success and incidence of adverse events such as myelosuppression and neuropathy. Twenty-three (23) studies conducted in fourteen (14) countries and involving 507 patients were retrieved. Only 1 randomized controlled trial was identified and none of the identified studies involved participants from Africa. The pooled proportion for treatment success was 77.36 % (95 % CI = 71.38-82.83 %, I(2) = 37.6 %) with culture conversion rate determined as 88.45 % (95 % CI = 83.82-92.38 %, I(2) = 45.4 %). There was no strong evidence for both culture conversion (p = 0.0948) and treatment success (p = 0.0695) between linezolid daily doses ≤ 600 and > 600 mg. Only myelosuppression showed a strong statistical significance (p linezolid also showed no significance upon dose comparisons (p = 0.3213, p = 0.9050 respectively). Available evidence presents Linezolid as a viable option in the treatment of MDR/XDR TB although patients ought to be monitored closely for the incidence of major adverse events such as myelosuppression and

Leading Edge. Volume 7, Number 3. Systems Safety Engineering

Science.gov (United States)

2010-01-01

foods were not always safe to eat given the sanitary conditions of the day. In 1943, the psychologist Abraham Maslow proposed a five-level... hierarchy of basic human needs, and safety was number two on this list. System safety is a specialized and formalized extension of our in- herent drive for...factors, hazards, mishaps, and ef- fects. The following is an example of each element within the hierarchy : An exposed sharp edge in a relay cabi- net

COOPERATION BETWEEN INSTITUTIONS OF PUBLIC ORDER AND SAFETY FROM BIHOR (ROMANIA AND HAJDU-BIHAR (HUNGARY: A CASE STUDY

Directory of Open Access Journals (Sweden)

Bucur Catalin-Adrian

2012-07-01

Full Text Available The forms and degree of cooperation between public order and safety on both sides of the border took on different forms from country to country, from one region to another. Some countries have a very extensive inter-institutional cooperation and substantial, while in other countries relations are characterized by a deep division, competition and lack of communication. To understand existing forms of cooperation, and how best practices can be transferred to some Member States it is necessary to understand the existing diversity across the European Union. This paper focuses on presenting several cooperation projects with direct reference to public order and safety activities implemented in Bihor - Hajdu-Bihar euroregion, within the CBC Programme Hungary-Romania 2004 and especially the project "Mirror network for operative and operational data trasfer", a joint project of cooperation in the public order and safety in Bihor - Hajdu-Bihar Euroregion. This paper is part of the doctoral thesis on Integrate perspective on companies sector, coordinated by professor Ph.D. Alina Bn#259;dulescu from University of Oradea, Faculty of Economics.

Safety review and approval process for the TFTR

International Nuclear Information System (INIS)

Levine, J.D.; Howe, H.J.; Howe, K.E.

1983-01-01

The design, construction, and operation of the Tokamak Fusion Test Reactor (TFTR) has undergone an extensive safety and enviromental analysis involving Princeton Plasma Physics Laboratory (PPPL), the U.S. Department of Energy (DOE), the Ebasco/Grumman Industrial Subcontractor Team, and other organizations. This analysis, which is continuing during the TFTR operational phase, has been facilitated by the preparation, review and approval of several documents, including an Environmental Statement (Draft and Final), a Preliminary Safety Analysis Report (PSAR), a Final Safety Analysis Report (FSAR), Operations Safety Requirements (OSRs) and Safety Requirements (SRs), and various Operating and Maintenance Manuals. Through TFTR Safety Group participation in formal system design evaluations, change control boards, and reviews of project procurement and installation documentation, the TFTR Management Configuration Control System assures that all aspects of the project, including proposed design, installation and operational changes, receive prompt and thorough safety analyses. These efforts will continue as the TFTR Program moves into the neutral beam and D-T operational phases. The safety review and approval experience that has been acquired on the TFTR Project should serve as a foundation for similar efforts on future fusion devices

Safety evaluation in the development of medical devices and combination products

CERN Document Server

Gad, Shayne C

2008-01-01

Capturing the growth of the global medical device market in recent years, this practical new guide is essential for all who are responsible for ensuring safety in the use and manufacture of medical devices. It has been extensively updated to reflect significant advances, incorporating combination products and helpful case examples of current real-life problems in the field.The Third Edition explores these key current trends:global device marketscontinually advancing technologythe increasing harmonization of device safety regulation worldwideEach aspect of safety evaluation is considered in ter

Crack arrest concepts for failure prevention and life extension. Proceedings

International Nuclear Information System (INIS)

Wiesner, C.S.

1996-01-01

These proceedings contain the thirteen papers presented at a seminar on crack arrest concepts for failure prevention and life extension. They provide a picture of the current position of crack arrest testing, models and applications, discussion of the relevance of recent research to industrial problems, and an assessment of whether the application of crack arrest models provides additional safety. Separate abstracts have been prepared for seven papers of relevance to the nuclear industry and, in particular, reactor pressure vessels. (UK)

Safety management of radioisotopes and others in educational institutions

International Nuclear Information System (INIS)

1981-01-01

Radioisotopes are extensively used in the fields of research in various educational institutions. While considerable progress has been seen in the safety management of RI utilization, such accidents as the loss of radioisotopes and radioactive contamination occurred. Under the situation, the safety management of RIs and others in RI-using facilities provided by the law has been examined by the ad hoc committee. A report by the committee is described as follows: need for a RI safety management organization, defining the responsibility of the chief technicians handling radiation, need for the practices of using RIs, etc. in education and traininng, planned RI-handling facilities, cautions for the loss of RIs and the contamination, centralization in RI safety management, improvement of remuneration for the chief technicians handling radiation, occasional restudy on the safety management of RIs, etc. (J.P.N.)

Calculational study for criticality safety data of fissionable actinides

International Nuclear Information System (INIS)

Nojiri, Ichiro; Fukasaku, Yasuhiro.

1997-01-01

This study has been carried out to obtain basic criticality safety characteristics of minor actinides nuclides. Criticality safety data of minor actinides nuclides have been surveyed through public literatures. Critical mass of seven nuclides, Np-237, Am-241, Am-242m, Am-243, Cm-243, Cm-244 and Cm-245, have been calculated by using two code systems of criticality safety analysis, SCALE-4 and MCNP4A, under some material and reflector conditions. Some applicable cross-section libraries have been used for each code systems. Calculated data have been compared with each other and with published data. The results of this comparison shows that there is no discrepancy within the computational codes and the calculated data is strongly depend on the cross-section library. (author)

Considerations on Fail Safe Design for Design Basis Accident (DBA) vs. Design Extension Condition (DEC): Lesson Learnt from the Fukushima Accident

International Nuclear Information System (INIS)

Ha, Jun Su; Kim, Sungyeop

2014-01-01

The fail safety design is referred to as an inherently safe design concept where the failure of an SSC (System, Structure or Component) leads directly to a safe condition. Usually the fail safe design has been devised based on the design basis accident (DBAs), because the nuclear safety has been assured by securing the capability to safely cope with DBAs. Currently regards have been paid to the DEC (Design Extension Condition) as an extended design consideration. Hence additional attention should be paid to the concept of the fail safe design in order to consider the DEC, accordingly. In this study, a case chosen from the Fukushima accident is studied to discuss the issue associated with the fail safe design in terms of DBA and DEC standpoints. For the fail safe design to be based both on the DBA and the DEC, a Mode Changeable Fail Safe Design (MCFSD) is proposed in this study. Additional discussions on what is needed for the MCFSD to be applied in the nuclear safety are addressed as well. One of the lessons learnt from the Fukushima accident should include considerations on the fail-safe design in a changing regulatory framework. Currently the design extension condition (DEC) including severe accidents should be considered during designing and licensing NPPs. Hence concepts on the fail safe design need to be changed to be based on not only the DBA but also the DEC. In this study, a case on a fail-safe design chosen from the Fukushima accident is studied to discuss the issue associated with the fail safe design in terms of DBA and DEC conditions. For the fail safe design to be based both on the DBA and the DEC, a Mode Changeable Fail Safe Design (MCFSD) is proposed in this study. Additional discussions on what is needed for the MCFSD to be applied in the nuclear safety are addressed as well

Recent activities within Nuclear Electric related to the qualification of digital systems and the extension of maintenance intervals

International Nuclear Information System (INIS)

Holt, G.P.

1993-01-01

Nuclear Electric is pursuing a program of modernization and enhancement of existing control and safety (C ampersand I) systems to improve power plant availability and increase power output. This paper describes recent experience in qualifying digital systems for safety applications. Also, described is the work currently in hand to reduce the frequency of maintenance periods for safety C ampersand I equipment. The qualification of digital systems is shown to be a more rigorous and much more extensive (and thus costly) exercise than the qualification of conventional equipment. This is illustrated by brief references to two software-based safety systems, the Single Channel Trip System at the Dungeness open-quotes Bclose quotesAGR and the Primary Protection System for the new PWR at Sizewell open-quotes Bclose quotes. The emphasis of the paper is on the use of Application Specific Integrated Circuits (ASICs) in safety systems, to reduce, or eliminate dependence on software for the fulfillment of requirements which need implementations that are complex or of a high functional density. Recent experience in the development of a prototype safety system based on ASICs, The Gaseous Activity Monitor and Trip Equipment (GAM), is used to illustrate their possible benefits and potential problems. When using complex integrated circuits like microprocessors or ASICs in digital systems a difficulty arises in analyzing the failure modes of the system. Efforts to overcome this difficulty led to the development of a method for performing failure analyses based on functional blocks. The techniques and benefits of such an approach are outlined. Finally, efforts to reduce maintenance costs, yet at the same time enhance safety, are leading towards an extension of maintenance intervals, for some safety equipment, from 3 months to 4 months and also towards lengthening the period between AGR outages from 2 years to 3 years

Safety training parks – A case study on the effectiveness of the trainings

DEFF Research Database (Denmark)

Räsänen, Tuula; Sormunen, E.; Reiman, Arto

The Safety Training Park (STP) concept is a unique Finnish safety training innovation. The STP provides different actors of the construction industry and other branches a practical occupational safety and health (OSH) training area. To the authors’ knowledge, no such parks exist in Europe besides...... Finland. Objec-tive was to study the effectiveness of the STP trainings at a large case company which participated in this study and which has actively trained its personnel in the park. The study was conducted from February 2015 to Feb-ruary 2017. Several key success factors were identified...... in the interviews of this case study. In addition, the company OSH statistics (2010 – 2016) showed a positive development at safety level. However, The Nordic Safety Climate Questionnaire did not show any significant change of results in a one year period. According to the results of the group interviews...

Studying Patient Safety Culture from the Viewpoint of Nurse in educational hospitals Ilam City

Directory of Open Access Journals (Sweden)

Milad Borji

2016-12-01

Full Text Available Introduction: Patient safety culture is the first necessary step to reduce medical errors and improve patient's condition. In this context, this article aims at studying the condition of patient safety culture in hospitals in Elam in 2016. Materials and Methods: In this cross-sectional study, 150 nurses in Ilam were randomly selected. The Culture Hospital Survey on Patient Safety (HSOPSC was used and its reliability and validity had been confirmed by the previous studies. The data were analyzed by SPSS17. Results: The results showed that the nurses' safety was at positive(62.37± 8.70 and there could be found no significant difference in patient safety among the studied hospitals in this article (P<.05. Extra-organizational teamwork and non-punitive response, among the aspects of patient safety, had the lowest means and organizational learning and general understanding had the highest. Conclusion: Considering the importance of patient safety, the interventions need to be performed in order to improve the patient safety condition among nurses, especially in two aspects of extra-organizational teamwork and non-punitive response that had the lowest means.

A proposal for performing software safety hazard analysis

International Nuclear Information System (INIS)

Lawrence, J.D.; Gallagher, J.M.

1997-01-01

Techniques for analyzing the safety and reliability of analog-based electronic protection systems that serve to mitigate hazards in process control systems have been developed over many years, and are reasonably understood. An example is the protection system in a nuclear power plant. The extension of these techniques to systems which include digital computers is not well developed, and there is little consensus among software engineering experts and safety experts on how to analyze such systems. One possible technique is to extend hazard analysis to include digital computer-based systems. Software is frequently overlooked during system hazard analyses, but this is unacceptable when the software is in control of a potentially hazardous operation. In such cases, hazard analysis should be extended to fully cover the software. A method for performing software hazard analysis is proposed in this paper. The method concentrates on finding hazards during the early stages of the software life cycle, using an extension of HAZOP

Overview of the reactor safety study consequence model

International Nuclear Information System (INIS)

Wall, I.B.; Yaniv, S.S.; Blond, R.M.; McGrath, P.E.; Church, H.W.; Wayland, J.R.

1977-01-01

The Reactor Safety Study (WASH-1400) is a comprehensive assessment of the potential risk to the public from accidents in light water power reactors. The engineering analysis of the plants is described in detail in the Reactor Safety Study: it provides an estimate of the probability versus magnitude of the release of radioactive material. The consequence model, which is the subject of this paper, describes the progression of the postulated accident after the release of the radioactive material from the containment. A brief discussion of the manner in which the consequence calculations are performed is presented. The emphasis in the description is on the models and data that differ significantly from those previously used for these types of assessments. The results of the risk calculations for 100 light water power reactors are summarized

Safety and efficacy of AMG 334 for prevention of episodic migraine

DEFF Research Database (Denmark)

Sun, Hong Yan; Dodick, David W; Silberstein, Stephen D

2016-01-01

BACKGROUND: The calcitonin gene-related peptide (CGRP) pathway is a promising target for preventive therapies in patients with migraine. We assessed the safety and efficacy of AMG 334, a fully human monoclonal antibody against the CGRP receptor, for migraine prevention. METHODS: In this multicentre...... in monthly migraine days from baseline to the last 4 weeks of the 12-week double-blind treatment phase. The primary endpoint was calculated using the least squares mean at each timepoint from a generalised linear mixed-effect model for repeated measures. Safety endpoints were adverse events, clinical...... laboratory values, vital signs, and anti-AMG 334 antibodies. The study is registered with ClinicalTrials.gov, number NCT01952574. An open-label extension phase of up to 256 weeks is ongoing and will assess the long-term safety of AMG 334. FINDINGS: From Aug 6, 2013, to June 30, 2014, 483 patients were...

Perception of Extension Specialists about the Role of Extension in the Production and Adoption of the Genetically Modified Crops in Iran

OpenAIRE

Seyed J.F. Hosseini

2008-01-01

Extension specialists were surveyed in order to explore their perception about the role of extension in the production and adoption of Genetically Modified (GM) crops in Iran. The methodology used in this study involved a combination of descriptive and quantitative research. The total population for this study was 120 extension specialists in Iran. Extension specialists believed that the first priority of extension should be to increase the participation of stakeholders in the development of ...

Safety and tolerability of flexible dosages of prolonged-release OROS methylphenidate in adults with attention-deficit/hyperactivity disorder.

NARCIS (Netherlands)

Buitelaar, J.K.; Ramos-Quiroga, J.A.; Casas, M.; Kooij, J.J.; Niemela, A.; Konofal, E.; Dejonckheere, J.; Challis, B.H.; Medori, R.

2009-01-01

The osmotic release oral system (OROS) methylphenidate formulation is a prolonged-release medication for the treatment of attention-deficit/hyperactivity disorder (ADHD) in children, adolescents, and adults. We conducted a seven-week open-label extension of a double-blind study to assess the safety

Subring Depth, Frobenius Extensions, and Towers

Directory of Open Access Journals (Sweden)

Lars Kadison

2012-01-01

Full Text Available The minimum depth d(B,A of a subring B⊆A introduced in the work of Boltje, Danz and Külshammer (2011 is studied and compared with the tower depth of a Frobenius extension. We show that d(B,A < ∞ if A is a finite-dimensional algebra and Be has finite representation type. Some conditions in terms of depth and QF property are given that ensure that the modular function of a Hopf algebra restricts to the modular function of a Hopf subalgebra. If A⊇B is a QF extension, minimum left and right even subring depths are shown to coincide. If A⊇B is a Frobenius extension with surjective Frobenius, homomorphism, its subring depth is shown to coincide with its tower depth. Formulas for the ring, module, Frobenius and Temperley-Lieb structures are noted for the tower over a Frobenius extension in its realization as tensor powers. A depth 3 QF extension is embedded in a depth 2 QF extension; in turn certain depth n extensions embed in depth 3 extensions if they are Frobenius extensions or other special ring extensions with ring structures on their relative Hochschild bar resolution groups.